Printable PDF file of this newsletter available at: http://www-rsicc.ornl.gov/NEWSLETTER.html.
A very significant error in the beryllium metal cross-section data contained
in the 238- and 44-Group ENDF/B-V libraries was recently discovered by
SCALE users at ORNL. Several critical experiments that involved beryllium
metal as the reflector were found to have > 1% difference in calculated
k-eff values between different versions of SCALE (4.3 vs. 4.4a). The Be
metal data in SCALE 4.4 and 4.4a contain a factor of 2 scaling error in
the Be thermal scattering transfer arrays. This error can result in non-conservative
errors in calculated k-eff values of greater than 1%. Users should download
the corrected data from the SCALE
Download page and install according to the directions provided in the
file. This error is NOT present in SCALE 4.3. For more information, read
the discussion on
395 of the SCALE Notebook. (Hard copy readers see: http://www.ornl.gov/scale/scale-home.html.)
One U.S. Nuclear Regulatory Commission (NRC) software package transferred from the Energy Science and Technology Software Center, Oak Ridge, Tennessee, to RSICC was processed this month. Please browse the computer code abstract available at RSICC's web site for more information on this package.
Four changes were made to the computer code collection this month: one
new package, one addition/correction, one correction and one update.
Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a corrected version of the ORIGEN2 isotope generation and depletion code system. This is the first update to ORIGEN2 in over 10 years and was stimulated by a user discovering a discrepancy in the mass of fission products calculated using ORIGEN2 V2.1. Code modifications, as well as reducing the irradiation time step to no more than 100 days/step, reduced the discrepancy from ~10% to 0.16%. The bug does not noticeably affect the fission product mass in typical ORIGEN2 calculations involving reactor fuels because essentially all of the fissions come from actinides that have explicit fission product yield libraries. Thus, most previous ORIGEN2 calculations that were otherwise set up properly should not be affected. Additional details are included in the transmittal memo, which is included in the distribution.
ORIGEN is a computer code system for calculating the buildup, decay, and processing of radioactive materials. ORIGEN2 is a revised version of ORIGEN and incorporates updates of the reactor models, cross sections, fission product yields, decay data, and decay photon data, as well as the source code.
The code runs on Pentium personal computers under Windows and was compiled
and linked with the Lahey F77L-EM/32 Fortran compiler version 5.20. The
executables, which run under Windows 95, Windows NT 4 and later, are included
in the package. The code was also tested on a Pentium III running RedHat
Linux 6.1 with The Portland Group, Inc. (PGI) F77 compiler 3.1-3 &
gcc. The PGI executables are also included in the Linux distribution. A
Fortran 77 compiler is required all other computers. The package is transmitted
on a CD which contains a self-extracting, compressed Windows file and a
GNU compressed tar file. Reference: ORNL/TM-7175 (July 1980). Fortran;
Argonne National Laboratory, Argonne, Illinois, contributed this code system for analysis of research reactor fuel cycles. REBUS-PC contains DIF3D 9.0/VARIANT9.0, a code system using variational nodal methods and finite difference methods to solve neutron diffusion and transport theory problems. REBUS-PC provides new capabilities beyond that of CCC-653, REBUS3/VARIANT8.0. Although REBUS-PC was developed for analysis of research reactor cores and fuel cycles, it remains generally useful for any reactor type.
REBUS-PC is a system of codes designed for the analysis of research reactor fuel cycles. It is based on an updated 9.0 version of DIF3D that is similar to RSICC Code Package CCC-653, REBUS-3/VARIANT 8.0 (which is intended for use on unix workstations). The full capabilities of the workstation version are retained and enhanced for use in a PC environment. 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 non-equilibrium operation of a reactor under a specified periodic or non-periodic fuel management program. For the equilibrium type problems, the code uses specified external fuel supplies to load the reactor. Optionally, reprocessing may be included in the specification of the external fuel cycle and discharged fuel may be recycled into the reactor. For non-equilibrium cases, the initial composition of the reactor core may be explicitly specified or the core may be loaded from external feeds and discharged fuel may be recycled into the reactor as in equilibrium problems.
The code is written entirely in Fortran 77. REBUS-PC 1.4 executables
are included with this package. The Windows executable was created on a
Micron Pentium III machine running Windows 2000 using Lahey Fortran 95
V5.56. The Linux executable was created using the LAHEY/Fujitsu Fortran
95 Linux Pro V6.1 compiler under Red Hat Linux 7.2. Other advanced Fortran
compilers could be used but would require changes in dynamic memory management
calls and clock timer routines or anywhere else the particular Fortran
dialect differs from Lahey Fortran 95. The operating system can be any
of Windows 95/98/NT4.0/2000 or newer or any Linux variation such as Red
Hat Linux 7.2 that is compatible. The package is distributed on a CD which
contains a self-extracting, compressed Windows file and a GNU compressed
tar file. Approximately 331 MB is required for installation. Included in
the distribution files are the source code, Windows and Linux executables,
sample problem input and output, and code dependent BCD and binary card-image
file descriptions. Reference: Argonne National Laboratory Report (December
21, 2001). Fortran 77, PC (C00708/PC586/00).
A minor change was made to version 15a of MARLOWE, which was developed at Oak Ridge National Laboratory, Oak Ridge, Tennessee. The value assigned to PI was corrected in the source/master/code.mmf file. The effect on any MARLOWE calculations would be exceedingly small (if anything) even if the code is run in double precision.
MARLOWE is a flexible, comprehensive, and highly portable program for
simulating atomic collision processes in crystalline solids in the binary
collision approximation. It is used to study phenomena governed by such
collisions, including the sizes and shapes of displacement cascades, sputtering,
ion ranges, ion reflection, and so on. The program has been used for many
years on many different computers and is fully supported on UNIX, Linux,
and Windows 95/98/ME/NT/2000/XP systems. Compilers are required on all
computers. No executables are included. The GNU f77 compiler can be used
on most systems. Fortran 90 and C; UNIX and Linux systems; Windows 95/98/NT
Los Alamos National Laboratory, Los Alamos, New Mexico, contributed two additions and a correction to this package of standard neutron, photon, electron, and proton data libraries. Additions include the LA150U photonuclear data and LA150H proton data tables. A modification was made to correct a small error in the original release of LA150N. The ZAID for Pb-208 was changed from 82208.24c to 82208.25c to differentiate from the earlier version. MCNPXDATA is for use with the MCNPX Monte Carlo code package and can be used with Version 4B, 4C and later of the MCNP transport code. These data provide a comprehensive set of cross sections for a wide range of radiation transport applications.
The LA150N neutron data library includes 42 isotopes: 1H, 2H, 9Be (100 MeV), natC, 14N, 16O, 27Al, 28Si, 29Si, 30Si, 31P, natCa, 50Cr, 52Cr, 53Cr, 54Cr, 54Fe, 56Fe, 57Fe, 58Ni, 60Ni, 61Ni, 62Ni, 64Ni, 63Cu, 65Cu, 93Nb, 182W, 183W, 184W, 186W, 196Hg, 198Hg, 199Hg, 200Hg, 201Hg, 202Hg, 204Hg, 206Pb, 207Pb, 208Pb, 209Bi.
The LA150U photonuclear library includes 12 isotopes: 12C, 16O, 27Al, 28Si, 40Ca, 56Fe, 63Cu, 181Ta, 184W, 206Pb, 207Pb, 208Pb.
LA150H proton data library (updated 11/20/01) includes 41 isotopes: 1H, 2H, 12C, 14N, 16O, 27Al, 28Si, 29Si, 30Si, 31P, 40Ca, 50Cr, 52Cr, 53Cr, 54Cr, 54Fe, 56Fe, 57Fe, 58Ni, 60Ni, 61Ni, 62Ni, 64Ni, 63Cu, 65Cu, 93Nb, 182W, 183W, 184W, 186W, 196Hg, 198Hg, 199Hg, 200Hg, 201Hg, 202Hg, 204Hg, 206Pb, 207Pb, 208Pb, 209Bi.
All data libraries are distributed in compressed mode. Expanded files
are in ASCII format and can be used with MCNPX on all computer platforms
supported by the code. The data are distributed in a GNU compressed tar
file on CD which also includes the MCNPX 2.3.0 code package. Note that
there is no Windows version of the MCNPX 2.3.0 code. The MCNPXDATA package
is alternately available in a self-extracting, compressed Windows file
for users who want the data but not the code package. Users must specify
whether tar or Windows format on the request form. References: The following
documents (and more) are distributed in electronic (PDF) form with the
package: Revised Appendix G of the MCNP4C manual, README (May 2002), LA-12891
(1994), X-6:HGH-93-77 (revised 1996), XTM:95-259 and LA-UR-96- 24 (1995),
X-6:RCL-87-225 (1987), XCI-RN(U)98-041, LA-UR-98-5718 (December 1998),
XTM:96-153 (April 1996), and XCI:CJW-99-25 (April 1999). (D00205/ALLCP/02).
DOSE Computation and Factors
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 devised 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. Next month: ENVIRONMENTAL TRANSPORT of RADIONUCLIDES.
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 alphabetically. 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 after
The University of New Mexico announces their 2002 schedule for Criticality Safety Courses. Dates are: July 9-11 for the Double Contingency & Criticality Safety Evaluation Workshop, July 15-19 is the Short Course, and July 23-25 is the Manager's Course.
For more detailed information about the 2002 Course offerings for Criticality
Safety and online registration, check out the web page at http://www-chne.unm.edu/crit/information.htm
or contact Cheryl Brozena at the University of New Mexico, Albuquerque
(tel 505-277-2225, fax 505-277-5433, email
The first announcement of "The 11th International Conference on Fusion
Reactor Materials (ICFRM-11)," which will be held in Kyoto, Japan Dec.
7-12, 2003, is now available on the ICFRM-11 website at: http://icfrm.iae.kyoto-u.ac.jp.
For further information, contact ICFRM-11 secretariat at firstname.lastname@example.org
or phone +81-774-38-3597, fax +81-774-38-3467.
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
Please return the following information (name, affiliation, phone, alternative email if preferable, topics of interest) to Youssef A. Shatilla at email@example.com.
Please remember that 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, in cooperation with the U.S. Department of Energy and the Fusion Engineering Division of the Atomic Energy Society of Japan will hold the 15th Topical Meeting on Technology of Fusion Energy. This meeting will be held as an embedded topical of the American Nuclear Society 2002 winter meeting, held November 17-21, 2002, in Washington, DC.
The purpose of this meeting is to bring together specialists in the area of fusion energy to discuss current work and future challenges in the area of fusion technology. In addition to bringing together the varied expertise of this aggressive research area, special sessions are planned to focus on similarities and differences between the inertial and magnetic fusion energy concepts and the interface between materials and design communities. The technical program will include paper and poster presentations as well as invited speakers.
Co-sponsors of this meeting are INEEL, LLNL, NRL, ORNL, and Kyoto University.
For more information, visit
To mark the beginning of the second century of nuclear science, the American Nuclear Society's Mathematics and Computation Division 2003 Topical Meeting is organized around the theme: Nuclear Mathematical and Computational Sciences: A Century in Review, A Century Anew. The conference will be held at the Park Vista Hotel, Gatlinburg, Tennessee, April 6-10, 2003. It is 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, Korean Nuclear Society, and the Canadian Nuclear Society.
The conference's web site is: http://meetingsandconferences.com/MC2003/.
It will be updated with new information as it becomes available. Please
bookmark and visit it occasionally for news and updates. Comments and suggestions
are most welcome. Contact: Yousry Azmy 865-574-8069, firstname.lastname@example.org
or Bernadette Kirk 865-574-6176,
announcement on SCALE 5 workshop, that will be held immediately before
the M&C Conference.)
The Fourth Meeting of the International MACCS Users Group (IMUG) will be held on September 6, 2002, in the Principality of Monaco. The focus of the Fourth IMUG Meeting will be the exchange of technical information relating to the application of MACCS, MACCS2, and COSYMA codes to relevant problems involving atmospheric dispersion of radioactive materials and resulting consequences.
There is no fee to participate in the meeting; however, for planning purposes, advance registration is requested. Everyone, including COSYMA users, is invited to present a paper. Please visit the website www.bnl.gov/est/IMUG2002/default.htm, and http://www.bnl.gov/est/IMUG2002/Latest_News.htm to find out about IMUG, register for the meeting or request notification of web updates. The website will be updated as additional information becomes available.
Please make your hotel arrangements as soon as possible. There is a
block of rooms being held at the Columbus Monaco Hotel for the meeting,
but there is another large conference being held in Monaco the same week.
The hotel registration form can be found by going to: www.bnl.gov/est/IMUG2002/
Along with the 2002 classes, the MCNP code developers announce the 2003
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 geometry 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 learning. 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
The class will be held September 9-13, 2002, 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 email@example.com).
Two classes are scheduled for 2003: March 17-21 and
September 8-12, both in Richland, Washington.
Lead Teachers: Drs. John Hendricks, Gregg McKinney, Laurie Waters
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.
For more information on code versions and their capabilities, go to the
MCNPX Workshops web site http://mcnpxworkshops.com.
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-37), August 12-16, 2002.
Monte Carlo Analysis: Monte Carlo is often the method of choice to solve complex problems in nuclear criticality safety and radiation shielding. To use Monte Carlo effectively, the analyst must understand the theoretical and computational fundamentals of the method, as well as the computational options available in particular computer tools. Also, it is sometimes advantageous to create new special-purpose Monte Carlo programs to solve particular problems rather than use an existing program. The Monte Carlo course runs five days.
Nuclear Criticality Safety: Engineers, scientists, and technical managers who wish to increase their knowledge and understanding of nuclear criticality safety will be interested in the intensive five-day 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 and experienced.
For additional information on all the courses offered during TIW-37,
contact Kristin England at The University of Tennessee, phone (865) 974-5048,
email firstname.lastname@example.org, url www.engr.utk.edu/nuclear/TIW.html.
Dates: August 5-7, 2002 in Braunschweig, Germany
Contact: Burkhard Wiegel, PTB
A training course on neutron spectra unfolding is being organized by the Neutron Dosimetry section of the Physikalisch-Technische Bundesanstalt (PTB), Braunschweig, Germany, in collaboration with the Health Physics Measurements Group (ESH-4) of the Los Alamos National Laboratory (LANL). Additional support is provided by the Helmholtz-Fonds e.V. The course will be given in August 2002 at PTB in Braunschweig, Germany, and in September 2002 in Los Alamos, New Mexico, USA.
Practical aspects of unfolding will be emphasized. The course is intended for those who do spectrometry in neutron or mixed neutron/photon fields and who need to analyze their data using unfolding procedures. The morning series of lectures will provide an introduction to unfolding as well as allow for discussions concerning the theory of unfolding. In the afternoon sessions the participants will work on specific examples at PC workplaces using unfolding software provided by PTB (the HEPRO package of unfolding codes and the MAXED code). We will focus on Bonner-sphere measurements for our discussion of few-channel unfolding, and liquid scintillation spectrometer (NE-213) measurements for our discussion of multi-channel unfolding.
The number of participants is restricted by the limited number of PC
workplaces at our disposal at each of the training centers. We therefore
encourage you to register as soon as possible. For online registration
and further information please visit our web site at: http://www.ptb.de/utc2002/.
The 48th Annual Radiobioassay and Radiochemical Measurements Conference will be held November 11-15, 2002, at the Marriott (formerly the Hyatt Regency) in Knoxville, Tennessee. This conference is a continuation of an informal conference with a long history. Over the past 47 years, the conference has also been known as:
Annual Bioassay and Analytical Chemistry Conference,
The objectives of the Conference (as adapted from the proceedings of the First Annual Bioassay and Analytical Chemistry Conference) are as follows:
1. To bring everyone up to date on some of the latest developments in
the field of bioassay, analytical, and environmental radiochemistry;
For more information, please visit the web site at: http://www.bioassay.org/2002/.
This online course is designed to teach current techniques for calculating the radiation dose from radionuclides administered in nuclear medicine. Lectures include Internal Dose Assessment Techniques, Resources for Internal Dose Assessment in Nuclear Medicine, Kinetic Modeling, Standard Kinetic Models and Phantoms, Extrapolation of Animal Data, Bone Marrow Dosimetry, Study Design for Radiopharmaceutical Dose Assessment, Patient Specific Dosimetry, and Small Scale and Microdosimetry. Problem-solving exercises and a comprehensive online exam are included. Users completing the exam will receive a certificate of completion. Users may also interact with instructors by email about any aspect of the course. The cost of this course is $495; access to the course is through www.internaldosimetry.com.
For questions or comments contact either of the course instructors,
Dr. Michael G. Stabin, (tel 615- 322-3190, fax 615-322-3764, email email@example.com)
or Dr. Richard B. Sparks (tel 865- 938-4949, fax 865-947-1550, email firstname.lastname@example.org,
url http://www.creative development.com,
The SCALE staff at Oak Ridge National Laboratory (ORNL) will be offering
two training courses this fall (October 14-18 and October 21-25)
at ORNL. 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 $3000 for both 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 for an additional fee of $700,
and the KENO3D 3-D visualization tool on CD is available for $800 (single
license). Registrations will be accepted on a first-come basis. Registration
forms submitted directly from the Web are preferred. Registration via fax
or email is also acceptable. The registration fee must be paid by check,
travelers checks, bank transfer, or credit card (VISA or MasterCard only).
The agenda and registration form are on the web page at
Contact: Kay Lichtenwalter (tel 865-574-9213, email email@example.com).
The first workshop on SCALE 5 is being planned in conjunction with the American Nuclear Society M&C 2003 Topical Meeting in Gatlinburg, Tennessee. The workshop will be hosted by Oak Ridge National Laboratory in nearby Oak Ridge, Tennessee. The course is scheduled for the week of March 31 - April 4, 2003, immediately before the M&C 2003 meeting.
The workshop will feature some of the new modules to be released in
SCALE 5, such as the SEN3 3-D sensitivity/uncertainty sequence and the
STARBUCS burnup credit sequence for criticality safety. The workshop 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 (there is
a $300 early registration discount). You can register online at www.ornl.gov/scale/register_scale5.html
as part of your M&C 2003 registration. The early registration deadline
is February 28, 2003. (See announcement on M&C 2003 Conference).
Snowmass Fusion Summer Study, July 8-19, 2002, Snowmass Village, CO (url http://fire.pppl.gov/snowmass02.html).
Spectrum 2002, Exploring Science-Based Solutions and Technologies, 9th Biennial International Conference on Nuclear and Hazardous Waste Management, Aug. 4-8, 2002, Reno, NV. Contact: Dr. Richard Jacobsen (email firstname.lastname@example.org, url www.ans.org/spectrum).
11th International Symposium on Reactor Dosimetry, Aug. 18-23,
2002, Brussels, Belgium. Contact: J. Adams (tel 301-975-6205, fax 301-926-1604,
email email@example.com, url
Fourth Meeting of the International MACCS Users Group (IMUG), Sept. 6, 2002, in the Principality of Monaco (url http://www.bnl.gov/est/IMUG2002).
22nd Symposium on Fusion Technology - SOFT, Sept. 8-13, 2002, Helsinki, Finland. Contact: Symposium Secretary Mrs. Merja Asikainen (tel +358 9 456 6854; fax +358 9 456 7002; email: firstname.lastname@example.org; url http://www.vtt.fi/val/soft2002/).
YUNSC 2002 - The 4th International Conference of Yugoslav Nuclear Society, Sept.30-Oct.3, 2002, Belgrade, Yugoslavia. Contact (tel ++381 11 454-796; fax ++381 11 444-74-57; email email@example.com. ac.yu, url www.vin.bg.ac.yu/YUNS).
8th Annual Workshop on Monte Carlo Simulation of Radiotherapy Treatment
Sources using the BEAM Code System, Sept. 30-Oct. 3, 2002, 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, e-mail firstname.lastname@example.org.
nrc.ca, url www.irs.inms.nrc.ca/inms/
2002 International Topical Meeting on Probabilistic Safety Assessment (PSA '02), Oct. 6-10, 2002, Detroit, MI. Contact: Rebecca Steinman (phone 734-930-7500, email email@example.com, url http://www-ners.engin.umich.edu/PSAConf/).
PHYSOR 2002, Oct. 7-10, 2002, Seoul, Korea, sponsored by the American Nuclear Society and hosted by the Korean Nuclear Society. Contact: Prof. Nam Zin Cho (tel +82-42-869-3819, fax +82-42-869-5859, email firstname.lastname@example.org, url http://physor2002.kaist.ac.kr).
First Asian and Oceanic Congress for Radiation Protection (AOCRP-1), Oct. 20-24, 2002, Seoul, Korea, sponsored by the Korean Association for Radiation Protection (KARP). Contact: Dr. Myung-Jae Song (tel +82-42-870-0202, fax +82-42-870-0269, email email@example.com, url www.aocrp-1.com).
The 48th Annual Radiobioassay and Radiochemical Measurements Conference, Nov. 11-15, 2002, Knoxville, Tennessee. Contact Tom Rucker (tel 865-481-2993, email firstname.lastname@example.org url http://www.bioassay.org/2002/.)
15th ANS Topical Meeting on the Technology of Fusion Energy, Nov. 17-21, 2002, Washington, DC. (url www.ans.org/).
International Symposium on Standards and Codes of Practice in Medical
Radiation Dosimetry, Nov. 25-28, 2002, IAEA, Vienna. Contact: Dr. Ken
R. Shortt (tel +43 1 2600 21664, fax +43 1 26007 21662, email
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 865-574-8069, email
or Bernadette Kirk (tel 865-574-6176, email email@example.com,
International Conference on Supercomputing in Nuclear Applications,
SNA 2003, Sept. 22-24, 2003, Paris, France. Organizers: CEA, SFANS,
co-organizer: OECD/NEA. (email SNAfirstname.lastname@example.org,
American Nuclear Society's Advances in Nuclear Fuel Management III
Topical Meeting, Oct. 5-8, 2003, Hilton Head Island, South Carolina.
Contact: Youssef A. Shatilla (email email@example.com,
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 firstname.lastname@example.org,,
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
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, 29, 2001-2017 . . . Optimization of MOX Enrichment Distributions in Typical LWR Assemblies Using a Simplex Method-Based Algorithm. . . . Cuevas Vivas, G.F.; Parish, T.A.; Curry, G.L. . . . November 2002 . . . Instituto de Investigaciones Electrias, Mor, Mexico; IAEA, Vienna, Austria; Texas A&M University, College Station, TX.
Ann. Nucl. Energy, 29, 2019-2027 . . . Cross-Section Measurements for the (n,p) and (n,) Reactions on 23Na and for the (n,p) Reaction on 26Mg at the Neutron Energies from 13.6 to 14.9 MeV. . . . Bostan, M.; Gultekin, E. . . . November 2002 . . . University of Istanbul, Turkey.
Ann. Nucl. Energy, 29, 2029-2040 . . . Pinhole Collimator Design for Nuclear Survey System. . . . Lee, W.; Cho, G. . . . November 2002 . . . Korea Advanced Institute of Science and Technology, Taejon, South Korea.
Ann. Nucl. Energy, 29, 2041-2053 . . . Characteristics of Hydriding and Hydrogen Embrittlement of the Ti-Al-Zr Alloy. . . . Kim, T-K. et al. . . . November 2002 . . . KAERI, Daejeon, South Korea.
Ann. Nucl. Energy, 29, 2055-2069 . . . Development of Severe Accident Management Advisor and Training Simulator (SAMAT). . . . Jeong, K-S.; Kim, K-R.; Jung, W-D.; Ha, J-J. . . . November 2002 . . . KAERI, Daejon, South Korea.
Ann. Nucl. Energy, 29, 2071-2085 . . . CHF Prediction in Nuclear Fuel Elements by Using Round Tube Data. . . . Fortini, M.A.; Veloso, M.A. . . . November 2002 . . . Universidade Federal de Minas Gerais, Belo Horizonte, Brazil; Cidade Universitária, Belo Horizonte, Brazil.
Ann. Nucl. Energy, 29, 2087-2103 . . . PWR System Simulation and Parameter Estimation with Neural Networks. . . . Akkurt, H.; Colak, U. . . . November 2002 . . . Hacettepe University, Ankara, Turkey.
Ann. Nucl. Energy, 29, 2105-2125 . . . ANEMONA: Multiassembly Neutron Transport Modeling. . . . Jevremovic, T.; Ito, T.; Inaba, Y. . . . November 2002 . . . Nuclear Fuel Industries, Ltd., Ibaraki-ken, Japan; Purdue University, West Lafayette, IN.
Ann. Nucl. Energy, 29, 2127-2141 . . . Temporal Adaptive Algorithm for TRAC-BF1/NEM/COBRA-TF Coupled Calculations in BWR Safety Analysis. . . .Slois, J.; Avramova, M.N.; Ivanov, K.N. . . . December 2002 . . . Pennsylvania State University, University Park, PA.
Ann. Nucl. Energy, 29, 2143-2158 . . . Multi-Group Theory of Neutron Noise Induced By Vibrating Boundaries. . . .Arzhanov, V. . . December 2002. . . Chalmers University of Technology, Göteborg, Sweden; Keldysh Institute of Applied Mathematics, Moscow, Russia.
Ann. Nucl. Energy, 29, 2159-2172 . . . PWS: An Efficient Code System for Solving Space-Independent Nuclear Reactor Dynamics. . . Aboanber, A.E.; Hamada, Y.M. . .December 2002 . . . Tanta University, Egypt.
Ann. Nucl. Energy, 29, 2173-2186 . . . Burn-Up Characteristics of ADS System Utilizing the Fuel Composition From MOX PWRs Spent Fuel. . . Marsodi, A.S. et al. . . December 2002. . .National Nuclear Energy Agency of Indonesia, Puspiptek-Serpong, Indonesia; JAERI, Tokai-Mura, Japan; Bandung Institute of Technology, Indonesia.
Ann. Nucl. Energy, 29, 2187-2209 . . .Temperature Distribution in Mixed ThO2-UO2 Fuel Rods Located in Blanket of an Inertial Fusion Energy Breeder. . . Yapici, H. . . December 2002. . . Erciyes Üniversitesi, Kayseri, Turkey.
Ann. Nucl. Energy, 29, 2211-2224 . . .Neutron Streaming in a Cylindrical Annulus: A Review of Theory and Comparison of Methods. . . Williams, M.M.R.; Cassell, J.S. . . .December 2002 . . . London Guildhall University, London, UK.
Ann. Nucl. Energy, 29, 2225-2234 . . . Analysis of Reactivity Induced Accidents at Pakistan Research Reactor-1. . . Bokhari, I.H.; Israr, M.; Pervez, S. . . .December 2002. . . Pakistan Institute of Nuclear Science and Technology, Islamabad, Pakistan.
Ann. Nucl. Energy, 29, 2235-2242 . . . First Experience with a Six-Loop Nodalization of a VVER-440 Using an New Coupled Neutronic-Thermohydraulics System KIKO3D-RETINA V1.1D. . . Farkas, I. et al. . . December 2002. . . KFKI Atomic Energy Research Institute, Budapest, Hungary.
Fus. Eng. Design, 60, 497-514 . . . Edge-Plasma Models and Characteristics for Magnetic Fusion Energy Devices. . . . Rognlien, T.D.; Rensink, M.E. . . . July 2002 . . . Lawrence Livermore National Laboratory, Livermore, CA.
Fus. Eng. Design, 60, 515-526 . . . Modeling of Sputtering Erosion/Redeposition - Status and Implications for Fusion Design. . . . Brooks, J.N. . . . July 2002 . . . Argonne National Laboratory, Argonne, IL.
Fus. Eng. Design, 60, 527-546 . . . Prediction of Material Erosion and Lifetime During Major Plasma Instabilities in Tokamak Devices. . . . Hassanein, A. . . . July 2002 . . . Argonne National Laboratory, Argonne, IL.
Fus. Eng. Design, 60, 547-564 . . . Actively Cooled Plasma Facing Components for Long Pulse High Power Operation. . . . Nygren, R.E. . . . July 2002 . . . Sandia National Laboratories, Albuquerque, NM.
IAEA-TECDOC-1285 . . . Reference Neutron Activation Library. . . April 2002 . . . IAEA Vienna, Austria.
IEEE Plasma Sci., 30, 227-238 . . . Z Pinch Imploding Plasma Density Profile Measurements Using a Two-Frame Laser Shearing Interferometer. . . . Qi, N. et al. . . . February 2002 . . . Alameda Applied Sciences Corp., San Leandro, CA; Naval Research Laboratory, Washington, DC; Defense Threat Reduction Agency, Fort Belvoir, VA.
IEEE Plasma Sci., 30, 286-292 . . . Nanosecond Pulsed Electric Field (nsPEF) Effects on Cells and Tissues: Apoptosis Induction and Tumor Growth Inhibition. . . . Beebe, S.J. et al. . . . February 2002 . . . Eastern Virginia Medical School, Norfolk, VA; Old Dominion University, Norfolk, VA.
IEEE Plasma Sci., 30, 318-326 . . . Numerical Modeling of Plasma Sheath Phenomena in the Presence of Secondary Electron Emission. . . . Jolivet, L.; Roussel, J-F. . . . February 2002 . . . French National Aerospace Research Establishment, Toulouse, France.
IEEE Plasma Sci., 30, 338-351 . . . Experimental Evaluation of a Megavolt Rod-Pinch Diode as a Radiography Source. . . . Commisso, R.J. et al. . . . February 2002 . . . Naval Research Laboratory, Washington, DC; JAYCOR, McLean, VA.
IEEE Plasma Sci., 30, 363-374 . . . Plasma Development in the Low-Pressure Channel Spark for Pulsed Intense Electron Beam Generation. . . . Dewald, E.; Frank, K.; Hoffmann, D.H.H.; Tauschwitz, A. . . . February 2002 . . . GSI Darnstadt, Germany; University of Erlangen-Nuremberg, Erlangen, Germany; Technical University Darnstadt, Germany.
ISSN 1344-1299 . . . Annual Report 2000, April 2000-March 2001, High Energy Accelerator Research Organization. . . . 2001. . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
ISSN 1423-7334 . . . PSI Scientific Report 2001/Volume IV, Nuclear Energy and Safety. . . . Smith, B. ed. . . . March 2002 . . . Paul Scherrer Institut, Villigen, Switzerland.
J. Nucl. Mater., 303, 1-28 . . . Progress in the Thermodynamic Modelling of the O-U Binary System. . . . Chevalier, P.-Y.; Fischer, E.; Cheynet, B. . . . May 2002 . . . Thermodata, Saint Martin d'Hères, France.
J. Nucl. Mater., 303, 29-33 . . . Homogeneity Characterisation of Sintered (U,Gd)O2 Pellets by X-Ray Diffraction. . . . Leyva, A.G.; Vega, D.; Trimarco, V.; Marchi, D. . . . May 2002 . . . Comisión Nacional de Energía Atómica, Buenos Aires, Argentina.
J. Nucl. Mater., 303, 34-43 . . . Temperature Effects on the Mechanical Properties of Candidate SNS Target Container Materials After Proton and Neutron Irradiation. . . . Byun, T.S. et al. . . . May 2002 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Los Alamos National Laboratory, Los Alamos, NM; General Atomics, San Diego, CA.
J. Nucl. Mater., 303, 44-51 . . . Effects of Fast Neutron and Gamma Irradiation on Electrical Conductivity of Some Borate Glasses. . . . Elalaily, N.A.; Mahamed, R.M. . . . May 2002 . . . National Center for Radiation Research and Technology, Cairo, Egypt.
J. Nucl. Mater., 303, 52-64 . . . TEM and PAS Study of Neutron Irradiated VVER-Type RPV Steels. . . . Koík, J.; Keilová, E.; Cíek, J.; Procházka, I. . . . May 2002 . . . Nuclear Research Institute e plc., Prague, Czech Republic; Charles University, Prague, Czech Republic.
J. Nucl. Mater., 303, 65-72 . . . Thermodynamic Properties of Hyperstoichiometric Urania in the UO2-UO2.25 Solid Solution Range. . . . Kurepin, V.A. . . . May 2002 . . . National Academy of Science, Kiev, Ukraine.
J. Nucl. Mater., 303, 73-81 . . . Corrosion Resistance of Structural Materials to Ga2O at 1000C . . . Sullivan, T.O. et al. . . . May 2002 . . . University of Texas at Austin, TX; Los Alamos National Laboratory, Los Alamos, NM.
KEK Progress Report 2001 . . . Photon Factory Activity Report 2000: Part A: Highlight and Facility Report #18. . . . . . . October 2001 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
KEK Report 2001-5 . . . A New Working Point for the KEKB. . . . Wu, Y.Z.; Funakoshi, Y.; Tawada, M.; Ohmi, K. . . . May 2001 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
KEK Report 2001-6 . . . On the Acceleration in a High- Structure. . . . Kato, T. . . . June 2001 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
KEK Report 2001-14 . . . The Annular Coupled Structure Optimization for JAERI/KEK Joint Project for High Intensity Proton Accelerators. . . . Paramonov, V.V. . . . October 2001 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
KEK Report 2001-20 . . . Feasibility of Laser Stripping via a Broad Stark State for Charge-Exchange Injection into a High-Intensity Proton Ring. . . . Yamane, I. . . . February 2002 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
KEK Report 2001-24 . . . Experimental Data of Deep-Penetration Neutrons Through a Concrete and Iron Shield at the ISIS Spallation Neutron Source Facility Using an 800-MeV Proton Beam. . . . Nunomiya, T. et al. . . . February 2002 . . . High Energy Accelerator Research Organization, Ibaraki-ken, Japan.
Nucl. Eng. Design, 214, 173-182 . . . Prestressed Concrete Containment of Nuclear Power Station with PWR. . . . Freidin, C.; Krichevsky, A. . . . June 2002 . . . Ben-Gurion University of the Negev, Israel.
Nucl. Eng. Design, 214, 183-193 . . . An Analysis of Stress Waves in 12Cr Steel, Stellite 6B and TiN by Liquid Impact Loading. . . . Lee, M-K. et al. . . . June 2002 . . . KAERI, Taejon, South Korea; Korea Advanced Institute of Science and Technology, Taejon, South Korea.
Nucl. Eng. Design, 214, 195-204 . . . Distribution Mixtures from Sampling of Inhomogeneous Microstructures: Variance and Probability Bounds of the Properties. . . . Todinov, M.T. . . . June 2002 . . . Cranfield University, Bedford, UK.
Nucl. Eng. Design, 214, 205-220 . . . Intergranular Stress Corrosion Cracking Behavior of Niobium-Added Type 308 Stainless Steel Weld Overlay Metal in a Simulated BWR Environment. . . . Hamada, I.; Yamauchi, K. . . . June 2002 . . . Babcock-Hitachi, Tokyo and Hiroshima-Ken, Japan.
Nucl. Eng. Design, 214, 221-229 . . . Crack Opening Behavior of Penetrated Crack Under Cyclic or Monotonic Loading. . . . Nam, K-W.; Ahn, S-H.; Yoo, Y-S.; Ando, K. . . . June 2002 . . . Pukyong National University, Pusan, South Korea; Yokohama National University, Japan.
Nucl. Eng. Design, 216, 1-11 . . . Measurement of Thermal Conductivity of Buffer Materials and Evaluation of Existing Correlations Predicting It. . . . Ould-Lahoucine, C.; Sakashita, H.; Kumada, T. . . . July 2002 . . . Hokkaido University, Sapporo, Japan.
Nucl. Eng. Design, 216, 13-26 . . . Experimental Study on Uniaxial and Nonproportionally Multiaxial Ratcheting of SS304 Stainless Steel at Room and High Temperatures. . . . Kang, G.; Gao, Q.; Cai, L.; Sun, Y. . . . July 2002 . . . Southwest Jiaotong University, Chengdu, People's Republic of China.
Nucl. Eng. Design, 216, 27-42 . . . A Modified Beremin Model to Simulate the Warm Pre-Stress Effect. . . . Lefevre, W.; Barbier, G.; Masson, R.; Rousselier, G. . . . July 2002 . . . Electricité de France, Moret-sur-Loing, France; Universität Stuttgart, Germany.
Nucl. Eng. Design, 216, 43-67 . . . The AMSTER Concept (Actinides Molten Salt TransmutER). . . . Vergnes, J.; Lecarpentier, D. . . . July 2002 . . . Electricité de France, Clamart, France.
Nucl. Eng. Design, 216, 69-75 . . . Study on Step-Up Characteristic of Hydraulic Control Rod Driving System. . . . Bo Hanliang et al. . . . July 2002 . . . Tsinghua University, China.
Nucl. Eng. Design, 216, 77-87 . . . An Integrated RELAP5-3D and Multiphase CFD Code System Utilizing a Semi-Implicit Coupling Technique. . . . Aumiller, D.L.; Tomlinson, E.T.; Weaver, W.L. . . . July 2002 . . . Bettis Atomic Power Laboratory, West Mifflin, PA; Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.
Nucl. Eng. Design, 216, 89-97 . . . RALOC4 Code Validation Against Measured Data at Ignalina NPP During Single Main Safety Valve Opening. . . . Urbonavicius, E.; Rimkevicius, S. . . .July 2002 . . . Lithuanian Energy Institute, Kaunas, Lithuania.
Nucl. Eng. Design, 216, 99-111 . . . Simulation of Ignalina NPP Accident Localisation System Behaviour Employing the RALOC4 Code in the Case of Group Distribution Header Rupture. . . . Rimkevicius, S.; Urbonavicius, E.; Cesna, B. . . . July 2002 . . . Lithuanian Energy Institute, Kaunas, Lithuania.
Nucl. Eng. Design, 216, 113-119 . . . A Metastable Wet Steam Turbine Stage Model. . . . Bassel, W.S.; Gomes, A.V. . . . July 2002 . . . Cidade Universitaria, São Paulo, Brazil.
Nucl. Eng. Design, 216, 121-137 . . . Relationship Between the Structure of Vapor Explosion and Fragmentation Mechanisms. . . . Liu, J.; Koshizuka, S.; Oka, Y. . . . July 2002 . . . University of Tokyo, Ibaraki-ken, Japan.
Nucl. Eng. Design, 216, 139-152 . . . Improvement of the Subcooled Boiling Model for Low-Pressure Conditions in Thermal-Hydraulic Codes. . . . Hari, S.; Hassan, Y.A. . . . July 2002 . . . Texas A&M University, College Station, TX.
Nucl. Eng. Design, 216, 153-164 . . . Model and Simulation of Gaseous Helium-3 Exchanges with the Atmosphere from a Tritiated Waste Drum. . . . Ravat, B.; Demange, D.; Pialot, H. Grivet, M. . . . July 2002 . . . CEA/DAM Valduc, Is sur Tille, France; Laboratoire de Microanalyses Nucleaires, Besancon, France.
Nucl. Eng. Design, 216, 165-181 . . . Modeling of Three-Dimensional Steady State Non-Linear Heat Transfer in CANDU Nuclear Fuel. . . . Yu, S.D.; Xu, S. . . . July 2002 . . . Ryerson University, Ontario, Canada.
Nucl. Eng. Design, 216, 183-201 . . . Mono-Dimensional Mechanical Modelling of Fuel Rods Under Normal and Off-Normal Operating Conditions. . . . Garcia, Ph.; Struzik, C.; Agard, M.; Louche, V. . . . July 2002 . . . Commissariat à l'Énergie Atomique, Saint-Paul-Lez-Durance, France.
Nucl. Eng. Design, 216, 203-211 . . . A Theoretical Procedure for Detection of Simulated Cracks in a Pipe by the Direct Current - Potential Drop Technique. . . . Chen, W-H.; Chen, J-S.; Fang, H-L. . . . July 2002 . . . National Tsinghua University, Taiwan, ROC.
Nucl. Eng. Design, 216, 213-220 . . . Strength Monitoring of a Prestressed Concrete Containment with Grouted Tendons. . . . Zaozhan Sun et al. . . . July 2002 . . . Nuclear Safety Center, Beijing, China; Engineering Structure Laboratory, Beijing, China.
Nucl. Eng. Design, 216, 221-238 . . . Numerical Evaluation and Correction Method for Multi-Sensor Probe Measurement Techniques in Two-Phase Bubbly Flow. . . . Le Corre, J-M.; Ishii, M. . . . July 2002 . . . Purdue University, West Lafayette, IN.
Nucl. Eng. Design, 216, 239-245. . .On the Round Table Discussion on Reactor Power Margins Published in Nuclear Engineering and Design 163 (1-2). . . . Olekhnovitch, A.; Teyssedou, A.; Tye, P. . . 2002. . . Ecole Polytechnique, Montreal, Quebec, Canada; BMA Inc., Montreal, Quebec, Canada.
Nucl. Technol., 137, 73-83 . . . High Local Power Densities Permissible at Siemens Pressurized Water Reactors. . . . Kuehnel, K.; Richter, K-D.; Drescher, G.; Endrizzi, I. . . . February 2002 . . . Siemens Nuclear Power, Erlangen, Germany.
Nucl. Technol., 137, 84-96 . . . Fast Burner Reactor Devoted to Minor Actinide Incineration. . . . Messaoudi, N.; Tommasi, J. . . . February 2002 . . . Commissariat á l'Energie Atomique, St. Paul-lez-Durance, France.
Nucl. Technol., 137, 97-110 . . . Reactivity, Isotopic, and Thermal Steady-State Analysis of Homogeneous Thoria-Urania Fuel. . . . Loewen, E.P.; Weaver, K.D.; Hohorst, J.K. . . . February 2002 . . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID.
Nucl. Technol., 137, 111-126 . . . Nuclide Composition Benchmark Data Set for Verifying Burnup Codes on Spent Light Water Reactor Fuels. . . . Nakahara, Y. et al. . . . February 2002 . . . JAERI, Naka-gun, Japan.
Nucl. Technol., 137, 139-146 . . . Removal of Metal-Oxide Layers Formed on Stainless and Carbon Steel Surfaces by Excimer Laser Irradiation in Various Atmospheres. . . . Kameo, Y.; Nakashima, M.; Hirabayashi, T. . . . February 2002 . . . JAERI, Ibaraki-ken, Japan.
Nucl. Technol., 137, 147-162 . . . An Optimization Scheme for High-Level-Waste Removal Sequencing Using ProdMod. . . . Paul, P.K.; Gregory, M.V.; Aldemir, T. . . . February 2002 . . . Westinghouse Savannah River Co., Aiken, SC; Ohio State University, Columbus, OH.
Nucl. Technol., 138, 1-16 . . . Radioactive Fission Product Release from Defective Light Water Reactor Fuel Elements. . . . Konyashov, V.V.; Krasnov, A.M. . . . April 2002 . . . State Scientific Centre of Russian Federation, Ulyanovsk Region, Russia.
Nucl. Technol., 138, 17-29 . . . Thorium Fuel Performance in a Tight-Pitch Light Water Reactor Lattice. . . . Kim, T.K.; Downar, T.J. . . . April 2002 . . . Purdue University, West Lafayette, IN.
Nucl. Technol., 138, 30-43 . . . Heavy-Metal Aerosol Transport in a Lead-Bismuth-Cooled Fast Reactor with In-Vessel Direct-Contact Steam Generation. . . . Buongiorno, J.; Todreas, N.E.; Kazimi, M.S. . . . April 2002 . . . Idaho National Engineering & Environmental Laboratory, Idaho Falls, ID.; Massachusetts Institute of Technology, Cambridge, MA.
Nucl. Technol., 138, 58-68 . . . Incorporating Plutonium Particle Size Effects in the Assessment of Active Mode Measurement Uncertainty in Passive-Active Neutron Radioassay Systems. . . . Blackwood, L.G.; Harker, Y.D. . . . April 2002 . . . Idaho National Engineering & Environmental Laboratory, Idaho Falls, ID.
Nucl. Technol., 138, 69-78 . . . The Effect of Hydrogen on Oxidative Dissolution of Spent Fuel. . . . Liu, L.; Neretnieks, I. . . . April 2002 . . . Royal Institute of Technology, Stockholm, Sweden.
Nucl. Technol., 138, 79-89 . . . Analysis of External Cooling of the Reactor Vessel During Severe Accidents. . . . Song, J.H.; Kim, S.B.; Kim, H.D. . . . April 2002 . . . Korea Atomic Energy Research Institute, Taejon, Korea.
Nucl. Technol., 138, 90-92 . . . An Estimate of the Crust Thickness on the Surface of a Thermally Convecting Liquid-Metal Pool. . . . Gubaidullin, A.A.; Sehgal, B.R. . . . April 2002 . . . Royal Institute of Technology, Stockholm, Sweden.
Prog. Nucl. Energy, 40, 161-206 . . . DECOBI: Investigation of Melt Coolability with Bottom Coolant Injection. . . . Paladino, D.; Theerthan, S.A.; Sehgal, B.R. . . . 2002 . . . Royal Institute of Technology, Stockholm, Sweden.
Prog. Nucl. Energy, 40, 207-215 . . . Measurement of the Syrian Miniature Neutron Source Core Average Temperature by Means of Reactivity. . . . Khamis, I. . . . 2002 . . . Atomic Energy Commission, Damascus, Syria.
Prog. Nucl. Energy, 40, 217-236 . . . Neutron Noise Theory in the P1 Approximation. . . . Pázsit, I. . . . 2002 . . . Chalmers University of Technology, Göteborg, Sweden.
Prog. Nucl. Energy, 40, 237-264 . . . Simplified PN and AN Methods in Neutron Transport. . . . Ciolini, R.; Coppa, G.G.M.; Montagnini, B.; Ravetto, P. . . . 2002 . . . Università degli Studi di Pisa, Italy; Politecnico di Torino, Italy.