Radiation Safety Information Computational Center
	Oak Ridge National Laboratory Post Office Box 2008 Oak Ridge, Tennessee 37831-6362 Managed by UT-Battelle, LLC for the U.S. Department of Energy under contract DE-AC05-00OR22725 Phone No. 865-574-6176 FAX 865-574-6182 Internet: PDC@ORNL.GOV WWW: http://www-rsicc.ornl.gov/rsic.html
No. 436	June 2001
"While one person hesitates because he feels inferior, the other is busy making mistakes and becoming superior" -- Henry C. Link

• RSICC Welcomes Dr. Di-Wen Chen
• Dr. R. G. "Tut" Alsmiller 1928-2001
• Congratulations Dr. Tanaka
• Dr. Tomonori Hyodo
• NRC Codes Made Available
• CHANGES TO THE COMPUTER CODE and DATA COLLECTION
• CONFERENCES, COURSES, SYMPOSIA
• Short Courses on Monte Carlo Analysis and Nuclear Criticality Safety
• The XIX Autumn School on
• New Perspectives with Nuclear Radioactivity
• Visual Editor Classes Offered
• SCALE Training Course Schedule
• Advanced Training Course on PENELOPE-2000
• Seventh International Radiopharmaceutical Dosimetry Symposium
• Calendar
• MAY ACCESSION OF LITERATURE

R.G. "Tut" Alsmiller Jr., 73, died Thursday, April 19, 2001, in Louisville, Ky. He retired from the Oak Ridge National Laboratory in 1992 following a long and distinguished career.

Tut served in the US Marine Corps during World War II. Following his military service, he attended the University of Louisville where he received a Bachelor of Arts degree in Physics in 1949. He received a Master of Science degree in Physics from Purdue University in 1952 and then attended the University of Kansas where he earned a Ph.D. in Physics in 1957. During his university studies, he met his wife, Fran, with whom he worked closely at ORNL during both of their careers. Fran shared Tut's enthusiasm for physics. She died in 1995.

Tut joined ORNL in 1957 as a member of the Neutron Physics Division. During his career he worked on the development of electromagnetic and hadronic transport codes and hadron-nucleus collision models. He led the group that pioneered work in the development of the High Energy Transport Code, HETC, that has been used extensively to carry out radiation transport analyses for accelerator facilities, space radiation shielding, cancer radiotherapy, and hadron detector development. Tut led efforts in fusion neutronics research including the measurement and calculation of neutron transport in fusion reactor shield assemblies. He developed high-energy cross-sections for deterministic transport codes and worked at length on economic system modeling, publishing extensively in all of these areas.

His associates remember him for the support and help he provided to enhance their careers. Tut was an extremely hard worker and expected the same of his associates. He was a strong believer in documenting and publishing the results of his research and he motivated his colleagues to do the same. Tut was recognized both nationally and internationally. He was a Fellow of the American Nuclear Society and a member of the American Physical Society.

Tut had many friends at ORNL and around the world. He will be remembered for his many contributions to the physics of radiation transport and its application to nuclear engineering problems.
 

Dr. Shun-ichi Tanaka, who is a long time RSICC friend and customer, and who also happens to be the Deputy Director General of Japan Atomic Energy Research Institute (JAERI), recently was awarded the Distinguished Research Service Award from the Japanese Ministry of Education, Culture, Sports, Science, and Technology on April 18, 2001. The award was for Dr. Tanaka's outstanding contributions on the development of shielding methods for gamma rays and neutrons, which are widely applied for the design of nuclear, medical and industrial facilities.
 

Betty Maskewitz recently heard from Dr. Tomonori Hyodo, a long time "shielder". Dr. Hyodo retired from Kyoto University in March 1986 and was president of a very small junior college for technical training for industry from 1986 to March 1990. He went back to Kyoto city, where he lived previously with his wife Toshiko until 1964. Now he lives with his family and elder son's family in Manazuru-machi, Kanagawa-Ken, Japan.
 
 

Four U.S. Nuclear Regulatory Commission (NRC) software packages which were transferred from the ESTSC to RSICC were incorporated into the RSICC computer code collection. Please browse the computer code abstracts available at RSICC's www site for more information on these packages.
 

CCC-602/SMART
PSR-425/DORIAN
PSR-439/ORINC (US distribution only)
PSR-461/PELE-IC
 
 

Two new and three newly frozen packages were added to the computer code software and data collection during the month, four of which are non-US contributions.

Universitat de Barcelona and Institut de Tècniques Energètiques, Universitat Politècnica de Catalunya in Barcelona, Spain, through the Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France, contributed a newly frozen version of PENELOPE. This code performs Monte Carlo simulation of electron gamma-ray showers in arbitrary materials. Initially, it was devised to simulate the PENetration and Energy LOss of Positrons and Electrons in matter; photons were introduced later. The adopted scattering model gives a reliable description of radiation transport in the energy range from about 1 keV (100 eV for electrons and positrons) to several hundred MeV. PENELOPE generates random electron-photon showers in complex material structures consisting of any number of distinct homogeneous regions (bodies) with different compositions. Several corrections and enhancements, which are listed in the file Readme.v2k, were made to the previous version, 1996.02.29, to create this release.

PENELOPE incorporates a scattering model that combines numerical total cross sections (or stopping cross sections) with simple analytical differential cross sections for the different interaction mechanisms. The simulation of electron and positron tracks is performed by means of a mixed (class II) algorithm. Individual hard elastic collisions, hard inelastic interactions and hard bremsstrahlung emission are simulated in a detailed way, i.e., by random sampling from the corresponding restricted differential cross sections.

PENELOPE can be run on almost any operating system supporting a Fortran 77 compiler (Unix, MS-DOS, Windows95, Windows NT, VMS, etc.). The included executables were created at RSICC using the Lahey Fortran 95 compiler under Windows2000. The NEA Data Bank tested PENELOPE on a PC INTEL PENTIUM-III 500Mhz under Red Hat Linux 6.1 with the g77 v0.5.24 compiler. Note that a Fortran compiler is required on all systems to build problem-specific executables. The package is transmitted on CD which contains the source, data files, PC executables, and test cases written in a self-extracting compressed file. References: PENELOPE Manual (August 28, 2000), Informes Tecnicos Ciemat 799 (June 1996), UBRPG-1998-01 (February 5, 1998). Fortran 77; DEC Alpha, Sun, and PC (C00682MNYCP01).
 
 

The National Nuclear Data Center, Brookhaven National Laboratory, Upton, New York, contributed a newly frozen version of these codes for handling ENDF/B-V and ENDF/B-VI data. The present release of the ENDF utility codes, version 6.12, supersedes all previous versions of the codes. The programs are written to process ENDF-6 formatted files. This release corrects all bugs in CHENDF 6.11 reported to NNDC before April 1, 2001 and incorporates all format changes adopted prior to this date. The modules included are: CHECKR, FIZCON, GETMAT, INTER, LISTEF, PLOTEF, PSYCHE, SETMDC, and STANEF. The standard distributed version of these programs is written in ANSI-77 Fortran and Fortran-90 and should operate on any computer with sufficient memory and a Fortran compiler conforming to these standards. The SETMDC utility configures CHENDF to run on Vaxes, IBM mainframes, IBM PC's or any machine with an ANSI Fortran compiler. The code system was tested by RSICC on an IBM RS/6000 and a Sun Solaris workstation. NNDC provided executables created with the Digital Visual Fortran compiler under Windows. These are included in the package. CHENDF is transmitted on a CD in WinZip self-extracting compressed files which include the source codes and sample problem input and output. Reference: Informal NNDC report (April 5, 2001). Fortran 77; Vax, IBM, Unix Workstations (P00333/MNYCP/03).
 
 

The Nuclear Data Section at the International Atomic Energy Agency, Vienna, Austria, contributed a newly frozen version of the pre-processing code system for data in ENDF/B format. The ENDF/B pre-processing codes are designed to be a modular set of computer codes, each of which reads evaluated nuclear data in the ENDF/B format, processes the data and outputs it in the ENDF/B format. Each code performs one or more independent operations on the data. These codes are designed to operate on virtually any type of computer with the included capability of optimization on any given computer. These codes can process datasets in any ENDF/B format, e.g. ENDF/B-IV, V or VI.

The PREPRO2000 codes include extensions to handle all current ENDF/B formats and procedures, and corrections to problems that existed in earlier versions of these codes. As such, the 2000 codes completely supersede all earlier versions; and it is strongly recommended that all users of these codes only use the 2000 version of these codes. Failure to heed this warning can lead to completely erroneous results.

PREPRO2000 is written in standard Fortran and runs on Unix workstations, personal computers and PowerMAC. UNIX and OpenVMS systems require X11 for the graphics capability. The Compaq Visual Fortran compiler was used to create the Windows executables included in the package. The Absoft Fortran 77 version 4.4 compiler under Redhat Linux 6.2 was used to create the included Linux executables. PREPRO2000 was tested at RSICC on the following machines:

IBM 43P Model 260P running AIX 4.3.3 with XLF 6.1 and XL C 4.4
SUN UltraSparc 60 under SunOS 5.6 using f77 5, Fortran 90 2 and C Version 5.0
Pentium running Windows2000 with included Compaq Visual Fortran executables
Pentium running Redhat Linux 6.1 with included Absoft F77 4.4 executables

The package is transmitted on a CD which contains the referenced document and 5 machine-dependent compressed files. The extracted directories contain Fortran 77 source files, executables for Linux and Windows personal computers, sample input and output, and an information file. Reference: IAEA-NDS-39, Rev. 10 (April 2000). Fortran 77 on IBM PC and compatibles (P00351/MNYCP/02) with portability to DEC Vax, IBM RS/6000, MAC, and other platforms.

ENEL SpA, Milano, Italy, through the Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France, contributed this code system for thermal-hydraulic transient analysis of Light Water Reactor fuel assemblies and cores. COBRA-EN is an upgraded version of COBRA-3C/MIT. Starting from a steady-state condition in a LWR core or fuel element, the code simulates the thermal-hydraulic transient response to user-supplied changes of the total power, of the outlet pressure and of the inlet enthalpy and mass flow rate.

The thermal-hydraulic homogeneous model of COBRA-EN is based on three partial differential equations that use a subchannel approximation to describe the conservation of mass, energy and momentum vector in axial and lateral directions for the water liquid/vapor mixture and the interaction of the two-phase coolant with the system structures. Optionally, a fourth equation can be added which tracks the vapor mass separately and which, along with the correlations for vapor generation and slip ratio, replaces the subcooled quality and quality/void fraction correlations needed to extend the capabilities of the essentially homogeneous three-equation model. COBRA-EN runs on personal computers under WINDOWS 3.1 or higher. The included executable was created with Digital Visual Fortran V.5 under Windows98. Reference: Report no. 1010/1 (September 1999). Fortran 77; IBM PC (P00507IBMPC00).
 
 

Atomic Energy of Canada Limited, Sheridan Park Research Community, Toronto, Canada, contributed these burnup-dependent ORIGEN-S cross-section libraries for CANDU reactor fuel characterization. In 1995, updated ORIGEN-S cross-section libraries were created as part of a program to upgrade and standardize the computer codes and nuclear data employed for used fuel characterization. The updated cross sections were generated using the WIMS-AECL lattice code and ENDF/B-V and -VI based data to provide cross section consistency between reactor physics codes and used fuel characterization codes. The libraries in this data collection are designed for characterizing used fuel from CANDU pressurized heavy water reactors. Two libraries are provided: one for the standard 28-element fuel bundle design, the other for the 37-element fuel bundle design. The libraries were generated for typical reactor operating conditions and are designed for use with the ORIGEN-S isotope generation and depletion code. The libraries may also be used with the ARP (Automated Rapid Processing) utility of SCALE, which performs interpolation of the library data to create problem-dependent libraries for an ORIGEN-S depletion analysis. ORIGEN-S and ARP are distributed in the CCC-545/SCALE4.4a package. See the SCALE home page for more information: http://www.cped.ornl.gov/scale/scale-home.html. The libraries are distributed in ASCII card-image format for platform compatibility. They are transmitted on two DS/HD DOS diskettes in a self-extracting, compressed Windows file and in a GNU compressed tar file. Reference: RC-1442, COG-I-95-200 (October 1995). ASCII (D00210MNYCP00).
 

RSICC attempts to keep its users/contributors advised of conferences, courses, and symposia in the field of radiation protection, transport, and shielding through this section of the newsletter. Should you be involved in the planning/organization of such events, feel free to send your announcements and calls for papers via email to finchsy@ornl.gov with "conferences" in the subject line. Please include the announcement in its native format as an attachment to the message. If the meeting is on a website, please include the url.

Every attempt is made to ensure that the links provided in the Conference and Calendar sections of this newsletter are correct and live. However, the very nature of the web creates the possibility that the links may become unavailable. In that case, please call or mail the contact provided.
 

The Department of Nuclear Engineering at the University of Tennessee-Knoxville is offering two short courses for radiation transport and criticality safety specialists during Tennessee Industries Week (TIW-36), August 13-17, 2001. The registration fee is $1195 per person for each course.
 

Monte Carlo Analysis is often the method of choice to solve complex problems in criticality safety and radiation shield design. The transport analyst must often choose between Monte Carlo and deterministic methods like discrete ordinates; or the nature of the design problem may dictate that he perform a coupled (Monte Carlo/discrete ordinates) calculation. Therefore, to use Monte Carlo and other transport methods effectively, the analyst must understand the theoretical and computational fundamentals. Rather than use an existing program, it is sometimes advantageous to create a new special-purpose Monte Carlo program. The procedures that are involved in preparing a user-written Monte Carlo program will be described in terms of the classical and conceptually simple straight-ahead, one-speed, slab transmission problem.

Many advanced topics will be included that will permit optimum use of existing computer codes such as MCNP. Special attention will be given to the understanding of the adjoint calculation. Advantages and disadvantages of the adjoint mode versus the forward mode of analysis will be described. The full range of variance reduction techniques will be studied for both forward and adjoint calculations.

The Monte Carlo Method offers the expectation that the true solution to the problem as modeled can be achieved. However, this may lead to a false sense of credibility, in particular when calculations are performed by relatively inexperienced users (the majority of people who use the Monte Carlo method do so only occasionally). Monte Carlo calculations are subject to major errors and/or misinterpretations because currently used statistical measures may be insufficient. Other methods for statistically characterizing Monte Carlo methods will be described.

The relationship of the Monte Carlo method to the other transport methods such as discrete ordinates will be described, including comparisons of computational advantages and disadvantages. The MCNP computer code will be described as required to illustrate the general features of large Monte Carlo computer programs.
 

Nuclear Criticality Safety specialists and technical managers who wish to increase their knowledge and understanding of nuclear criticality safety will be interested in this intensive one-week short course. The topics covered in the course are based primarily on the experience of the five instructors which totals over 120 years of nuclear criticality safety related experience. Such a wealth of experience needs to be shared with the criticality safety community including both new professionals in the field as well as experienced professionals.

The course topics include illustrative applications using the SCALE system developed at Oak Ridge National Laboratory with emphasis on the Monte Carlo code KENO Va, standards, regulations, review of accidents, hand calculation methods, subcritical limits, code validation techniques, emergency response, process upsets and recovery actions, and transient excursion modeling.

The deadline for registration for these courses is July 31, 2001. You may register via the website at http://www.engr.utk.edu/dept/nuclear/TIW.html. For additional information contact Kristin England, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 865-974-5048; email kengland@utk.edu).
 

Date: October 8-13, 2001
Location: Instituto Superior Tecnico, Lisbon, Portugal
Contact: Inquiries should be addressed to Ms. Sandra Oliveira, (tel +351-21-8419092, fax +351-21-8419143, email NRAD2001@CFIF.IST.UTL.PT).
 

The aim of the school is to bring together fundamental issues of nuclear radioactivity and nuclear astrophysics as well as some of the technological applications. The indicators show that sciences with a strong social impact will occupy a predominant position in the turn of the century. Nuclear physics is one of the branches of science that is expected to play an important role in this new era. On the other hand, astrophysics has always been an attraction to the human mind. Here, nuclear physics has an essential part. It is thus timely that the nuclear physics community participates actively, either addressing fundamental questions, or applying its knowledge to astrophysics and practical aspects of our society.

There will be a set of invited talks, addressing the most burning issues within the topics of the school, in a format that will allow the participant to get acquainted with some basic ideas, and simultaneously learn about the most recent developments. There will also be some invited seminars and selected short contributions.

A one-page abstract, in LaTex form, is required for the selection of oral contributions. It must be sent by e-mail to NRAD2001@CFIF.IST.UTL.PT. June 1 is the deadline for the submission of abstracts. The final decision will be communicated before June 30. The registration fee is 35 000 PTE. It includes coffee breaks, the welcome reception, the school banquet and a copy of the proceedings. Payment must be done on arrival. The deadline for registration is July 31.
 

The Visual Editor is a powerful visualization tool that can be used to rapidly create complex Monte Carlo N Particle (MCNP 4C) geometry models, including lattices, universes, fills, and other geometrical transformations. The Visual Editor can:
 

Display MCNP 4C geometries in multiple plot windows.
Create surfaces and cells to build a geometry.
Create materials using the local xsdir file.
Store commonly used materials in a material library.
Sub-divide large cells into smaller cells.
Full geometry capabilities including universes and lattices.
Interactively set cell importances from the plot window.
Display source points and collision points in the plot window.

A three-day class is to be held October 8-10, 2001, in Richland, Washington. This class will only focus on the use of the visual editor. Users should already be familiar with the use of MCNP. Computer demonstrations and exercises will focus on creating and interrogating input files with the Visual Editor. Demonstrations of advanced visualization work using MCNP will also be made. The class will be taught on Pentium computers running the Linux operating system or Windows NT version if it is working by then. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. Further information on this class can be located at: http://www.pnl.gov/eshs/software/ved/class2.html, or by contacting: Randy Schwarz at 509-372-4042 or email: randy.schwarz@pnl.gov.
 

The SCALE staff at ORNL will be offering two fall training courses this year. The courses will emphasize hands-on experience solving practical problems on PCs. There will be workgroups of two persons each. No prior experience in the use of SCALE is required to attend. The registration fee is $1800 for one course or $2700 for both fall courses ($300 discount if you register at least one month before the course). A copy of the SCALE software and manual on CD may be obtained directly from RSICC for an additional fee of $450 payable to RSICC. Registrations will be accepted on a first-come basis. Registration forms submitted directly from the Web are preferred. Registration via fax (815-327-6460, yes, the fax area code is different!) or e-mailing Kay Lichtenwalter at lichtenwalsk@ornl.gov is also acceptable. The registration fee must be paid by check, traveler's checks, or credit card (VISA or MasterCard only).

Class size is limited and courses are subject to cancellation if minimum enrollment is not obtained one month prior to the course. Course fees are refundable up to one month before each class. Classes are cosponsored by RSICC. Foreign nationals must register at least six weeks in advance. For further information, contact Kay at 865-574-9213 or visit the web, http://www.cped.ornl.gov/scale/ trcourse.html.
 
 

SCALE Shielding and Source Terms Course (October 15-19, 2001)

The SCALE Shielding and Source Terms Course emphasizes SAS2 and ORIGEN-ARP (depletion/source-term generation) and SAS3 and SAS4 using MORSE-SGC (3-D Monte Carlo neutron/gamma shielding). It also covers SAS1/XSDRNPM (1-D neutron/gamma shielding) and QADS/QAD-CGGP (3-D point kernel gamma shielding).
 

SCALE KENO-Va Criticality Course (October 22-26, 2001)

The SCALE KENO V.a Criticality Course focuses on KENO V.a and the associated criticality analysis sequences in CSAS. KENO V.a is a widely used 3-D multigroup Monte Carlo criticality safety analysis code that has been in use for approximately 15 years. It is a fast, easy-to-use code that allows users to build complex geometry models using basic geometrical bodies of cuboids, spheres, cylinders, hemispheres, and hemicylinders. Two-dimensional color plots of the geometry model can be generated.
 
 

Advanced Training Course on PENELOPE-2000 - Physics, Code Structure and Operation to be held for 3 days, the latter half of November (date to be announced later) in Paris, France. Details of the course and participation form can be accessed in http://www.nea.fr/html/dbprog/penelope2001-1.html.

If you are interested in participating, please send the completed form on the web site by end of July 2001. The course will be taught by the code authors F. Salvat, J.M. Fernandez-Varea, and J. Sempau.

PENELOPE performs Monte Carlo simulation of coupled electron-photon transport in arbitrary materials. A mixed procedure is used for the simulation of electron and positron interactions (elastic scattering, inelastic scattering and bremsstrahlung emission), in which 'hard' events (i.e. those with deflection angle and/or energy loss larger than pre-selected cutoffs) are simulated in a detailed way, while 'soft' interactions are calculated from multiple scattering approaches. Photon interactions (Rayleigh scattering, Compton scattering, photoelectric effect and electron-positron pair production) are simulated in a detailed way.
 

The Seventh International Radiopharmaceutical Dosimetry Symposium will be held in Nashville, TN, April 17-19, 2002. Six of these interesting and important meetings have been held approximately every 5 years since 1970, with distribution of published proceedings. Most previous meetings were held in Oak Ridge, TN and were organized by the Radiation Internal Dose Information Center. Despite the decline in funding and staffing for this center, it was decided that this important symposium series should continue. Due to continued interest in the international community the series will continue approximately every 2 years, alternating between a U.S. and European site.

All announcements and other mailings for this meeting will be done electronically (no paper mail will be sent). A call for abstracts (also electronic) will go out in a few months, with authors notified of outcome in approximately October of this year. Contributors will be required to bring an electronic version of their manuscript to the meeting in April 2002; early plans are to have the proceedings published as a supplement to the Journal of Nuclear Medicine. You can contact Michael Stabin (michael.g.stabin@vanderbilt.edu) if you have questions.
 

8th International Training Course/Workshop on Methodologies for Particle Transport Simulation of Nuclear Systems (Design, Dosimetry & Shielding), June 25-29, 2001, University Park, PA. Contact: Prof. Ali Haghighat ( tel 814-865-0039, email haghighat@psu.edu, url http://psttg.mne.psu.edu/wshop02/wshop02.html).

July 2001

ANS Executive Conference on Nuclear Facility Decommissioning and Used Fuel Management, July 8-12, 2001, Ledyard, CT. Contact: Russell Mellor, general chair (tel 860-267-3690, fax 860-267-3535, email ramellor@aol.com).

August 2001

Monte Carlo Analysis, Aug. 13-17, 2001, Knoxville, TN, a short course by the Univ. of Tennessee. Contact: Kristin England, Univ. of Tennessee, Knoxville (tel 865-974-5048, email utne@tennessee.edu, url http://www.engr.utk.edu/dept/nuclear/TIW.html).

Nuclear Criticality Safety, Aug. 13-17, 2001, Knoxville, TN, a short course by the Univ. of Tennessee. Contact: Kristin England, Univ. of Tennessee, Knoxville (tel 865-974-5048, email utne@tennessee.edu, url http://www.engr.utk.edu/dept/nuclear/TIW.html).

U.S. Women in Nuclear, Aug. 19-21, 2001, St. Petersburg Beach, FL, sponsored by the Nuclear Energy Institute. Contact: Katie Hart, NEI (tel 202-739-8077, fax 202-785-4019, email kgh@nei.org; url www.nei.org).

September 2001

International Conference on Topical Issues in Nuclear Safety, Sept. 3-6, 2001, Vienna, Austria, sponsored by the International Atomic Energy Agency. Contact: IAEA (tel +43-1-2600-21270, fax +43-1-2600-29610, email official.mail@iaea.org, url www.iaea.org).

13th International Symposium on the Packaging and Transportation of Radioactive Materials (PATRAM 2001), Sept. 3-7, 2001, Chicago, IL, sponsored by the U.S. Dept. of Energy. Contact Institute of Nuclear Materials Management (tel 847-480-6342, fax 847-480-9282, email rairth@patram.com, url www.patram.org).

M&C 2001 Annual Meeting - Special Session: Variance Reduction for Monte Carlo Criticality Simulations, Sept. 9-13, 2001, Salt Lake City, UT. Contact: Dr. Bojan Petrovic, (tel 412-256-1295, fax 412-256-2444, email PetrovB@westinghouse.com, url http://www.srv.net/~ians/MC2001).

M&C 2001 - International Meeting on Mathematical Methods for Nuclear Applications, Sept. 9-13, 2001, Salt Lake City, UT. Contact: Jeff Borkowski, technical program chair (tel 208-522-1060, fax 208-522-1187, email jeff@soa.com, url www.srv.net/~ians/MC2001/).

Second International Conference on Inertial Fusion Science and Applications (IFSA '01), Sept. 10-14, 2001, Kyoto, Japan, sponsored by the Institute of Laser Engineering and others, and cosponsored by ANS. Contact: ILE (email ifsa01@ile.osaka-u.ac.jp, url www.ile.osaka-u.ac.jp/ifsa2001/top.html).

Eighth International Conference on Radioactive Waste Management and Environmental Remediation (ICEM '01), Sept. 30-Oct. 4, 2001, Bruges, Belgium, sponsored by the American Society of Mechanical Engineers and others. Contact: Donna McComb, (tel 520-292-5652, fax 520-292-9080, email dmccomb@laser-options.com, url www.icemcomf.com).

October 2001

7th Annual Workshop on Monte Carlo Simulation of Radiotherapy Treatment Sources using the OMEGA/BEAM Code System, Oct. 1-4, 2001, National Research Council of Canada, Ottawa, Canada. Contact: Blake Walters (tel 613-993-2715, fax 613-952-9865, e-mail bwalters@irs.phy.nrc.ca, url www.irs.inms.nrc.ca/inms/irs/BEAM/beamhome.html).

November 2001

Actinides Conference, Nov. 4-9, 2001, Hayama, Japan. Contact: Dr. T. Ogawa, Secretary for Actinides-2001 (fax +81 29 282 5922, email actq@act2001.tokai.jaeri.go.jp, url http://act2001.tokai.jaeri.go.jp/).

ANS Nuclear Criticality Safety Division Embedded Topical Meeting "Practical Implementation of Nuclear Criticality Safety," Nov. 11-15, 2001, Reno, NV. Contact: (email topical@ncsd.ans.org; url, http://ncsd.ans.org/topical/).

The 5th KEK Topical Conference - Frontiers in Flavor Physics, Nov. 20-22, 2001, KEK, Tsukuba, Japan. Contact: Dr. Sakue Yamada, Chairman (email kektc5@kek.jp, url http://kektc5.kek.jp).

Advanced Training Course on PENELOPE-2000 - Physics, Code Structure and Operation, 3-day course date to be announced later, Paris, France. Contact: Enrico Sartori (tel +33 1 45 24 10 72 or 78, fax +33 1 45 24 11 10 or 28, email sartori@nea.fr, url http://www.nea.fr/html/dbprog/penelope2001-1.html).

March 2002

Hardened Electronics and Radiation Technology (HEART) Conference, Mar. 11-15, 2002, Monterey, CA. Contact: Thomas Stringer, chair (tel 719-599-1719, fax 719-599-1991).

June 2002

Topical Meeting: Industrial Radiation and Radioisotope Measurement Applications IRRMA-V A Class IV Topical, June 9-14, 2002, Bologna, Italy, co-sponsored by the American Nuclear Society. Contact: Prof. Jorge Fernandez (Chair) (e-mail: jorge.fernandez@mail.ing.unibo.it).

October 2002

First Asian and Oceanic Congress for Radiation Protection (AOCRP-1), Oct. 20-24, 2002, Seoul, Korea, sponsored by the Korean Association for Radiation Protection (KARP). Contact: Dr. Myung-Jae SONG (tel +82-42-870-0202, fax +82-42-870-0269, email mjsong@khnp.co.kr; url www.aocrp-1.com).
 
 

The following literature cited has been reviewed and placed in the RSICC Information Storage and Retrieval Information System (SARIS), now searchable on the RSICC web server (http://www-rsicc.ornl.gov/SARIS.html). This early announcement is made as a service to the nuclear sciences community. Copies of the literature are not distributed by RSICC. They may generally be obtained from the author or from a documentation center such as the National Technical Information Service (NTIS), Department of Commerce, Springfield, Virginia 22161. For literature listed as available from INIS contact INIS Clearinghouse, International Atomic Energy Agency, P.O. Box 100, A-1400 Vienna.
 

Nuclear Systems Literature (Shielding, Safety, Materials)

J. Nucl. Mater., 288, 87-91 . . . Thermal Conductivity of U₃O₈ from 300 to 1100 K. . . . Pillai, C.G.S.; Dua, A.K.; Raj, P. . . . February 2001 . . . Bhabha Atomic Research Centre, Mumbai, India.

J. Nucl. Mater., 288, 92-99 . . . A Mechanism for the Sintered Density Decrease of UO₂-Gd₂O₃ Pellets Under an Oxidizing Atmosphere. . . .Song, K.W.; Kim, K.S.; Yang, J.H.; Kang, K.W.; Jung, Y.H. . . . February 2001 . . . Korea Atomic Energy Research Institute, Daejon, South Korea.

J. Nucl. Mater., 288, 100-129 . . . Thermodynamic Modelling of the C-U and B-U Binary Systems. . . . Chevalier, P.Y.; Fischer, E. . . . February 2001 . . . Thermodata, INPG-CNRS, UMS THERMA, Saint Martin d'Heres Cedex, France.

J. Nucl. Mater., 288, 130-136 . . . Cracks as Sink of Irradiation Created Point Defects. . . . Sarce, A. . . . February 2001 . . . Comision Nacional de Energia Atomica, Buenos Aires, Argentina.

J. Nucl. Mater., 288, 137-147 . . . On the Role of Grain Boundary Diffusion in Fission Gas Release. . . . Olander, D.R.; Van Uffelen, P. . . . February 2001 . . . University of California, Berkeley, CA; SCK-CEN, Mol, Belgium.

J. Nucl. Mater., 288, 148-152 . . . O₂ Erosion of Graphite Tile Substrates. . . . Davis, J.W.; Hamilton, C.G.; Haasz, A.A. . . . February 2001 . . . University of Toronto Institute for Aerospace Studies, Toronto, Ontario, Canada.

J. Nucl. Mater., 288, 153-162 . . . Evaluation of Chemical Erosion Data for Carbon Materials at High Ion Fluxes Using Bayesian Probability Theory. . . . Dose, V.; Preuss, R.; Roth, J. . . . February 2001 . . . Max-Planck-Institut fur Plasmaphysik, Garching Bei Muchen, Germany.

J. Nucl. Mater., 288, 163-169 . . . Effects of Temperature and Contact Stress on the Sliding Wear of Ni-Base Deloro 50 Hardfacing Alloy. . . . Kim, S-J.; Kim, J-K. . . . February 2001 . . . Hanyang University, Seoul, South Korea.

J. Nucl. Mater., 288, 170-178 . . . Tritium Depth Profiles in Graphite and Carbon Fibre Composite Material Exposed to Tokamak Plasmas. . . . Penzhorn, R.-D.; Bekris, N.; Berndt, U.; Coad, J.P.; Ziegler, H.; Nagele, W. . . . February 2001 . . . Tritium Laboratory, Karlsruhe, Germany; JET Joint Undertaking, Oxfordshire, UK; Hot Cells, Karlsruhe, Germany.

J. Nucl. Mater., 288, 179-186 . . . Stress Corrosion Cracking on Irradiated 316 Stainless Steel. . . . Furutani, G.; Nakajima, N.; Konishi, T.; Kodama, M. . . . February 2001 . . . Institute of Nuclear Safety System Inc., Fukui-ken, Japan; Nippon Nuclear Fuel Development Co., Ltd., Ibaraki, Japan.

J. Nucl. Mater., 288, 187-196 . . . Studies on Hydrogen Permeability of 2.25% Cr-1% Mo Ferritic Steel: Correlation With Microstructure. . . . Parvathavarthini, N.; Saroja, S.; Dayal, R.K.; Khatak, H.S. . . . February 2001 . . . Indira Gandhi Centre for Atomic Research, Kalpakkam, India.

J. Nucl. Mater., 288, 197-201 . . . A Fracture Mechanics Analysis of the PWR Nuclear Power Plant Reactor Pressure Vessel Beltline Weld. . . . Young, L-J. . . . February 2001 . . . Chung-Hua University, Taiwan, Republic of China.

J. Nucl. Mater., 288, 202-207 . . . The Effects of Tungsten Addition on the Microstructural Stability of 9Cr-Mo Steels. . . . Hong, S.G.; Lee, W.B.; Park, C.G. . . . February 2001 . . . Pohang University of Science and Technology, Kyungbuk, South Korea.

J. Nucl. Mater., 288, 208-216 . . . Heavy-Ion Irradiation Effects on Structures and Acid Dissolution of Pyrochlores. . . . Begg, B.D.; Hess, N.J.; Weber, W.J.; Devanathan, R.; Icenhower, J.P.; Thevuthasan, S.; McGrail, B.P. . . . February 2001 . . . Pacific Northwest National Laboratory, Richland, WA.

J. Nucl. Mater., 288, 217-221 . . . The Sn-Ti-Zr System: Equilibrium Phases at 900 Degrees C. . . . Arico, S.F.; Gribaudo, L.M. . . . February 2001 . . . Comision Nacional de Energia Atomica, Buenos Aires, Argentina.

J. Nucl. Mater., 288, 222-232 . . . Microstructure and Mechanical Properties of Inconel 625 Superalloy. . . . Shankar, V.; Bhanu Sankara Rao, K.; Mannan, S.L. . . . February 2001 . . . Indira Gandhi Center for Atomic Research, Kalpakkam, India.

J. Nucl. Mater., 288, 233-236 . . . Some Aspects of the Use of ZrN as an Inert Matrix for Actinide Fuels. . . . Burghartz, M.; Ledergerber, G.; Hein, H.; van der Laan, R.R.; Konings, R.J.M. . . . February 2001 . . . Paul Scherrer Institute, Villigen PSI, Switzerland; Kernkraftwerk Leibstadt AG, Leibstadt, Switzerland; NRG, Petten, The Netherlands; European Commission, Joint Research Centre, Karlsruhe, Germany.

J. Nucl. Mater., 288, 237-240 . . . Influence of Precipitate Density on the Nodular Corrosion Resistance of Zr-Sn-Fe-Cr Alloys at 500C. . . . Charquet, D. . . . February 2001 . . . Centre de Recherches d'Ugine, Ugine, France.

J. Nucl. Mater., 288, 241-247 . . . Raman Spectra of Tetragonal Zirconia: Powder to Zircaloy Oxide Frequency Shift. . . . Barberis, P.; Corolleur-Thomas, G.; Guinebretiere, R.; Merle-Majean, T.; Mirgorodsky, A.; Quintard, P. . . . February 2001 . . . CEZUS, Ugine Cedex, France; Laboratoire de Science des Procedes Ceramiques, Limoges, France.

J. Nucl. Mater., 289, 219-226 . . . Preliminary Study of Irradiation Effects on Thorium Phosphate-Diphosphate. . . . Pichot, E.; Dacheux, N.; Emery, J.; Chaumont, J.; Brandel, V.; Genet, M. . . . March 2001 . . . Universite de Paris-Sud, Orsay Cedex, France; Universite du Maine, Le Mans, France.

J. Nucl. Mater., 289, 227-242 . . . Investigation of Models to Predict the Corrosion of Steels in Flowing Liquid Lead Alloys. . . . Balbaud-Celerier, F.; Barbier, F. . . . March 2001 . . . d'Electrochimie et de Chimie des Fluides, Gif-sur-Yvette, France.

J. Nucl. Mater., 289, 243-246 . . . Gibbs Energy of Formation of Ba(OH)₂ Vapor Species Using the Transpiration Technique. . . . Ali (Basu), M.; Mishra, R.; Kerkar, A.S.; Bharadwaj, S.R.; Das, D. . . . March 2001 . . . Bhabha Atomic Research Centre, Mumbai, India.

J. Nucl. Mater., 289, 247-253 . . . Short-Time Creep and Rupture Tests on High Burnup Fuel Rod Cladding. . . . Goll, W.; Spilker, H.; Toscano, E.H. . . . March 2001. . . Siemens Nuclear Power GmbH, Erlangen, Germany; Gesellschaft fur Nuklear-Behalter mbH, Essen, Germany; European Commission Joint Research Centre at Karlsruhe, Karlsruhe, Germany.

J. Nucl. Mater., 289, 254-262 . . . Kinetics of Uranium Release from Synroc Phases. . . . Zhang, Y.; Hart, K.P.; Bourcier, W.L.; Day, R.A.; Colella, M.; Thomas, B.; Aly, Z.; Jostsons, A. . . March 2001 . . . Australian Nuclear Science and Technology Organisation, Menai, Australia; Lawrence Livermore National Laboratory, Livermore, CA.

J. Nucl. Mater., 289, 263-269 . . . The Effect of Manganese on the Strain-Induced Martensitic Transformation and High Temperature Wear Resistance of Fe-20Cr-1C-1Si Hardfacing Alloy. . . . Kim, J-K.; Kim, G-M.; Kim, S-J. . . . March 2001 . . . Hanyang University, Seoul, South Korea.

J. Nucl. Mater., 289, 270-280 . . . Oxygen Potential and Defect Structure of the Solid Solution, Mg-Gd-UO₂. . . . Fujino, T.; Sato, N.; Yamada, K.; Okazaki, M.; Fukuda, K.; Serizawa, H.; Shiratori, T. . . . March 2001 . . . Tohoku University, Sendai, Japan; Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

J. Nucl. Mater., 289, 281-290 . . . Dissolution Behaviour of Magnetite Film Formed Over Carbon Steel in Dilute Organic Acid Media. . . . Prince, A.A.M.; Velmurugan, S.; Narasimhan, S.V.; Ramech, C.; Murugesan, N.; Raghavan, P.S.; Gopalan, R. . . March 2001 . . . Madras Christian College, Tamil Nadu, India; BARC, Tamil Nadu, India; IGCAR, Tamil Nadu, India.

J. Nucl. Mater., 289, 291-302 . . . Co-Permeation of Deuterium and Hydrogen Through Pd. . . . Kizu, K.; Pisarev, A.; Tanabe, T. . . . March 2001 . . . Nagoya University, Nagoya, Japan; Moscow State Engineering and Physics Institute (Technical University), Moscow, Russian Federation

J. Nucl. Mater., 289, 303-307 . . . Lithium Titanate Pebbles Reprocessing by Wet Chemistry. . . . Alvani, C.; Carconi, P.L.; Casadio, S.; Contini, V.; Dibartolomeo, A.; Pierdominici, F.; Deptula, A.; Lagos, S.; Nannetti, C.A. . . March 2001 . . . ENEA, Rome, Italy; Institute of Nuclear Chemistry and Technology, Warsaw, Poland; CCHEN, CEN La Reina, Santiago, Chile.

J. Nucl. Mater., 289, 308-314 . . . Absorption of Molten Fluoride Salts in Glassy Carbon, Pyrographite and Hastelloy B. . . . Vacik, J.; Naramoto, H.; Cervena, J.; Hnatowicz, V.; Peka, I.; Fink, D. . . . March 2001 . . . Japan Atomic Energy Research Institute, Gunma, Japan; Academy of Sciences of Czech Republic, Rez, Czech Republic, Nuclear Research Institute plc, Rez near Prague, Czech Republic, Hahn-Meitner-Institute, Berlin, Germany.

J. Nucl. Mater., 289, 315-328 . . . Pre-Transition Oxidation Behaviour of Pre-Hydrided Zircaloy-2. . . . Oskarsson, M.; Ahlberg, E.; Sodervall, U.; Andersson, U.; Pettersson, K. . . . March 2001 . . . Royal Institute of Technology, Stockholm, Sweden; University of Goteborg, Goteborg, Sweden; Chalmers University of Technology, Goteborg, Sweden.

J. Nucl. Mater., 289, 329-333 . . . Thermophysical Properties of Zirconium Hydride and Uranium-Zirconium Hydride. . . . Tsuchiya, B.; Huang, J.; Konashi, K.; Teshigawara, M.; Yamawaki, M. . . . March 2001 . . . Tohoku University, Ibaraki-ken, Japan; Japan Atomic Energy Research Institute, Ibaraki-ken, Japan; University of Tokyo, Tokyo, Japan.

J. Nucl. Mater., 289, 334-337 . . . Effect of Molybdenum on Electron Radiation Damage of Zr-Base Alloys. . . . Lee, J.H.; Hwang, S.K.; Yasuda, K.; Kinoshita, C. . . . March 2001 . . . Inha University, Inchon, South Korea; Kyushu University, Fukuoka, Japan.

J. Nucl. Mater., 289, 338-341 . . . Shadow Corrosion or Crevice Corrosion? . . . Garzarolli, F.; Hoffmann, P.B.; Seibold, A. . . . March 2001 . . . Framatome ANP, Erlangen, Germany.

J. Nucl. Mater., 289, 342-345 . . . Formation of Nitrides at the Surface of U-Zr Alloys. . . . Akabori, M.; Itoh, A.; Ogawa, T. . . . March 2001 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

J. Nucl. Mater., 294, 1-7 . . . Heat Capacity Measurements on Unirradiated and Irradiated Fuel Pellets. . . . Amaya, M.; Une, K.; Minato, K. . . . April 2001 . . . Nippon Nuclear Fuel Development Co., Ltd., Ibaraki-ken, Japan; Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

J. Nucl. Mater., 294, 8-12 . . . Phase Equilibria in the UO₂-PuO₂ System Under a Temperature Gradient. . . . Kleykamp, H. . . . April 2001 . . . Forschungszentrum Karlsruhe, Karlsruhe, Germany.

J. Nucl. Mater., 294, 13-17 . . . An Investigation of the Pu Migration Phenomena During Irradiation in Fast Reactor. . . . Ishii, T.; Asaga, T. . . . April 2001 . . . Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan.

J. Nucl. Mater., 294, 18-23 . . . Thermochemical Data and Modelling for Ex-Vessel Corium Behaviour During a Severe Accident. . . . Cordfunke, E.H.P.; Huntelaar, M.E.; Funke, F.; Koch, M.K.; Kortz, Ch.; Mason, P.K.; Mignanelli, M.A.; Newland, M.S. . . . April 2001 . . . Netherlands Energy Research Foundation, Petten, The Netherlands; Siemens, Erlangen, Germany; Ruhr University Bochum, Bochum, Germany; AEA Technology plc, Oxfordshire, United Kingdom.

J. Nucl. Mater., 294, 24-27 . . . Carbothermic Synthesis of (Cm,Pu)N. . . . Takano, M.; Itoh, A.; Akabori, M.; Ogawa, T.; Numata, M.; Okamoto, H. . . . April 2001 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

J. Nucl. Mater., 294, 28-31 . . . Thermal Properties of Hydride Fuel 45% U-ZrH_1.6. . . . Kakiuchi, K.; Itagaki, N.; Furuya, T.; Hattori, T.; Nakazono, Y.; Ono, F.; Yamaguchi, K.; Yamawaki, M. . . . April 2001 . . . Nuclear Fuel Industries Ltd., Ibaraki-ken, Japan; Tokyo Electric Power Company, Yokohama, Japan; The University of Tokyo, Tokyo, Japan.

J. Nucl. Mater., 294, 32-38 . . . A Qualitative Comparison of Barium Behaviour in the PHEBUS FPT0 Test and Analytical Tests. . . . Dubourg, R.; Taylor, P. . . . April 2001 . . . Institut de Protection et de Surete, Nucleaire, CEA/Cadarache, France.

J. Nucl. Mater., 294, 39-44 . . . Fission Gas Release and Volume Diffusion Enthalpy in UO₂ Irradiated at Low and High Burnup. . . . Hiernaut, J.P.; Ronchi, C. . . . April 2001 . . . European Commission Institute for Transuranium Elements, Karlsruhe, Germany.

J. Nucl. Mater., 294, 45-52 . . . Migration Behaviour of Iodine in Nuclear Fuel. . . . Hocking, W.H.; Verrall, R.A.; Muir, I.J. . . . April 2001 . . . Atomic Energy of Canada Ltd., Chalk River, Ont., Canada.

J. Nucl. Mater., 294, 53-58 . . . Thermodynamic Systematics of the Formation of Liquid Alloys of f-Elements with Bismuth. . . . Yamana, H.; Sheng, J.; Kawamoto, K.; Moriyama, H. . . . April 2001 . . . Kyoto University, Osaka, Japan.

J. Nucl. Mater., 294, 59-63 . . . High-Temperature, Knudsen Cell-Mass Spectroscopic Studies on Lanthanum Oxide/Uranium Dioxide Solid Solutions. . . . Sunder, S.; McEachern, R.; LeBlanc, J.C. . . . April 2001 . . . Atomic Energy of Canada Limited, Chalk River, Ontario, Canada.

J. Nucl. Mater., 294, 64-68 . . . The Modelling of Fuel Volatilisation in Accident Conditions. . . . Manenc, H.; Mason, P.K.; Kissane, M.P. . . . April 2001 . . . Institut de Protection et de Surete Nucleaire, CEA/Cadarache, France; AEA Technology, United Kingdom.

J. Nucl. Mater., 294, 69-76 . . . Vaporization Chemistry of Hypo-Stoichiometric (U,Pu)O₂. . . . Viswanathan, R.; Krishnaiah, M.V. . . . April 2001 . . . Indira Gandhi Centre for Atomic Research, Tamil Nadu, India.

J. Nucl. Mater., 294, 77-83 . . . Thermodynamic Study of Liquid Lithium-Lead Alloys Using the EMF Method. . . . Gasior, W.; Moser, Z. . . . April 2001 . . . Polish Academy of Sciences, Krakow, Poland.

J. Nucl. Mater., 294, 85-87 . . . Mass Spectrometric Study of UO₂-ZrO₂ Pseudo-Binary System. . . . Baichi, M.; Chatillon, C.; Gueneau, C.; Chatain, S. . . . April 2001 . . . DRN/DEC/SECI/LARA, Grenoble, France; Laboratoire de Thermodynamique et de Physico-Chimie Metallurgiques, Saint Martin d'Heres, France; DCC/DPE/SPCP/LEPCA, Gif-sur-Yvette, France.

J. Nucl. Mater., 294, 88-93 . . . Selected Thermal Properties of Beryllium and Phase Equilibria in Berylllium Systems Relevant for Nuclear Fusion Reactor Blankets. . . . Kleykamp, H. . . . April 2001 . . . Forschungszentrum Karlsruhe, Karlsruhe, Germany.

J. Nucl. Mater., 294, 94-98 . . . Thermal Properties of Zirconium Hydride. . . . Yamanaka, S.; Yamada, K.; Kurosaki, K.; Uno, M.; Takeda, K.; Anada, H.; Matsuda, T.; Kobayashi, S. . . . April 2001 . . . Osaka University, Osaka, Japan; Sumitomo Metal Industries, Ltd., Amagasaki, Japan; Nuclear Fuel Industries, Ltd., Osaka, Japan.

J. Nucl. Mater., 294, 99-103 . . . Thermophysical Properties of BaUO₃. . . . Yamanaka, S.; Kurosaki, K.; Matsuda, T.; Uno, M. . . . April 2001 . . . Osaka University, Osaka, Japan.

J. Nucl. Mater., 294, 104-111 . . . Thermodynamics of (Mg,Ce,U)O_2+x(x0) Solid Solutions. . . . Funjino, T.; Park, K.; Sato, N.; Yamada, M. . . . April 2001 . . . Tohoku University, Sendai, Japan; Kyunghee University, Suwon, South Korea.

J. Nucl. Mater., 294, 112-118 . . . Thermodynamic Studies of ThGa₂. . . . Prabhakara Reddy, B.; Kandan, R.; Babu, R.; Nagarajan, K.; Vasudeva Rao, P.R. . . . April 2001 . . . Indira Gandhi Centre for Atomic Research, Tamil Nadu, India.

J. Nucl. Mater., 294, 119-122 . . . Some Properties of a Lead Vanado-Iodoapatite Pb₁₀(VO₄)₆I₂. . . . Uno, M.; Shinohara, M.; Kurosaki, K.; Yamanaka, S. . . . April 2001 . . . Osaka University, Osaka, Japan.

J. Nucl. Mater., 294, 123-129 . . . Thermodynamic Evaluation of the Quaternary U-Pu-Zr-Fe System - Assessment of Cladding Temperature Limits of Metallic Fuel in a Fast Reactor. . . . Kurata, M.; Nakamura, K.; Ogata, T. . . . April 2001 . . . Central Research Institute of Electric Power Industry, Tokyo, Japan.

J. Nucl. Mater., 294, 130-134 . . . Thermal Expansion of (Ca_1-xPu_x)TiO₃. . . . Sato, T.; Hanajiri, Y.; Yamashita, T.; Matsui, T.; Nagasaki, T. . . . April 2001 . . . Nagoya University, Nagoya, Japan; Japan Atomic Energy Research Institute, Ibaraki, Japan.

J. Nucl. Mater., 294, 135-140 . . . Enthalpy and Heat Capacity of (Ca_1-xPu_x)TiO₃(x=0 and 0.20). . . . Sato, T.; Yamazaki, S.; Yamashita, T.; Matsui, T.; Nagasaki, T. . . . April 2001 . . . Nagoya University, Nagoya, Japan; Japan Atomic Energy Research Institute, Ibaraki, Japan.

J. Nucl. Mater., 294, 141-147 . . . The Corrosion of Alloy 690 in High-Temperature Aqueous Media - Thermodynamic Considerations. . . . Lemire, R.J.; McRae, G.A. . . . April 2001 . . . AECL, Chalk River, Ontario, Canada.

J. Nucl. Mater., 294, 148-153 . . . The Oxidation Kinetics and the Structure of the Oxide Film on Zircaloy Before and After the Kinetic Transition. . . . Arima, T.; Masuzumi, T.; Furuya, H.; Idemitsu, K.; Inagaki, Y. . . . April 2001 . . . Kyushu University, Fukuka, Japan.

J. Nucl. Mater., 294, 154-159 . . . Thermodynamic Analysis of Chemical States of Fission Products in Uranium-Zirconium Hydride Fuel. . . . Huang, J.; Tsuchiya, B.; Konashi, K.; Yamawaki, M. . . . April 2001 . . . Tohoku University, Ibaraki-ken, Japan; University of Tokyo, Tokyo, Japan.

J. Nucl. Mater., 294, 160-167 . . . Molecular Dynamics Study of Mixed Oxide Fuel. . . . Kurosaki, K.; Yamada, K.; Uno, M.; Yamanaka, S.; Yamamoto, K.; Namekawa, T. . . . April 2001 . . . Osaka University, Osaka, Japan; Japan Nuclear Cycle Development Institute, Ibaraki, Japan.

J. Nucl. Mater., 294, 168-174 . . . X-Ray Photoelectron Spectroscopy on Uranium Oxides: A Comparison Between Bulk and Thin Layers. . . . Van Den Berghe, S.; Miserque, F.; Gouder, T.; Gaudreau, B.; Verwerft, M. . . . April 2001 . . . SCK-CEN, Mol, Belgium; European Commission, Karlsruhe, Germany; Inversite de Limoges, Limoges, Cedex, France.

J. Nucl. Mater., 294, 175-178 . . . Application of a New Thermochemical Measurement Method for Nuclear Materials at Temperatures Beyond 3000 K. . . . Hastie, J.W.; Bonnell, D.W.; Schenck, P.K. . . . April 2001 . . . National Institute of Science and Technology, Gaithersburg, MD.

J. Nucl. Mater., 294, 179-182 . . . Thermal Properties of Mo₃Te₄. . . . Kurosaki, K.; Kosuga, A.; Uno, M.; Yamanaka, S. . . . April 2001 . . . Osaka University, Osaka, Japan.

J. Nucl. Mater., 294, 183-187 . . . Thermal Expansion and Solubility Limits of Plutonium-Doped Lanthanum Zirconates. . . . Yamazaki, S.; Yamashita, T.; Matsui, T.; Nagasaki, T. . . . April 2001 . . . Nagoya University, Nagoya, Japan; Japan Atomic Energy Research Institute, Ibaraki, Japan.

J. Nucl. Mater., 294, 188-192 . . . Thermodynamic and Mechanical Properties of Ce_1-xHf_xO₂ (x=0-0.10) Solid Solutions. . . . Nakajima, N.; Mitani, H.; Yamamura, Y.; Tsuji, T. . . . April 2001 . . . Japan Advanced Institute of Science and Technology, Ishikawa, Japan; Nagoya University, Nagoya, Japan.

J. Nucl. Mater., 294, 193-197 . . . Thermal Conductivity of (U,Ce)O₂ With and Without Nd or Zr. . . . Kurosaki, K.; Ohshima, R.; Uno, M.; Yamanaka, S.; Yamamoto, K.; Mamekawa, T. . . . April 2001 . . . Osaka University, Osaka, Japan; Japan Nuclear Cycle Development Institute, Ibaraki, Japan.

J. Nucl. Mater., 294, 198-201 . . . Solubility Limits and Bulk Thermal Expansion of TO₂:Mⁿ⁺ (M= Y³⁺, Sr²⁺ and Ba²⁺). . . . Tyagi, A.K.; Mathews, M.D.; Ramachandran, R. . . . April 2001 . . . Bhabha Atomic Research Center, Mumbai, India.

J. Nucl. Mater., 294, 202-205 . . . Thermoelectric Properties of Rh-Doped Ru₂Si₃ Prepared by Floating Zone Melting Method. . . . Arita, Y.; Mitsuda, S.; Nishi, Y.; Matsui, T.; Nagasaki, T. . . . April 2001 . . . Nagoya University, Nagoya, Japan.

J. Nucl. Mater., 294, 206-208 . . . Thermoelectric Properties of URu₂Si₂ and U₂Ru₃Si₅. . . . Arita, Y.; Terao, K.; Mitsuda, S.; Nishi, Y.; Matsui, T.; Nagasaki, T. . . . April 2001 . . . Nagoya University, Nagoya, Japan.

J. Nucl. Mater., 294, 209-211 . . . Boron Isotope Effects on the Thermoelectric Properties of UB₄ at Low Temperatures. . . . Nishi, Y.; Arita, Y.; Terao, K.; Matsui, T.; Nagasaki, T. . . . April 2001 . . . Nagoya University, Nagoya, Japan.

J. Nucl. Mater., 294, 223-231 . . . Stability of SiC/SiC Fibre Composites Exposed to Li₄SiO₄ and Li₂TiO₃ in Fusion Relevant Conditions. . . . La Barbera, A.; Riccardi, B.; Donato, A.; Nannetti, C.A.; Moreschi, L.F. . . . April 2001 . . . ENEA INN-NUMA, Rome, Italy; EURATOM ENEA, Rome and Camugnao, Italy.

J. Nucl. Mater., 294, 232-240 . . . Thermodynamic Properties of Lanthanide Metals in Liquid Bismuth. . . . Yamana, H.; Sheng, J.; Souda, N.; Moriyama, H. . . . April 2001 . . . Kyoto University, Osaka-fu, Japan.

J. Nucl. Mater., 294, 241-249 . . . Hydrogen Analysis and Slow Strain Rate Test in Ar Gas for Irradiated Austenitic Stainless Steel. . . . Morisawa, J.; Kodama, M.; Yokota, N.; Nakata, K.; Fukuya, K.; Shima, S.; Asano, K. . . . April 2001 . . . Nippon Nuclear Fuel Development Co. Ltd., Ibaraki-ken, Japan; Hitachi Research Laboratory, Ibaraki-ken, Japan; Toshiba Corp., Kanagawa-ken, Japan; Tokyo Electric Power Company, Kanagawa-ken, Japan.

J. Nucl. Mater., 294, 250-255 . . . Mass-Spectrometric Investigation of UO₃(g). . . . Nakajima, K.; Arai, Y. . . . April 2001 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

J. Nucl. Mater., 294, 256-266 . . . Characterization of Plastic Deformation in a Disk Bend Test. . . . Byun, T.S.; Lee, E.H.; Hunn, J.D.; Farrell, K.; Mansur, L.K. . . . April 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 294, 267-273 . . . Numerical Simulation Modeling on the Effects of Grain Boundary Misorientation on Radiation-Induced Solute Segregation in 304 Austenitic Stainless Steels. . . . Duh, T.S.; Kai, J.J.; Chen, F.R.; Wang, L.H. . . . April 2001 . . . National Tsing Hua University, Taiwan, Republic of China.

J. Nucl. Mater., 294, 274-287 . . . The Role of Cu in Displacement Cascades Examined by Molecular Dynamics. . . . Becquart, C.S.; Domain, C.; van Duysen, J.C.; Raulot, J.M. . . . April 2001 . . . Laboratoire de Metallurgie Physique et Genie des Materiaux, Villeneuve d'Ascq, France; EDF-DRD Departement EMA, Moret sur Loing, France.

J. Nucl. Mater., 294, 288-298 . . . Temperature-Dependence of Defect Creation and Clustering by Displacement Cascades in -Zirconium. . . . Gao, F.; Bacon, D.J.; Howe, L.M.; So, C.B. . . . April 2001 . . . The University of Liverpool, Liverpool, UK; AECL, Chalk River Laboratories, Chalk River, Ontario, Canada.

J. Nucl. Mater., 294, 299-304 . . . Observation of Second-Phase Particles in Bulk Zirconium Alloys Using Synchrotron Radiation. . . . Erwin, K.T.; Delaire, O.; Motta, A.T.; Chu, Y.S.; Mancini, D.C.; Birtcher, R.C. . . . April 2001 . . .The Pennsylvania State University, University Park, PA; Argonne National Laboratory, Argonne, IL.

J. Nucl. Mater., 294, 305-314 . . . Study of Surface Modification of Uranium and UFe₂ By Various Surface Analysis Techniques. . . . Bonino, O.; Dugne, O.; Merlet, C.; Gat, E.; Holliger, Ph.; Lahaye, M. . . . April 2001 . . . Laboratorie de Metallographie, Pierrlatte, France; Universite de Montpellier II, Montpellier, France; BIOPHY Research, Marseille, France; CEA Grenoble-DTA/LETI/SCPM, Grenoble, France; CNRS-CECAMA-ICMCB, Pessac, France.

J. Nucl. Mater., 294, 315-329 . . . Multi-Component Gas Transport in the Fuel-to-Clad Gap of Candu Fuels Rods During Severe Accidents. . . . Szpunar, B.; Lewis, B.J.; Arimescu, V.I.; Dickson, R.S.; Dickson, L.W. . . . April 2001 . . . Royal Military College of Canada, Kingston, Ontario, Canada; AECL, Chalk River Laboratories, Chalk River, Ontario, Canada.

J. Nucl. Mater., 294, 330-338 . . . Effect of Plastic Shearing on Damage and Texture on Zircaloy-4 Cladding Tubes: Experimental and Numerical Study. . . . Girard, E.; Guillen, R.; Weisbecker, P.; Francois, M. . . . April 2001 . . . Laboratoire d'Applications des Materiaux a la Mecanique, Saint Nazaire, France; LSG2M Ecole Nationale Superieure des Mines de Nancy Parc de Saurupt, Nancy, France.

J. Nucl. Mater., 294, 339-343 . . . Influence of Low-Temperature Air Oxidation on the Dissolution Behaviour of High Burn-Up LWR Spent Fuel. . . . Serrano, J.A.; Glatz, J.P.; Toscano, E.H.; Barrero, J.; Papaioannou, D. . . . April 2001 . . . Institute for Transuranium Elements, Karlsruhe, Germany; Centro de Investigaciones Energeticas Technologicas y Medioambientales, Madrid, Spain.

J. Nucl. Mater., 294, 344-348 . . . Preparation of Homogeneous (th_0.8U_0.2)O₂ Powders by Mechanical Blending of Th(C₂O₄)₂ ·6H₂O and U(c₂O₄)₂ ·6H₂O Powders. . . . Altas, Y.; Eral, M.; Tel, H. . . . April 2001 . . . Ege University, Bornova-Izmir, Turkey.

Nucl. Eng. Des., 204, 1-27 . . . The Effects of Complexity, of Simplicity and of Scaling in Thermal-Hydraulics. . . . Zuber, N. . . . February 2001 . . . No company.

Nucl. Eng. Des., 204, 29-44 . . . The Analysis of Two-Phase Flow and Heat Transfer Using a Multidimensional, Four Field, Two-Fluid Model. . . . Lahey, Jr., R.T.; Drew, D.A. . . . February 2001 . . . Rensselaer Polytechnic Institute, Troy, NY.

Nucl. Eng. Des., 204, 45-55 . . . Study on Interfacial Structures in Slug Flows Using a Miniaturized Four-Sensor Conductivity Probe. . . . Kim, S.; Fu, X.Y.; Wang, X.; Ishii, M. . . . February 2001 . . . Purdue University, West Lafayette, IN.

Nucl. Eng. Des., 204, 57-67 . . . Impedance Imaging of Two-Phase Flow Field with Mesh Grouping Method. . . . Cho, K.H.; Kim, S.; Lee, Y.J. . . . February 2001 . . . Cheju National University, Cheju, South Korea.

Nucl. Eng. Des., 204, 69-85 . . . Investigation of Vertical Slug Flow with Advanced Two-Phase Flow Instrumentation. . . . Mi, Y.; Ishii, M.; Tsoukalas, L.H. . . . February 2001 . . . Purdue University, West Lafayette, IN.

Nucl. Eng. Des., 204, 87-100 . . . Flow Regime Identification Methodology with Neural Networks and Two-Phase Flow Models. . . . Mi, Y.; Ishii, M.; Tsoukalas, L.H. . . . February 2001 . . . Purdue University, West Lafayette, IN.

Nucl. Eng. Des., 204, 101-115 . . . On the Stability of a One-Dimensional Two-Fluid Model. . . . Song, J.H.; Ishii, M. . . . February 2001 . . . Korea Atomic Energy Research Institute, Taejon, South Korea; Purdue University, West Lafayette, IN.

Nucl. Eng. Des., 204, 117-128 . . . Local Void Fraction and Velocity Field Description in Horizontal Bubbly Flow. . . . Iskandrani, A.; Kohasoy, G. . . . February 2001 . . . University of Wisconsin-Milwaukee, Milwaukee, WI.

Nucl. Eng. Des., 204, 129-142 . . . Modeling and Analysis of Hydrodynamic Instabilities in Two-Phase Flow Using Two-Fluid Model. . . . Zhou, J.; Pokowski, M.Z. . . . February 2001 . . . Rensselaer Polytechnic Institute, Troy, NY.

Nucl. Eng. Des., 204, 143-153 . . . Numerical Investigation of Boiling Regime Transition Mechanism by a Lattice-Boltzmann Model. . . . Yang, Z.L.; Dinh, T.N.; Nourgaliev, R.R.; Seghal, B.R. . . . February 2001 . . . Royal Institute of Technology, Stockholm, Sweden.

Nucl. Eng. Des., 204, 155-166 . . . The Second Gradient Theory: A Tool for the Direct Numerical Simulation of Liquid - Vapor Flows with Phase-Change. . . . Jamet, D.; Lebaigue, O.; Coutris, N.; Delhaye, J.M. . . . February 2001 . . . Commissariat a l'Energie Atomique, Grenoble, France.

Nucl. Eng. Des., 204, 167-175 . . . Oscillations of a Drop in Aerodynamic Levitation. . . . Hervieu, E.; Coutris, N.; Boichon, C. . . . February 2001 . . . Commissariat a l'Energie Atomique, Grenoble, France; Ecole Nationale Superieure de Physique, Saint Martin d'Herres, France.

Nucl. Eng. Des., 204, 177-190 . . . Multi-Dimensional Modelling of Multiphase Flow Physics: High-Speed Nozzle and Jet Flows - A Case Study. . . . Murphy, J.; Schmidt, D.; Wang, S.P.; Corradini, M.L. . . . February 2001 . . . University of Wisconsin, Madison, WI.

Nucl. Eng. Des., 204, 191-203 . . . Thermal Hydraulics of PWRS with Respect to Boron Dilution Phenomena. Experimental Results from the Test Facilities PKL and UPTF. . . . ; Umminger, K. Kastner, W.; Liebert, J.; Mull, T. . . . February 2001 . . . Siemens AG, Erlangen, Germany.

Nucl. Eng. Des., 204, 205-220 . . . Reflooding Experiments with LWR-Type Fuel Rod Simulators in the QUENCH Facility. . . . Sepold, L.; Hofmann, P.; Leiling, W.; Miassoedov, A.; Piel, D.; Schmidt, L.; Steinbruck, M. . . . February 2001 . . . Forschungszentrum Karlsruhe, Karlsruhe, Germany.

Nucl. Eng. Des., 204, 221-232 . . . Reflux Condensation Behavior in a U-Tube Steam Generator With or Without Noncondensables. . . . Liu, T-J. . . . February 2001 . . . Institute of Nuclear Energy Research, Taiwan, Republic of China.

Nucl. Eng. Des., 204, 233-250 . . . Heat and Mass Transfer Models in LWR Containment Systems. . . . Oriolo, F.; Paci, S. . . . February 2001 . . . Universita di Pisa, Pisa, Italy.

Nucl. Eng. Des., 204, 251-265 . . . Modeling of Condensation in Horizontal Tubes. . . . Schaffrath, A.; Krussenberg, A.-K.; Fjodorow, A.; Gocht, U.; Lischke, W. . . . February 2001 . . . Forschungszentrum Rossendorf, Schonfeld-Weissig, Germany; University for Applied Sciences, Zittau, Germany.

Nucl. Eng. Des., 204, 267-284 . . . Experimental Data Base for Containment Thermalhydraulic Analysis . . . Cheng, X.; Bazin, P.; Cornet, P.; Hittner, D.; Jackson, J.D.; Lopez Jimenez, J.; Naviglio, A.; Oriolo, F.; Petzold, H. . . . February 2001 . . . Forschungszentrum Karlruhe, Karlsruhe, Germany; Commisariat a l'Energie Atomique, Grenoble and Saclay, France; Framatome, France; University of Manchester, Manchester, United Kingdom; Medioambientales y Tecnologicas, Spain; Universita di Roma 'La Sapienza,' Italy; Universita degli Studi di Pisa, Pisa, Italy.

Nucl. Eng. Des., 204, 285-298 . . . Influence of the Distribution of Noncondensibles on Passive Containment Condenser Performance in PANDA. . . . Bandurski, T.; Huggenberger, M.; Dreier, J.; Aubert, C.; Putz, F.; Gamble, R.E.; Yadigaroglu, G. . . . February 2001 . . . Paul Scherrer Institut Wuerenlingen & Villigen, Villigen PSI, Switzerland; General Electric Co., San Jose, CA; Swiss Federation Institute of Technology, Zurich, Switzerland.

Nucl. Eng. Des., 204, 299-320 . . . A One-Dimensional Lagrangian Model for Large-Volume Mixing. . . . Christensen, J.; Peterson, P.F. . . . February 2001 . . . University of California, Berkeley, Berkeley, CA.

Nucl. Eng. Des., 204, 321-336 . . . Pressure Suppression Pool Mixing in Passive Advanced BWR Plants. . . . Gamble, R.E.; Nguyen, T.T.; Shiralkar, B.S.; Peterson, P.F.; Greif, R.; Tabata, H. . . . February 2001 . . . GE Nuclear Energy, San Jose, CA; University of California, Berkeley, CA; Japan Atomic Power Co., Tokyo, Japan.

Nucl. Eng. Des., 204, 337-345 . . . Density Stratification from Buoyancy-Driven Exchange Flow Through Horizontal Partitions in a Liquid Tank. . . . Kuhn, S.Z.; Bernardis, R.D.; Lee, C.H.; Peterson, P.F. . . . February 2001 . . . University of California, Berkeley, CA.

Nucl. Eng. Des., 204, 347-359 . . . An Experimental Study on Evaporative Heat Transfer Coefficient and Applications for Passive Cooling of AP600 Steel Containment. . . . Kang, Y.M.; Park, G.C. . . . February 2001 . . . Seoul National University, Seoul, South Korea.

Nucl. Eng. Des., 204, 361-368 . . . Quenching of Hot Oxidizing Surfaces. . . . Davidy, A.; Elias, E.; Okek, S. . . . February 2001 . . . Technion I.I.T., Haifa, Israel; Israel Electric Corporation, Haifa, Israel.

Nucl. Eng. Des., 204, 369-376 . . . Corium Melt Quenching Tests at Low Pressure and Subcooled Water in FARO. . . . Magallon, D.; Huhtiniemi, I. . . . February 2001 . . . European Commission Joint Research Centre, Ispra, Italy.

Nucl. Eng. Des., 204, 377-389 . . . Viscosity Models for Corium Melts. . . . Ramacciotti, M.; Journeau, C.; Sudreau, F.; Cognet, G. . . . February 2001 . . . Commissariat a l'Energie Atomique, St. Paul Lez Durance, France.

Nucl. Eng. Des., 204, 391-400 . . . Insight into Steam Explosions with Corium Melts in KROTOS. . . . Huhtiniemi, I.; Magallon, D. . . . February 2001 . . . CEC Joint Research Center, Ispra, Italy.

Nucl. Eng. Des., 204, 401-412 . . . Model Development for the Calculation of Corium-Ceramic Interaction During Severe Accidents in LWRs. . . . Seiler, J.M.; Labergri, F.; Froment, K.; Valin, F. . . . February 2001 . . . CEA/GRENOBLE, Grenoble, France; CEA/SACLAY, Gif-sur-Yvette, France.

Nucl. Eng. Des., 204, 413-427 . . . Investigation of Natural Convection Heat Transfer to the Cooled Top Boundary of a Heated Pool. . . . Bernaz, L.; Bonnet, J.M.; Seiler, J.M. . . . February 2001 . . . CEA Grenoble, Grenoble, France.

Nucl. Eng. Des., 205, 219-225 . . . Structure Mechanics and Thermal-Hydraulic Behaviour of a PWR Coolant Loop with a Postulated Crack Like Leakage. . . . ; Grebner, H.; Muller, C.; Sievers, J. . . . April 2001 . . . Gesellschaft f. Anlagen- und Reaktorsicherheit (GRS), Cologne, Germany.

Nucl. Eng. Des., 205, 227-240 . . . The FEM Based Calculation of Crack-Tip Strain Rate for Determining the Crack Growth Rate of 304 Stainless Steel in BWR Environments. . . . Lu, P.-C. . . . April 2001 . . . National Lien Ho College of Technology, Miaoli, Taiwan.

Nucl. Eng. Des., 205, 241-249 . . . Statistical Model for the Random Cyclic Strain - Life Relations of 1Cr18Ni9Ti Pipe-Weld Metal Under Temperature of 240C. . . . Zhao, Y.X.; Wang, J.N.; Gao, Q. . . . April 2001 . . . Southwest Jiaotong University, Chengdu, People's Republic of China.

Nucl. Eng. Des., 205, 251-263 . . . An Exact Exit Condition for Multiphase Critical Flow. . . . Lellouche, G.S. . . . April 2001 . . . Technical Data Services, Kenmore, WA.

Nucl. Eng. Des., 205, 265-279 . . . Critical Heat Flux Under Zero Flow Conditions in Vertical Annulus with Uniformly and Non-Uniformly Heated Sections. . . . Chun, S-Y.; Moon, S-K.; Chung, H-J.; Yang, S-K.; Chung, M-K.; Aritomi, M. . . . April 2001 . . . Korea Atomic Energy Research Institute, Taejon, South Korea; Tokyo Institute of Technology, Tokyo, Japan.

Nucl. Eng. Des., 205, 281-294 . . . A Scale Analysis of the Turbulent Mixing Rate for Various Prandtl Number Flow Fields in Rod Bundles. . . . Kim, S.; Chung, B-J. . . . April 2001 . . . Cheju National University, Cheju, South Korea; The University of Manchester, Manchester, United Kingdom.

Nucl. Eng. Des., 205, 295-303 . . . Mechanistic Modeling for Ring-Type BWR Fuel Spacer Design 2. Local Pressure Drop and Narrow Channel Effect. . . . Yano, T.; Aritomi, M.; Kikura, H.; Obata, H. . . . April 2001 . . . Tokyo Institute of Technology, Tokyo, Japan; The Japan Atomic Power Company, Ltd., Tokyo, Japan.

Nucl. Eng. Des., 205, 305-311 . . . On-Line Extraction of the Variance Caused by Burn-Up in In-Core Three-Dimensional Power Distribution. . . . Wang Yaqi, Luo Zhengpei, Li Fu, Liu Wenfeng . . . April 2001 . . . Tsinghua University, Beijing, China.

Nucl. Eng. Des., 205, 313-322 . . . Dynamic Response Analysis of Tube Array in Calandria to Rotational Vault Motion. . . . Joshi, S.P. . . . April 2001 . . . Case Western Reserve University, Cleveland, OH.

Nucl. Eng. Des., 205, 323-331 . . . Remote Sensing for Flow Induced Vibrations in the PARR-1 Core Assembly. . . . Hussain, A.; Ayazuddin, S.K.; Ikram, M.; Mudassar, A.A.; Qureshi, A.A.; Iqbal, M. . . . April 2001 . . . Pakistan Institute of Nuclear Science and Technology, Islamabad, Pakistan; Pakistan Institute of Engineering and Applied Sciences, Islamabad, Pakistan.

Nucl. Eng. Des., 206, 119-128 . . . Protection Against High-Energy Line Breaks in WWER Power Plants. . . . Andersen, A.; Bergmann, H.; Horstmann, R. . . . June 2001 . . . SIEMENS Nuclear Power GmbH, Offenbach and Erlangen, Germany.

Nucl. Eng. Des., 206, 129-137 . . . Root Cause Analysis of Operational Induced Vibrations in a Feedwater System. . . . Diesselhorst, T.; Klaui, E. . . . June 2001 . . . Siemens Nuclear Power GmbH, Erlangen, Germany; Sulzer Innotec AG, Winterthur, Germany.

Nucl. Eng. Des., 206, 139-150 . . . Numerical Weld Modeling -- A Method for Calculating Weld-Induced Residual Stresses. . . . Fricke, S.; Keim, E.; Schmidt, J. . . . June 2001 . . . Siemens AG, Erlangen, Germany.

Nucl. Eng. Des., 206, 151-166 . . . LISA - A European Project for FEM-Based Limit and Shakedown Analysis. . . . Staat, M.; Heitzer, M. . . . June 2001 . . . FH-Aachen Division Julich, Julich, Germany.

Nucl. Eng. Des., 206, 167-176 . . . Fluid-Structure-Interaction for the Analysis of the Dynamics of Fuel Storage Racks in the Case of Seismic Loads. . . . Stabel, J.; Ren, M. . . . June 2001 . . . Siemens AG, Erlangen, Germany.

Nucl. Eng. Des., 206, 177-184 . . . Improved Method to Demonstrate the Structural Integrity of High Density Fuel Storage Racks. . . . Hinderks, M.; Ungoreit, H.; Kremer, G. . . . June 2001 . . . Siemens Nuclear Power GmbH, Offenbach/Main, Germany.

Nucl. Eng. Des., 206, 185-199 . . . Conservatism of ASME K_IR-Reference Curve with Respect to Crack Arrest. . . . Wallin, K.; Rintamaa, R.; Nagel, G. . . . June 2001 . . . VTT Manufacturing Technology, PL, Finland.

Nucl. Eng. Des., 206, 201-219 . . . Investigations on the Evaluation of the Residual Fatigue Life-Time in Austenitic Stainless Steels. . . . De Backer, F.; Schoss, V.; Maussner, G. . . . June 2001 . . . Siemens Nuclear Power GmbH, Erlangen, Germany.

Nucl. Eng. Des., 206, 221-234 . . . Fatigue - Determination of a More Realistic Usage Factor. . . . Lang, H. . . . June 2001 . . . Siemens AG, Erlangen, Germany.

Nucl. Eng. Des., 206, 235-247 . . . Cyclic Plastic Deformation Tests to Verify FEM-Based Shakedown Analyses. . . . Lang, H.; Wirtz, K.; Heitzer, M.; Staat, M.; Oettel, R. . . . June 2001 . . . Siemens Ag-Power Generation Group, Erlangen, Germany; Julich Research Center, Julich, Germany; Aachen University of Applied Science, Julich, Germany; Siempelkamp Pruf-und Gutachtergesellschaft, Dresden, Germany.

Nucl. Eng. Des., 206, 249-259 . . . Repair Welding of Cracked Steam Turbine Blades Using Austenitic and Martensitic Stainless-Steel Consumables. . . . Bhaduri, A.K.; Gill, T.P.S.; Albert, S.K.; Shanmugam, K.; Iyer, D.R. . . . June 2001 . . . Indira Gandhi Centre for Atomic Research, Kalpakkam, India.

Nucl. Eng. Des., 206, 261-378 . . . Application of High Strength MnMoNi Steel to Pressure Vessels for Nuclear Power Plant. . . . Suzuki, K.; Kurihara, I.; Sasaki, T.; Koyoma, Y.; Tanaka, Y. . . . June 2001 . . . The Japan Steel Works Ltd., Tokyo and Hokkaido, Japan.

Nucl. Eng. Des., 206, 279-289 . . . In-Service Monitoring and Fractographic Inspection of Ultrasonic Indications on a Feed Water Suction Pipe of the Gundremmingen Nuclear Power Plant. . . . Hofstotter, P.; Keller, H.P.; Trobitz, M.; Walkmann, M. . . . June 2001 . . . TUV Anlagentechnik GmbH, Cologne, Germany; Kernkraftwerke Gundremmingen, Gundremmingen, Germany.

Nucl. Eng. Des., 206, 291-309 . . . Planning and Use of Condition-Dependent NDT for the Interaction Between Fracture Mechanics and Quantitative NDT. . . . Schmitz, V.; Kroning, M.; Roos, E.; Blind, D.; Eisele, U. . . . June 2001 . . . Fraunhofer-Inst. Zerstorungsfreie, Stuttgart, Germany.

Nucl. Eng. Des., 206, 311-323 . . . Qualification of the LF-Eddy Current Technique for the Inspection of Stainless Steel Cladding and Applications on the Reactor Pressure Vessel. . . . Weiss, R.; Becker, R.; Lucht, B.; Mohr, F.; Hartwig, K. . . . June 2001 . . . Fraunhofer-Institut fur

Zerstorungsfrie, Stade, Germany; Siemens AG, Germany.

Nucl. Eng. Des., 206, 325-336 . . . New Applications Using Phased Array Techniques. . . . Erhard, A.; Schenk, G.; Hauser, Th.; Volz, U. . . . June 2001 . . . Bundesanstalt fur Materialforschung und-Prufung, Berlin, Germany.

Nucl. Eng. Des., 206, 337-350 . . . Copper Precipitates in 15NicuMoNb 5(WB 36) Steel: Material Properties and Microstructure, Atomistic Simulation, and Micromagnetic NDE Technique. . . . Altpeter, I.; Dobmann, G.; Katerbau, K.-H.; Schick, M.; Binkele, P.; Kizler, P.; Schmauder, . . . June 2001 . . . Fraunhofer-Institut fur Zerstorungsfreie, Stuttgart, Germany.

Nucl. Eng. Des., 206, 351-362 . . . Crack Detection and Sizing Technique by Ultrasonic and Electromagnetic Methods. . . . Komura, I.; Hirasawa, T.; Nagai, S.; Takabayashi, J-I.; Naruse, K. . . . June 2001 . . . Toshiba Corp., Yokohama, Japan.

Nucl. Eng. Des., 206, 363-374 . . . Aging Material Evaluation and Studies by Non-Destructive Techniques (AMES-NDT) - A European Network Project. . . . Dobmann, G.; Debarberis, L.; Coste, J-F. . . . June 2001 . . . Fraunhofer Institut for Nondestructive Testing, Saarbrucken, Germany; Joint Research Center, Petten, The Netherlands; Electricite de France (EDF), Moret-sur-Loing, France.

Nucl. Eng. Des., 207, 125-135 . . . Ultrasonic Measurement of Gap Between Calandria Tube and Liquid Injection Shutdown System Tube in PHWR. . . . Kim, T.R.; Sohn, S.M.; Lee, J.S.; Lee, S.K.; Lee, J.P. . . . July 2001 . . . Korea Electric Power Research Institute, Taejon, South Korea; Research Institute of Korea Advanced Inspection Technology, Taejon, South Korea.

Nucl. Eng. Des., 207, 137-145 . . . Evaporation and Condensation of Steam-Water in a Vertical Tube. . . . Sun, G.; Hewitt, G.F. . . . July 2001 . . . McMaster University, Ontario, Canada; Imperial College of Science, Technology, and Medicine, London, United Kingdom.

Nucl. Eng. Des., 207, 147-162 . . . Seismic Design Method of Clamped-Free Thin Cylindrical Shells Immersed in Fluid. . . . Fukuyama, M.; Nakagawa, M.; Yashiro, T.; Toyoda, Y.; Akiyama, H. . . . July 2001 . . . Mechanical Engineering Research Laboratory, Hitachi Ltd., Ibaraki, Japan; Hitachi Works, Hitachi Ltd., Ibaraki, Japan; Central Research Institute for Power and Industry, Chiba, Japan; Nihon University, Tokyo, Japan.

Nucl. Eng. Des., 207, 163-180 . . . Simulation of Subcooled Flow Instability for High Flux Research Reactors Using the Extended Code ATHLET. . . . Hainoun, A.; Schaffrath, A. . . . July 2001 . . . Atomic Energy Commission of Syria, Damascus, Syria; Forschungszentrum Rossendorf, Dresden, Germany.

Nucl. Eng. Des., 207, 181-188 . . . Static and Transient Cavitation Threshold Measurements for Mercury with Dissolved Air and Helium. . . . Taleyarkhan, R.P.; Moraga, F. . . . July 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Oak Ridge Associated Universities, Oak Ridge, TN.

Nucl. Eng. Des., 207, 189-197 . . . The OECD Halden Reactor Projects Fuels Testing Programme: Methods, Selected Results and Plans. . . . Wiesenack, W.; Tverberg, T. . . . July 2001 . . . Institutt for Energiteknikk, Halden, Norway.

Nucl. Eng. Des., 207, 199-206 . . . Achievements and Further Plans for the OECD Halden Reactor Project Materials Programme. . . . Karlsen, T.M. . . . July 2001 . . . Institutt for Energiteknikk, Halden, Norway.

Nucl. Eng. Des., 207, 207-221 . . . Overview of the OECD-Halden Reactor Project. . . . Vitanza, C. . . . July 2001 . . . Institutt for Energiteknikk, Halden, Norway.

Nucl. Eng. Des., 207, 223-230 . . . Cracking and Fracture of Valve Shafts in the Secondary Steam Circuit of a Nuclear Power Plant. A Case Investigation. . . .Vodopivec, F.; Vojvodic-Tuma, J.; Breskvar, B.; Arzensek, B. . . . July 2001 . . . Institute of Metals and Technology, Ljubljana, Slovenia.

Nucl. Eng. Des., 207, 231-240 . . . Subsurface Stress Valuation in Steel Plates and Bars Using the L_CR Ultrasonic Wave. . . . Bray, D.E.; Tang, W. . . . July 2001 . . . Texas A&M University, College Station, TX; Grant Prideco, Inc., Navasota, TX.

Nucl. Eng. Des., 207, 241-248 . . . Plant Life Management Activities of LWR Plants in Japan. . . . Minematsu, A. . . . July 2001 . . . Tokyo Electric Power Co., Tokyo, Japan.

Nucl. Eng. Des., 207, 249 . . . Erratum to "Conceptual Design and Analysis of a Semi-Passive Containment Cooling System for a Large Concrete Containment" [Nucl. Eng. Des. 199 (2000) 227-242]. . . . Byun, C.S.; Jerng, D.W.; Todreas N.E.; Driscoll, M.J. . . . July 2001 . . . Korea Electric Power Research Institute, Taejon, South Korea; Massachusetts Institute of Technology, Cambridge, MA.

Eng. Fail. Anal., 8, 311-324 . . . Reliability-Based Fatigue Failure Analysis for Causes Assessment of a Collapsed Steel Truss Bridge. . . . Cho, H-N.; Lim, J-K.; Choi, H-H. . . . August 2001 . . . Hanyang University, Kyungki, South Korea; Seung-Hwa Engineering & Construction Co., Seoul, South Korea.

Eng. Fail. Anal., 8, 325-338 . . . Failure Analysis of Exit Edges in Ceramic Machining Using Finite Element Analysis. . . . Cao, Y. . . . August 2001 . . . University of Maryland, College Park, MD.

Eng. Fail. Anal., 8, 339-354 . . . Numerical Analysis of Wheel Cornering Fatigue Tests. . . . Kocabicak, U.; Firat, M. . . . August 2001 . . . University of Sakarya, Adapazari, Turkey.

Eng. Fail. Anal., 8, 355-359 . . . Analysis of Casting Die Failures. . . . Kosec, B.; Kosec, L.; Kopac, J. . . . August 2001 . . . University of Ljubljana, Ljubljana, Slovenia.

Eng. Fail. Anal., 8, 361-370 . . . Analysis of a Blow-Molded HDPE Bottle That Failed by Brittle Fracture. . . . Luckey, Jr., S.G.; Henshaw, J.M.; Dewan, C.; Eltanany, G.M.; Teeters, D. . . . August 2001 . . . The University of Tulsa, Tulsa, OK.

Eng. Fail. Anal., 8, 371-397 . . . Compliance Measurements for Assessing Structural Integrity. . . . Pitt, S.; Jones, R. . . . August 2001 . . . Monash University, Victoria, Australia; Aeronautical and Maritime Research Laboratory, Victoria, Australia.

Eng. Fail. Anal., 8, 399-407 . . . Failure Analysis and Fitness-for-Service Assessment for a Pipeline. . . . Feng Yaorong, Li Helin, Zhang Pingsheng, Du Baiping, Ma Baodian, Jin Zhihao . . . August 2001 . . . Tubular Goods Research Center of CNPC, Shaanxi, China; Jiao Tong University, Shaanxi, China.

Nucl. Technol., 134, 97-109 . . . Risk-Oriented Safety Evaluation of the CAREM-25 Prototype Reactor. . . .Baron, J.H.; Nunez McLeod, J.E.; Rivera, S.S. . . . May 2001 . . . Universidad Nacional de Cuyo, Mendoza, Argentina.

Nucl. Technol., 134, 110-129 . . . Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - I: Dupic Fuel Fabrication Cost. . . . Choi, H.; Ko, W.I.; Yang, M.S. . . . May 2001 . . . Korea Atomic Energy Research Institute, Taejon, Korea.

Nucl. Technol., 134, 130-148 . . . Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - II: Dupic Fuel-Handling Cost. . . . Choi, H.; Ko, W.I.; Yang, M.S.; Namgung, I.; Na, B-G. . . . May 2001 . . . Korea Atomic Energy Research Institute, Taejon, Korea; Korea Power Engineering Co., Inc., Taejon, Korea.

Nucl. Technol., 134, 149-166 . . . Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - III: Spent Dupic Fuel Disposal Cost. . . . Ko, W.I.; Choi, H.; Roh, G.; Yang, M.S. . . . May 2001 . . . Korea Atomic Energy Research Institute, Taejon, Korea.

Nucl. Technol., 134, 167-186 . . . Economic Analysis on Direct Use of Spent Pressurized Water Reactor Fuel in CANDU Reactors - IV: Dupic Fuel Cycle Cost. . . . Ko, W.I.; Choi, H.; Yang, M.S. . . . May 2001 . . . Korea Atomic Energy Research Institute, Taejon, Korea.

Nucl. Technol., 134, 187-195 . . . Numerical Study of Coolant Mixing Caused by the Flow Deflectors in a Nuclear Fuel Bundle. . . . In, W.K. . . . May 2001 . . . Korea Atomic Energy Research Institute, Taejon, Korea.

Nucl. Technol., 134, 208-220 . . . Radioiodine Volatilization in the Presence of Organic Compounds. . . . Shinn, J.L.; Wilson, J.W.; Singleterry, R.C.; Xapsos, M.A.; Taghipour, F.; Evans, G.J. . . . May 2001 . . . University of Toronto, Toronto, Ontario, Canada.

ORNL/TM-8111 . . . Monte Carlo Calculations of Control-Rod Worth of a Medium-Size Pebble-Bed Reactor. . . . Tang, J.S.; Worley, B.A. . . . September 1982 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

ORNL/TM-9215 . . . A One-Dimensional Modeling of Radial Heat Removal During Depressurized Heatup Transients in Modular Pebble-Bed and Prismatic High Temperature Gas-Cooled Reactor . . . Savage, M.G. . . . July 1984 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

NUREG/CR-4694; ORNL/TM-9905 . . . Application of Thermix-Konvek Code to Accident Analyses of Modular Pebble Bed High Temperature Reactors (HTRs). . . . Cleveland, J.C.; Greene, S.R. . . . August 1986 . . . Oak Ridge National Laboratory, Oak Ridge, TN.