In today's world, software licenses and export control regulations are integral parts of software distribution. Adherence to both is the shared responsibility of RSICC and its user community.
Our users should be aware of a major change in the software licensing of RSICC code and data packages. In mid-April 2003, the former site license each requester submitted to receive RSICC software was replaced by a new single user license.
The previous site license restricted use of RSICC software to the site to which it was sent. The software could not leave that physical location and could not be placed on a network accessible by off-site users. Use of the software could be shared with colleagues located at that same site, and any software received under that site license continues to be governed by those terms.
Requests submitted for RSICC code and data packages since mid-April 2003 now include a single user license. RSICC software is currently restricted to use by the recipient only. It can no longer be shared with others either on or off site. With the change to the new individual license, any software received through RSICC is now solely for use by the licensee.
The new license allows software to be installed and run on a shared network under the following condition: Each user of the RSICC software package on the network must first submit his own RSICC registration form, request form, license form, and export control understanding and agreement form. On receipt of his own licensed copy of the software from RSICC, the network user can then be given network access to that particular code or data package.
If you have particular questions related to the new license, feel free to contact us. Our staff will do its best to clarify issues as they arise both through our monthly newsletter and our web site. A new FAQ's for the RSICC License will be instituted on our web site home page at http://www-rsicc.ornl.gov/rsicc.html.
Thank you for your considerable efforts to help RSICC continue to be the leader in nuclear system safety, design, and research.
Hamilton T. Hunter, Director of RSICC, June, 2003
William F. Naughton, general manager of research and development for Exelon Generation Company, was honored on April 14 as an Outstanding Engineering Alumnus by Penn State University. This is the highest honor conferred by Penn States' College of Engineering: Only 231 men and women - out of 75,000 alumni worldwide - have received the award during the 37-year history. He received his master's and Ph.D degrees in nuclear engineering from Penn State. An ANS member since 1973, Naughton is the newly elected ANS treasurer for 2003-05.
E. Gail de Planque, Fellow and past president (1988-89) of ANS
and renowned nuclear technology expert, is the 2003 recipient of the Henry
DeWolf Smyth Nuclear Statesman Award. This is awarded jointly by ANS and
the Nuclear Energy Institute to recognize outstanding contributions to
the development of peaceful uses of nuclear energy. The Smyth award was
established in 1972 in honor of Henry DeWolf Smyth, chairman of Princeton
University's physics department.
Octave J. Du Temple, executive director emeritus of the American
Nuclear Society, received Michigan Technological University's highest honor,
the Melvin Calvin Medal of Distinction, which is given to individuals affiliated
with the university who have exhibited truly distinguished professional
and personal accomplishments. Du Temple received his bachelor's and master's
degrees in chemical engineering from Michigan Tech, and went on to earn
a master's degree in business administration from Northwestern University
in 1955. He joined ANS in July 1958 as the Society's first full-time executive
director, a position he held for 32 years. The ANS headquarters building,
in La Grange Park, Illinois was dedicated to Du Temple in 1992.
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.
One new package was added to the computer code collection this month.
The Chinese Institute of Atomic Energy, Beijing, People's Republic of China, contributed this code system to calculate multistep compound nucleus neutron cross-sections and spectra for structural materials. The UNF code (2003 version) calculates fast neutron reaction data of structure materials with incident energies from about 1 keV up to 20 MeV. It consists of the spherical optical model, the unified Hauser-Feshbach and exciton model. The angular momentum dependent exciton model is established to describe the emissions from compound nucleus to the discrete levels of the residual nuclei in pre-equilibrium processes, while the equilibrium processes are described by the Hauser-Feshbach model with width fluctuation correction. The emissions to the discrete level in the multi-particle emissions for all opened channels are included. The double-differential cross sections of neutrons and protons are calculated by the linear momentum dependent exciton state density. Since the improved pickup mechanism has been employed based on the Iwamoto-Harada model, the double-differential cross sections of alpha-particle, 3He, deuteron and triton can be calculated by using a new method based on the Fermi gas model. The recoil effects in multi-particle emissions from continuum state to discrete level as well as from continuum to continuum state are strictly taken into account, so the energy balance is held accurately in every reaction channel. If the calculated direct inelastic scattering data and the calculated direct reaction data of the outgoing charged particles are available from other codes, one can input them so that the calculated results will include the effects of the direct reaction processes. To keep the energy balance, the recoil effects are taken into account for all of the reaction processes. The gamma-production data are also calculated. The calculated neutron reaction data can be output in ENDF/B-6 format.
UNF is written in Fortran 90. An executable created on a Pentium IV
1400 MHZ under Windows 2000 with the Compaq Visual Fortran Version 6.6a
compiler is included. The package is transmitted on a CD which includes
documentation, the Fortran source, PC executable, and test case input and
output in a self-extracting compressed Windows file. Reference: CNDC-0032
(December 2001). Fortran 90; Pentium (P00521PC58600).
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 'Subject 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. This month's code focus is Thermodynamics and Fluid Dynamics.
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.
American Nuclear Society's Advances in Nuclear Fuel Management III Topical
Meeting will be held in Hilton Head Island, South Carolina, October
5-8, 2003. 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.
This workshop will be held at McGill University, Montreal, Canada, from May 3-5, 2004, and aims to bring together medical physicists and researchers to discuss development, clinical implementation and clinical evaluation of Monte Carlo treatment planning techniques in radiotherapy. The meeting will have both invited speakers and proffered contributions and is designed to have plenty of opportunity for informal and in-depth discussions.
For details regarding registration, program, invited speakers, abstract
submission, etc, please consult our workshop website: http://mctp.medphys.mcgill.ca.
Early registration is encouraged as the number of participants will be
limited to around 100.
The Tenth International Conference on Radiation Shielding (ICRS-10) and the Thirteenth Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society (RPS 2004) will be held May 9-14, 2004.
The Local Organization has been assigned to ITN (the Nuclear and Technological Institute, in Lisbon), a laboratory of the Portuguese Ministry of Science and Higher Education. At the international level, the joint organization is co-sponsored by the Nuclear Energy Agency (NEA) of the Organization for Economic Co-operation and Development (OECD), the Radiation Protection and Shielding Division (RPSD) of the American Nuclear Society (ANS), and the Radiation Safety Information Computational Center (RSICC, Oak Ridge National Laboratory).
It is anticipated that this will be the most important event in the areas of Radiation Shielding and Radiation Protection during 2004. For further information please refer to the Conferences' Web pages at the following URL http://www.itn.mces.pt/ICRS-RPS. Please don´t hesitate to contact the Conference Secretariat at email@example.com.
In addition, if you would be interested in serving on the Scientific
Program Committee, and contribute to the success of the meeting by either
submitting or encouraging colleagues to submit papers, and participating
in the technical review process, please contact the Conference Secratariat
at the above email and provide your name, organization, email and topics
of interest or expertise. The Organizing Committee welcomes your comments
and suggestions to make your meeting a success.
The 6th International Symposium on ESR Dosimetry and Applications will
be held October 12-16, 2003, in Campos do Jordão, Brazil.
For complete information, please see http://www.if.usp.br/
VI_ESR_2003/ and click on "second announcement (PDF version)" on the
left side of the screen.
The 7th International Conference on Nuclear Criticality Safety (ICNC2003)
will be held October 20-24, 2003, in Tokai-mura, Japan. This conference
has been held approximately every 4 years under the support of OECD/Nuclear
Energy Agency/Nuclear Science Committee. The last conference, hosted by
Japan, was the 3rd conference held in Tokyo in 1987. In the Versailles
conference held in 1999, over 300 people from 25 countries participated,
and more than 200 presentations were given on the recent activities in
research work, industrial applications, regulatory studies, and other topics
related to criticality safety. ICNC2003 will provide a good opportunity
for communication among researchers, engineers, plant operators, and regulators.
The Conference will consist of invited talks, contributed talks, and poster
sessions. On the final day of the conference, technical tours to nuclear
facilities are scheduled, and social programs are planned during conference.
Please see the website for more information: http://www.icnc.jp/.
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 are 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 the knowledge and skills necessary to create
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 professions, 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 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 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 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 class will be based on MCNP5 and will cover the new capabilities of version 5. Attendees may elect to receive the new package. If you have previously received an older registered version of MCNP from RSICC, you may request that the MCNP5 package be sent to you at no charge. If you have not received an older version of MCNP from RSICC, you will be charged the applicable transmittal fee.
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 class 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,
The class is scheduled September 8-12, 2003, 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 firstname.lastname@example.org).
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.
More information on code versions and capabilities is available at MCNPX
Workshops web site http://mcnpxworkshops
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 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.
Those who are interested in participating in the workshop are invited
to register (no fee) before August 1, 2003, using the workshop website
There is also information on workshop topics, accommodations, transportation,
and key dates. Please contact Aleksandra Kelic, A.Kelic@gsi.de
if you have questions.
The Chicago Section of the American Nuclear Society is pleased to announce that it will host the PHYSOR-2004 Topical Meeting, April 25-29, 2004, in Chicago, IL. The meeting is co-sponsored by the Reactor Physics Division of the ANS and the OECD Nuclear Energy Agency. The conference will be held at the Hyatt Regency in downtown Chicago.
The title for the meeting is "The Physics of Fuel Cycles and Advanced
Nuclear Systems: Global Developments." The technical program will cover
more than 15 topical focus areas; the deadline for submission of 1000-word
summaries is September 5, 2003. You are invited to visit the meeting website
to obtain updated information and to download a copy of the meeting announcement.
Contact: Ray Klann, Technical Program Co-Chair, at 630-252-4305 or email@example.com.
The SCALE KENO V.a Criticality Course, Nov. 3-7, 2003, will focus on KENO V.a and the associated criticality analysis sequences in CSAS. KENO V.a is a widely used 3-D multigroup Monte Carlo criticality safety code that has been in use for more that 15 years. KENO V.a is a fast, easy-to-use code that allows users to build complex geometry models using basic geometrical bodies of cuboids, spheres, cylinders, hemispheres, and hemicylinders. Two-dimensional color plots of the geometry model can be generated in KENO V.a or the model may be viewed using the KENO3D 3D visualization tool.
The SCALE Shielding and Source Terms Course covers SAS2 and ORIGEN-ARP
(depletion/source-term generation), SAS1/XSDRNPM (1-D neutron/gamma shielding),
SAS4/MORSE-SGC (3-D Monte Carlo neutron/gamma shielding), and QADS/QAD-CGGP
(3-D point kernel gamma shielding). The course will be Nov. 10-14, 2003,
and will feature the use of the SCALE Windows GUIs: OrigenArp for Windows,
ORIGEN-S plotting utility PlotOPUS, and the ESPN shielding input processor
for SAS4. For further information, visit http://www.ornl.gov/scale/trcourse.html#href1
or contact Kay Lichtenwalter, firstname.lastname@example.org,
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-38), August 11-15, 2003. One course is on the Monte Carlo method and the other course is on Nuclear Criticality Safety.
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 for 5 days.
Engineers, scientists, and technical managers who wish to increase their knowledge and understanding of nuclear criticality safety will be interested in the criticality safety course, which also runs for five days. The topics covered in the course are based primarily on the experience of the five instructors which totals over 120 years of nuclear criticality safety related experience. Such a wealth of experience needs to be shared with the criticality safety community including both new professionals in the field as well as experienced professionals.
For additional information on these two and other courses offered during
TIW-38, contact Kristin England at the University of Tennessee, phone (865)
974-5048, email email@example.com,
The conference on "Supercomputing in Nuclear Applications" SNA-2003, will be held in Paris, September 22-24, 2003. 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.
PENELOPE Training Course, July 7-10, 2003, OECD/NEA Headquarters, France. Please see http://www.nea.fr/lists/penelope.html for official announcement.
Intercomparison on the Usage of Computational Codes in Radiation Dosimetry, July 14-16, 2003, Bologna, Italy. Contact: Gianfranco Gualdrini (tel 39-051-6098350, fax 39-051-6098003, email guald@bologna. enea.it, url http://www.nea.fr/ download/quados/quados.html).
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).
Short Courses on Monte Carlo Analysis and Nuclear Criticality Safety, Aug. 11-15, 2003, Knoxville, TN. Contact: Kristin England (phone 865-974-5048, email: firstname.lastname@example.org, url www.engr.utk.edu/nuclear/TIW.html).
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/).
MCNP5 Introductory Training Course, Sept. 15-19, 2003, Issy-les-Moulineaux, France. Organized by OECD/NEA and RSICC. Contact: Enrico Sartori (fax 33-1-45241110, email email@example.com, url http://www.nea.fr/html/dbprog/mcnpcourses2003-2.html).
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).
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 firstname.lastname@example.org, url http://rpd.ans.org/nfm.htm).
7th International Conference on Nuclear Criticality Safety (ICNC2003), Oct. 20-24, 2003, Contact: Dr. Yoshinori Miyoshi (tel +81-29-282-6671; fax +81-29-282-6798, email email@example.com. jaeri.go.jp, url http://www.icnc.jp/).
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).
SCALE KENO V.a Criticality Safety Course, Nov. 3-7, 2003, Oak Ridge National Laboratory. Contact: Kay Lichtenwalter (tel 865-574-9213, email firstname.lastname@example.org, url http://www.ornl.gov/scale/trcourse.html#href1).
SCALE Source Terms & Shielding Course, Nov. 10-14, 2003, Oak Ridge National Laboratory. Contact: Kay Lichtenwalter (tel 865-574-9213, email email@example.com, url http://www.ornl.gov/scale/trcourse.html#href1).
ANS/ENS International Winter Meeting and Nuclear Technology Expo, Nov. 16-20, 2003, New Orleans, LA. Contact: (url http://www.ans.org/meetings/).
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, url http://icfrm.iae.kyoto-u.ac.jp).
PHYSOR 2004 Reactor Physics Topical Meeting, Apr. 25-29, 2004, Chicago, IL. Jointly sponsored by the Reactor Physics Division of the ANS and the Nuclear Energy Agency of the OECD. Contact: Ray Klann (tel 630-252-4305, email email@example.com, url www.td.anl.gov/PHYSOR2004).
Current Topics in Monte Carlo Treatment Planning, May 3-5, 2004, McGill University, Montreal, Canada. Contacts: Jan Seutjens and Frank Verhaegen (tel 514-934-8052, url http://mctp.medphys.mcgill.ca).
International Conference on Radiation Shielding (ICRS-10) and Topical
Mtg. on Radiation Protection & Shielding (RPS 2004), May 9-14,
2004, Funchal, Madeira Island (Portugal). Contact: Conference Secretariat
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, 953-981. . . Model-Free Fuzzy Tracking Control of a Nuclear Reactor. . . .Marseguerra, M. et al.. . . . June 2003. . Politecn. Milan, Italy.
Ann. Nucl. Energy, 30, 983-1000. . . Sensitivities of the Proton Beam Current Resulting from Variations in the Source Term for a Pb-Bi Cooled Accelerator Driven System with a PB-Bi Target. . . .Pelloni, S. . . . June 2003. . . Paul Scherrer Inst., Villigen, Switzerland.
Ann. Nucl. Energy, 30, 1001-1007. . . Measurements and Statistical Model Calculations of Activation Cross Sections for F-19(n,p)O-19 Reaction Between 13.6 and 14.9 MeV Neutron Energies.. . .Reyhancan, I.A. . . . June 2003. . . Cekmece Nucl. Res. & Training, Center, Istanbul, Turkey.
Ann. Nucl. Energy, 30, 1009-1031. . . An Integral Equation Arising in Neutron Transport Theory. . . .Cassell, J.S. et al. . . . June 2003. . . London Metropolitan Univ., London, England.
Ann. Nucl. Energy, 30, 1033-1063. . . Simulation of Creep Tests with French or German RPV-Steel and Investigation of a RPV-Support Against Failure. . . .Willschutz, H.G. et al.. . . July 2003. . . Forschungszentrum Rossendorf EV, Dresden, Germany; Royal Inst. Technol., Stockholm, Sweden.
Ann. Nucl. Energy, 30, 1065-1074. . . Neutronic Optimization of PHWR Fuel. . . .Notari, C. . . . July 2003. . . Atomic Energy Commission Argentina, Buenos Aires, Argentina.
Ann. Nucl. Energy, 30, 1075-1088. . . Some Futher Considerations on Goertzel's Minimum Critical Mass Problem. . . .Williams. M.M.R . . . July 2003.
Ann. Nucl. Energy, 30, 1089-1106. . . A Monte Carlo Based Nodal Diffusion Model for Criticality Analysis of Spent Fuel Storage Lattices. . Ilas, G. et al. . . . July 2003. . . Georgia Inst. Technology, Atlanta, GA.
Ann. Nucl. Energy, 30, 1109-1110. . . The 2Z-N Correlation Related to the Total Delayed Neutron Yield of Am-243. . . .Ronen, Y. . . . July 2003. . . Ben Gurion Univ. Negev, Beer Sheva, Israel.
Ann. Nucl. Energy, 30, 1111-1122. . . Power Series Solution (PWS) of Nuclear Reactor Dynamics with Newtonian Temperature Feedback. . . .Aboanber, A.E. et al. . . . July 2003. . . Tanta Univ., Tanta, Egypt.
Ann. Nucl. Energy, 30, 1123-1134. . . Measurement of Neutron Total Cross-Section of Dy at Pohang Neutron Facility. . . .Kim, G. et al.. . . July 2003. . . Pohang Univ Sci. & Technol., Pohang, South Korea; KAERI, Taejon, South Korea; JINR, Moscow, Russia.
Ann. Nucl. Energy, 30, 1135-1153. . . The Influence of a Non-Uniform Radial Temperature Distribution in the Fuel on the Results of Calculation of Transients. . . .Goltsev, A.O. et al. . . July 2003. . . Russian Resh. Ctr., Moscow, Russia.
Ann. Nucl. Energy, 30, 1155-1179. . . Evaluation of Resolved and Unresolved Resonance Range of 232-U. . . .Maslov, V.M. et al. . . . July 2003. . . Joint Inst. Nucl. & Energy Resh., Minsk, Byelarus; Tohoku Univ., Miyagi, Japan; JAERI, Ibaraki-ken, Japan.
Ann. Nucl. Energy, 30, 1181-1197. . . Effects of Cross Section Sets and Quadrature Orders on Neutron Fluxes and on Secondary Na-24 Activation Rate of a Pool Type 500 MWe FBR. . . Devan, K. et al. . . . July 2003. . . Indira Gandhi Ctr. Atom. Resh. Tamil Nadu, India.
J. Nucl. Mater., 317, 1-12. . . Effect of Beta Phase, Precipitate and Nb-Concentration in Matrix on Corrosion and Oxide Characteristics of Zr-xNb Alloys. . . .Jeong, Y.H. et al. . . . April 2003. . . KAERI, Taejon, South Korea; Yonsei Univ., Seoul, South Korea.
J. Nucl. Mater., 317, 13-31. . . Evolution of Fine-Scale Defects in Stainless Steels Neutron-Irradiated at 275 Degrees C. . . .Edwards, D.J. et al. . . . April 2003. . . Pacific NW Natl. Lab., Richland, WA.
J. Nucl. Mater., 317, 32-45. . . Influence of Irradiation Temperature and Dose Gradients on the Microstructural Evolution in Neutron-Irradiated 316SS. . . .Edwards, D.J. et al. . . . April 2003. . . Pacific NW Natl. Lab., Richland, WA.
J. Nucl. Mater., 317, 46-53. . . Examination of U Valence States in the Brannerite Structure by Near-Infrared Diffuse Reflectance and X-Ray Photonelectron Spectroscopies. . . .Finnie, K.S. et al.. . . April 2003. . . Australian Nucl. Sci. & Technol. Org., Menai, Australia.
J. Nucl. Mater., 317, 54-61 . . . Thermal Expansion Characteristics of a Titanium Modified Austenitic Stainless Steel: Measurement by High-Temperature X-Ray Diffraction and Modelling Using Gruneisen Formalism. . . .Jose, R. et al. . . . April 2003. . . Indira Gandhi Ctr. Atom. Resh., Tamil Nadu, India.
J. Nucl. Mater., 317, 62-68. . . On the Solubility of Chromium Sesquioxide in Uranium Dioxide Fuel. . . .Leenaeers, A. et al. . . . April 2003. . . CEN SCK, Mol, Belgium; Framatome, Lyon, France.
J. Nucl. Mater., 317, 69-82. . . Statistical Approach and Benchmarking for Modeling of Multi-Dimensional Behavior in TRISO-Coated Fuel Particles. . . .Miller, G.K. et al. . . . April 2003. . . Idaho Natl. Eng. & Environmental Lab., Idaho Falls, ID.
J. Nucl. Mater., 317, 83-92. . . Study of Gel Development During SON68 Glass Alteration Using Atomic Force Microscopy. Comparison with Two Simplified Glasses. . . .Donzel, N. et al. . . . April 2003. . . Univ. Montpellier, France; CEA Valrho, Bagnols Sur Ceze, France.
J. Nucl. Mater., 317, 93-101. . . Swelling Rate Versus Swelling Correlation in 20% Cold-Worked 316 Stainless Steels. . . .Ukai, S. et al. . . . April 2003. . . Japan Nucl. Cycle. Dev. Inst., Ibaraki-ken, Japan.
J. Nucl. Mater., 317, 102-108. . . Enthalpy and Gibbs Energy of Formation of Cerium Dicarbide.. . .Vidhya, R. et al. . . . April 2003. . . Indira Gandhi Ctr. Atom. Resh., Tamil Nadu, India; Indian Inst. Technol., Tamil Nadu, India.
J. Nucl. Mater., 317, 109-116. . . Thermophysical Studies on the Binary System UO2(NO3)(2) Center Dot 6H(2)O-Sr(NO3)(2). . . .Ravindran, P.V. et al. . . . April 2003. . . Bhabha Atom. Resh. Ctr., Maharashtra, India.
J. Nucl. Mater., 317, 117-129. . . Determination of Dislocation Density and Composition of Beta-Zr in Zr-2.5Nb Pressure Tubes Using X-Ray and TEM. . . .Kim, Y.S. et al. . . . May 2003. . . KAERI, Taejon, South Korea.
J. Nucl. Mater., 317, 130-144. . . Differences in Reactivity of Oxide Growth During the Oxidation of Zircaloy-4 in Water Vapour Before and After the Kinetic Transition. . . .Tupin, M. et al. . . . May 2003. . . Ecole Natl. Super. Mines, Etienne, France; Framatome, Lyon, France; Cezus, Ugine, France.
J. Nucl. Mater., 317, 145-159. . . Defect Structure and Evolution in Silicon Carbide Irradiated to 1 DPA-SiC at 1100 Degrees C. . . Senor, D.J. et al. . . . May 2003. . . Pacific NW Natl. Lab., Richland, WA; Lockheed Martin Corp., Schenectady, NY.
J. Nucl. Mater., 317, 160-166. . . Compatibility of Steel No. 1.4970 with Liquid Sodium at High Temperatures. . . .Borgstedt, H.U. . . May 2003. . . Forschungszentrum Karlsruhe, Germany.
J. Nucl. Mater., 317, 167-174. . . Irradiation Creep of Annealed 304L Stainless Steel at Low Dose Levels.. . .Foster, J.P. et al. . . . May 2003. . . Westinghouse Elect. Co., Columbia, SC; Argonne National Lab., Idaho Falls, ID.
J. Nucl. Mater., 317, 175-188. . . The Nature and Effects of the Thermal Stability of Lithium Hydroxide. . . .Dinh, L.M. et al. . . . May 2003. . . LLNL, Livermore, CA.
J. Nucl. Mater., 317, 189-194. . . Transport Properties of Iodine and Tellurium in a Thoria-2 Mol% Urania Matrix. . . .Kaimal, K.N.G. et al. . . . May 2003. . . Bhabha Atom. Resh. Ctr., Maharashtra, India.
J. Nucl. Mater., 317, 195-203. . . Permeation of Hydrogen Through Tantalum: Influence of Surface Effects. . . .Pisarev, A. et al. . . . May 2003. . . Moscow Eng. Phys. Inst., Moscow, Russia; Nagoya Univ., Aichi, Japan.
J. Nucl. Mater., 317, 204-211. . . Grain Size Control of UO2 Pellets by Adding Heat-Treated U2O8 Particles to UO2 Powder. . . .Song, K.W. et al. . . . May 2003. . . KAERI, Taejon, South Korea.
J. Nucl. Mater., 317, 212-216. . . Diffusion Bonding of Stainless Steel to Zircaloy-4 in the Presence of a Ta Intermediate Layer.. . .Ahmad, M. et al.. . . May 2003. . . Pakistan Inst. Nucl. Sci. & Technol., Islamabad, Pakistan.
J. Nucl. Mater., 317, 217-225. . . Mechanical Behaviour of Macro-Dispersed Inert Matrix Fuels.. . .Neeft, E.A.C. et al. . . . May 2003. . Joint Resh. Ctr., Petten, Netherlands; Interfac. Reactor Inst., JB Delft, Netherlands.
J. Nucl. Mater., 317, 226-233. . . Oxidation of Spent UO2 Fuel Stored in Moist Environment.. . .Leenaers, A. et al. . . . May 2003. . . CEN SCK, Mol, Belgium.
J. Nucl. Mater., 317, 234-242. . . Application of the Local Fracture Stress Model on the Cleavage Fracture of the Reactor Pressure Vessel Steels in the Transition Temperature Region.. . .Yang, W.J. et al. . . . May 2003. . . KAERI, Taejon, South Korea; Korea Univ., Seoul, South Korea.
J. Nucl. Mater., 317, 243-251. . . Investigation of Vaporization Behaviour of Hyper-Stoichiometric Uranium Dioxide by Knudsen Effusion Mass Spectrometry .. . .Nakajima, K. et al.. . . May 2003. . . JAERI, Ibaraki-ken, Japan.
J. Nucl. Mater., 317, 252-255. . . Compression Properties of Lead-Bismuth.. . .Dai, Y. et al. . . . May 2003. . . Paul Scherrer Inst., Villigen, Switzerland.
J. Nucl. Mater., 317, 256-260. . . Anisotropy of In-Reactor Deformation of Zr-2.5Nb Pressure Tubes. . . .Holt, R.A. et al. . . . May 2003. . Queens Univ., Kingston, Canada; AECL, Chalk River, Canada.
Nucl. Sci. Eng., 144, 115-128. . . Validation of Minor Actinide Cross Sections by Studying Samples Irradiated for 492 Days at the Dounreay Prototype Fast Reactor - I: Radiochemical Analysis.. . .Shinohara, N. et al. . . . June 2003. . . JAERI, Ibaraki-ken, Japan; Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Sci. Eng., 144, 129-141. . . Validation of Minor Actinide Cross Sections by Studying Samples Irradiated for 492 Days a the Dounreay Prototype Fast Reactor - II: Burnup Calculations. . . .Tsujimoto, K. et al. . . . June 2003. . . JAERI, Ibaraki-ken, Japan; Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Sci. Eng., 144, 142-156. . . Precise Validation of Database (n,y) Cross Sections Using a Lead-Slowing-Down Spectrometer and Simulation from 0.1 eV to 30 keV: Methodology and Data for a Few Elements.. . .Perrot, L. et al. . . . June 2003. . . Institut des Sciences Nucleaires, Grenoble, France.
Nucl. Sci. Eng., 144, 157-173. . . Photonuclear Physics in Radiation Transport - I: Cross Sections and Spectra. . . .Chadwick, M.B. et al. . . . June 2003. . . Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Sci. Eng., 144, 174-189. . . Photonuclear Physics in Radiation Transport - II: Implementation. . . .White, M.C. et al. . . . June 2003. . . Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Technol., 142, 205-229. . . Simulation of Boiling Water Reactor One-Pump Trip Transient by TRAC/BF1-ENTREE. . . .Hotta, A. et al.. . . June 2003. . . TEPCO Systems Corp, Tokyo, Japan; Tokyo Electric Power Co, Tokyo, Japan; Tokyo Institute of Technology, Tokyo, Japan.
Nucl. Technol., 142, 230-242. . . The Neutronics Design and Analysis of a 200-MW (Electric) Simplified Boiling Water Reactor Core. . . Tinkler, D.R.; Downar, T.J. . . . June 2003. . . Purdue University, West Lafayette, IN.
Nucl. Technol., 142, 243-249. . . Basic Considerations on Defining Safety Goals. . . .Hakata, T. . . . June 2003. . . Nuclear Safety Commission of Japan, Tokyo, Japan.
Nucl. Technol., 142, 250-259. . . Investigation of Irradiation Behavior of SiC-Coated Fuel Particle at Extended Burnup. . . .Tobita, T.; Sawa, K. . . . June 2003. . . JAERI, Ibaraki-ken, Japan.
Nucl. Technol., 142, 260-269. . . Out-of-Pile Properties of Hyperstoichiometric (U0.45Pu0.55)C Fuel for the Fast Breeder Test Reactor. . . .Sengupta, A.K. et al. . . . June 2003. . . Bhabha Atomic Research Centre, Mumbai, India.
Nucl. Technol., 142, 270-282. . . Experimental and Numerical Investigations on Debris Bed Coolability in a Multidimensional and Homogeneous Configuration with Volumetric Heat Source.. . .Atkhen, K.;Berthoud, G. . . . June 2003. . Electricite de France, Chatou, France; Commissariat a l'Energie Atomique, Grenoble, France.
Nucl. Technol., 142, 283-293. . . Taming the Crud Problem: A Utility Perspective. . . .Schmidt, J.S.; Lukic, Y.D. . . . June 2003. . . Arizona Public Service, Tonopah, AZ.
Nucl. Technol., 142, 294-305. . . Study of the Consequences of Secondary Water Radiolysis Surrounding a Defective Canister. . . .Liu, J. et al. . . June 2003. . . Royal Institute of Technology, Stockholm, Sweden; Swedish Nuclear Power Inspectorate, Stockholm, Sweden.
Nucl. Technol., 142, 306-317. . . Heterogeneous Target to Reduce the Toxicity of Spallation Products in an Accelerator-Driven System. . . .Stankovsky, A.Y. et al. . . . June 2003. . . Tokyo Institute of Technology, Tokyo, Japan.
Prog. Nucl. Energy, 42, 123-157. . . The Multiphase Eulerian-Lagrangian Transport (MELT-3D) Approach for Modeling of Multiphase Mixing in Fragmentation Processes. . . .Nourgaliev, R.R. et al. . . . 2003. . . Royal Inst. Technol., Stockholm, Sweden.
Prog. Nucl. Energy, 42, 159-177. . . Progress of Radioactive Waste Management in Korea. . . .Hwang, Y.S. et al. . . . 2003. . . KAERI, Taejon, South Korea.
Prog. Nucl. Energy, 42, 179-197. . . Analytical Solution of the Point Kinetics Equations by Exponential Mode Analysis. . . .Aboanber, A.E.. . . 2003. . . Tanta Univ., Tanta, Egypt.
Prog. Nucl. Energy, 42, 199-220. . . Progress of R&D on Total System Performance Assessment of a Potential High Level Radioactive Waste Repository in Korea. . . .Hwang, Y.S. et al. . . 2003. . . KAERI, Taejon, South Korea.
Prog. Nucl. Energy, 42, 221-235. . . Effects of Education on Nuclear Risk Perception and Attitude: Theory. . . .Yim, M.S. et al.. . . 2003. . . North Carolina State Univ., Raleigh, NC; Univ. St. Petersburg, Russia.