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. 435 May 2001
"Experience is often what you get when you were expecting something else." Author unknown

Price Increase to Take Place May 1, 2001

Notice: Effective May 1, 2001, the cost of RSICC packages will rise to meet standards set by OSTI (Office of Science and Technical Information) cost recovery levels. As we continue to provide RSICC special services in software management and distribution, i.e., quality checks and repackaging, we will now have charges that reflect the partial funding needs to handle the 4000 active customers per year. The new schedule is listed below. RSICC wishes to thank those offices within DOE and NRC which provide additional support that help keep costs down and quality up.
RSICC's DOE/NRC funding offices and their contractors No charge
DOE contractors, other government agencies, educational institutions, Non-Profit organizations $450
General public (includes other government contractors) $1150
ALL Foreign installations  $1900


NRC Codes Made Available

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.



Three new and two newly frozen packages were added to the computer code software and data collection during the month, one of which is a foreign contribution.

OP SYS: Unix
Language: F77 and C
Computers: Sun, IBM RS/6000
Format: tar

Argonne National Laboratory, Argonne, Illinois, contributed a newly frozen version of this code system which uses variational nodal methods and finite difference methods to solve neutron diffusion and transport theory problems. The DIF3D8.0/ VARIANT8.0 release differs from the previous DIF3D7.0 release in that it includes a significantly expanded set of solution techniques using variational nodal methods. DIF3D's nodal option solves the multigroup steady-state neutron diffusion equation in two- and three-dimensional hexagonal and cartesian geometries and solves the transport equation in two- and three-dimensional cartesian geometries. Eigenvalue, adjoint, fixed source and criticality (concentration) search problems are permitted as are anisotropic diffusion coefficients. Flux and power density maps by mesh cell and region-wise balance integrals are provided.

The included installation procedure requires Fortran 77 and C compilers. With modifications the program can be executed entirely in Fortran. Optional dynamic memory allocation and timing routines supplied from host machine libraries or code in "C" may be used on Unix workstations. Although developed on the Cray and IBM 30xx, the current version is tailored to Sun SparcStations and IBM AIX RS/6000. It was tested at RSICC under SOLARIS 2.6 on a SPARCStation and under AIX 4.3.3 on an IBM RS/6000. The package is transmitted on CD as a UNIX tar file which includes source code, sample problem input and output, scripts, and documentation. References: ANL-82-64 (1984), ANL-83-1 (1983), ANL-95/40 (October 1995), and ANL-83-3 (May 1992). Fortran 77 and C; Unix Workstations: Sun SparcStation and IBM RS/6000 (C00649/MFMWS/01).

OP SYS: Unix
Language: F77 and C
Computers: Sun and IBM RS/6000
Format: tar

Argonne National Laboratory, Argonne, Illinois, contributed a newly frozen version of this code system designed for the analysis of fast reactor fuel cycles. Two basic types of analysis problems are solved: 1) the infinite-time, or equilibrium, conditions of a reactor operating under a fixed fuel management scheme, or 2) the explicit cycle-by-cycle, or nonequilibrium operation of a reactor under a specified periodic or non-periodic fuel management program. REBUS-3 will handle both equilibrium and non-equilibrium problems using a number of different core geometries including triangular and hexagonal mesh. The neutronics solution may be obtained using finite difference, nodal diffusion-theory and variational nodal transport methods. Fixed source depletion may be done with the three solution methods. Microscopic cross sections are permitted to vary as a function of the atom density of various reference isotopes in the problem as appropriate for soft spectrum systems. The user may specify control rod positions at each time node in the problem.

REBUS-3 is fully compatible with the CCCC coding standards and interface data sets. It utilizes the nodal option of DIF3D8.0 and VARIANT 8.0 (CCC-649) codes to obtain the neutronics solution.

However, this CCC-653 distribution does not include the DIF3D main program, which is in the CCC-649/ DIF3D package.

The included installation procedure requires Fortran 77 and C compilers. It was tested at RSICC under SOLARIS 2.6 on a SPARCStation and under AIX 4.3.3 on an IBM RS/6000. The package is transmitted on CD as a UNIX tar file which includes source code, sample problem input and output, scripts, and documentation. References: ANL-83-2 (March 1983 revised October 26, 1990), ANL-7721 (October 1978). Fortran 77 and C; Sun SparcStation, IBM RS/6000 (C00653/MNYWS/01).

OP SYS: Unix
Language: N/A
Computers: Many
Format: GNU compressed tar

ENEA - Centro Ricerche, Bologna, Italy, through the OECD Nuclear Energy Agency Data Bank, Issy-les-Molineaux, France, contributed a new library processed in ACE format for the MCNP Monte Carlo transport code with the NJOY-94.66 nuclear data processing system. This continuous energy cross-section data library designated MCJEF22NEA.BOLIB is based on JEF-2.2 and IRDF-90. It contains 107 isotopes/natural elements, including fission products, processed for up to eight temperatures: 300 K, 500 K, 560 K, 760 K, 800 K, 1000 K, 1500 K and 2200 K. The processed data include gamma-ray and gas production data when available in the specific JEF-2.2 evaluated data files.

Thermal scattering cross sections were processed for some of the most important moderator materials using the thermal scattering matrices S (alpha, beta) at various temperatures, included in the original JEF-2.2 thermal scattering law data file.

Nuclides include: H-1, H-2, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-nat, N-14, N-15, O-16, O-17, F-19, Na-23, Mg-nat, Al-27, Si-nat, Cl-nat, Ti-nat, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Zr-90, Zr-91, Zr-92, Zr-94, Zr-96, Zr-nat, Nb-93, Mo-92, Mo-94, Mo-95, Mo-96, Mo-97, Mo-98, Mo-100, Mo-nat, Tc-99, Ru-101, Ru-102, Ru-104, Rh-103, Pd-105, Pd-107, Ag-109, I-129, Xe-131, Cs-133, Pr-141, Nd-143, Nd-145, Pm-147, Sm-147, Sm-149, Sm-150, Sm-151, Sm-152, Eu-153, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158, Gd-160, Hf-174, Hf-176, Hf-177, Hf-178, Hf-179, Hf-180, Pb-nat, Bi-209, Th-232, U-234, U-235, U-236, U-238, Np-237, Pu-238, Pu-239, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-242, Am-242m, Am-243, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248.

H in CH2 (polyethylene), H in H2O (light water), D in D2O (heavy water), C (graphite),

Be (beryllium metal)

DOSIMETRY CROSS-SECTION: 16-S-32, 48-Cd-0, 79-Au-197

The distribution was prepared on a Unix system. On a Windows-based PC, one may use utilities such as WinZip(R) to unzip and extract the library files. The data libraries are transmitted on a CD in a tar file which includes the data libraries in GNU compressed files and xsdir files. The 372 MB tar file is transmitted on either a CD-ROM. The uncompressed ASCII files are about one GB. References: ENEA - KT-SCG-00008 (February 24, 2000) and Readme.txt (March 2000). ASCII card images; Unix workstation (D00203/MNYCP/00).

OP SYS: Windows/Unix
Language: Fortran
Computers: Many
Format: WinZip

The National Institute of Standards and Technology, Department of Commerce, Gaithersburg, Maryland, contributed this database of cross sections for the elastic scattering of electrons and positrons by atoms. The database includes cross sections at 61 energies for electrons and 41 energies from positrons, covering the energy region from 1 KeV to 100 MeV. The number of deflection angles included in the database is 314. Up to 10 MeV, the RELEL code was used to calculate the data. Above 10 MeV the ELSCAT code was used, which calculated the factored cross sections and evaluated the screening factor Kscr in WKB approximation. These data are an extension of an earlier database, ELAST (Report NISTIR 5188, 1993). This database was developed to provide input for transport codes, such as ETRAN, and includes differential cross sections, the total cross sections, and the transport cross sections. In addition, a code TRANSX is provided that generates transport cross section of arbitrary order, which are needed to evaluate the coefficients in Goudsmit-Saunderson multiple-scattering angular distribution. The database is transmitted on CD which includes documentation and the self-extracting archived data files and Fortran source codes written in a self-extracting compressed DOS file. No executables are included in this package. Reference: NISTIR 6573 (November 1, 2000). ASCII card images, Personal Computers (D00208/MNYCP/00).

OP SYS: Unix
Language: N/A
Computers: Many
Format: GNU comprressed tar

The University of Texas, Austin, Texas, contributed these continuous-energy neutron cross section libraries for temperatures 300 to 1365 K developed for use with MCNP. UTXS6 is based on ENDF/B-VI except for zinc and erbium for which the Russian (BROND-2) and the Chinese (CENDL-2) libraries were used. UTXS is a project whereby continuous-energy cross section libraries in ACE format were generated using the NJOY94.105 processing code. Libraries for various materials were generated at typical operating temperatures of the U.S. Pressurized Water Reactor (PWR), Boiling Water Reactor (BWR), and the Russian PWR (VVER), as well as libraries for other non-reactor applications such as nuclear medicine. Isotopes/natural elements, including fission products, were processed for up to nineteen temperatures: 300 K, 450 K, 479 K, 500 K, 558 K, 560 K, 570 K, 579 K, 600 K, 620 K, 755 K, 833 K, 900 K, 920 K, 1027 K, 1100 K, 1145 K, 1154 K, and 1365 K.

The data libraries are transmitted on a CD in a 610 MB tar file which includes GNU compressed data files and xsdir. The uncompressed ASCII files are about 1.6 GB. The UTXS library distribution was prepared on a Unix system. On a Windows-based PC, one may use utilities such as WinZip(R) to unzip and extract the library files. Reference: ANRCP-1999-28 (October 1999). ASCII card images; Unix workstation (D00211/MNYCP/00).


Clifford G. Shull, who pioneered neutron scattering research with Ernest Wollan at ORNL in the 1940s and won a Nobel Prize in physics in 1994 for the work, died March 31 after a brief illness. He was 85. Shull started working on neutron scattering in 1946 with Wollan, and for the next nine years they explored ways of using the neutrons produced by nuclear reactors to probe the atomic structure of materials. Shull visited ORNL shortly after he received his Nobel to great acclaim and last visited ORNL as special guest for the groundbreaking of the Spallation Neutron Source, in December 1999. He was a professor emeritus at the Massachusetts Institute of Technology.
ORNL Today

 Samuel H. Untermyer II, 88, ANS Fellow Emeritus, charter and honorary lifetime ANS member, and inventor of the boiling water reactor. Untermyer was engaged in power plant engineering since graduating from MIT in 1934. He became associated with nuclear energy after beginning work at ORNL in 1946 as Eugene Wigner's assistant, joined Argonne National Laboratory in 1949 and developed the design for the CP-5 heavy-water reactor and participated in the facility's startup. Among other things, he served as chairman of the National Nuclear Corporation from 1967 to 1985 and in the late 1980's he formed the Explosive Detection Corp. and served as president. He died on January 27 at home in Portola Valley, CA.

ANS Nuclear News

 Donald C. Lawrence, 69, retired nuclear and health physicist and brachytherapy pioneer died December 28, 2000. While managing the health physics department at Hazelton Nuclear Science Corp. in the early 1960s, he developed iodine-125 implants, which increased the value of brachytherapy to cancer patients. He founded Lawrence Soft Ray Corp in the late 1960s to produce and market the radiation seeds, and later sold the company to 3M Corp.

ANS Nuclear News



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.


Argonne National Laboratory will conduct a training workshop on the RESRAD family of risk assessment codes on May 8-11, 2001.  The latest probabilistic versions of RESRAD 6.0 and RESRAD-BUILD 3.0 will be used.  The tentative agenda of this workshop can be found on the RESRAD web site http://web.ead.anl.gov/resrad/training/agendaMay2001.htm.  Space is limited.  For registration, please contact Carole Ealy at 630-252-5677 or email: RESRAD@anl.gov. (Due to the date of this workshop, this announcement will appear only in the web version of the newsletter.)


A training workshop for the Monte Carlo criticality code MONK8 is being held at the University of New Mexico, June 4-8, 2001. The price of the workshop is $1,500 per person excluding taxation and local duties.

MONK is a well-known, widely-used and fully supported criticality code that brings together powerful geometry modelling, accurate collision physics and robust convergence into a convenient easy-to-use package. Supporting visualization and productivity tools, a selection of modern nuclear data libraries and an extensive validation database provide further benefits to the criticality practitioner.

The 5-day workshop is aimed at providing new or inexperienced users of MONK with a broad understanding of the capabilities of the code and hands-on experience of constructing input specifications. A mixture of lectures and practical sessions provide an opportunity for constructing MONK models for sample problems, checking the input specifications and performing full calculations. The course tutors have considerable experience in developing the MONK code and in its application to practical problems. It will be appropriate for those with some criticality analysis experience but little or no experience using the MONK code.

MONK is licensed by AEA Technology Engineering Services Inc. through its 'ANSWERS Software Service'. For organizations new to MONK, the ANSWERS Software Service is pleased to be able to offer course attendees a FREE MONK CODE TRIAL for the six-month period following the course. This will provide attendees with an extended opportunity to assess the benefits that the use of MONK could bring to their organizations.

For details of this and other UNM criticality courses see the 'Critical Comments' newsletter at http://www-chne.unm.edu/ncssc/webversion.pdf.

Seventh International Radiopharmaceutical Dosimetry Symposium

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.

Short Courses on Monte Carlo Analysis and Nuclear Criticality Safety

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).

The XIX Autumn School on New Perspectives with Nuclear Radioactivity

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.

MCNP™ Workshops

The following is the 2001 schedule for Monte Carlo N-Particle Transport Code Workshop. These classes are taught by the team who develops and maintains MCNP.
5-8 June
                    Introductory Class Los Alamos Natl. Laboratory

The Introductory class is for people who have little or no experience with MCNP. The class surveys 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.

NOTE: While MCNP supports a number of platforms, class computers are usually Unix machines. Experience with Unix will be helpful to the student but is not essential.

Costs For Domestic U.S. Class: Cost for the class is $1,800. There is a $300 discount if payment is received by the close of registration/early payment deadline for each class. Radiation Safety Information Computational Center (RSICC) provides the code and data package and documentation for a reduced fee of $310 to all who complete the class and free to students employed by sponsors that fund RSICC.

The class fee includes a notebook with all class viewgraphs (over 300) and handouts. Dinner the first evening is included as part of your registration fee and snacks and refreshments are provided during class breaks. Lodging will be available for roughly $75 per night. Information will be sent by follow-up letter or email when we receive your registration information.

The class provides interactive computer learning. Time will be available to discuss individual questions and problems with MCNP experts. To register for the LANL class via the Internet, go to http://www.solutionsbyhqc.com/mcnpform.html.

Visual Editor Classes Offered

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.

SCALE Training Course Schedule

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

 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 2000. 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.


June 2001

International Joint Power Conference, June 4-7, 2001, New Orleans, LA, sponsored by the American Society of Mechanical Engineers. Contact: ASME (tel 800-843-2763, fax 212-591-7674, email infocentral@asme.org, url www.asme.org).

MONK Nuclear Criticality Introductory Workshop (Includes code trial), June 4-8, 2001, University of New Mexico, Albuquerque. Contact: Simon Aplin, AEA Technology, ANSWERS Software Service. (tel +44 (0) 1305 203634, fax +44 (0) 1305 202746, email simon.aplin@aeat.co.uk, url www.aeat.co.uk/answers).

28th Annual Meeting and International Conference on Nuclear Energy, June 10-12, 2001, Las Vegas, NV, sponsored by the World Nuclear Fuel Market. Contact: WNFM (tel 678-328-1245, fax 770-263-7982, email dcason@nacintl.com, url www.wnfm.com).

ANS Annual Meeting, June 17-21, 2001, Milwaukee, WI. Contact: Michael Sellman, general chair, (tel 715-377-3302, fax 715-377-3355, email mbsellman@nmcco.com, url www.ans.org).

Embedded Topical Meeting: Nuclear Safety Goals and Safety Culture, June 17-21, 2001, Milwaukee, WI, sponsored by the Nuclear Society of Russia and the Ministry of the Russian Federation for Atomic Energy and cosponsored by ANS. Contact: Edward Fuller, technical program co-chair (tel 408-356-3090, email efuller2039@hotmail.com, url www.ans.org).

European Nuclear Fuel Seminar, June 18-21, 2001, Zurich, Switzerland, sponsored by NAC International. Contact: NAC, (tel 770-447-1144, fax 770-447-1797).

48th Annual Meeting of the Society of Nuclear Medicine, June 23-27, 2001, Toronto, Ontario, Canada. Contact: SNM (tel 703-708-9000, fax 703-708-9015, url www.snm.org).

ASTM Committee E10 on Nuclear Technology and Applications, June 24-27, 2001, Norfolk, VA, sponsored by the American Society of Testing and Materials. Contact: Jeff Adkins, ASTM (tel 610-832-9738; fax 610-832-9555; email: jadkins@astm.org; url www.astm.org).

Annual Scientific and Technical Conference on Research Reactors: Science and High Technology, June 25-29, 2001, Dimitrovgrad, Ulyanovsk region, Russia, sponsored by the Nuclear Society of Russia and the Ministry of the Russian Federation for Atomic Energy. Contact: Nina Antoshkina (tel +7 095 196 9887, fax +7 095 882 5937, email agagarin@kiae.ru).

EPRI 2001 International Low-Level Waste Conference and Exhibit Show, and ASME/EPRI Radwaste Workshop, June 25-29, 2001, Orlando, FL, sponsored by the Electric Power Research Institute. Contact: Vy Dang (tel 650-855-2239, email vdang@epri.com).

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).

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).

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).


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)
Proceedings on CD . . . The First International Symposium on Supercritical Water-cooled Reactors, Design and Technology.. . . 2001 . . . The University of Tokyo, Tokyo, Japan. www.tokai.t.u-tokyo.ac.jp.

Ann. Nucl. Energy, 28, 723-739 . . . Measurements of Neutron Induced Fission Cross-Section for 242mAm from 0.003 eV to 10 keV Using Lead Slowing-Down Spectrometer, Thermal Neutron Facility and Time-of-Flight Method . . . Kai, T.; Kobayashi, K.; Yamamoto, S.; Cho, H-J.; Fujita, Y.; Kimura, I.; Ohkawachi, Y.; Wakabayashi, T.. . . May 2001 . . . Kyoto University, Osaka, Japan; Japan Nuclear Cycle Development Institute, Ibaraki, Japan.

Ann. Nucl. Energy, 28, 741-754 . . . The Three-Dimensional Power Distribution Control in Load Following of the Heating Reactor. . . . Liu Wenfeng, Luo Zhengpei, Li Fu, Wang Yaqi . . . May 2001 . . . Tsinghua University, Beijing, China.

Ann. Nucl. Energy, 28, 755-776 . . . On Some One-Speed Neutron Transport Problems Revisited and Reformulated. . . . Williams, M.M.R. . . . May 2001.

Ann. Nucl. Energy, 28, 777-803 . . . Groundwater Contaminant Transport in Presence of Colloids I. A Stochastic Nonlinear Model and Parameter Identification. . . . Marseguerra, M.; Patelli, E.; Zio, E. . . . May 2001 . . . Polytechnic of Milan, Milan, Italy.

Ann. Nucl. Energy, 28, 805-824 . . . A 3D Nodal Mixed Dual Method for Nuclear Reactor Kinetics with Improved Quasistatic Model and a Semi-Implicit Scheme to Solve the Precursor Equations. . . . Dahmani, M.; Baudron, A.M.; Lautard, J.J.; Erradi, L. . . . May 2001 . . . CEA-DRN/DMT/SERMA, Gif-sur-Yvette, France; Laboratoire de Physique Nucleaire, Rabat, Morocco; Ecole Polytechnique de Montreal, Montreal, Canada.

Ann. Nucl. Energy, 28, 825-829 . . . The Critical Problem with High-Order Anisotropic Scattering. . . . Siewert, C.E. . . . May 2001 . . . North Carolina State University, Raleigh, NC.

Ann. Nucl. Energy, 28, 831-855 . . . Improvement of Reactivity Coefficients of Metallic Fuel LMFBR by Adding Moderating Material. . . . Tsujimoto, K.; Iwasaki, T.; Hirakawa, N.; Osugi, T.; Okajima, S.; Andoh, M. . . . June 2001 . . . Tohoku University, Miyagi, Japan; JAERI, Ibaraki, Japan.

Ann. Nucl. Energy, 28, 857-873 . . .Validation of Coupled Neutron Kinetic/Thermal-Hydraulic Codes. Part 1: Analysis of a VVER-1000 Transient (Balakovo-4) . . . Mittag, S.; Kliem, S.; Weib, F.P.; Kyrki-Rajamaki, R.; Hamalainen; Langenbuch, S.; Danilin, S.; Hadek, J.; Hegyi, G.; Kuchin, A.; Panayotov, D.. . . June 2001 . . . FZR Forschungszentrum Rossendorf, Dresden, Germany; GTT Energy/Nuclear Energy, VTT, Finland; GRS, Gesellschaft fur Anlagen- und Reaktorsicherheit, Garching, Germany; Kurchatov Institute, Moscow, Russia; NRI Nuclear Research Institute, Czech Republic; AEKI-KFKI Atomic Energy Research Institute, Budapest, Hungary; STCNRS-Scientific & Technical Center on Nuclear and Radiation Safety, Kiev, Ukraine; INRNE-Institute of Nuclear Research and Nuclear Energy, Sofia, Bulgaria.

Ann. Nucl. Energy, 28, 875-893 . . . An Approach to Multi-attribute Utlity Analysis Under Parametric Uncertainty. . . . Kelly, M.; Thorne, M.C. . . . June 2001 . . . AEA Technology, Oxon, United Kingdom.

Ann. Nucl. Energy, 28, 895-912 . . . A Hierarchial Domain Decomposition Boundary Element Method with a Higher Order Polynomial Expansion for Solving 2-D Multiregion Neutron Diffusion Equations. . . . Chiba, G.; Tsuji, M.; Shimazu, Y. . . . June 2001 . . . Hokkaido University, Sapporo, Japan.

Ann. Nucl. Energy, 28, 913-921 . . . Study of Kinetic Parameters in the RA-4 Reactor by Means of Computational Modeling and Neutron Noise Measurements. . . . Quinteiro, G. . . . June 2001 . . . Comision Nacional de Energia Atomica, Capital Federal, Argentina.

Ann. Nucl. Energy, 28, 923-933 . . . Numerical Solution of the Chain Model of Fission Product Nuclides. Effect on the Reactivity of the Reactor. . . . Aboanber, A.E. . . . June 2001 . . . Tanta University, Tanta, Egypt.

Ann. Nucl. Energy, 28, 937-951 . . . Measurements of Double-Differential Neutron Emission Cross-Sections of 238U and 232Th for 2.6, 3.6 and 11.8 MeV Neutrons. . . . Miura, T.; Baba, M.; Ibaraki, M.; Win, T.; Sanami, T.; Hirasawa, Y. . . . July 2001 . . . Tohoku University, Sendai, Japan.

Ann. Nucl. Energy, 28, 953-966 . . . Monitoring the Stability of BWR Oscillation by Nonlinear Time Series Modeling. . . . Shi, Z.; Tamura, Y.; Ozaki, T. . . . July 2001 . . . The Institute of Statistical Mathematics, Tokyo, Japan.

Ann. Nucl. Energy, 28, 967-982 . . . Implementation of an Integrated On-Line Process Surveillance and Diagnostic System at the Halden Reactor Project: MOAS. . . . Kim, I.S.; Grini, R-E.; Nilsen, S. . . . July 2001 . . . Hanyang University, Seoul, South Korea; OECD Halden Reactor Project, Halden, Norway.

Ann. Nucl. Energy, 28, 983-991 . . . Estimation of the Moderator Temperature Coefficient of Reactivity Via Noise Analysis Using Closed-Loop Transfer Functions. . . . Housiadas, C.; Antonopoulos-Domis, M. . . . July 2001 . . . Demokritos National Centre for Scientific Research, Athens, Greece.

Ann. Nucl. Energy, 28, 993-1011 . . . Analytic Solutions of Radionuclide Transport with the Limited Diffusion from the Fracture into a Porous Rock Matrix. . . . Park, J.B.; Hwang, Y.; Lee, K.J. . . . July 2001 . . . Korea Advanced Institute of Science and Technology, Taejon, South Korea; Korea Atomic Energy Research Institute, Taejon, South Korea.

Ann. Nucl. Energy, 28, 1013-1018 . . . Extension of Rational Approximation Method to P-wave Collision Amplitudes in Reich-Moore Resonance Formalism. . . . Devan, K.; Keshavamurthy, R.S. . . . July 2001 . . . Indira Gandhi Centre for Atomic Research, Tamilnadu, India.

Ann. Nucl. Energy, 28, 1019-1031 . . . Improved Lumped Parameter Formulation for Simplified LWR Thermohydraulic Analysis. . . . Su, J.; Cotta, R.M. . . . July 2001 . . . COPPE/UFRJ, Rio de Janeiro, Brazil.

Ann. Nucl. Energy, 28, 1033-1042 . . . Spectral Green's Function Method for Neutron Transport: Isotropic, Forward, and Backward Scattering in 1-D Slab Geometry. . . . Anli, F. . . . July 2001 . . . K.S.U. Fen-Ed. Fak., K. Maras, Turkey.

Fusion Eng. Design, 54, 331-336 . . . ITER Test-Blanket Safety Assessment. . . . Bartels, H.-W.; Enoeda, M.; Futterer, M.; Kleefeldt, K.; McCarthy, K. . . . April 2001 . . . ITER Garching JWS, Garching, Germany; JAERI, Ibaraki-ken, Japan; CEA Cadarache, St. Paul-lez-Durance, France; FZK, IRS, Karlsruhe, Germany; INEEL, Idaho Falls, ID.

Fusion Eng. Design, 54, 349-352 . . . Management of Waste from Six Potential Fusion Power Plant Models. . . . Broden, K.; Lindberg, M.; Olsson, G. . . . April 2001 . . . Association EURATOM-NFR, Nykoping, Sweden.

Fusion Eng. Design, 54, 353-359 . . . Comparisons of Facility-Specific and Generic Component Failure Rates for Tritium-Bearing Components Used in Fusion Research. . . . Cadwallader, L.C. . . . April 2001 . . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.

Fusion Eng. Design, 54, 361-374 . . . Safety Classification of the ITER Fusion Power Shutdown System and Resulting Safety Requirements. . . . Costa, M. . . . April 2001 . . . Commissariat a l'Energie Atomique, St. Paul-lez-Durance, France.

Fusion Eng. Design, 54, 375-385 . . . Assessment of Occupational Radiation Exposure for Two Fusion Power Plant Designs. . . . Natalizio, A.; Di Pace, L.; Pinna, T. . . . April 2001 . . . ENSAC Associates Ltd., Toronto, Canada; Associazione Euratom-ENEA sulla Fusione, Rome, Italy.

Fusion Eng. Design, 54, 387-395 . . . SAFPAQ-II, A New Tool for the Production of Activation Data Libraries. . . . Forrest, R.A. . . . April 2001 . . . Euratom/UKAEA Fusion Association, Oxfordshire, United Kingdom.

Fusion Eng. Design, 54, 413-419 . . . Analyses of Temperature Transients in ITER Design Concepts Following Hypothetical Loss of Cooling Accidents. . . . Han, W.E. . . . April 2001 . . . Euratom/UKAEA Fusion Association, Oxfordshire, United Kingdom.

Fusion Eng. Design, 54, 421-430 . . . In-vessel Hydrogen Deflagration and Detonation in ITER-FEAT. . . . Iseli, M. . . . April 2001 . . . ITER Joint Central Team, Ibaraki, Japan.

Fusion Eng. Design, 54, 431-442 . . . Activation Product Transport Using TRACT: ORE Estimation of a Generic Cooling Loop Under SEAFP-99 Conditions. . . . Karditsas, P.J. . . . April 2001 . . . UKAEA Fusion, Oxfordshire, United Kingdom.

Fusion Eng. Design, 54, 451-464 . . . Fusion Safety Studies in Russia from 1996 to 2000. . . . Kolbasov, B.M.; Biryukov, A.Y.; Davydov, D.A.; Guseva, M.I.; Khripunov, B.I.; Koshunov, S.N.; . . . April 2001 . . . Kurchatov Institute, Moscow, Russia; SSC RF A.A. Bochvar Research Institute of Inorganic Materials, Moscow, Russia; Troitsk Institute of Innovative and Thermonuclear Investigations, Moscow Region, Russia.

Fusion Eng. Design, 54, 465-471 . . . Fracture Mechanics Evaluation of a Crack Generated in SiC/SiC Composite First Wall. . . . Kurihara, R.; Ueda, S.; Nishio, S.; Seki, Y. . . . April 2001 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan; JAERI Wien Office, Wien, Austria; JAERI Tokai Research Establishment, Ibaraki-ken, Japan.

Fusion Eng. Design, 54, 485-493 . . . A Lithium-Air Reaction Model for the MELCOR Code for Analyzing Lithium Fires in Fusion Reactors. . . . Merrill, B.J. . . . April 2001 . . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.

Fusion Eng. Design, 54, 505-514 . . . Occupational Doses and Impact on Fusion Economics. . . . Mustoe, J.; Currie, I.D.; Pascual Frias, M. . . . April 2001 . . . NC Ltd., Cheshire, United Kingdom; IBERTEF, Madrid, Spain.

Fusion Eng. Design, 54, 515-522 . . . Safety Activities in JAERI Related to ITER. . . . O'hira, S.; Tada, E.; Hada, K.; Neyatani, Y.; Maruo, T.; Hashimoto, M.; Araki, T.; Nomoto, K . . . April 2001 . . . JAERI, Ibaraki-ken, Japan.

Fusion Eng. Design, 54, 523-535 . . . Simulation Study of Intentional Tritium Release Experiments in the Caisson Assembly for Tritium Safety at the TPL/JAERI. . . . Iwai, Y.; Hayashi, T.; Kobayashi, K.; Nishi, M. . . . April 2001 . . . JAERI, Ibaraki-ken, Japan.

Fusion Eng. Design, 54, 547-553 . . . Assessment of the Performance of the JET Exhaust Detritiation System. . . . Sabathier, F.; Brennan, D.; Skinner, N.; Patel, B. . . . April 2001 . . . UKAEA Culham Centre, Oxfordshire, United Kingdom.

Fusion Eng. Design, 54, 555-561 . . . Modelling of Two-Phase Flow Under Accidental Conditions Fusion Codes Benchmark. . . . Sardain, P.; Girard, C.; Andersson, J.; Porfiri, M.T.; Kurihara, R.; Masson, X.; Mignot, G.; . . . April 2001 . . . CEA Cadarache, Saint-Paul-lez Durance, France; Studsvik Ecosafe, Sweden; ENEA Frascati, Italy; JAERI Naka, Japan; Technicatome, France; ITER JCT Garching, Germany.

Fusion Eng. Design, 54, 563-573 . . . Selection of DBEs for ITER EDA 1998 Final Design by GEMSAFE Methodology. . . . Sawada, T.; Saito, M.; Inoue, T. . . . April 2001 . . . Tokyo Institute of Technology, Tokyo, Japan.

Fusion Eng. Design, 54, 593-603 . . . Results of Two-Phase Flow Experiments with an Integrated Ingress-of-Coolant Event (ICE) Test Facility for ITER Safety. . . . Takase, K.; Akimoto, H.; Topilski, L.N. . . . April 2001 . . . JAERI, Ibaraki-ken, Japan; ITER-Garching Joint Work Site, Garching, Germany.

Fusion Eng. Design, 54, 617-625 . . . Neutronic Apsects of the Safety and Environmental Performance of Silicon Carbide as Blanket Structural Material. . . . Taylor, N.P.; Forrest, R.A. . . . April 2001 . . . EURATOM/UKAEA Fusion Association, Oxfordshire, United Kingdom.

Fusion Eng. Design, 54, 627-633 . . . Validation and Benchmarking in Support of ITER-FEAT Safety Analysis. . . . Topilski, L.M.; Masson, X.; Porfiri, M.T.; Pinna, T.; Sponton, L.-L.; Andersen, J.; Takase, . . . April 2001 . . . ITER Garching Joint Work Site, Garching, Germany; Techicatome, France; ENEA Centro Ricerche Frascati, Rome, Italy; Studsvik Eco & Safety AB, Nykoping, Sweden; JAERI, Ibaraki-ken, Japan; CEA, Cadarache Center, Saint-Paul-lez Durance, France.

Fusion Eng. Design, 54, 635-643 . . . Clearance, Recycling and Disposal of Fusion Activated Material. . . . Zucchetti, M.; Forrest, R.; Forty, C.; Gulden, W.; Rocco, P.; Rosanvallon, S. . . . April 2001 . . . Politecnico di Torino, Torino, Italy; EURATOM/UKAEA Fusion Association, Abingdon, United Kingdom; EFDA, Garching, Germany; CEA, Cadarache, France.

J. Nucl. Mater., 289, 1-9 . . . Tensile Strength and Fracture Surface Characterization of Hi-Nicalon SiC Fibers. . . . Youngblood, G.E.; Lewinsohn, C.; Jones, R.H.; Kohyama, A. . . . February 2001 . . . Pacific Northwest National Laboratory, Richland, WA; Kyoto University, Kyoto, Japan.

J. Nucl. Mater., 289, 10-15 . . . Failure Mechanisms in Continuous-Fiber Ceramic Composites in Fusion Energy Environments. . . . Lewinsohn, C.A.; Henager Jr., C.H.; Youngblood, G.E.; Jones, R.H.; Lara-Curzio, E.; Scholz, R.. . . February 2001 . . . Pacific Northwest National Laboratory, Richland, WA; Oak Ridge National Laboratory, Oak Ridge, TN; JRC, Ispra, Italy.

J. Nucl. Mater., 289, 16-22 . . . Computational Analysis of Creep Fracture Deformation in SiC/SiC Composites. . . . Serizawa, H.; Ando, M.; Lewinsohn, C.A.; Murakawa, H. . . . February 2001 . . . Osaka University, Osaka, Japan; Pacific Northwest National Laboratory, Richland, WA.

J. Nucl. Mater., 289, 23-29 . . . Improvement of Mechanical Properties of SiC/SiC Composites by Various Surface Treatments of Fibers. . . . Hinoki, T.; Yang, W.; Nozawa, T.; Shibayama, T.; Katoh, Y.; Kohyama, A. . . . February 2001 . . . Kyoto University, Kyoto, Japan; Hokkaido University, Sapporo, Japan; Japan Science and Technology Corp., Saitama, Japan.

J. Nucl. Mater., 289, 30-36 . . . Microstructural and Mechanical Characteristics of SiC/SiC Composites with Modified-RS Process. . . . Lee, S.P.; Katoh, Y.; Park, J.S.; Dong, S.; Kohyama, A.; Suyama, S.; Yoon, H.K. . . . February 2001 . . . Kyoto University, Kyoto, Japan; Dong-eui University, Pusan, South Korea; Toshiba Corp., Yokohama, Japan.

J. Nucl. Mater., 289, 37-41 . . . Development of SiC/SiC Composites by PIP in Combination with RS. . . . Kotani, M.; Kohyama, A.; Katoh, Y. . . . February 2001 . . . Kyoto University and CREST-ACE, Kyoto, Japan.

J. Nucl. Mater., 289, 42-47 . . . Properties and Radiation Effects in High-temperature Pyrolyzed PIP-SiC/SiC. . . . Katoh, Y.; Kotani, M.; Kishimoto, H.; Yang, W.; Kohyama, A. . . . February 2001 . . . Kyoto University, Kyoto, Japan; CREST, Saitama, Japan.

J. Nucl. Mater., 289, 48-51 . . . XPS Characterization of Beryllium Carbide Thin Films Formed Via Plasma Deposition. . . . Xie, Y.; Morosoff, N.C.; James, W.J. . . . February 2001 . . . University of Missouri - Rolla, Rolla, MO.

J. Nucl. Mater., 289, 52-56 . . . Long-term Stability of Ceramics in Liquid Lithium. . . . Pint, B.A.; Chitwood, L.D.; Di Stefano, J.R. . . . February 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 289, 57-70 . . . Molecular Dynamics Simulation of Irradiation-Induced Amorphization of Cubic Silicon Carbide. . . . Malerba, L.; Perlado, J.M. . . . February 2001 . . . Universidad Politecnica de Madrid, Madrid, Spain.

J. Nucl. Mater., 289, 71-79 . . . Molecular Dynamics Refinement of Topologically Generated Reconstructions of Simulated Irradiation Cascades in Silica Networks. . . . Yuang, X.; Pulim, V.; Hobbs, L.W. . . . February 2001 . . . Massachusetts Institute of Technology, Cambridge, MA.

J. Nucl. Mater., 289, 80-85 . . . Structural Stability of Irradiated Ceramics. . . . Ossi, P.M. . . . February 2001 . . . Politecnico di Milano, Milano, Italy.

J. Nucl. Mater., 289, 86-95 . . . New Mechanism for Radiation Defect Production and Aggregation in Crystalline Ceramics. . . . Dubinko, V.I.; Turkin, A.A.; Vainshtein, D.I.; den Hartog, H.W. . . . February 2001 . . . Kharkov Institute of Physics and Technology, Kharkov, Ukraine; University of Groningen, AG Groningen, The Netherlands.

J. Nucl. Mater., 289, 96-101 . . . Accumulation and Recovery of Disorder on Silicon and Carbon Sublattices in Ion-Irradiated 6H-SiC. . . . Jiang, W.; Weber, W.J.; Thevuthasan, S.; Shutthanandan, V. . . . February 2001 . . . Pacific Northwest National Laboratory, Richland, WA.

J. Nucl. Mater., 289, 102-109 . . . Physical Property Change of Heavily Neutron-Irradiated Si3N4 and SiC By Thermal Annealing. . . . Yano, T.; Akiyoshi, M.; Ichikawa, K.; Tachi, Y.; Iseki, T. . . . February 2001 . . . Tokyo Institute of Technology, Tokyo, Japan; Japan Nuclear Cycle Development Institute, Higashi-Ibaragi, Japan.

J. Nucl. Mater., 289, 110-114 . . . Effects of Xe Ion Irradiation and Subsequent Annealing on the Structural Properties of Magnesium-Aluminate Spinel. . . . Afanasyev-Charkin, I.V.; Dickerson, R.M.; Cooke, D.W.; Bennett, B.L.; Gritsyna, V.T.; Sickafus, K.E. . . . February 2001 . . . Los Alamos National Laboratory, Los Alamos, NM; Kharkiv National University, Kharkiv, Ukraine.

J. Nucl. Mater., 289, 115-121 . . . Behaviour of Implanted Xenon in Yttria-stabilised Zirconia as Inert Matrix of a Nuclear Fuel. . . . Degueldre, C.; Pouchon, M.; Dobeli, M.; Sickafus, K.; Hojou, K.; Ledergerber, G.; Abolhassani-Dadras, S.. . . February 2001 . . . Paul Scherrer Institut, Villigen, Switzerland; Los Alamos National Laboratory, Los Alamos, NM; JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 289, 122-127 . . . Effects of Fission Product Incorporation on the Microstructure of Cubic Zirconia. . . . Wang, L.M.; Wang, S.X.; Zhu, S.; Ewing, R.C. . . . February 2001 . . . University of Michigan, Ann Arbor, MI.

J. Nucl. Mater., 289, 128-135 . . . Hydrogen-Damage Interactions in Yttria-stabilized Zirconia. . . . Shutthanandan, V.; Thevuthasan, S.; Young, J.S.; Orlando, T.M.; Weber, W.J. . . . February 2001 . . . Pacific Northwest National Laboratory, Richland, WA.

J. Nucl. Mater., 289, 136-166 . . . Alpha-Decay Damage and Aqueous Durability of Actinide Host Phases in Natural Systems. . . . Lumpkin, G.R. . . . February 2001 . . . Australian Nuclear Science and Technology Organisation, Menai, Australia.

J. Nucl. Mater., 289, 167-176 . . . Computational Study of Plutonium-Neodymium Fluorobritholite Ca9Nd0.5Pu0.5(SiO4)(PO4)5F2 Thermodynamic Properties and Threshold Displacement Energies. . . . Meis, C. . . . February 2001 . . . Commissariat a l'Energie Atomique, Gif-sur-Yvette, France.

J. Nucl. Mater., 289, 177-187 . . . Heavy Ion Irradiation Studies of Columbite, Brannerite, and Pyrochlore Structure Types. . . . Lumpkin, G.R.; Smith, K.L.; Blackford, M.G. . . . February 2001 . . . Australian Nuclear Science and Technology Organisation, Menai, Australia.

J. Nucl. Mater., 289, 188-193 . . . Heavy-Ion Irradiation Effects in Gd2(Ti2-xZrx)O7 Pyrochlores. . . . Begg, B.D.; Hess, N.J.; McCready, D.E.; Thevuthasan, S.; Weber, W.J. . . . February 2001 . . . Australian Nuclear Science and Technology Organisation, Menai, Australia; Pacific Northwest National Laboratory, Richland, WA.

J. Nucl. Mater., 289, 194-198 . . . Determination of the Defect Creation Mechanism in Fluoroapatite. . . . Soulet, S.; Chaumont, J.; Krupa, J-C.; Carpena, J.; Ruault, M-O. . . . February 2001 . . . Centre de Spectrometrie Nucleaire et de Spectrometrie de Masse, Orsay Campus, France; CEA-Cadarache, Saint-Paul-lez-Durance, France; Institut de Physique Nucleaire, Orsay Cedex, France.

J. Nucl. Mater., 289, 199-203 . . . Optical Emission Due to Ionic Displacements in Alkaline Earth Titanates. . . . Cooper, R.; Smith, K.L.; Colella, M.; Vance, E.R.; Phillips, M. . . . February 2001 . . . University of Melbourne, Parksville, Australia; Australian Nuclear Science and Technology Organisation, Menai, Australia; University of Technology, Sydney, Australia.

J. Nucl. Mater., 289, 204-209 . . . Accumulation and Thermal Recovery of Disorder in Au2+-Irradiated SrTiO3. . . . Thevuthasan, S.; Jiang, W.; Shutthanandan, V.; Weber, W.J. . . . February 2001 . . . Pacific Northwest National Laboratory, Richland, WA.

Nucl. Eng. Design, 206, 1-12 . . . Development of Structural Analysis Program for Non-Linear Elasticity by Continuum Damage Mechanics. . . . Kaji, Y.; Gu, W.; Ishihara, M.; Arai, T.; Nakamura, H. . . . May 2001 . . . JAERI, Ibaraki-ken, Japan; CRC Research Institute, Tokyo, Japan.

Nucl. Eng. Design, 206, 13-20 . . . Stress Intensity Factor Evaluation of a Circumferential Crack in a Finite Length Thin-Walled Cylinder for Arbitrarily Distributed Stress on Crack Surface by Weight Function Method . . . Meshii, T.; Watanabe, K. . . . May 2001 . . . Fukui University, Fukui, Japan; University of Tokyo, Tokyo, Japan.

Nucl. Eng. Design, 206, 21-33 . . . Stainless Steel Containers for the Storage of Low and Medium Level Radioactive Waste. . . . Vehovar, L.; Tandler, M. . . . May 2001 . . . Institute of Metals and Technology, Ljubljana, Slovenia.

Nucl. Eng. Design, 206, 35-44 . . . Effects of Thermal Aging on the Low Cycle Fatigue Behavior of Austenitic-Ferritic Duplex Cast Stainless Steel. . . . Kwon, J-d.; Woo, S-w.; Lee, Y-s.; Park, J-c.; Park, Y-w. . . . May 2001 . . . Yeungnam University, Kyongbuk, South Korea; Korea Institute of Nuclear Safety, Taejon, South Korea.

Nucl. Eng. Design, 206, 45-56 . . . Creep Crack Initiation and Creep Crack Growth Assessments in Welded Structures. . . . Assire, A.; Michel, B.; Raous, M. . . . May 2001 . . . CEA/Cadarache, Saint-Paul-lez Durance, France; CNRS/LMA, Marseille, Cedex, France.

Nucl. Eng. Design, 206, 57-89 . . . Stress Corrosion Cracking of Low-Alloy, Reactor-Pressure-Vessel Steels in Oxygenated, High-temperature Water. . . . Heldt, J.; Seifert, H.P. . . . May 2001 . . . Paul Scherrer Institute, Villigen, Switzerland.

Nucl. Eng. Design, 206, 91-96 . . . Flow Excursion Instability in Downward Flow Systems Part I. Single-Phase Instability. . . . Babelli, I.; Ishii, M. . . . May 2001 . . . King Abdulaziz City for Science and Technology, Riyadh, Saudi Arabia; Purdue University, West Lafayette, IN.

Nucl. Eng. Design, 206, 97-104 . . . Flow Excursion Instability in Downward Flow Systems Part II: Two-Phase Instability. . . . Babelli, I.; Ishii, M. . . . May 2001 . . . King Abdulaziz City for Science and Technology, Riyadh, Saudi Arabia; Purdue University, West Lafayette, IN.

Nucl. Eng. Design, 206, 105-111 . . . Transient Analyses of the Passive Residual Heat Removal System. . . . Zang Xinian; Guo Weijun; Huang Bing; Shen Shifei . . . May 2001 . . . Tsinghua University, Beijing, PR China.

Nucl. Technol., 134, 3-14 . . . Regularization of Feedwater Flow Rate Evaluation for Venturi Meter Fouling Problem in Nuclear Power Plants. . . . Gribok, A.V.; Attieh, I.K.; Hines, J.W.; Uhrig, R.E. . . . April 2001 . . . University of Tennessee, Knoxville, TN.

Nucl. Technol., 134, 23-36 . . . Predictive Modeling of Steam Condensation onto Finned Tubes in the Presence of Noncondensable Gases for Passive Safety Reactor Containment Heat Exchangers. . . . Munoz-Cobo, J.L.; Palomo, M.J.; Herranz, L.E. . . . April 2001 . . . Universidad Politecnica de Valencia, Valencia, Spain; CIEMAT, Madrid, Spain.

Nucl. Technol., 134, 37-48 . . . Quantifying the Effects of Break Source Flow Rates on AP600 Containment Stratification. . . . Woodcock, J.; Peterson, P.F.; Spencer, D.R. . . . May 2001 . . . Westinghouse Nuclear Services Division, Pittsburgh, PA; University of California at Berkeley, Berkeley, CA; Westinghouse Electro-mechanical Division, Cheswick, PA.

Nucl. Technol., 134, 49-61 . . . Phase Distribution in a BWR Fuel Assembly and Evaluation of a Multidimensional Multifield Model. . . . Windecker, G.; Anglart, H. . . . April 2001 . . . Westinghouse Atom, Vasteras, Sweden.

Nucl. Technol., 134, 62-70 . . . Revaporization of a Csl Aerosol in a Horizontal Straight Pipe in a Severe Accident Condition. . . . Shibazaki, H.; Maruyama, Y.; Kudo, T.; Hashimoto, K.; Maeda, A.; Harada, Y.; Hidaka, A.; Sugimoto, J. . . . April 2001 . . . JAERI, Ibaraki-ken, Japan; Japan Nuclear Cycle Development Institute, Ibaraki-ken, Japan; MRI Systems Inc., Tokyo, Japan; Mitsubishi Heavy Industries, Ltd., Kobe, Japan.

Nucl. Technol., 134, 71-83 . . . Assessment of the 3-D Thermal-Hydraulic Nuclear Core Computer Code FLICA-IV on Rod Bundle Experiments. . . . Bergeron, A.; Caruge, D.; Clement, P. . . . April 2001 . . . Commissariat a l'Energie Atomique, Gif-sur-Yvette, France.

Nucl. Technol., 134, 84-96 . . . Turbulence Modification Due to Wave Action at Low Reynolds Numbers in Horizontal Open-Channel Flow. . . . Stamatiou, E.; Chung, P.M-Y.; Kawaji, M. . . . April 2001 . . . University of Toronto, Ontario, Canada.

CNIC-01530; CNDC-0028; INDC(CPR)-052/L . . . Communication of Nuclear Data Progress, No. 24. . . . . . . 2000 . . . China Nuclear Data Center, Beijing, China.