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 http://www-rsicc.ornl.gov/rsicc.html
No. 455	January 2003
"Footprints on the sands of time are not made by sitting down" -- Anonymous

• E. O. Lawrence Award Recipient
• Updated RSICC Web Address
• Visitors
• Greening of the Nuclear Age
• Available NRC Codes
• Changes to the Computer Code and Data Collection
• CCC-430/EDMULT 6.4
• CCC-434/SNAP-3D
• CCC-647/DRAGON 3.04e
• Monthly Code Focus
• CONFERENCES, COURSES, SYMPOSIA
• Condensed Table of Conferences
• Advances in Nuclear Fuel Management III - Call For Papers
• ENS TopFuel 2003/ANS LWR Fuel Performance Meeting
• 2003 IEEE Nuclear and Space Radiation Effects Conference (NSREC)
• 2003 International Congress on Advanced Nuclear Power Plants (ICAPP '03)
• 9th International Conference on Environmental Remediation and Radioactive Waste Management
• 21st International System Safety Conference
• 9th International Symposium in Radiation Physics (ISRP-9)
• M&C 2003
• MCNP Courses for 2003
• MCNP Visual Editor Classes** updated (1/6)
• MCNPX Workshops for 2003
• Workshop on Nuclear Data for the Transmutation of Nuclear Waste
• Practical MCNP for the HP, Medical Physicist, and Rad Engineer
• SAMMY Workshop
• SCALE 5 Plus Workshop
• Software Quality Forum 2003 (SQF 2003)
• Supercomputing in Nuclear Applications
• CALENDAR
• ACCESSION OF NUCLEAR SYSTEMS LITERATURE

Paul J. Turinsky, ANS Fellow and member since 1971, is a recipient of the U.S. Dept. of Energy's E.O. Lawrence Award for outstanding contributions in the field of atomic energy. Turinsky, technical director of North Carolina State University's Electric Power Research Center and head of the university's department of nuclear engineering, is being honored for his contributions to the fuel cycle management of light water reactors that have significantly improved the safety and economics of nuclear power. The award was presented at a ceremony in Washington, D.C. on October 28.

RSICC's new web address is http://www-rsicc.ornl.gov/rsicc.html. The only difference is we now have two c's at the end where there used to be only one. Everything should forward with no problem, but we thought you should know so you can update your links.
 
 

On November 25, 2002, RSICC had three visitors from Japan, Dr. Toshio Fujishiro and Kojiro Yamagishi from RIST and Dr. Yoshio Suzuki from JAERI. In the morning program, RSICC director Hamilton Hunter gave a presentation on the RSICC program and its current activities. RSICC staff member, Dr. Jy-An John Wang, provided information on the recent developments in the Power Reactor Embrittlement Database, Information Fusion Technique and Spiral Notch Torsion Test for toughness evaluation. Dr. Fujishiro presented "Introduction to RIST and its Recent Activities," and Dr. Suzuki presented "Activities at CCSE/JAERI and the ITBL Project." Dr. Xiao-Ming Xu from the ORNL Physics Division gave a presentation on "Parallel Calculations for Relativistic Heavy Ion Collision Physics." Dr. Al Ekkebus, SNS User Coordinator, gave our visitors a guided tour of the SNS construction site, which was the highlight of the visit.
 
 

The Greening of the Nuclear Age brochure prepared for the World Summit on Sustainable Development, is available for purchase from the American Nuclear Society. The price of the glossy six-page, color brochure is $1 each for up to 100 copies; larger quantities can be purchased at reduced prices. Click on "ANS Store," then "Public Information" at www.ans.org,or you can download it from www.ans.org/pi/brochures.
 
 

Two U.S. Nuclear Regulatory Commission (NRC) software packages transferred from the Energy Science and Technology Software Center, Oak Ridge, Tennessee, to RSICC were processed this month. Please browse the computer code abstracts available at RSICC's web site for more information on these packages.

CCC-289/SKYSHINE-III
PSR-270/UPDATE
 
 

Three changes were made to the computer code collection this month. All three are newly frozen versions and foreign contributions.

CCC-430/EDMULT 6.4
OP SYS: Unix, Windows
Language: Fortran 77
Computers: PC & IBM RS/6000
Format: tar & Windows

The Institute for Data Evaluation and Analysis, Sakai, Osaka, Japan; Research Institute for Advanced Science and Technology, Osaka Prefecture University, Sakai, Osaka Japan; Shanghai Applied Radiation Institute, Shanghai University, Jia Ding, Shanghai, China; and Department of Radiation Oncology, Indiana University School of Medicine, Indianapolis, Indiana, contributed a newly frozen version of EDMULT.

Version 6.4 evaluates depth-dose distributions produced by plane-parallel electron beams normally incident on one- to six-layer slab absorbers. EDMULT is based on an analytic expression of the depth-dose curve in semi-infinite medium and a simple model of electron penetration through a multilayer absorber. The effect of the different medium beyond an interface is accounted for by the difference of backscattering, which is evaluated by considering the branching of electron beam into transmitted and backscattered components. Special features of the present version compared with previous ones are as follows:

(1) Higher accuracy (root-mean-square deviations from accurate Monte Carlo results are 1-2% for effectively semi-infinite absorbers and 5-7% for absorbers consisting of more than two layers).

(2) Applicability to the absorbers consisting of a larger number of layers of different materials (up to six layers).

(3) Use of the mean atomic number given in ICRU Report 35 (page 37) for material mixtures and compounds instead of the effective atomic number used in earlier versions.

The code is operable on almost any computer with a Fortran compiler. The developer ran it on several computers including Macintosh with the Absoft compiler. An executable created with the DVF 6.0 compiler is included in the package for PC Windows users. EDMULT was tested at RSICC on:

IBM RS/6000 Model 270 running AIX 4.3.3 with XL Fortran Version 7.1
Intel-Linux 7 with f77 Version 2.96 under RedHat Linux 7
Windows2000 on Pentium IV with Digital Visual Fortran 6.0

The package is transmitted on a CD which contains documentation, source, sample problem input and output, and PC Windows executable in 2 formats: a self-extracting compressed Windows file and a Unix tar file. Reference: RCOP TR-8 (November 1987). Fortran 77; Intel PC, MacIntosh, Workstations (C00430/MNYCP/01).
 

CCC-434/SNAP-3D
OP SYS: Unix, Windows
Language: Fortran 77
Computers: PC & Workstations
Format: tar & Windows

UKAEA Technology, Risley, United Kingdom, through the OECD Nuclear Energy Agency Data Bank, Issy-les-Moulineaux, France, contributed this one-, two-, or three-dimensional multigroup diffusion code system. SNAP-3D can also be used to carry out gamma-ray calculations if the diffusion approximation is accurate enough. It is suitable for fast and thermal reactor core calculations and for shield calculations. The problem classes are: 1) eigenvalue search for critical k-effective, 2) eigenvalue search for critical buckling, 3) eigenvalue search for critical time-constant, 4) fixed source problems in which the sources are functions of regions, and 5) fixed source problems in which the sources are provided, on disc, for every mesh point and group. The finite difference equations are solved by a combination of source iteration and successive over-relaxation. If desired, a coarse mesh rebalancing algorithm may be used at intervals to accelerate the source iterations.

SNAP-3D has run on DEC Vax 4000, DEC ALPHA Station 200-4/166, Pentium 166MHz, HP 9000/7xx, IBM RISC/6000, and SUN SPARCStation. The code is expected to run on any operating system on which a Fortran 77 compiler is available. Fortran compilers are required on all Unix machines. An executable created with Microsoft Powerstation 4.0 is included for PC users. The distribution CD contains the referenced documents and a self-extracting compressed file and a compressed tar file with the source, PC executable and test cases. References: AEA-RS-1214 (February 1993) and TRG Report 2677(R) (October 1975). Fortran 77 PC and workstation (C00434/MNYCP/01).
 

CCC-647/DRAGON 3.04e
OP SYS: Unix, Linux
Language: Fortran 77 & C
Computers: Workstation & PC
Format: tar

Ecole Polytechnique de Montreal, Canada, contributed a newly frozen version of this lattice cell code system. DRAGON is a collection of models to simulate the neutronic behavior of a unit cell or a fuel assembly in a nuclear reactor. It includes all of the functions that characterize a lattice cell code, namely: interpolation of microscopic cross sections supplied by means of standard libraries; resonance self-shielding calculations in multidimensional geometries; multigroup and multidimensional neutron flux calculations which can take into account neutron leakage; transport-transport or transport-diffusion equivalence calculations as well as editing of condensed and homogenized nuclear properties for reactor calculations; and finally isotopic depletion calculations.

DRAGON contains a multigroup iterator conceived to control a number of different algorithms for the solution of the neutron transport equation. Each of these algorithms is presented in the form of a one-group solution procedure where the contributions from other energy groups are included in a source term. The current version contains three such algorithms. The JPM option solves the integral transport equation using the interface current method applied to homogeneous blocks; the SYBIL option solves the integral transport equation using the collision probability method for simple one-dimensional (1-D) or two-dimensional (2-D) geometries and the interface current method for 2-D Cartesian or hexagonal assemblies; and the EXCELL option solves the integral transport equation using the collision probability method for more general 2-D geometries and for three-dimensional (3-D) assemblies. In addition, it is now possible to solve the transport equation for 2-D geometries using the method of cyclic characteristics.

DRAGON runs on IBM RS/6000, HP9000/700 workstations, SUN SparcStations and Linux systems. There is no Windows version of this release. At RSICC the system was successfully tested on an IBM RS/6000 model 270 under AIX 4.3.3 with XL Fortran version 7.1 and on an Intel PC under RedHat7.2 Linux with the GNU g77 0.5.26 compiler. The package is transmitted on a CD-ROM in a GNU compressed Unix tar file which contains installation instructions, documentation, Fortran source, installation scripts, and test input and output for AIX and Linux. References: IGE-174 Rev. 5 (April 2000), IGE-232 Rev. 3 (April 2000), IGE-251 Rev. 1, (March 2002), IGE-236 Rev. 1 (October 2001), IGE-158 (March 2000), and IGE-163 (December 1999). Fortran 77 and C; Intel Linux, IBM RS/6000, and Sun(C00647/MNYWS/02).
 
 

As years have gone by many different codes and applications have been sent to RSICC for stewardship. We currently have over 1700 analytical code and data packages and distribute as many each year to 73 countries in the world. To help 'categorize' each package, we have developed a database of 'Main Categories' to attach applications to the packages at RSICC. Doing so requires investigation into each code package, user feedback from end use statements, and extensive RSICC staff experience and analysis so that we can deliver useful information each month on the 30 different categories we have identified thus far. Links to the package abstracts are embedded into the WWW version of the RSICC Newsletter. Feedback from our Newsletter community is very valuable so please direct your comments and/or suggestions to PDC@ORNL.GOV. Many packages in the RSICC code collection are in this subject category. A few are highlighted here for your review.

BOLD VENTURE IV
CANDULIB-AECL
CARMEN SYSTEM
CITATION-LDI2
COBRA-EN
DANCOFF-MC
DIF3D8-VARIANT8
EMPIRE-II
HATCHES
MOSRA-LIGHT
NORMA
NORMA-FP
ORIGEN-ARP-2
PWR-AXBUPRO-SNL
TDTORT
TRIGLAV
VENTURE-PC
VSOP94
WIMS-ANL 4.0
WIMSD 5B

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 by the 20th of each month. 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. Below is a condensed list of the conferences only. More details are listed following the table.
 
 

Preparations for the American Nuclear Society's Advances in Nuclear Fuel Management III Topical Meeting to be held in Hilton Head Island, South Carolina, during the period of October 5-8, 2003, have now begun in earnest. You are invited to serve on the Meeting's Technical Program Committee (TPC). In this capacity your commitment will include:

1. Electronically submit one or more papers, and encourage colleagues to do the same,

2. Help identify and organize special session(s) on timely topics you are interested in, and

solicit participation, and

3. Electronically review papers assigned to you in a timely and professional manner

Please return the following information (name, affiliation, phone, alternative email if preferable, topics of interest) to Youssef A. Shatilla at shatilya@westinghouse.com.

The success of this meeting depends on your active support and involvement. Finally, please bookmark the conference web site: http://rpd.ans.org/nfm.htm and visit it occasionally for news and updates. Comments and suggestions are most welcome.
 
 

The American Nuclear Society (ANS) and the European Nuclear Society (ENS) have agreed to bundle their conference activities concerning nuclear fuel. The well established ANS "LWR Fuel Performance Meeting" and the ENS "TopFuel Conference" will from now on be jointly held, alternating the location between the USA and Europe.

The first joined conference will be organized by the local nuclear society in Germany, the KTG (Kerntechnische Gesellschaft e.V.) from March 16-19, 2003, at Würzburg. The program will comprise invited and contributed papers. Please visit the website for more information: http://www.topfuel2003.de.
 
 

The 2003 IEEE Nuclear and Space Radiation Effects Conference (NSREC) will be held in Monterey, California, July 21-25, 2003. This annual meeting of engineers and scientists presents the latest techniques for enhancing the performance of microelectronic devices and circuits that are used in radiation environments. The final call for papers for the 2003 IEEE Nuclear and Space Radiation Effects Conference (NSREC) is available on the web site at www.nsrec.com. Deadline for submission is February 7, 2003.

Make plans for the 2003 short course in Monterey. Joe Benedetto and his team of professors have put together an interesting program about radiation effects on device scaling. The syllabus is at www.nsrec.com/short.htm.

Forms to nominate an outstanding colleague for the 2003 Radiation Effects Award are at www.nsrec.com/nominate.htm. This award comes with a handsome IEEE plaque and $2000 check.

University professors - Forms are available on the NSREC web site to nominate an outstanding student for the 2003 IEEE NPSS Phelps Continuing Education Grant. The cash award ($500 - $1000)

comes with an IEEE certificate and complimentary short course registration. NSREC plans to award two grants this year. See www.nsrec.com/steering.htm.

Keep checking the web site at www.nsrec.com for the latest NSREC information. Contact Paul Dodd, Sandia National Laboratories, 505-844-1447 if you have questions.
 
 

We are pleased to announce the call for papers for the "2003 International Congress on Advanced Nuclear Power Plants" (ICAPP '03) which will be held in Cordoba, Spain, May 4-7, 2003, at the Congress Palais. Please make note of the October 15, 2002 deadline for abstracts.

Following the highly successful ICAPP '02 meeting held in Hollywood, Florida, this international congress will bring together international experts of the nuclear industry involved in the operation,

development, building, regulation, and research related to nuclear power plants. The conference is sponsored by the leading nuclear societies of Europe, Asia, and the USA.

The program will cover the full spectrum of nuclear power plant issues from design, deployment and construction of plants to research and development of future designs and advanced systems. The program is expected to cover lessons learned from power, research and demonstration reactors from over 50 years of experience with operation and maintenance, structures, materials, technical specifications, human factors, system design, and reliability. You may visit the ICAPP '03 website at www.ans.org/goto/ icapp03 for updated information on the congress and to download a copy of the Call For Papers.
 
 

The conference will be held in Oxford, England, September 21-25, 2003. Session M-6 - Applying Strategic Planning, Decision-making, and Risk Reduction Methodologies in EM, includes the following:

-- Applications of strategic planning, decision-making, and/or risk reduction methodologies and

tools (e.g., roadmapping) to resolve environmental management issues Innovative approaches

to decision-making to resolve problems/issues related to environmental management

-- Innovative approaches to assessing risk and cost-effective reduction of risk for issues related to

environmental management

-- Innovative approaches to strategically plan for and implement science and technology (S&T) to

resolve environmental barriers to project completion

-- Ways to effectively integrate strategic planning, decision-making, and risk reduction techniques

and tools to resolve environmental management issues

-- Methodologies used in developing the sites' plans to meet DOE EM's goals of site closures,

cost savings, schedule acceleration, and risk reduction

Additional details on the ICEM conference is on the website at http://www.icemconf.com.
 
 

The System Safety Society is pleased to announce the 21st International System Safety Conference, August 4-8, 2003, in Ottawa, Ontario, Canada. The conference is an international forum for the technical presentation and discussion of all aspects and issues regarding system safety engineering and management. The conference theme is "Broader Perspectives, Focused Solutions." The emphasis is on knowledge and skills necessary to create the system safety solutions for increasingly complex technologies and missions. The range of topics will cover both the art and science of system safety and the organizational issues influencing the effective management of system safety in the product life cycle. This is the major conference for system safety and related professionals, with a week of technical sessions, tutorials, workshops, special events, social affairs, luncheons, and the society's awards banquet. The conference proceedings are the premier collection of work in the system safety field. For more information, please visit: http://www.russona.com/issc21/.
 
 

The 9th International Symposium on Radiation Physics (ISRP-9) will be held in Cape Town, South Africa, October 27-31, 2003. This triennial event will be organized jointly by the International Radiation Physics Society ( IRPS ) and iThemba Laboratory for Accelerator Based Sciences ( iThemba LABS) [formerly the National Accelerator Centre]. The Symposium is the latest one in a series which began in Calcutta in 1974 and thereafter continued in Penang (1982), Ferrara (1985), São Paulo (1988), Dubrovnik (1991), Rabat (1994), Jaipur (1997) and Prague (2000). A 2½ day "Workshop on Radiation-Based Analytical Techniques" (WoRBAT) will be held prior to ISRP-9 (October 24-26, 2003) with the emphasis on x-ray fluorescence and diffraction (XRF, XRD) and particle-induced x-ray emission (PIXE). For more information, please visit www.medrad.tlabs.ac.za/isrp9.htm.
 
 

The American Nuclear Society's Mathematics and Computation Topical Meeting, M&C 2003, will be held in Gatlinburg, Tennessee, April 6-10, 2003. The unique setup for this conference, entitled "Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew," promises to provide an exciting and unprecedented opportunity for students and professionals in the field to learn about its rich intellectual heritage from leading figures. The Review section of the conference is comprised of eight lectures on selected topics of common interest to the membership of the Mathematics and Computation Division, the primary sponsor of the meeting. The Anew section of the meeting will include contributed and invited papers on standard topics in this series of conferences. Please refer to the conference web site http://meetingsandconferences.com/MC2003/ for details on the lecture series and lecturers, a list of topics for contributed papers and special sessions, author instructions, and general information about the conference.

The web site for M&C 2003 is now open for submitting papers. Please check the "Call for Papers" link to learn about the topics of interest in this conference, including special session topics. The "Authors" link has templates for preparing full papers in MS Word, WordPerfect, and LaTeX. Please note that abstract submission is not required due to the Math & Computational Sciences Division's policy of reviewing only full papers for inclusion in meetings where the division is the primary sponsor. We look forward to welcoming you to Gatlinburg.
 
 

Registration: http://www-xdiv.lanl.gov/x5/MCNP/registration.html
MCNP home page: http://www-xdiv.lanl.gov/x5/MCNP/index.html
LANL contact: selcow@lanl.gov
European contact: sartori@nea.fr
Japanese contact: tadakazu@hero.tokai.jaeri.go.jp
 
 

The introductory class is for people who have little or no experience with MCNP. The intermediate to advanced class will be held for people who have used MCNP and want to extend their knowledge and understanding of the code system.

The classes will be based on MCNP5. The code and data package will be available through RSICC at a reduced rate to class participants. The new capabilities of version 5 will be covered.

The other capabilities on MCNP will also be covered, including: basic and advanced geometry, source definitions, tallies, data, variance reduction, statistical analysis, criticality, plotting of geometry, and particle tracks, neutron/photon/electron physics.

All classes provide interactive computer instruction. Time will be available to discuss individual questions and problems with MCNP experts or to pursue in more detail topics mentioned in the talks.

Please note that other classes are offered based on MCNP. The classes mentioned here are the only ones that are taught by the people who develop and write MCNP.
 
 

The Visual Editor is a powerful visualization tool that can be used to rapidly create complex Monte Carlo N Particle (MCNP 4C2) geometry models, including lattices, universes, fills, and other geometrical transformations. The Visual Editor can:

Display MCNP 4C2 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,

Create cells containing universes and lattices,

Interactively set cell importances from the plot window, and

Display source points and collision points in the plot window.

Two classes are scheduled: The March class has been moved to June 2-6, 2003, and the second class is September 8-12, 2003, both in Richland, Washington. The class will focus on the use of the visual editor, with an overview of MCNP. The fifth day is optional and will focus on using the Visual Editor and MCNP to do some example problems.

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/train.html, or by contacting Randy Schwarz (email randyschwarz@mcnpvised.com).
 
 

Lead Teachers: Drs. John Hendricks, Gregg McKinney, Laurie Waters
Organizer: HQC Professional Services Contact: bill@solutionsbyhqc.com
More Information: http://mcnpxworkshops.com MCNPX homepage: http://mcnpx.lanl.gov

MCNPX is the LANL all-particle, all-energy (eV-TeV) Monte Carlo transport code based on MCNP4C, LAHET, CEM, etc. MCNPX has been in active development since 1995, sponsored by the particle accelerator community. It has now become an accepted tool for a broad range of applications by nuclear engineers, physicists, and scientists. The MCNPX development effort has expanded the use of the Los Alamos tools to applications such as APT, waste transmutation, accelerator shielding and health physics, particle beam cancer therapy, space shielding and cosmic ray analysis, single event effects in semiconductors, radiography, and more detailed analysis of the effects of light and heavy ions in matter. In addition, the entire functionality of MCNP4C is retained. New variance reduction and data analysis techniques, many adapted from high energy accelerator methodologies, have also been added, such as the extensive 'mesh tally' capability which allows up to 3-d plotting of particle tracks, fluence and fluence-derived quantities, energy deposition, next event estimator generation contributions and particle sources.

The workshops include hands-on instruction, generally on PC Windows machines. Subject to participant export approval for the MCNPX beta test team, participants will be able to access the Fortran-90 version of MCNPX 2.4, the LA150 (150 MeV) cross-section data for over 40 isotopes for incident neutrons and protons, and 12 for photonuclear interactions, and a notebook of viewgraphs.

Follow-up consultation for class participants will be provided.

Classes are taught by experienced MCNPX code developers and instructors. More information on code versions and capabilities is available at MCNPX Workshops web site http://mcnpxworkshops .com.
 
 

The "Workshop on Nuclear Data for the Transmutation of Nuclear Waste" will be held September 1-5, 2003, at GSI-Darmstadt, Germany. The workshop is organized on the occasion of the end of the HINDAS research program, a collaboration of several European Institutes working on the subject of "High and Intermediate Nuclear Data for Accelerator Driven Systems." Please note that the topics included in the workshop are not restricted to the HINDAS research program. All contributions to the subject of the workshop are more than welcome.

The workshop time-schedule will be organized in the following way: Monday, September 1, 2003, will be dedicated to a closed HINDAS meeting. On Tuesday, the open sessions will start and last till the end of the workshop on Friday, September 5, 2003.

Those who are interested in participating in the workshop are invited to register (no fee) before August 1, 2003, using the workshop website http://www-wnt.gsi.de/tramu. There is also information on workshop topics, accommodations, transportation, and key dates. Please contact Aleksandra Kelic, A.Kelic@gsi.de if you have questions.
 
 

DATE: June 16-20, 2003 (4.5 days)
FEE: $1,450 per person
PLACE: The MESA Complex, Room 130, University of New Mexico-Los Alamos Campus

Monte Carlo type calculations are ideally suited to solving a variety of problems in radiation protection and dosimetry. This course is aimed at the HP, medical physicist, and rad engineer with no prior experience with Monte Carlo techniques. The focus is almost entirely on the application of MCNP™ to solve a variety of practical problems in radiation shielding and dosimetry. The intent is to "jump start" the student toward using MCNP™ productively. Extensive interactive practice sessions are conducted on a personal computer. Topics will include overview of the MCNP™ code and the Monte Carlo method, basic concepts, input file preparation, geometry, source definition, standard MCNP tallies, interpretation of the output file, exposure and dose rate calculations, radiation shielding, photon skyshine, detector simulation and dosimetry. Students will be provided with a comprehensive class manual and a diskette containing all of the practice problems. This course has been granted 32 Continuing Education Credits by the AAHP, and 4.5 CM points by the American Board of Industrial Hygiene.

The course is offered by the Health Physics Measurements Group at the Los Alamos National Laboratory and is co-sponsored by RSICC. Registration is available online at http://drambuie.lanl.gov/~esh4 mcnp.htm. Make checks payable to the University of California (checks must be in U.S. dollars on a U.S. bank) and mail together with name, address, and phone number to: Los Alamos National Laboratory, Group HSR-4, MCNP Class/David Seagraves, Mail Stop J573, Los Alamos, NM 87545.

This course is offered by the Health Physics Measurements Group at LANL and is a completely separate offering from the other courses offered by other groups at Los Alamos.

Inquiries regarding registration and class space availability should be made to David Seagraves, 505-667-4959, fax: 505-665-7686, e-mail: dseagraves@lanl.gov. Technical questions may also be directed to Dick Olsher, 505-667-3364, e-mail: dick@lanl.gov.
 
 

RSICC is pleased to announce that a five-day workshop on Oak Ridge National Laboratory's (ORNL) SAMMY code will be held May 12-16, 2003, in Knoxville, Tennessee. This training course is intended for those who are interested in the theory of neutron cross sections in the resonance region, and in the use of SAMMY for the analysis of experimental neutron-induced cross-section data for extracting values and covariances for resonance parameters. Both novice and experienced SAMMY users would benefit from the intensive and extensive examination of all aspects of resonance parameter analyses.

During the workshop, lectures and computer applications will alternate. Lectures will include both theoretical discussion and practical examples for each topic. The lecturer is Dr. Nancy Larson of the Nuclear Data and Information Analysis Group, Nuclear Science and Technology Division of ORNL, author of the SAMMY code.

Topics include (but are not limited to) the following:

I. R-matrix formalisms (both resolved and unresolved resonance region)

II. Simulation of experimental conditions
A. Multiple nuclides in the sample
B. Doppler- and resolution-broadening
C. Self-shielding and multiple-scattering corrections
D. Other data-reduction effects

III. Mathematical methods used for experimental data-fitting
A. Use of covariance information

IV. Reporting results for Evaluated Nuclear Data Files

V. Features in the latest version of the analysis code SAMMY

The workshop will include hands-on computer applications using the latest version of SAMMY (M6). Computer exercises will lead participants through the various features of the code beginning with simple examples and leading to realistic situations. Participants who are experienced SAMMY users are encouraged to bring their own examples as well.

The number of PC workplaces available at the training center restricts the number of workshop participants accepted. Therefore, we encourage you to register as early as possible. The SAMMY workshop web site with further detailed information and on-line registration can be accessed at http://www-rsicc.ornl.gov/SAMMY/intro.html). Please bookmark the site and visit it occasionally for news and updates as they become available.
 
 

Version 5 of the SCALE software system is scheduled for release in 2003. This half-day tutorial workshop will highlight signficant new computational capabilities in SCALE 5 plus current developments that will appear in later SCALE releases. The workshop will be part of the American Nuclear Society M&C 2003 Topical Meeting in Gatlinburg, Tennessee. The workshop will be hosted by Oak Ridge National Laboratory at the conference hotel in Gatlinburg on Thursday afternoon April 10, 2003, immediately following the final technical sessions of the topical meeting.

The workshop will feature presentations on the following new computational capabilities to be released in SCALE 5:

· SEN3 3-D sensitivity/uncertainty sequence (using KENO V.a)

· TRITON/NEWT 2-D flexible mesh discrete ordinates automated sequences for criticality safety and depletion/source term analyses.

· New resonance cross-section processing capabilities using continuous energy and ENDF/B-VI cross sections.

· New 2-D interactive plotting of KENO and XSDRNPM results with Javapeno.

Plus, the workshop will also feature presentations on the following developments planned for release:

· Continuous energy version of the KENO V.a criticality safety code

· 3-D automated variance reduction for Monte Carlo radiation shielding analysis

The registration fee is $200. You can register online at www.ornl.gov/scale/register_scale5.html or as part of your M&C 2003 registration. The early registration deadline is February 28, 2003.
 
 

The Forum will be held March 25-26, 2003, at the Crystal Gateway Marriott Hotel, which is conveniently located in Arlington, Virginia.

The Program Committee is now accepting presentation proposals for the Software Quality Forum 2003 (SQF 2003). The Forum offers an exciting opportunity for software professionals in the Department of Energy (DOE), other government agencies, private industry, and academia to share their knowledge about trends and technologies in the acquisition, development, support, and management of software intensive systems. Well-known keynote speakers, tutorials on key Forum topics, a showcase for high-visibility IT projects using cutting-edge technologies, and a vendor exhibit area are included in the program.

This is a tri-annual event sponsored by the Software Quality Assurance Subcommittee (SQAS) of the Quality Managers within the DOE Nuclear Weapons Complex. The 2003 Forum is co-hosted by the DOE Office of the Chief Information Officer and the National Nuclear Security Administration, Office of Advanced Simulation and Computing within the Office of Defense Programs.

Please note the following due dates: submission of proposal, abstract, and biography was due November 15, 2002, notification of acceptance was December 31, 2002, final abstract is January 15, 2003, and electronic and paper versions of presentation are due February 1, 2003.

For more information visit the web site http://cio.doe.gov/sqas. Look for the "Forum 2003" heading on the left side of the home page. There will be a website devoted to the SQF 2003 in a week or so, which will be linked from the above website. If you have questions, send email to Kathleen Canal at kathleen.canal@ hq.doe.gov. If interested in submitting a presentation proposal, please contact Brenda Coblentz, Program Committee Chair, at brenda.coblentz@hq.doe.gov.
 
 

The deadline for submitting abstracts for the international conference on "Supercomputing in Nuclear Applications" SNA-2003, Paris, September 22-24, 2003, was extended to December 16, 2002.

The web pages (http://sna-2003.cea.fr/) were expanded to include information on tours, sightseeing and events scheduled at the time of the conference.

One of the events at SNA-2003 is linked to the museum of "arts et metier", literally of arts & crafts; art is here used in its primary meaning: skills acquired through studies and by practice, technical knowledge. In this museum are displayed among many other items the "supercomputer" of 1642: arithmetical machine by Blaise Pascal, the original pendulum of Foucault (1851) or the instrument he developed to measure the speed of light (1852), or a decimal clock with a day of 10 hours each of 100 minutes and a minute of 100 seconds etc. Abstracts can be submitted http://www.nea.fr/html/science/ meetings/sna2003/registration.html.
 
 

January 2003

2nd International Workshop on Advanced Radiation Transport Simulation with PENELOPE, Jan. 8-10, 2003, Tarragona, Spain. Contact: Dr Francesc Salvat (tel 34 9340 21186, fax 34 9340 21174, email cesc@ecm.ub.es).

MCNP Course, Jan. 27-30, 2003, Mass. Inst. of Technology, Cambridge, MA. Contact: Elizabeth Selcow (emailselcow@lanl.gov, url http://www-xdiv.lanl.gov/x5/MCNP/index.html).

February 2003

MCNPX Workshop, Feb. 24-28, 2003, Las Vegas, NV. Contact: Bill Hamilton (tel 505-662-9097, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

MCNP Course, Feb. 2003, (TBA), North Carolina State University. Contact: Elizabeth Selcow (email selcow@lanl.gov, url http://www-xdiv.lanl.gov/x5/MCNP/index.html ).

March 2003

14th Annual U.S. Hydrogen Meeting, Mar. 4-6, 2003, Washington, DC. Contact: Catherine E. Grégoire Padró (tel 303-275-2919, fax 303-275-2905, email owner-hydrogen@mail.nrel.gov, url http://www.hydrogenconference.org/).

Software Quality Forum 2003, Mar. 24-26, 2003, in Arlington, VA. Contact: Kathleen Canal (email kathleen.canal@hq.doe.gov, url http://cio.doe.gov/sqas).

MCNPX Workshop, Mar. 31-Apr. 4, 2003, Knoxville, TN. Contact: Bill Hamilton (tel 505-662-9097, email registrar@mcnpxworkshops.com url http://mcnpxworkshops.com for details).

SCALE5 Workshop, Mar. 31-Apr. 4, 2003, Oak Ridge, TN. Contact: Kay Lichtenwalter (email x4s@ornl.gov, scalehelp@ornl.gov, url http://www.ornl.gov/scale/ workshop_mc2003.html).

April 2003

ANS Topical Meeting, Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew, Apr. 6-10, 2003, Gatlinburg, TN. Co-sponsored by the American Nuclear Society's Reactor Physics, and Radiation Protection and Shielding Divisions, as well as the ANS Oak Ridge/Knoxville Local Section, Oak Ridge National Laboratory's Radiation Safety Information Computational Center, the Nuclear Energy Agency of the OECD, the Korean Nuclear Society, and the Canadian Nuclear Society. Contacts: Yousry Azmy (tel 814-865-0039, email yya3@psu.edu or Bernadette Kirk (tel 865-74-6176, email kirkbl@ornl.gov, url http://meetingsandconferences.com /MC2003/index.html).

Visual Editor for MCNP, Apr. 6, 2003, Gatlinburg, TN. Contact: Randy Schwartz (url http://www.mcnpvised. com/ved/class7.html).

39th NCRP Meeting, Apr. 9-10, 2003, Arlington, VA. Contact: William Beckner (tel 301-657-2652, fax 301-907-8768, url http://www.ncrp.com).

May 2003

Radiation Transport Calculations using the EGS Monte Carlo System, May 5-8, 2003, Ottawa, Canada. Contact: Blake Walters, Ionizing Radiation Standards, National Research Council of Canada, Ottawa, Canada, K1A 0R6. (tel 613-993-2715, fax 613-952-9865, email bwalters@irs.phy.nrc.ca, url http://www.irs.inms.nrc.ca/inms/irs/papers/ egsnrc/brochure.html).

MCNP Course, May 12-16, 2003, Japan. Contact: Elizabeth Selcow (email selcow@lanl.gov, url http://www-xdiv.lanl.gov/x5/MCNP/index.html).

MCNPX Workshop, May 2003, Los Alamos/Santa Fe, NM. Contact: Bill Hamilton (tel 505-662-9097, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

June 2003

Practical MCNP For The HP, Medical Physicist, And Rad Engineer, June 16-20, 2003, Los Alamos, NM. Contact: David Seagraves (tel 505-667-4959, fax 505-665-7686, email dseagraves@lanl.gov, url drambuie.lanl.gov/~esh4/mcnp.htm).

MCNPX Workshop, June 2003, Europe. Contact: Bill Hamilton (tel 505-662-9097, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

MCNP Course, June 2003, (TBA), Los Alamos National Laboratory, Los Alamos, NM. Contact: Elizabeth Selcow (email selcow@lanl.gov, url http://www-xdiv.lanl.gov/x5/MCNP /index.html).

July 2003

2003 IEEE Nuclear and Space Radiation Effects Conference (NSREC), July 21-25, 2003, Monterey, CA. Contact: Paul Dodd (tel 505-844-1447, url http://www.nsrec.com).

August 2003

21st International System Safety Conference, Aug. 4-8, 2003, Ottawa, Canada. Contact: Gerry Einarsson, Chair, (tel 613-824-2468, email einargk@rogers.com, url http://www.russona.com/issc21/).

MCNP Course, Aug. 2003, (TBA), Los Alamos National Laboratory, Los Alamos, NM. Contact: Elizabeth Selcow (email selcow@lanl.gov, url http://www-xdiv.lanl.gov/x5/MCNP/ index.html).

September 2003

Workshop on Nuclear Data for the Transmutation of Nuclear Waste, Sept. 1-5, 2003, GSI-Darmstadt, Germany, Contact: Aleksandra Kelic (tel 49-0- 6159-71-2727, fax 49-0-6159-71-2785, email A.Kelic@gsi.de, url http://www-wnt.gsi.de/tramu).

Nuclear Energy for New Europe 2003, Sept. 8-11, 2003, Portorož, Slovenia, Contact: Tomaz Zagar (phone +386-1-588-5450, fax +386-1-561-2335, email PORT2003@ijs.si, url http://www.drustvo -js.si/port2003/).

9th International Conference on Environmental Remediation and Radioactive Waste Management, Sept. 21-25, 2003, Oxford, England. Contact: (url www.icemconf.com).

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

October 2003

American Nuclear Society's Advances in Nuclear Fuel Management III Topical Meeting, Oct. 5-8, 2003, Hilton Head Island, SC. Contact: Youssef A. Shatilla (email shatilya@westinghouse.com, url http://rpd.ans.org/nfm.htm).

9th Triennial International Symposium in Radiation Physics, Oct. 27-31, 2003, Cape Town, South Africa. Contact: Dr. D. T. L. Jones (tel +27-21-843-1336, fax +27-21-843-3382, email Jones@tlabs.ac.za url www.medrad. tlabs.ac.za/isrp9.htm).

December 2003

The 11th International Conference on Fusion Reactor Materials (ICFRM-11), Dec. 7-12, 2003, Kyoto, Japan. Contact ICFRM-11 secretariat ( tel +81-774-38-3597, fax +81-774-38-3467, email icfrm@iae.kyoto-u.ac.jp, url http://icfrm.iae.kyoto-u.ac.jp).
 
 

The nuclear systems literature (shielding, safety, materials) cited below 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). We now include medical physics in addition to material science, radiation dosimetry, radiation safety, reactor dynamics, reactor safeguards, risk assessment, waste management, fuel cycle, fusion and plasmas, high energy particle transport, and shielding. 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.

Ann. Nucl. Energy, 30, 513-547. . . The Flat Flux Problem in One-Speed Neutron Transport Theory. . . .Williams, M.M.R. . . . March 2003.

Ann. Nucl. Energy, 30, 549-553. . . On the Average Chord Length in Reactor Physics. . . .de Kruijf, W.J.M.; Kloosterman, J.L. . . . March 2003. . . Delft University of Technology, JB Delft, The Netherlands.

Ann. Nucl. Energy, 30, 555-565. . . Coarse-Grained Parallel Genetic Algorithm Applied to a Nuclear Reactor Core Design Optimization Problem. . . .Pereira, C.M.N.A.; Lapa, C.M.F. . . . March 2003. . . Comissao Nacional de Energia Nuclear, Rio de Janeiro, Brazil; Universidade Federal do Rio de Janeiro, Brazil.

Ann. Nucl. Energy, 30, 567-583. . . Acceleration Techniques for Trajectory-Based Deterministic 3D Transport Solvers. . . .Wu, G.J.; Roy, R. . . . March 2003. . . Ecole Polytechnique de Montreal, Quebec, Canada.

Ann. Nucl. Energy, 30, 585-601. . . Reactor Pressure Analysis at the Initial Stage of a Loss of Coolant Accident. . . .Valero, E.; Parra, I.E. . . . March 2003. . . Universidad Politecnica de Madrid, Spain.

Ann. Nucl. Energy, 30, 603-613. . . Nuclear Fuel Loading Pattern Optimisation Using a Neutral Network. . . .Faria, E.F.; Pereira, C. . . . March 2003. . . UFMG, Belo Horizonte, Brazil.

Ann. Nucl. Energy, 30, 615-631. . . Practical Correction of Dead Time Effect in Variance-To-Mean Ratio Measurement. . . .Hazama, T. . . . March 2003. . . Japan Nuclear Cycle Development Institute, Ibaraki, Japan.

Ann. Nucl. Energy, 30, 633-649. . . Determination of the Optimal Plutonium Fraction in Transuranium Discharged from Pressured Water Reactor (PWR) Spent Fuel for a Flat Fission Power Generation in the Force-Free Helical Reactor (FFHR) Al. . .Yapici, H. . . . April 2003. . . Erciyes Universitesi, Kayseri, Turkey.

Ann. Nucl. Energy, 30, 651-667. . . Numerical Study of Optimal Equilibrium Cycles for Pressurized Water Reactors.. . .Mahlers, Y.P. . . . April 2003. . . Institute for Nuclear Research, Kiev, Ukraine.

Ann. Nucl. Energy, 30, 669-683. . . Neutronics Analysis of HYLIFE-II Blanket for Fissile Fuel Breeding in an Inertial Fusion Energy Reactor.. . .Sahin, S. et al.. . . April 2003. . . Gazi Universitesi, Ankara, Turkey; Bahcesehir Universitesi, Istanbul, Turkey.

Ann. Nucl. Energy, 30, 685-714. . . On the Application of Field Codes to the Analysis of Gas Mixing in Large Volumes: Case Studies Using CFX and GOTHIC.. . .Andreani, M. et al. . . . April 2003. . . Paul Scherrer Institut, Villigen, Switzerland.

Ann. Nucl. Energy, 30, 715-727. . . Hilbert-Huang Analysis of BWR Neutron Detector Signals: Application to DR Calculation and to Corrupted Signal Analysis. . . .Monetesinos, M.E. et al.. . . April 2003. . . Universidad Politecnica de Valencia, Valencia, Spain; University of Colorado, Boulder, CO.

Ann. Nucl. Energy, 30, 729-738. . . The WIMSD Library in the ENDF/B Format. . . .Caldeira, A.D.. . . April 2003. . . Instituto de Estudos Avancados, Sao Jose dos Campos, Brazil.

J. Nucl. Mater., 306, 1-9. . . De-Agglomeration of Thorium Oxalate - A Method for the Synthesis of Sinteractive Thoria.. . .Anathasivan, K. et al.. . . November 2002. . . Indira Gandhi Centre for Atomic Research, Kalpakkam, India.

J. Nucl. Mater., 306, 10-14. . . Thermal Conductivity of Rare Earth-Uranium Ternary Oxides of the Type Re6UO12. . . .Krishnaiah, M.V. et al.. . . November 2002. . . Indira Gandhi Centre for Atomic Research, Kalpakkam, India.

J. Nucl. Mater., 306, 15-20. . . Recombination of Deuterium Atoms on the Surface of Molten Li-LiD. . . .Baldwin, M.J. et al. . . . November 2002. . . University of California - San Diego, CA; Sandia National Laboratories, Livermore, CA.

J. Nucl. Mater., 306, 21-29. . . The Determination of Hydrogen and Deuterium in Zr-2.5Nb Material By Hot Vacuum Extraction Mass Spectrometry.. . .Bickel, G.A. et al. . . . November 2002. . . AECL - Chalk River, Ontario, Canada.

J. Nucl. Mater., 306, 30-43. . . Fuel Oxidation and Thermal Conductivity Model for Operating Defective Fuel Rods.. . .Lewis, B.J.; Szpunar, B.; Iglesias, F.C. . . . November 2002. . . Royal Military College of Canada, Ontario, Canada; Bruce Power, Ontario, Canada.

J. Nucl. Mater., 306, 44-53. . . Oxidation Characteristics of Bassal (0002) Plane and Prism (1120) Plane in HCP Zr.. . .Kim, H.G.; Kim, T.H.; Jeong, Y.H. . . . November 2002. . . Yonsei University, Seoul, South Korea; KAERI, Daejon, South Korea.

J. Nucl. Mater., 306, 54-60. . . Processing and Fabrication of Mixed Uranium/Refractory Metal Carbide Fuels with Liquid-Phase Sintering.. . .Knight, T.W.; Anghaie, S. . . . November 2002. . . University of Florida, Gainesville, FL.

J. Nucl. Mater., 306, 61-72. . . Molecular Dynamics Simulation of the Gamma-Recoil Nucleus Displacement Cascade in Zirconolite.. . .Veiller, L.; Crocombette, J.-P.; Ghaleb, D. . . . November 2002. . . Commissariat a l'Energie Atomique, Gif-sur-Yvette, France.

J. Nucl. Mater., 306, 73-77. . . Observations of Hydrocarbon Film Deposition in the MAST Tokamak.. . .Tabasso, A. et al.. . . November 2002. . . Culham Science Centre, Oxon, United Kingdom; University of Sussex, Brighton, United Kingdom.

J. Nucl. Mater., 306, 78-83. . . Contribution of Thermal Neutrons to Radiation Hardening of Pure Copper.. . .Fabritsiev, S.A.; Pokrovsky, A.S. . . . November 2002. . . D.V. Efremov Scientific Research Institute of Electrophysical Apparatus, St. Petersburg, Russia; Scientific Research Institute of Atomic Reactors, Dimitrovgrad, Russia.

J. Nucl. Mater., 306, 85-98. . . Transport Properties of Zirconium Alloy Oxide Films.. . .Frank, H.. . . December 2002. . . Czech Technical University, Prague, Czech Republic.

J. Nucl. Mater., 306, 99-104. . . Iodine Release from Oxidised Zircaloy Cladding in Contact with an Alkaline Solution. . . .Poulard, K. . . . December 2002. . . Institut de Physique Nucleaire de Lyon, Villeurbanne, France; ANDRA, Chatenay-Malabry, France.

J. Nucl. Mater., 306, 105-111. . . Positron Lifetime Computations of Defects in Nickel Containing Hydrogen or Helium.. . .Shivachev, B.L. et al.. . . December 2002. . . Bulgarian Academy of Sciences, Sofia, Bulgaria; Kyoto University Osaka, Japan.

J. Nucl. Mater., 306, 112-120. . . Effect of Sputtering in Xe Ion Irradiated Yttria-Stabilized Zirconia.. . .Afanasyev-Charkin, I.V.; Sickafus, K.E. . . . December 2002. . . Los Alamos National Laboratory, Los Alamos, NM.

J. Nucl. Mater., 306, 121-125. . . Effects of Xe-Ion Irradiation at High Temperature on Single Crystal Rutile.. . .Li, F.; Lu, P.; Sickafus, K.E. . . . December 2002. . . New Mexico Institute of Mining and Technology, Socorro, NM; Los Alamos National Laboratory, Los Alamos, NM.

J. Nucl. Mater., 306, 126-133. . . Characterization of Hot Deformation Behaviour of Zr-2.5Nb in Beta Phase. . . .Kapoor, R.; Chakravartty, J.K. . . . December 2002. . . Bhabha Atomic Research Centre, Mumbai, India.

J. Nucl. Mater., 306, 134-146. . . Influence of the pH on the Dissolution of TPD and Associated Solid Solutions.. . .Robisson, A.C.; Dacheux, N., Aupiais, J. . . . December 2002. . . Universite Paris-Sud, Orsay, France; CEA, Bruyeres le Chatel, France.

J. Nucl. Mater., 306, 147-152. . . Study of Decomposition and Reactions with Aluminum Matrix of Dispersed Atomized U-10 wt% Mo Alloy.. . .Lee, J-S. et al.. . . December 2002. . . KAERI, Daejeon, South Korea; Institute of Nuclear Physics, Tashkent, Uzbekistan.

J. Nucl. Mater., 306, 153-172. . . Microstructure of Irradiated SBR MOX Fuel and Its Relationship to Fission Gas Release.. . .Fisher, S.B. et al. . . . December 2002. . . British Nuclear Fuels, Cumbria, UK; Joint Research Center, Karlsruhe, Germany; BNFL R&T, Gloucestershire, UK; Nordostschweizerische Kraftwerke, Baden, Switzerland; AEA Technology, Cumbria, UK.

J. Nucl. Mater., 306, 173-179. . . Radiogenic Silicon Precipitates in Neutron Irradiated Aluminum.. . .Brosh, E.; Kiv, A. . . . December 2002. . . Ben-Gurion University of the Negev, Beer Sheva, Israel.

J. Nucl. Mater., 306, 180-189. . . Helium Behaviour and Defect Evolution in Amorphous Spinel During Thermal Annealing.. . .Damen, P.M.G. et al. . . . December 2002. . . Joint Research Centre, Karlsruhe, Germany; Delft University of Technology, JB Delft, The Netherlands; Los Alamos National Laboratory, Los Alamos, NM.

J. Nucl. Mater., 306, 190-193. . . Studies on the Oxidation Behavior of Niobium-Implanted Zircaloy-4 at 500 Degrees Celcius.. . .Chen, X.W. et al.. . . December 2002. . . Tsinghua University, Beijing, China; Jianzhong Chemical Cooperation, Sichuan, China.

J. Nucl. Mater., 306, 194-201. . . Study of the Thermoelectric Power Evolution of Zr-Based Alloys with Nb Additions.. . .Kim, S.J.; Hong, H.S.; Oh, Y.M. . . . December 2002. . . Hanyuang University, Seoul, South Korea.

J. Nucl. Mater., 306, 202-212. . . Raman Microspectrometric Identification of Corrosion Products Formed on UO2 Nuclear Fuel During Leaching Experiments.. . .Amme, M. et al.. . . December 2002. . . Joint Research Centre, Karlsurhe, Germany; Forschungszentrum Karlsruhe, Germany; University of Stuttgart, Germany; SVSMF, Basel, Switzerland.

J. Nucl. Mater., 306, 213-217. . . Experimental Verification of the Existence and Structure of Zeta Pu5Fe in a Pu-Ga Alloy.. . .Moore, K.T.; Wall, M.A.; Schwartz, A.J. . . . December 2002. . . Lawrence Livermore National Laboratory, Livermore, CA.

J. Nucl. Mater., 306, 218-231. . . Effect of Helium on the Swelling of GlidCop A125 IG Alloy.. . .Fabritsiev, S.A. et al.. . . December 2002. . . D. V. Efremov Scientific Research Institute of Electrophysical Apparatus, St. Petersburg, Russia; Scientific Research Institute of Atomic Reactors, Dimitrovgrad, Russia; Oak Ridge National Laboratory, Oak Ridge, TN.

J. Nucl. Mater., 306, 232-240. . . Plasma-Driven Superpermeation of Hydrogen Through Nb Membranes: Bulk Effects.. . .Skovoroda, A.A. et al.. . . December 2002. . . Kurchatov Institute, Moscow, Russia; Technical University, Moscow, Russia; Moscow State University, Moscow, Russia; Yaroslavl State Technical University, Yaroslavl, Russia.

KEK Proceedings 2002-8. . . Proceedings of the APPI Winter Institute. . .Fujii, Y. ed. . . . July 2002. . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.

KEK Proceedings 2002-11. . . Second CPP Symposium Computational Particle Physics.. . .Kurihara, Y. ed.. . . August 2002. . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.

Nucl. Eng. Design, 219, 1-10. . . Thermal Resistance Contributions of Oxides Growth on Incoloy 800 Steam Generator Tubes.. . .Iglesias, A.M.; Raffo-Calderon, M.A.. . . January 2003. . . Comision Nacional de Energia Atomica, Buenos Aires, Argentina.

Nucl. Eng. Design, 219, 11-18. . . Effect of Loading Rate Upon Fracture Behavior of Ferritic Steel Under Large Scaled Yielding.. . .Kang, K-J. et al.. . . January 2003. . . Chonnam National University, Kwangju, South Korea; Korea Electric and Nuclear Power Co., Daejon, South Korea.

Nucl. Eng. Design, 219, 19-34. . . Validation Study of Computer Code SPHINCS for Sodium Fire Safety Evaluation of Fast Reactor.. . .Yamaguchi, A.; Yajima, Y. . . . January 2003. . . Japan Nuclear Cycle Development Institute, Ibaraki, Japan; ENO Suri Kaiseki Research, Chiba, Japan.

Nucl. Eng. Design, 219, 35-46. . . Thermal-Hydraulic Analysis for a Sodium-Heated Steam Generator Using a Multi-Shell Method. . . .Sakai, T.; Yamaguchi, A.; Metz, P. . . . January 2003. . . Japan Nuclear Cycle Development Institute, Ibaraki, Japan.

Nucl. Eng. Design, 219, 57-60. . . Fluctuation Characteristics of Heating Surface Temperature Near an Obstacle in Transient Boiling Two-Phase Flow in a Vertical Annular Channel.. . .Fukano, T.; Mori, S.; Nakagawa, T. . . . January 2003. . . Kyushu University, Fukuoka, Japan.

Nucl. Eng. Design, 219, 61-75. . . Interfacial Area Transport and Evaluation of Source and Sink Terms for Confined Air-Water Bubbly Flow.. . .Kim, S. et al.. . . January 2003. . . Purdue University, West Lafayette, IN.

Nucl. Eng. Design, 219, 77-86. . . Flow Sheet Calculations in Thorex Method for Reprocessing Th-Based Spent Fuels. . . .Zabunoglu, O.H.; Akbas, T.. . . January 2003. . . Hacettepe University, Ankara, Turkey; Turkish Atomic Energy Authority, Ankara, Turkey.

Nucl. Eng. Design, 219, 87-89. . . Erratum to "Prestressed Concrete Containment of Nuclear Power Station with PWR" [Nucl. Eng. Design, 214 (2002) 73-182]. . . .Freidin, C.; Krichevsky, A. . . . January 2003. . . Ben-Gurion University, Negev, Israel.

Nucl. Sci. Eng., 142, 245-257. . . Computing Moment-Based Probability Tables for Self-Shielding Calculations in Lattice Codes. . . .Hebert, A.; Coste, M. . . . November 2002. . . Centre d'Etudes de Saclay, Gif-sur-Yvette, Cedex, France.

Nucl. Sci. Eng., 142, 258-269. . . Simulation of Mixed-Oxide and Low-Enriched Uranium Fuel Burnup in a Pressurized Water Reactor and Validation Against Destructive Analysis Results. . . .Murphy, B.D.; Primm, III, R.T.. . . November 2002. . . Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Sci. Eng., 142, 270-291. . . Finite Element Solution of the Self-Adjoint Angular Flux Equation for Coupled Electron-Photon Transport.. . .Liscum-Powell, J.L. et al. . . . November 2002. . . Sandia National Laboratories, Albuquerque, NM; University of New Mexico, Albuquerque, NM; Los Alamos National Laboratory, Los Alamos, NM.

Nucl. Sci. Eng., 142, 292-304. . . Comparative Measures of Radionuclide Containment in the Crystalline

Geosphere. . . .Cvetkovic, V. et al. . . . November 2002. . . Royal Institute of Technology, Stockholm, Sweden; Southwest Research Institute, San Antonio, TX; Swedish Nuclear Fuel and Waste Management Co., Stockholm, Sweden.

Nucl. Sci. Eng., 142, 305-314. . . Mechanisms of Positive Temperature Reactivity Coefficients of Dilute Plutonium Solutions.. . .Yamamoto, T.; Miyoshi, Y. . . November 2002. . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

Nucl. Sci. Eng., 142, 315-326. . . A Spent-Fuel Combination Method for Minimizing Composition Variability of DUPIC Fuel. . . .Na, M.G. et al.. . . November 2002. . . Chosun University, Kwangju, Korea; KAERI, Taejon, Korea.

Nucl. Sci. Eng., 142, 327-341. . . An Alternative Implementation of the Differential Operator (Taylor Series) Perturbation Method for Monte Carlo Criticality Problems.. . .Favorite, J.A. . . . November 2002. . . Los Alamos National Laboratory, Los Alamos, NM.

Nucl. Sci. Eng., 142, 342-348. . . Photon Interaction Studies with Some Glasses and Building Materials.. . .Singh, H. et al.. . . November 2002. . . Guru Nanak Dev University, Amritsar, India; Bhabha Atomic Research Centre, Mumbai, India; Punjabi University, Patiala, India.