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. 439	September 2001
"We judge ourselves by what we feel capable of doing, while others judge us by what we have already done." -- Henry Wadsworth Longfellow

• ***Second Notice***
• Proceedings of NJOY Workshop
• Sheldon Datz, Fermi-winning physicist, dies
• NRC Codes Made Available
• CHANGES TO THE COMPUTER CODE and DATA COLLECTION
• CONFERENCES, COURSES, SYMPOSIA
• MCNP™ Workshops
• MCNPX Classes
• Visual Editor Classes
• SCALE Training Course Schedule
• Advanced Training Course on PENELOPE-2000
• Seventh International Radiopharmaceutical Dosimetry Symposium
• Calendar
• AUGUST ACCESSION OF LITERATURE

Dear NJOYers,

Web based proceedings of the WORKSHOP on NJOY-2001 and USER GROUP MEETING held at Aix-en-Provence on 15 May 2001 are accessible via Internet. They consist of a table of contents in HTML format and the links to the papers and/or viewgraphs that have been distributed or displayed at the meeting. The last paper is the summary of the meeting.

The URL is: http://www.nea.fr/html/dbprog/Njoy/njoyaixproc.html

I wish to take this opportunity of thanking all those who have made presentations and for providing the texts for the proceedings. Thanks go also to those who have taken care of the local organisation and for the generous treatment they have given us.
 

Sheldon Datz, an ORNL physicist whose many awards include the Enrico Fermi Award presented to him by President Clinton last year, died August 15th at the age of 74. He retired from the Oak Ridge National Laboratory last year as head of the Physics Division's Atomic and Molecular Physics section. He was a strong supporter of the Lab's Wigner Fellowship program.

Sheldon described himself in a 1999 interview, as a researcher who "filled the gaps" in basic research between larger physics facilities and smaller experiments. He and ORNL's Ellison Taylor were early explorers of molecular-beam physics that broke ground for the field of chemical dynamics. Researchers who followed up on those studies eventually received Nobel prizes.

Seemingly arcane basic science, Sheldon said, sometimes resulted in billion-dollar industries. He cited ORNL's early work in particle-solid interactions, which resulted in analytical methods and the surface modification of materials widely used in industry today.

Sheldon's work took him around the globe. He was a veteran of experiments at CERN in Switzerland and had a close relationship with physical science facilities at the University of Stockholm, Sweden, which presented him with an honorary doctorate in 1998, the same year he received a similar award in Japan. He also received the American Physical Society's Davisson-Germer Prize for his research into atomic interactions with ions, electrons and photons.
 

CCC-624/DOSE-SGTR

DLC-173/HPPOS V2

DLC-215/EDSFI (Distribution is restricted to the United States)

PSR-491/NRCPAGE

PSR-494/MINTEQ
 

A personal computer version of this code system for fission product inventory, release, transport and dose calculation is now available. FISSP calculates the fission product inventory in a (U-235 fueled) reactor for a specified power history. In addition, following the specified power history, FISSP computes an instantaneous point (puff) release of the fission products to the atmosphere, and continues to calculate the radioactivity history of each released fission product. CLOUD calculates the external gamma and beta dose, and the internal dose to the lung, thyroid, gastro-intestine, bone, and whole body resulting from inhalation of the passing radioactive cloud. FISSP & CLOUD were developed at Sandia National Laboratories, Albuquerque, New Mexico, on CDC computers and contributed to RSICC in 1972. In this update, the IBM mainframe source files were compiled at RSICC on a Pentium III running Windows98 with the Digital Visual Fortran 5 compiler to create executables which were added to the package. No changes were made to the CDC and IBM mainframe codes in this package, which are also included. The package is transmitted on one DS/HD diskette which contains the source codes, PC executables and sample problem input and output written in compressed, self-extracting Windows files. References: SC-RR-70-338 (July 1970) and supplementary material. Fortran IV; CDC 6600, IBM 360 and IBM PC (C00163/MNYCP/01).
 
 

Oak Ridge National Laboratory, Oak Ridge, Tennessee; Athey Consulting, Charles Town, West Virginia; Pacific Northwest National Laboratory, Richland, Washington; and the Nuclear Regulatory Commission, Washington, DC, contributed a newly frozen release of this code system for radiological assessment for consequence analysis. RASCAL, Version 3.0.1, (June 2001 release) estimates reactor source term, atmospheric transport and doses resulting from radiological emergencies and can be used to assist in making protective action decisions. The Radiological Assessment System for Consequence AnaLysis (RASCAL) is designed to be used in the independent assessment of dose projections during response to radiological emergencies. The system supplements assessments based on plant conditions and quick estimates based on hand-calculational methods. The tools are designed to provide a comparison to EPA Protective Action Guidance and thresholds for acute health effects. RASCAL will be used by NRC personnel to conduct an independent evaluation of dose and consequence projections and for training and drills. The model was developed to allow consideration of the dominant aspects of source term, transport, dose, and consequences. The software consists of 4 tools accessed from a menu program (or shell). These 4 tools are:

• Source Term to Dose model (STDose) of RASCAL provides estimates of the integrated doses and consequences resulting from the accidental release of radionuclides to the atmosphere. Source terms are computed for reactor accidents, UF6 releases, uranium fires and explosions, and other materials accidents.
• Field Measurement to Dose model (FMDose) computes emergency worker limits and early-phase and intermediate-phase doses and derived intervention levels (DILs) from the analyses of field measurements.
• Decay Calculator (DecayCalc) computes radiological decay and daughter ingrowth.
• Meteorological Data Processor (MetProc) is the STDose module used for entering meteorological data and preparing the data for use by the atmospheric transport and diffusion models in RASCAL.

The package is transmitted on one CD which includes installation instructions, executables, data, help files, and an install procedure. Source files are not included in this release. Reference: Informal report. Fortran 77, Basic; Pentium running Windows95, NT or later (C00553/PC586/05).
 
 

Los Alamos National Laboratory, Los Alamos, New Mexico, contributed a newly frozen version of this code system for calculating alpha,n; spontaneous fission; and delayed neutron sources and spectra. The SOURCES decay data library, tape5, was updated to include spontaneous fission information for 252 Cf. Decay information for the data library was also updated for the 43 isotopes and isomers having Watt fission spectra parameters. Future work will update the remainder of the nuclides. This work will upgrade SOURCES from version 4A to 4B. The only changes to the code package are the revision of tape5 and sample problem result files. For more information on the changes to tape5, see LA-UR-00-5016 "Data Updates for the SOURCES-4A Computer Code," which was added to the package documentation.

SOURCES-4B runs on many computers. At RSICC it was tested on Sun Sparcstation under OS5.6, on IBM RS/6000 under 4.3.3, and on a Pentium running WindowsNT. A Lahey F77/L3-EM32 v5.2 compiled executable for PC users is included in the package; all other computers require a Fortran 77 compiler. The package is transmitted on a CD which includes the electronic documents and the Fortran source, PC executable, data libraries, and test cases in a self-extracting compressed Windows file and in a GNU compressed tar file. References: LA-13639 (September 1999) and LA-UR-00-5016 (2000). Fortran 77; IBM PC; Sun, IBM RS/6000 (C00661/MNYCP/02).
 
 

Los Alamos National Laboratory, Los Alamos, New Mexico, released a newly frozen version of this general-purpose, continuous-energy, generalized geometry, time-dependent, coupled neutron-photon-electron Monte Carlo transport code system. The major new features of MCNP4C2 include: photonuclear physics, interactive plotting, plot superimposed weight window mesh, implement remaining macrobody surfaces, upgrade macrobodies to surface sources and other capabilities, revised summary tables, and weight window improvements

The DLC-200/MCNPDATA code package includes data for use with MCNP and is distributed with the code for the convenience of users. A new LA150U photonuclear library of particle emission data for nuclear events from incident neutrons, protons and photons with energies up to 150 MeV is included in the MCNP4C2 package. The following twelve isotopes have photonuclear evaluations in LA150U: C-12, O-16, Al-27, Si-28, Ca-40, Fe-56, Cu-63, Ta-181, W-184, Pb-206, Pb-207, and Pb-208. See the MCNP home page for more information http://www-xdiv.lanl.gov/XCI/PROJECTS/MCNP with a link to the MCNP Forum. See the Electronic Notebook at http://www-rsicc.ornl.gov/rsic.html for information on user experiences with MCNP.

MCNP is operable on Cray computers under UNICOS, workstations or PC's running Unix or Linux, and Windows-based PC's. Compilation of MCNP requires both FORTRAN and ANSI C standard compilers for Unix and under Windows for the dynamic memory option (pointer) with Digital Visual Fortran. Executables are included for Windows users. For the PC Windows systems, the supported operating systems are Windows NT/9x. The included MCNP and MAKXSF executables run as DOS applications under Windows 9x/NT and Windows 2000. The Lahey Fortran 95 5.50h LF95 PRO v5.5 Professional Edition compiler was used to create an executable with MDAS=4,000,000. The Digital Visual Fortran 6.0 Professional Edition and Microsoft Visual C++ 6.0 Professional Edition compilers were used to create MCNP executables with the dynamic memory option (pointer). PC executables linked with the standard DVF and Lahey graphics are included, and PC executables linked with X11 graphics routines are also included. To use the latter, X11 must be installed on your PC. An X-windows server is required to display the X11 graphics. Suggested servers include ReflectionX, Exceed, and X-Deep/32.

MCNP4C2 is transmitted on a CD in Windows and UNIX format. References: LANL Memo X-5:RN (U)-JSH-01-01 (30 January, 2001) and LA-13709-M (April 2000). Fortran 77 or 90 and C; Unix workstations, Intel-based PCs, and Cray (C00701/ALLCP/00).
 
 

Oak Ridge National Laboratory, Oak Ridge, Tennessee, and Nuclear Data Evaluation Laboratory, Korea Atomic Energy Research Institute, Taejon, Korea, contributed a code system for suggesting the orbital angular momentum of a neutron resonance from the magnitude of its neutron width. SUGGEL produces a "suggested value" for the orbital angular momentum (l) of a resonance from the magnitude of its g'n . The code also either suggests the most probable resonance spin (J), or assigns the spin value randomly, according to user preference.

The suggestion is based on the probability that a resonance having a certain value of g'n is an l-wave resonance. The probability is calculated by using Bayes' theorem on the conditional probability. The probability density functions take two possible channel spins into account. SUGGEL is a tool which evaluators will use to construct resonance parameters and to help assign resonance spin. The use of this tool is expected to reduce time and effort in the evaluation procedure, since the number of repeated runs of the fitting code (e.g., SAMMY PSR-158) may be reduced. SUGGEL was installed and tested on DEC Alpha using Fortran 90 and on IBM RS/6000 workstations using Fortran 77. The code is transmitted in a Unix tar file on a DOS formatted diskette. Reference: ORNL/TM-2000/314 (February 2001). Fortran 77; DEC Alpha and IBM RS/6000 (P00508/MNYWS/00).
 

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 10th in a series will be held May 21-23, 2002, at the University of Michigan, Ann Arbor, MI.  The program will emphasize research and recent development in ionizing radiation measurements.  Proposed session topics are: radiation sources, including secondary target sources; detectors and detection systems; data acquisition and data analysis systems and methods; radiation spectroscopy; particle-induced X-ray emission and radiation-induced fluorescence; analytical standards and elemental analysis; new and unique applications of ionizing radiation; industrial radiography and tomography; nuclear methods in space exploration and planetary science.

First call for papers: deadline for receipt of summaries is January 23, 2002.  For more information see the website at: http://rma-symposium.engin.umich.edu/ or contact David K. Wehe at dkw@umich.edu.

              September 10-14, 2001                  Introductory level                     Stuttgart, Germany

Introductory classes are for people who have little or no experience with MCNP. The classes survey the features of MCNP so the beginning user will be exposed to the capabilities of the program, and will have hands-on experience at running the code to solve rudimentary problems. Course topics include Basic Geometry, Source Definitions, Output (Tallies) Specification and Interpretation, Advanced Geometry (repeated structures specification), Variance Reduction Techniques, Statistical Analysis, Criticality, Plotting of Geometry, Tallies, and Particle Tracks, and Neutron/Photon/Electron Physics.

For European courses, contact Enrico Sartori, sartori@nea.fr. For USA, contact Judi Briesmeister, jfb@lanl.gov.

We note that a number of other organizations, including competing groups at Los Alamos, are offering MCNP courses. There are other MCNP workshops out there, but these are the only classes taught by the actual developers of MCNP.
 

Teachers: Dr. John Hendricks, Dr. Gregg McKinney, and Dr. Laurie Waters

Organizer: Hamilton Quality Consulting

Registration: http://mcnpxworkshops.com
 

September 24-28	Intermediate	Los Alamos National Laboratory, Los Alamos, NM
October 22-26	Intermediate	Oak Ridge National Laboratory, Knoxville, TN
November 5-9	level to be decided	Tokyo, Japan

MCNPX is the LANL all-particle, all-energy (eV-GeV) Monte Carlo transport code based on MCNP4C2, LAHET, CEM, etc. MCNPX has been developed for the past six years, particularly for the high-energy accelerator community, and has now become an accepted tool for a broad range of applications by nuclear engineers, physicists, and scientists. All workshops are hands-on and will include a distribution of MCNPX 2.3 (subject to participant export approval), LA150 (150 MeV) cross-section data, and a notebook of viewgraphs. More information on course topics and fees can be found at the registration website.
 

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 running MCNP.

This class will include computer demonstrations and exercises that will focus on creating and interrogating input files with the Visual Editor. Advanced visualization work using MCNP will also be demonstrated. The class will be taught on Pentium computers running the Linux operating system and Windows NT. Class attendees can use either the Linux or Windows version of the visual editor. 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.mcnpvised.com/, or by contacting Randy Schwarz (email randyschwarz@mcnpvised.com).
 

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.
 

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.
 

All announcements and other mailings for this meeting will be done electronically (no paper mail will be sent). Abstracts (also electronic) are being accepted until September 30, 2001, with authors notified of outcome in approximately October. 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. The web site is http://www.doseinfo-radar.com/symphome.html.
 

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).

Nuclear Data for Science and Technology, Embracing the Future at the Beginning of the 21st Century, Oct. 7-12, 2001, Tsukuba, Japan. Sponsored by JAERI, co-sponsored by OECD/Nuclear Energy Agency and Atomic Energy Society of Japan. Contact: My Associates, Inc. (tel +81-3-3422-8584, fax +81-3-3422-7534, email myasso@ad.il24.net).

The XIX Autumn School on New Perspectives with Nuclear Radioactivity, Oct. 8-13, 2001, Libson, Portugal. Contact: Ms. Sandra Oliveira (tel +351-21-8419092, fax +351-21-8419143, email nrad2001@cfif.ist.utl.pt).

Visual Editor Class, Oct. 8-10, 2001, Richland, WA. Contact: Randy Schwarz (tel 509-372-4042, email randy.schwarz@mcnpvised.com, url http://www.mcnpvised.com).
 

Nuclear Safety Research Conference, (formerly called the Annual Water Reactor Safety Meeting) Oct.22-24, 2001, Marriott Metro Center, Washington, D.C. Sponsored by the Office of Nuclear Regulatory Research. Contact: Susan Monteleone (phone 631-344-7235, email susanm@bnl.gov, url http://www.nrc.gov./RES/meetings.htm).

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/).

ANS Winter Meeting, Gathering and Technical Sessions in Memory of Dr. Allan F. Henry (1935-2001), Nov. 11-14, 2001, Reno, NV. These are special sessions, and refreshments will be served. Contact: Kord Smith (email kord@soa.com, url http://www.ans.org/meetings/).

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, Nov. 5-7, 2001, 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).

April 2002

Thirty-Eight Annual Meeting of the National Council on Radiation Protection and Measurements, Apr. 10-12, 2002, Arlington, VA. Contact: William M. Beckner (tel 301-657-2652, fax 301-907-8768, url www.ncrp.com).

Back to the Future of Nuclear Technology, 2002 ANS Student Conference, Apr. 10-13, 2002, University Park, PA. Contact: Frank Buschman (tel 814-865-6351, email fxb129@psu.edu, url www.clubs.psu.edu/ ANS).

12th Biennial RPSD Topical Meeting, Apr. 14-17, 2002, Santa Fe, NM. Hosted by the ANS Trinity Section and cosponsored by the Health Physics Society, L'Organisation de cooperation et de developpement/L'Agence pour l'energie nucleaire (OECD/AEN, and RSICC. Contact: (email rpsd2002@lanl. gov, url www.lanl.gov/ RPSD2002/).

International Youth Nuclear Congress 2002, Apr. 16-20, 2002, Taejon, Korea. Contact: Alexandre Tsiboulia or Han Seong Son (email alexts@ippe.obninsk.ru,hsson@nanum.kaeri.re.kr, url http://www.iync.org).

Seventh International Radiopharmaceutical Dosimetry Symposium, Apr. 17-19, 2002, Nashville, TN. Contact: Michael Stabin (email michael.g.stabin@vanderbilt.edu, url http://www.doseinfo-radar.com/symphome.html).

May 2002

Symposium on Radiation Measurements and Applications, May 21-23, 2002, Ann Arbor, MI. Contact: General Chair David K. Wehe (tel 734-764-6215, email dkw@umich.edu, url http://rma-symposium.engin.umich.edu/).

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

PHYSOR 2002, Oct. 7-10, 2002, Seoul, Korea, sponsored by the American Nuclear Society and hosted by the Korean Nuclear Society. Contact: Prof. Nam Zin Cho (tel +82-42-869-3819, fax +82-42-869-5859, email tpc@physor2002.kaist.ac.kr, url http://physor2002.kaist.ac.kr).

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).

September 2003

International Conference on Supercomputing in Nuclear Applications, SNA 2003, September 22-24, 2003, Paris, France. Organizers: CEA, SFANS, co-organizer: OECD/NEA. (email SNA-2003@cea.fr, url http://SNA-2003.cea.fr).
 

Ann. Nucl. Energy, 28, 1329-1341 . . . Pressurized Water Reactor Reloading Optimization Using Genetic Algorithms. . . . Wu Hongchun . . . September 2001 . . . Xi'an Jiaotong University, Shaanxi, China.

Ann. Nucl. Energy, 28, 1343-1363 . . . The Modeling of Fuel Rod Behaviour Under RIA Conditions in the Code DYN3D. . . . Rohde, U. . . . September 2001 . . . Forschungszentrum Rossendorf, Dresden, Germany.

Ann. Nucl. Energy, 28, 1365-1375 . . . Build-Up of Actinides in Irradiated Fuel Rods of the ET-RR-1 Reactor. . . . Adib, M.; Naguib, K.; Morcos, H.N. . . . September 2001 . . . Atomic Energy Authority, Cairo, Egypt.

Ann. Nucl. Energy, 28, 1485-1492 . . . Influence of the Grain Size on the Effective Absorption Cross-Section of Thermal Neutrons in a Medium Containing Highly Absorbing Centres. . . . Drozdowicz, K.; Gabanska, B.; Krynicka, E.; Woznicka, U. . . . October 2001 . . . Henryk Niewodniczanski Institute of Nuclear Physics, Krakow, Poland.

Ann. Nucl. Energy, 28, 1499-1517 . . . A Linear Multiple Balance Method with High Order Accuracy for Discrete Ordinates Neutron Transport Equations. . . . Park, C.J.; Cho, N.Z. . . . October 2001 . . . Korea Advanced Institute of Science and Technology, Taejon, South Korea.

Ann. Nucl. Energy, 28, 1519-1547 . . . Subcritical Reactivity Monitoring in Accelerator Driven Systems. . . . Munoz-Cobo, J.L.; Rugama, Y.; Valentine, T.E.; Mihalczo, J.T.; Perez, R.B. . . . October 2001 . . . Universidad Politecnica de Valencia, Valencia, Spain; Oak Ridge National Laboratory, Oak Ridge, TN.

Ann. Nucl. Energy, 28, 1549-1562 . . . Measurement of keV-Neutron Capture Cross-Sections for 164Dy. . . . Kim, G. et al. . . . October 2001 . . . Pohang Accelerator Laboratory, Pohang, South Korea; Pusan National University, Pusan, South Korea; Donga University, Pusan, South Korea; Tokyo Institute of Technology, Tokyo, Japan.

Ann. Nucl. Energy, 28, 1563-1581 . . . On Criticality Calculations in Multislab Geometry. . . . Caldeira, A.D.; Garcia, R.D.M. . . . October 2001 . . . Instituto de Estudos Avancados, Sao Jose dos Campos, Brazil; HSH Scientific Computing, Sao Jose dos Campos, Brazil.

Eng. Fail. Analysis, 8, 513-520 . . . Failure Analysis of an Automobile Valve Spring. . . . Sudhakar, K.V. . . . December 2001 . . . Central Michigan University, Mount Pleasant, MI.

Eng. Fail. Analysis, 8, 521-528 . . . Failure Analysis of High Temperature Studs. . . . Chowdhury, S.G.; Kumar, P.; Das, S.K.; Bhattacharya, D.K.; Parida, N. . . . December 2001 . . . National Metallurgical Laboratory, Jamshedpur, India.

Eng. Fail. Analysis, 8, 529-540 . . . A Remaining Life Assessment of a Cracked Attemperator Steam Line. . . . Bulloch, J.H.; Bernard, P.J. . . . December 2001 . . . Power Generation, Dublin, Ireland.

Eng. Fail. Analysis, 8, 541-556 . . . Fracture Behavior of a Corroded Structural Component Under Bending Load. . . . Ohashi, M.; Yamamoto, H.; Itoh, Y. . . . December 2001 . . . National Research Institute of Police Science, Chiba, Japan.

Eng. Fail. Analysis, 8, 557-570 . . . Load Distribution in the Axial Direction in a Spline Coupling. . . . Tjernberg, A. . . . December 2001 . . .Volvo Construction Equipment Components, Eskilstuna, Sweden.

Eng. Fail. Analysis, 8, 571-576 . . . Failure Analysis of an AM 350 Steel Bellows. . . . Shaikh, H.; George, G.; Khatak, G.S. . . . December 2001 . . . Indira Gandhi Centre for Atomic Research, Kalpakkam, India.

Fus. Eng. Design, 55, 107-118 . . . ITER R&D: Executive Summary: Design Overview. . . . Aymar, R. . . . July 2001 . . . ITER Garching Joint Work Site, Garching, Germany.

Fus. Eng. Design, 55, 119-136 . . . ITER R&D: Executive Summary: R&D Overview. . . . Mizoguchi, T. . . . July 2001 . . . ITER Naka Joint Work Site, Ibaraki-ken, Japan.

Fus. Eng. Design, 55, 137 . . . ITER R&D: Executive Summary: Concluding Remarks. . . . Mizoguchi, T. . . . July 2001 . . . ITER Naka Joint Work Site, Ibaraki-ken, Japan.

Fus. Eng. Design, 55, 139-140 . . . ITER R&D: Magnets: Introduction. . . . Mizoguchi, T.; Mitchell, N. . . . July 2001 . . . ITER Naka Joint Work Site, Ibaraki-ken, Japan.

Fus. Eng. Design, 55, 141-151 . . . ITER R&D: Magnets: Conductor and Joint Development. . . . Tsuji, H.; Egorov, S.; Minervini, J.; Mitchell, N.; Okuno, K.; Salpietro, E. . . . July 2001 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan; Institute of Electrophysical Apparatus, Sovetsky, Russia; MIT, Cambridge, MA; ITER Naka Joint Work Site, Ibaraki-ken, Japan; EDFA, Garching bei München, Germany.

Fus. Eng. Design, 55, 153-170 . . . ITER R&D: Magnets: Central Solenoid Model Coil . . . Tsuji, H. et al. . . . July 2001 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan; D.V. Institute of Electrophysical Apparatus, St. Petersburg, Russia.

Fus. Eng. Design, 55, 171-190 . . . ITER R&D: Magnets: Toroidal Field Model Coil. . . . Mitchell, N.; Salpietro, E. . . . July 2001 . . . ITER Naka Joint Work Site, Ibaraki-ken, Japan; EFDA, Garching bei München, Germany.

Fus. Eng. Design, 55, 191 . . . ITER R&D: Vacuum Vessel and In-Vessel Components: Introduction. . . . Mizoguchi, T. . . . July 2001 . . . ITER Naka Joint Work Site, Ibaraki-ken, Japan.

Fus. Eng. Design, 55, 193-203 . . . ITER R&D: Vacuum Vessel and In-Vessel Components: Vacuum Vessel . . . Koizumi, K.; Jones, L.; Krylov, V.; Nelson, D.E.; Onozuka, M. . . . July 2001 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan; EFDA, Garching bei München, Germany; Institute of Electrophysical Apparatus, St. Petersburg, Russia; Lockheed Martin Energy Systems, Oak Ridge, TN; ITER Garching Joint Work Site, Garching, Germany.

Fus. Eng. Design, 55, 205-217 . . . ITER R&D: Vacuum Vessel and In-Vessel Components: Shield Blanket Module . . . Danner, .W.; Cardella, A.; Ioki, K.; Mattas, R.; Ohara, Y.; Strebkov, Y. . . . July 2001 . . . EDFA, Garching bei München, Germany; ITER Garching Joint Work Site, Garching, Germany; Argonne National Laboratory, Argonne, IL; JAERI, Ibaraki-ken, Japan; Research & Development Institute of Power Engineering, Moscow, Russia.

Fus. Eng. Design, 55, 219-229 . . . ITER R&D: Vacuum Vessel and In-Vessel Components: Divertor Cassette . . . Tivey, R.; Akiba, M.; Driemeyer, D.; Mazul, I.; Merola, M.; Ulrickson, M. . . . July 2001 . . . ITER Garching Joint Work Site, Garching, Germany; JAERI, Ibaraki-ken, Japan; Boeing Corp., St. Louis, MO; Efremov Institute, St. Petersburg, Russia; EFDA, Garching bei München, Germany; Sandia National Laboratories, Albuquerque, NM.

Fus. Eng. Design, 55, 231-246 . . . ITER R&D: Vacuum Vessel and In-Vessel Components: Materials Development and Test. . . . Kalinin, G.; Barabash, V.; Fabritsiev, S.; Kawamura, H.; Mazul, I.; Ulrickson, M.; Wu, C.; Zinkle, S. . . . July 2001 . . . ITER Garching Joint Work Site, Garching, Germany; Efremov Institute, St. Petersburg, Russia; JAERI, Ibaraki-ken, Japan; Sandia National Laboratories, Albuquerque, NM; EFDA, Garching bei München, Germany; Oak Ridge National Laboratory, Oak Ridge, TN.

Fus. Eng. Design, 55, 275-280 . . . ITER R&D: Auxiliary Systems: Ion Cyclotron Heating and Current Drive System. . . . Bosia, G.; Kock, R.; Swain, D.W. . . . July 2001 . . . DRFC/SCCP/GSAC, Saint Paul Lez Durance, France; Institut fuer Plasmaphysik, Juelich, Germany; Oak Ridge National Laboratory, Oak Ridge, TN.

Fus. Eng. Design, 55, 281-289 . . . ITER R&D: Auxiliary Systems: Electron Cyclotron Heating and Current Drive System . . . Imai, T.; Kobayashi, N.; Temkin, R.; Thumm, M.; Tran, M.Q.; Alikaev, V. . . . July 2001 . . . JAERI, Ibaraki-ken, Japan; ITER Garching Joint Work Site, Garching, Germany; MIT, Cambridge, MA; Forschungszentrum Karlsruhe, Karlsruhe, Germany; Ecole Polytechnique Federale de Lausanne, Lausanne, Switzerland; INF RRC Kurchatov Institute, Moscow, Russia.

Fus. Eng. Design, 55, 291-301 . . . ITER R&D: Auxiliary Systems: Neutral Beam Heating and Current Drive System. . . . Inoue, T.; Hemsworth, R.; Kulygin, V.; Okumura, Y. . . . July 2001 . . . ITER Naka Joint Work Site, Ibaraki-ken, Japan; CEA Cadarache, St. Paul lez Durance, France; Kurchatov Institute, Moscow, Russia; JAERI, Ibaraki-ken, Japan.

Fus. Eng. Design, 55, 303-311 . . . ITER R&D: Auxiliary Systems: Fuelling and Vacuum Pumping System. . . . Ladd, P.; Gouge, M.J.; Murdoch, D.; Saksaganskiy, G.L. . . . July 2001 . . . ITER Garching Joint Work Site, Garching, Germany; Oak Ridge National Laboratory, Oak Ridge, TN; EFDA-CSU, Garching bei München, Germany; D.V. Efremov Scientific Research Institute of Electrophysical Apparatus, St. Petersburg, Russia.

Fus. Eng. Design, 55, 313-323 . . . ITER R&D: Auxiliary Systems: Tritium Systems. . . . Yoshida, H.; Murdoch, D.; Nishi, M.; Tebus, V.; Willms, S. . . . July 2001 . . . ITER Naka Joint Work Site, Ibaraki-ken, Japan; EDFA-CSU, Garching bei München, Germany; JAERI, Ibaraki-ken, Japan; Bochvar Research Institute of Inorganic Materials, Moscow, Russia; Los Alamos National Laboratory, Los Alamos, NM.

Fus. Eng. Design, 55, 325-330 . . . ITER R&D: Auxiliary Systems: Coil Power Supply Components. . . . Mondino, P.L.; Bonicelli, T.; Kuchinskiy, V.; Roshal, A. . . . July 2001 . . . ITER Naka Joint Work Site, Ibaraki-ken, Japan; EDFA-CSU, Garching bei München, Germany; Efremov Institute, St. Petersburg, Russia.

Fus. Eng. Design, 55, 331-346 . . . ITER R&D: Auxiliary Systems: Plasma Diagnostics. . . . Costley, A.E.; Campbell, D.J.; Kasai, S.; Young, K.E.; Zaveriaev, V. . . . July 2001 . . . ITER Naka Joint Work Site, Ibaraki-ken, Japan; EDFA, Garching, Germany; JAERI, Ibaraki-ken, Japan; Princeton Plasma Physics Laboratory, Princeton, NJ; Kurchatov Institute, Moscow, Russia.

Fus. Eng. Design, 55, 347-357 . . . ITER R&D: Auxiliary Systems: Safety Related R&D. . . . Gordon, C.; Gulden, W.; Kolbasov, B.; Petti, D.; Takase, K. . . . July 2001 . . . ITER Garching Joint Work Site, Garching, Germany; EDFA, Garching bei München, Germany; Kurchatov Institute, Moscow, Russia; Idaho National Engineering Laboratory, Idaho Falls, ID; JAERI, Ibaraki-ken, Japan.

Health Phys., 81, 3-7 . . . A Dose Reconstruction of ⁶⁰Co-Contaminated Window Frames in a Taiwanese School. . . . Brock, K.M.; Neumann, C.M.; Higley, K.A.; Chang, W.P.; Rossignol, A.M. . . . July 2001 . . . Oregon State University, Corvallis, OR; National Yang Ming University, Taipei, Taiwan.

Health Phys., 81, 15-26 . . . An Alternative Method for the Release Criteria and Calculation of the Total Dose Equivalent to Another Individual from a Patient Treated with a Therapeutic Dose of ¹³¹I . . . DeSantis, D.M.; Chabot, G.E. . . . July 2001 . . . Harvard Medical School, Boston, MA; University of Massachusetts Lowell, Lowell, MA.

Health Phys., 81, 27-34 . . . Evaluation of Eight Decision Rules for Low-Level Radioactivity Counting. . . . Strom, D.J.; MacLellan, J.A. . . . July 2001 . . . Pacific Northwest National Laboratory, Richland, WA.

Health Phys., 81, 57-69 . . . Investigation of the Air Pressure Characteristics Influencing the Variability of Radon Gas and Radon Progeny in Domestic Vernacular Buildings. . . . Marley, F. . . . July 2001 . . . University College Northampton, Northampton, England.

Health Phys., 81, 70-75 . . . Reconstruction of Doses from Radionuclide Inhalation for Nuclear Power Plant Workers Using Air Concentration Measurements and Associated Uncertainties. . . . Linkov, I.; Burmistrov, D. . . . July 2001 . . . Arthur D. Little, Inc.; Cambridge, MA; Menzie-Cura & Associates, Inc., Chelmsford, MA.

Health Phys., 81, 82 . . . Book Review: Environmental Exposure: Facts vs. Fiction - A Festschrift for Merril Eisenbud. . . . Kearfott, K. . . . July 2001.

J. Nucl. Mater., 296, 1-16 . . . R&D for the Spallation Neutron Source Mercury Target. . . . Mansur, L.K.; Gabriel, T.A.; Haines, J.R.; Lousteau, D.C. . . . July 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 296, 17-33 . . . MEGAPIE, A 1 MW Pilot Experiment for a Liquid Metal Spallation Target. . . . Bauer, G.S.; Salvatores, M.; Geusener, G. . . . July 2001 . . . Paul Scherrer Institut, Villigen-PSI, Switzerland; CEA Cadarache, St. Paul lez Durance, France; Forschungszentrum Karlsruhe, Karlsruhe, Germany.

J. Nucl. Mater., 296, 34-42 . . . Current Status of JAERI Spallation Target Material Program. . . . Kikuchi, K.; Sasa, T.; Ishikura, S.; Mukugi, K.; Kai, T.; Ouchi, N.; Ioka, I. . . . July 2001 . . . JAERI, Ibaraki-ken, Japan; Mitsubishi Heavy Industry Ltd., Ibarki-ken, Japan.

J. Nucl. Mater., 296, 43-53 . . . Status of the First SINQ Irradiation Experiment, STIP-I. . . . Dai, Y.; Bauer, G.S. . . . July 2001 . . . Paul Scherrer Institut, Villigen PSI, Switzerland.

J. Nucl. Mater., 296, 54-60 . . . Radiation Damage to the 316 Stainless Steel Target Container Vessel at SNS. . . . Barnett, M.H.; Wechsler, M.S.; Dudziak, D.J.; Mansur, L.K.; Murphy, B.D. . . . July 2001 . . . North Carolina State University, Raleigh, NC; Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 296, 61-65 . . . Simulation of the Implantation of Recoils and Displacement Production in the 316 Stainless Steel Mercury-Container Vessel at SNS. . . . Zheng, Y.; Wechsler, M.S.; Dudziak, D.J.; Hunn, J.D.; Mansur, L.K. . . . July 2001 . . . North Carolina State University, Raleigh, NC; Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 296, 66-82 . . . Determination of Helium and Hydrogen Yield from Measurements on Pure Metals and Alloys Irradiated by Mixed High Energy Proton and Spallation Neutron Spectra in LANSCE . . . Garner, F.A.; Oliver, B.M.; Greenwood, L.R.; James, M.R.; Ferguson, P.D.; Maloy, S.A.; Sommer, W.F. . . . July 2001 . . . Pacific Northwest National Laboratory, Richland, WA; Los Alamos National Laboratory, Los Alamos, NM.

J. Nucl. Mater., 296, 83-89 . . . Helium Production for 0.8-2.5 GeV Proton Induced Spallation Reactions, Damage Induced in Metallic Window Materials. . . . Hilscher, D. et al. . . . July 2001 . . . Hahn-Meitner-Institute, Berlin, Germany; Forschungszentrum Julich, Julich, Germany; GANIL, Caen, France; Warsaw University, Warsaw, Poland.

J. Nucl. Mater., 296, 90-100 . . . Multiscale Modeling of Radiation Damage: Applications to Damage Production by GeV Proton Irradiation of Cu and W, and Pulsed Irradiation Effects in Cu and Fe. . . . Caturla, M.J.; Diaz de la Rubia, T.; Victoria, M.; Corzine, R.K.; James, M.R.; Greene, G.A. . . . July 2001 . . . Lawrence Livermore National Laboratory, Livermore, CA; Swiss Federal Inst. of Technology, Villigen, PSI, Switzerland; Los Alamos National Laboratory, Los Alamos, NM; Brookhaven National Laboratory, Upton, NY.

J. Nucl. Mater., 296, 101-111 . . . Does Pulsing in Spallation Neutron Sources Affect Radiation Damage? . . . Trinkaus, H.; Ullmaier, H. . . . July 2001 . . . Institut fur Festkorperforschung, Julich, Germany.

J. Nucl. Mater., 296, 112-118 . . . Microstructural Origins of Radiation-Induced Changes in Mechanical Properties of 316 L and 304 L Austenitic Stainless Steels Irradiated with Mixed Spectra of Hi . . . Sencer, B.H.; Bond, G.M.; Hamilton, M.L.; Garner, F.A.; Maloy, S.A.; Sommer, W.F. . . . July 2001 . . . New Mexico Institute of Mining and Technology, Socorro, NM; Pacific Northwest National Laboratory, Richland, WA; Los Alamos National Laboratory, Los Alamos, NM.

J. Nucl. Mater., 296, 119-128 . . . The Mechanical Properties of 316L/304L Stainless Steels, Alloy 718 and Mod 9Cr-1Mo After Irradiation in a Spallation Environment. . . . Maloy, S.A. et al. . . . July 2001 . . . Los Alamos National Laboratory, Los Alamos, NM; Oak Ridge National Laboratory, Oak Ridge, TN; Pacific Northwest National Laboratory, Richland, WA.

J. Nucl. Mater., 296, 129-138 . . . Tensile Properties of Candidate SNS Target Container Materials After Proton and Neutron Irradiation in the LANSCE Accelerator. . . . Farrell, K.; Byun, T.S. . . . July 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 296, 139-144 . . . The Mechanical Properties of an Alloy 718 Window After Irradiation in a Spallation Environment. . . . James, M.R.; Maloy, S.A.; Gac, F.D.; Sommer, W.F.; Chen, J.; Ullmaier, H. . . . July 2001 . . . Los Alamos National Laboratory, Los Alamos, NM; Forschungszentrum Julich, Julich, Germany.

J. Nucl. Mater., 296, 145-154 . . . Correlation of Radiation-Induced Changes in Mechanical Properties and Microstructural Development of Alloy 718 Irradiated with Mixed Spectra of High-Energy Protons and Spallation Neutrons . . . Sencer, B.H.; Bond, G.M.; Garner, F.A.; Hamilton, M.L.; Maloy, S.A.; Sommer, W.F. . . . July 2001 . . . New Mexico Institute of Mining and Technology, Socorro, NM; Pacific Northwest National Laboratory, Richland, WA; Los Alamos National Laboratory, Los Alamos, NM.

J. Nucl. Mater., 296, 155-164 . . . Impact of Irradiation on the Tensile and Fatigue Properties of Two Titanium Alloys. . . . Marmy, P.; Leguey, T. . . . July 2001 . . . Ecole Polytechnique Federale de Lausanne, Villigen Switzerland.

J. Nucl. Mater., 296, 165-173 . . . Retention of Implanted Hydrogen and Helium in Martensitic Stainless Steels and Their Effects on Mechanical Properties. . . . Jung, P.; Liu, C.; Chen, J. . . . July 2001 . . . Institut fur Festkorperforschung, Julich, Germany.

J. Nucl. Mater., 296, 174-182 . . . Microstructure of Both As-Irradiated and Deformed 304L Stainless Steel Irradiated with 800 MeV Protons. . . . Dai, Y.; Jia, X.; Chen, J.C.; Sommer, W.F.; Victoria, M.; Bauer, G.S. . . . July 2001 . . . Paul Scherrer Institut, Villigen PSI, Switzerland; Institut fur Festkoperforschung, Julich, Germany; Los Alamos National Laboratory, Los Alamos, NM; Ecole Polytechnique Federal de Lausanne, Villigen, Switzerland.

J. Nucl. Mater., 296, 183-191 . . . Origin of Hardening and Deformation Mechanisms in Irradiated 316 LN Austenitic Stainless Steel. . . . Lee, E.H.; Byun, T.S.; Hunn, J.D.; Farrell, K.; Mansur, L.K. . . . July 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 296, 192-202 . . . Auger Electron Spectroscopy Study of Alloy 718 and 304L Stainless Steel Irradiated with 800 MeV Protons. . . . García-Mazarío, M.; Hernández-Mayoral, M.; Lancha, A.M. . . . July 2001 . . . CIEMAT, Madrid, Spain.

J. Nucl. Mater., 296, 203-209 . . . Ion-Irradiation-Induced Hardening in Inconel 718. . . . Hunn, J.D.; Lee, E.H.; Byun, T.S.; Mansur, L.K. . . . July 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 296, 210-218 . . . Thermal Gradient Mass Transfer of Type 316L Stainless Steel and Alloy 718 in Flowing Mercury. . . . Pawel, S.J.; DiStefano, J.R.; Manneschmidt, E.T. . . . July 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 296, 219-224 . . . A Study on Martensitic and Austenitic Steels After Exposure in Mercury at 573 K Up to 5000 h. . . . Zalavutdinov, R.Kh. et al. . . . July 2001 . . . Russian Academy of Sciences, Moscow, Russia; Paul Scherrer Institut, Villigen PSI, Switzerland.

J. Nucl. Mater., 296, 225-230 . . . The Effect of Mercury on the Fatigue Behavior of 316 LN Stainless Steel. . . . Strizak, J.P.; DiStefano, J.R.; Liaw, P.K.; Tian, H. . . . July 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN; University of Tennessee, Knoxville, TN.

J. Nucl. Mater., 296, 231-236 . . . Corrosion Behavior of Steels in Flowing Lead-Bismuth. . . . Barbier, F.; Rusanov, A. . . . July 2001 . . . CEA-CEREM/SCECF, Gif-sur-Yvette, France; IPPE, Kaluga Region, Russia.

J. Nucl. Mater., 296, 237-242 . . . Corrosion Investigations of Steels in Flowing Lead at 400C and 550C. . . . Glasbrenner, H.: Konys, J.; Mueller, G.; Rusanov, A. . . . July 2001 . . . Forschungszentrum Karlsruhe, Karlsruhe, Germany; IPPE, Kaluga Region, Russia.

J. Nucl. Mater., 296, 243-248 . . . Compatibility Tests on Steels in Molten Lead and Lead-Bismuth. . . . Fazio, C.; Benamati, G.; Martini, C.; Palombarini, G. . . . July 2001 . . . ENEA-EURATOM, Bologna, Italy; Universita di Bologna, Bologna, Italy.

J. Nucl. Mater., 296, 249-255 . . . Evaluation of the Mechanical Properties of T91 Steel Exposed to Pb and Pb-Bi at High Temperature in Controlled Environment. . . . Schmidt, B.; Guerin, S.; Pastol, J.L.; Plaindoux, P.; Dallas, J.P.; Leroux, C.; Gorse, D. . . . July 2001 . . . CNRS-CECM, Vitry/Seine, France.

J. Nucl. Mater., 296, 256-264 . . . Embrittlement of the Martensitic Steel 91 Tested in Liquid Lead. . . . Nicaise, G.; Legris, A.; Vogt, J.B.; Foct, J. . . . July 2001 . . . Laboratoire de Metallugie Physique et Genie des Materiaux, Villeneuve d'ascq, France.

J. Nucl. Mater., 296, 265-272 . . . Behaviour of F82H Mod. Stainless Steel in Lead-Bismuth Under Temperature Gradient. . . . Gómez Briceño, D.; Martín Muñoz, F.J.; Soler Crespo, L.; Esteban, F.; Torres, C. . . . July 2001 . . . CIEMAT, Madrid, Spain.

J. Nucl. Mater., 296, 273-281 . . . Short-Term Static Corrosion Tests in Lead-Bismuth. . . . Soler Crespo, L.; Martín Muñoz, F.J.; Gómez Briceño, D. . . . July 2001 . . . CIEMAT, Madrid, Spain.

J. Nucl. Mater., 296, 282-288 . . . Intergranular Penetration and Embrittlement of Solid Nickel Through Bismuth Vapour Condensation at 700C. . . . Marié, N.; Wolski, K.; Biscondi, M. . . . July 2001 . . . Ecole Nationale Superieure des Mines de Saint-Etienne, Saint-Etienne, France.

J. Nucl. Mater., 296, 289-294 . . . Development of Oxygen Meters for the Use in Lead-Bismuth. . . . Konys, J.; Muscher, H.; Voss, Z.; Wedemeyer, O. . . . July 2001 . . . Forschungszentrum Karlsruhe, Karlsruhe, Germany.

J. Nucl. Mater., 296, 295-300 . . . Experimental Setup for Steel Corrosion Characterization in Lead Bath. . . . Ghetta, V.; Gamaoun, F.; Fouletier, J.; Henault, M.; Lemoulec, A. . . . July 2001 . . . LTPCM/ENSEEG and LEPMI/ENSEEG, Saint Martin d'Heres, France.

J. Nucl. Mater., 296, 301-304 . . . Kinetics of Gas Phase Oxygen Control Systems (OCS) for Stagnant and Flowing Pb-Bi Systems. . . . Lefhalm, C.H.; Knebel, J.U.; Mack, K.J. . . . July 2001 . . . Forschungszentrum Karlsruhe, Karlsruhe, Germany.

J. Nucl. Mater., 296, 305-311 . . . Monitoring of Low-Cycle Fatigue Degradation in X6CrNiTi18-10 Austenitic Steel. . . . Grosse, M.; Niffenegger, M.; Kalkhof, D. . . . July 2001 . . . Paul Scherrer Institute, Villigen, PSI, Switzerland.

J. Nucl. Mater., 296, 312-320 . . . Fabrication of a Tantalum-Clad Tungsten Target for KENS. . . . Kawai, M.; Kikuchi, K.; Kurishita, H.; Li, J-F.; Furusaka, M. . . . July 2001 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan; JAERI, Ibaraki-ken, Japan; Tohoku University, Ibaraki-ken, Japan.

J. Nucl. Mater., 296, 321-325 . . . Summary of the Fourth International Workshop on Spallation Materials Technology (IWSMT-4). . . . Bauer, G.S.; Dai, Y.; Maloy, S.; Mansur, L.K.; Ullmaier, H. . . . July 2001 . . . Paul Scherrer Institute, Villigen, Switzerland; Los Alamos National Laboratory, Los Alamos, NM; Oak Ridge National Laboratory, Oak Ridge, TN; Forschungszentrum Jülich, Jülich, Germany.

J. Nucl. Mater., 297, 1-6 . . . Optical Phenomena in KU-1 Silica Core Fiber Waveguides Under Pulsed Reactor Irradiation. . . . Demenkov, P.V.; Plaksin, O.A.; Stepanov, V.A.; Stepanov, P.A.; Chernov, V.M.; Golant, K.M.; Tomashuk, A.L. . . . July 2001 . . . State Scientific Centre of Russian Federation, Kaluga Region, Obninsk, Russia; General Physics Institute of the Russian Academy of Sciences, Moscow, Russia.

J. Nucl. Mater., 297, 7-13 . . . Vitrification of Liquid Waste from Nuclear Power Plants. . . . Sheng, J.; Choi, K.; Song, M-J. . . . July 2001 . . . China Institute of Atomic Energy, Beijing, China; Nuclear Environment Technology Institute, Taejon, South Korea.

J. Nucl. Mater., 297, 14-26 . . . Texture Dependent Plastic Behavior of Zr 702 at Large Strain. . . . Castelnau, O.; Rrancillette, H.; Bacroix, B.; Lebensohn, R.A. . . . July 2001 . . . Institut Galilee, Villentaneuse, France; GRCM, Rennes, France; Instituto de Fisica Rosario, Rosario, Argentina.

J. Nucl. Mater., 297, 27-34 . . . Surface Inventory of Tritium on Li₂TiO₃. . . . Kawagoe, T.; Nishikawa, M.; Baba, A.; Beloglazov, S. . . . July 2001 . . . Kyushu University, Fukuoka, Japan.

J. Nucl. Mater., 297, 35-42 . . . Coarsening-Densification Transition Temperature in Sintering of Uranium Dioxide. . . . Balakrishna, P.; Murty, B.N.; Chakraborthy, K.P.; Jayaraj, R.N.; Ganguly, C. . . . July 2001 . . . Nuclear Fuel Complex, Hyderabad, India.

J. Nucl. Mater., 297, 43-51 . . . Application of Normal Pulse Voltammetry to On-Line Monitoring of Actinide Concentrations in Molten Salt Electrolyte. . . . Iizuka, M.; Inoue, T.; Shirai, O.; Iwai, T.; Arai, Y. . . . July 2001 . . . Central Research Institute of Electric Power Industry, Tokyo, Japan; JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 297, 52-56 . . . Hydrogen Uptake and Corrosion Behavior of Zr-2.5Nb Pressure Tubes in Wolsong Unit 1. . . . Choo, K-N.; Kim, Y-S. . . . July 2001 . . . Korea Atomic Energy Research Institute, Taejon, South Korea.

J. Nucl. Mater., 297, 57-61 . . . 90-19/U HLW-Glass Leaching Mechanism in Underground Water. . . . Jiawei Sheng, Shanggeng Luo . . . July 2001 . . . China Institute of Atomic Energy, Beijing, China.

J. Nucl. Mater., 297, 62-68 . . . Oxide Layers of Zr-1% Nb Under PWR Primary Circuit Conditions. . . . Nagy, G.; Kerner, Z.; Battistig, G.; Pinter-Csordas, A.; Balogh, J.; Pajkossy, T. . . . July 2001 . . . KFKI Atomic Energy Research Institute, Budapest, Hungary; HAS Research Institute for Technical Physics and Materials Science, Budapest, Hungary.

J. Nucl. Mater., 297, 69-76 . . . An AB Initio Study of Formation and Desorption Reactions of H₂O Molecules from Surface Hydroxyl Groups in Silicates. . . . Nakazawa, T.; Yokoyama, K.; Grismanovs, V.; Katano, Y. . . . July 2001 . . . JAERI, Ibaraki-ken, Japan; OECD Halden Reactor Project, Halden, Norway.

J. Nucl. Mater., 297, 77-88 . . . Characterisation of Pre-Transition Oxides on Zircaloys. . . . Oskarsson, M.; Ahlberg, E.; Andersson, U.; Pettersson, K. . . . July 2001 . . . Royal Institute of Technology, Stockholm, Sweden; Goteborg University, Goteborg, Sweden.

J. Nucl. Mater., 297, 89-96 . . . Radiation Damage and Nanocrystal Formation in Uranium-Niobium Titanates. . . . Lian, J.; Wang, S.X.; Wang, L.M.; Ewing, R.C. . . . July 2001 . . . University of Michigan, Ann Arbor, MI.

J. Nucl. Mater., 297, 97-106 . . . What's New on Plutonium Up To 4000 K? . . . Boivineau, M. . . . July 2001 . . . Commissariat a l'Energie Atomique, Is-sur-Tille, France.

J. Nucl. Mater., 297, 107-112 . . . Measurement of Hydriding Susceptibility of Zircaloy Cladding by the Tube-Burst Technique at High Pressure and High Temperature. . . . Hong, H.S.; Olander, D.R. . . . August 2001 . . . University of California at Berkeley, Berkeley, CA.

J. Nucl. Mater., 297, 113-119 . . . Investigation on the Oxidation Characteristics of Copper-Added Modified Zircaloy-4 Alloys in Pressurized Water at 360C. . . . Hong, H.S.; Moon, J.S.; Kim, S.J.; Lee, K.S. . . . August 2001 . . . Hanyang University, Seoul, Republic of Korea.

J. Nucl. Mater., 297, 120-128 . . . Densification Behaviour and Sintering Kinetics of PuO₂ Pellets. . . . Kutty, T.R.G.; Khan, K.B.; Hedge, P.V.; Sengupta, A.K.; Majumdar, S.; Purushotham, D.S.C. . . . August 2001 . . . Bhabha Atomic Research Centre, Mumbai, India.

J. Nucl. Mater., 297, 129-137 . . . Preliminary Results on the Leaching Process of Phosphate Ceramics, Potential Hosts for Actinide Immobilization. . . . Bois, L.; Guittet, M. J.; Carrot, F.; Trocellier, P.; Gautier-Soyer, M. . . . August 2001 . . . Laboratoire Pierre Sue, Gif-sur-Yvette, France; SRSIM, Gif-sur-Yvette, France.

J. Nucl. Mater., 297, 138-148 . . . Effects of Carbide Precipitation on the Strength and Charpy Impact Properties of Low Carbon Mn-Ni-Mo Bainitic Steels. . . . Im, Y-R.; Oh, Y.J.; Lee, B-J.; Hong, J.H.; Lee, H-C. . . . August 2001 . . . Seoul National University, Seoul, South Korea; Korea Atomic Energy Research Institute, Taejon, South Korea; Korea Research Institute of Standards and Science, Taejon, South Korea.

J. Nucl. Mater., 297, 149-152 . . . On the Mechanism for Dose Rate Dependence of Stationary Luminescence of F and F+ Centres Excited by Electron Beam in Alpha-Al2O3. . . . Meshakin, V.I.; Tanabe, T. . . . August 2001 . . . Nagoya University, Nagoya, Japan.

J. Nucl. Mater., 297, 153-160 . . . Diffusion Reactions in Titanium/Inconel-600 System. . . . Patil, R.V.; Kale, G.B.; Gawde, P.S. . . . August 2001 . . . Bhabha Atomic Research Centre, Mumbai, India.

J. Nucl. Mater., 297, 161-175 . . . Microstructure Evolution in Austenitic Fe-Cr-Ni Alloys Irradiated with Rotons: Comparison with Neutron-Irradiated Microstructures. . . . Gan, J.; Was, G.S. . . . August 2001 . . . Pacific Northwest National Laboratory, Richland, WA; University of Michigan, Ann Arbor, MI.

J. Nucl. Mater., 297, 176-205 . . . Post-Irradiation Examination of High Burnup Mg Doped UO2 in Comparison with Undoped UO2, Mg-Nb Doped UO2 and Ti Doped UO2. . . . Fujino, T.; Shiratori, T.; Sato, N.; Fukuda, K.; Yamada, K.; Serizawa, H. . . . August 2001 . . . Tohoku University, Sendai, Japan; JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 297, 206-213 . . . Influence of the Precursor and the Calcination Temperature on the Dissolution of Thorium Dioxide. . . . Hubert, S.; Barthelet, K.; Fourest, B.; Lagarde, G.; Dacheux, N.; Baglan, N. . . . August 2001 . . . Universite Paris-Sud, Orsay, France; Institut de Protection et de Surete Nucleaire, Fontenay-aux-Roses, France.

J. Nucl. Mater., 297, 214-219 . . . A Kinetic Model for Corrosion and Precipitation in Non-Isothermal LBE Flow Loop. . . . He, B.X.; Li, N.; Mineev, M. . . . August 2001 . . . Los Alamos National Laboratory, Los Alamos, NM.

J. Nucl. Mater., 297, 220-229 . . . Diffusion Reaction Between Zr-2.5 wt% Nb Alloy and Martensitic Grade 403 Stainless Steel. . . . Bhanumurthy, K.; Patil, R.V.; Srivatsava, D.; Gawde, P.S.; Kale, G.B. . . . August 2001 . . . Bhabha Atomic Research Centre, Mumbai, India.

Nucl. Eng. Design, 207, 257-267 . . . Current Topics of the Structural Design for LWR Plants in Japan. . . . Minematsu, A. . . . August 2001 . . . Tokyo Electric Power Co., Tokyo, Japan.

Nucl. Eng. Design, 207, 269-286 . . . Probabilistic Fracture Mechanics Analysis of Nuclear Structural Components: A Review of Recent Japanese Activities. . . . Yagawa, G.; Kanto, Y.; Yoshimura, S.; Machida, H.; Shibata, K. . . . August 2001 . . . University of Tokyo, Tokyo, Japan; Toyohashi University of Technology, Aichi-ken, Japan; Advanced Reactor Technology Co., Japan; JAERI, Ibaraki-ken, Japan.

Nucl. Eng. Design, 207, 287-298 . . . Risk-Benefit Analyses of SG Tube Maintenance Based on Probabilistic Fracture Mechanics. . . . Isobe, Y.; Sagisaka, M.; Oshimura, S.; Yagawa, G. . . . August 2001 . . . Nuclear Fuel Industries Ltd., Osaka, Japan; University of Tokyo, Tokyo, Japan.

Nucl. Eng. Design, 207, 299-305 . . . Steam Generator Mock-Up for Assessment of Inservice Inspection Technology. . . . Kupperman, D.S.; Bakhtiari, S.; Muscara, J. . . . August 2001 . . . Argonne National Laboratory, Argonne, IL; U.S. Nuclear Regulatory Commission, Washington, DC.

Nucl. Eng. Design, 207, 307-316 . . . Experience with Piping in German NPPs with Respect to Ageing-Related Aspects. . . . Michel, F.; Reck, H.; Schulz, H. . . . August 2001 . . . Gesellschaft fur Anlagen, Cologne, Germany.

Nucl. Eng. Design, 207, 317-325 . . . Non-Destructive Diagnosis Technique for Aging of Cables Used at Nuclear Power Plants. . . . Nishida, Y. . . . August 2001 . . . Kansai Electric Power Co., Osaka, Japan.

Nucl. Eng. Design, 207, 327-339 . . . Behaviour of a PWR Vessel Dissimilar Metal Weld During a Steam Line Break Transient. . . . Bhandari, S.; Dubois, D.; Guichard, D. . . . August 2001 . . . Framatome, Paris and Saint Marcel, France.

Nucl. Eng. Design, 207, 341-350 . . . Plastic Collapse and LBB Behavior of Statically Indeterminate Piping System Subjected to a Static Load. . . . Yoo, Y.S.; Ando, K. . . . August 2001 . . . Yokohama National University, Kanagawa-ken, Japan.

Nucl. Eng. Design, 207, 351-357 . . . Application of Statically Indeterminate Fracture Mechanics, SIFM, to a Circumferentially Cracked Cylinder Problem. . . . Matsubara, M.; Stumpfrock, L.; Roos, E. . . . August 2001 . . . Gunma University, Gunma-ken, Japan; Universität Stuttgart, Stuttgart, Germany.

Nucl. Eng. Design, 208, 1-13 . . . Development of a PFM Code for Evaluating Reliability of Pressure Components Subject to Transient Loading. . . . Shibata, K.; Kato, D.; Li, Y. . . . August 2001 . . . JAERI, Ibaraki-ken, Japan; Fuji Research Institute Corp., Tokyo, Japan.

Nucl. Eng. Design, 208, 15-28 . . . A 3-D Lagrangian Stochastic Model for the Meso-Scale Atmospheric Dispersion Applications. . . . Raza, S.S.; Avila, R.; Cervantes, J. . . . August 2001 . . . Instituto Nacional de Investigaciones Nucleares, Mexico; Facultad de Ingenieria, UNAM, Mexico.

Nucl. Eng. Design, 208, 29-50 . . . Performance Analysis of Coated Plutonia Particle Fuel Compact for Radioisotope Heater Units. . . . El-Genk, M.S.; Tournier, J-M. . . . August 2001 . . . University of New Mexico, Albuquerque, NM.

Nucl. Eng. Design, 208, 51-66 . . . Computations of Post-Trip Reactor Core Thermal Hydraulics Using a Strain Parameter Turbulence Model. . . . Cotton, M.A.; Ismael, J.O.; Kirwin, P.J. . . . August 2001 . . . University of Manchester, Manchester, UK; Brunel University, Uxbridge, UK; Perkins Technology, Ltd.; Peterborough, UK.

Nucl. Eng. Design, 208, 67-85 . . . Boron Mixing in Complex Geometries: Flow Structure Details. . . . Kiger, K.T.; Gavelli, F. . . . August 2001 . . . University of Maryland, College Park, MD; Catholic University of America, Washington, DC.

Nucl. Eng. Design, 208, 87-97 . . . Entrainment of Soluble and Non Soluble Tracers from a Boiling Water Surface. . . . Cosandey, J.O.; von Rohr, P.R. . . . August 2001 . . . Swiss Federal Institute of Technology, Zurich, Switzerland.

Nucl. Eng. Design, 208, 99-116 . . . Study on Local Hydrogen Behaviors in a Subcompartment of the NPP Containment. . . . Choi, Y-S.; Lee, U-J.; Park, G-C. . . . August 2001 . . . Seoul National University, Seoul, South Korea.

Nucl. Technol., 135, 1-16 . . . BWR Regional Instability Analysis by TRAC/BF1-ENTREE - I: Application to Density-Wave Oscillation. . . . Hotta, A.; Honma, M.; Ninokata, H.; Matsui, Y. . . . July 2001 . . . Toden Software, Inc., Tokyo, Japan; Tokyo Institute of Technology, Tokyo, Japan.

Nucl. Technol., 135, 17-38 . . . BWR Regional Instability Analysis by TRAC/BF1-ENTREE - II: Application to Ringhals Unit-1 Stability Test. . . . Hotta, A.; Zhang, M.; Ninokata, H. . . . July 2001 . . . Toden Software, Inc., Tokyo, Japan; Tokyo Institute of Technology, Tokyo, Japan.

Nucl. Technol., 135, 39-50 . . . Parallel Computing Adaptive Simulated Annealing Scheme for Fuel Assembly Loading Pattern Optimization in PWRs. . . . Lee, H.C.; Shim, H.J.; Kim, C.H. . . . July 2001 . . . Seoul National University, Seoul, Korea.

Nucl. Technol., 135, 51-66 . . . Thermal-Hydraulic Analysis of the 3-MW Triga Mark-II Research Reactor Under Steady-State and Transient Conditions. . . . Huda, M.Q.; Bhuiyan, S.I.; Chakrobortty, T.K.; Sarker, M.M.; Mondal, M.A.W. . . . July 2001 . . . Atomic Energy Research Establishment, Dhaka, Bangladesh.

Nucl. Technol., 135, 92-108 . . . Characterization of the Mobilities of Selected Actinides and Fission/Activation Products in Laboratory Columns Containing Subsurface Material from the Snake River Plain . . . Fjeld, R.A. et al. . . . August 2001 . . . Clemson University, Anderson, SC; Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.

Nucl. Technol., 135, 109-122 . . . Using an IIST 1% Cold-Leg SBLOCA Experiment with Passive Safety Injection to Assess the RELAP5/MOD3.2 Code. . . . Lee, C-H.; Huang, I-M.; Chang, C-J. . . . August 2001 . . . Institute of Nuclear Energy Research, Lung Tan, Taiwan.

Nucl. Technol., 135, 131-145 . . . A Tomographic Method for Verification of the Integrity of Spent Nuclear Fuel Assemblies - I: Simulation Studies. . . . Jacobsson, S.; Andersson, C.; Håkansson, A.; Bäcklin, A. . . . August 2001 . . . Uppsala University, Uppsala, Sweden.

Nucl. Technol., 135, 146-153 . . . A Tomographic Method for Verification of the Integrity of Spent Nuclear Fuel Assemblies - II: Experimental Investigation. . . . Jacobsson, S.; Håkansson, A.; Jansson, P.; Bäcklin, A. . . . August 2001 . . . Uppsala University, Uppsala, Sweden.

Nucl. Technol., 135, 154-161 . . . Effect of Water Radiolysis Caused by Dispersed Radionuclides on Oxidative Dissolution of Spent Fuel in a Final Repository. . . . Liu, J.; Neretnieks, I. . . . August 2001 . . . Royal Institute of Technology, Stockholm, Sweden.