The American Nuclear Society (ANS) honored five members as ANS Fellows during the Society's winter meeting in Reno, Nevada, in November 2001. ANS bestows the Fellow designation to recognize outstanding accomplishment by members in one or more disciplines or fields of nuclear science and engineering. The five disciplines are: Notable original research or invention in the nuclear field; Scientific or technical leadership in a nuclear enterprise of substantial scope; Outstanding leadership as a teacher in the nuclear field; Outstanding leadership in design, engineering and operating efforts in the nuclear field; and Outstanding efforts in the areas of nuclear health, safety and regulation. The newest ANS Fellows are:
Dr. Marvin L. Adams, associate professor of nuclear engineering at Texas A&M University. Adams, of College Station, Texas, was recognized for the development and analysis of advanced spatial discretization methods, as well as the development and analysis of rapidly convergent interactive methods for transport challenges. He also was recognized for his excellence in teaching and advising undergraduate and graduate nuclear engineering students.
Steven A. Arndt, team leader for instrumentation and control with the U.S. Nuclear Regulatory Commission. Arndt, a resident of Damascus, Maryland, was recognized for extraordinary leadership in promoting the safe operation of nuclear reactors through advances in the areas of nuclear instrumentation and control, software quality assurance, reliability engineering and nuclear power plant simulators.
Dr. Nam Zin Cho, professor of nuclear engineering at the Korea Advanced Institute of Science and Technology. Cho, of Taejon, Korea, was recognized for his achievements in developing reactor physics and transport theory methods used worldwide in laboratories and industry, and for inspiring a new generation of nuclear engineers in academia, research institutes and industry in Korea.
Calvin M. Hopper, senior distinguished research and development engineer with the Oak Ridge National Laboratory. Hopper, of Clinton, Tennessee, was recognized for his outstanding effort in the field of nuclear criticality safety, and for his leadership roles in developing national and international consensus standards, in developing and directing technology support programs and preparing guidance on the elements of a criticality safety program.
Dr. George J. Rotariu, a consultant in nuclear energy and retired senior scientist for the Division of Nuclear Safety in the U.S. Department of Energy's Office of Environment, Health and Safety. Rotariu, a resident of Bethesda, Maryland, was recognized for his design and management overview of construction of the first large *cobalt-60* irradiator in the United States, and his management roles for the AEC programs on process radiation and isotopic instrumentation development.
The American Nuclear Society, based in the Chicago suburb of La Grange Park, Illinois, is a not-for-profit, international, scientific and educational organization. It was established in 1954 by professionals in diverse fields to promote the advancement of engineering and science relating to the atomic, nuclear and allied sciences and arts. More than 11,000 individuals belong to the Society and exchange research, provide scholarships, hold meetings and disseminate information on nuclear science and technology.
The shielding community was saddened to learn
of the passing of John L. "Kampy" Kamphouse
on December 3, 2000. Kampy had served as the chairman of two teams that
revised and reaffirmed two major radiation protection and shielding standards:
ANS-6.4-1997 (Revision of ANSI/ANS-6.4-1985) - Nuclear Analysis and Design
of Concrete Radiation Shielding for Nuclear Power Plants and ANS-6.4.2-1985;
R1997 - Specification for Radiation Shielding Materials. Kampy had been
a lead shield engineer at Gilbert/Commonwealth Engineers before coming
to serve as a senior nuclear engineer for shielding and dose analysis for
TVA's Brown Ferry's Nuclear Power stations from which he retired. He was
also the dean of Bethel Bible College and had earned a doctoral degree
in sacred theology and religion from Bethany Seminary in Dothan, Alabama.
He will be greatly missed. RSICC apologizes for this late announcement.
Dr. Dixon Callihan, a resident of Oak Ridge, Tennessee, for 48 years before moving to Davidson, North Carolina in 1993, died after a brief illness Sunday, December 9, 2001. Callihan was born July 10, 1908, in Scarbro, West Virginia. Dr. Callihan received his undergraduate degree from Marshall College, Huntington, West Virginia, Masters from Duke University, and Ph.D. in Physics from New York University. He was a Professor of Physics at New York University and then City College New York when, in 1941, he joined a group working with the Atomic Energy Research Project (Manhattan District Project) at Columbia University. He came to Oak Ridge in 1945 where he began a long career contributing to the many interrelated disciplines of nuclear energy. Dr. Callihan retired in 1973 from the Oak Ridge National Laboratory as associate director of the Neutron Physics Division and director of the Critical Experiments Facility, and he continued work as a consultant until 1993. He was a member of the Nuclear Standards board of the American National Standard Institute since its inception in 1957. He was editor of the American Nuclear Society's Journal of Nuclear Science and Engineering until 1983, and served as an administrative judge on the Atomic Safety & Licensing Board panel of the U.S. Nuclear Regulatory Commission until 1990. Dr. Callihan received the Distinguished Service Award from the American Nuclear Society in 1983 for his many significant contributions to the Society, especially his founding of the Nuclear Criticality Safety Division. He was presented with the ANS Standards Committee Service Award in 1988 for thirty years of service to the program and his participation in both national and international standards groups. In 1964, he was awarded an Honorary Doctor of Science degree by Marshall University as a leader in the development of atomic energy for peaceful uses; and he also received the Marshall University Alumni Association's Distinguished Alumnus Award in 1985. He was a fellow of the American Physical Society and the American Nuclear Society. He was preceded in death by his first wife, Alva Stroh Callihan. Surviving are his wife Mildred Martin Callihan; two stepdaughters Dr. Virginia Dalton, Tuscon, Arizona, and Nancy Chikes and her husband Peter, Concord, North Carolina; and four step-grandchildren. Dr. Callihan was a founder and continuing supporter of the Oak Ridge Playhouse, serving as its president 1952-1955 and a member of the Board of Directors from 1963-1993. Memorials may be made to Marshall University Foundation, Inc., One John Marshall Dr., Huntington, WV 25755 or The Pines Resident Support Fund, 400 Avinger Lane, Davidson, NC 28036.
Workshop/Tutorial (tentative) on AMPX-2000, the latest version of the AMPX cross-section processing system that is developed and maintained by the Oak Ridge National Laboratory (ORNL). AMPX-2000 processes nuclear data evaluations that conform to the Evaluated Nuclear Data File (ENDF/B) format specifications. AMPX-2000 has the capability to process ENDF/B formats through Version VI and generate continuous-energy or multigroup cross-section libraries for neutron and/or photon transport. The objective of the workshop is to introduce new and experienced users to AMPX-2000. The workshop consists of classroom instruction provided by the AMPX code developers with an emphasis on use of the code system to process nuclear data evaluations. The workshop will also provide the participants with the opportunity to use AMPX to process nuclear data evaluations. Upon completion of the workshop, participants will have an understanding of the code system and be able to use AMPX to process ENDF/B evaluations and generate cross-section data for use in radiation transport codes. The proposed Agenda for a 5-day Workshop/Tutorial follows:
Day 1 - The first day will provide an introduction to ENDF/B formats and concepts associated with cross-section data. Followed by an overview of the AMPX-2000 code system that will include a discussion of the modular design philosophy and special features associated with the code system. The history of its sponsorship, major releases, etc., will be covered. In addition, a comprehensive overview of the processing capabilities will be provided. Differences and similarities to the NJOY processing system will be reviewed as appropriate. The remaining part of the first day will be devoted to a description of the AMPX modules and procedures that are used to generate continuous-energy cross sections from ENDF/B evaluations. In addition, the AMPX modules and procedures for processing the ENDF/B collision kinematics data will be described in detail.
Day 2 - Classroom instruction for the second day will focus on the modules and procedures that are used to produce multigroup neutron and photon cross-section libraries. The morning session will emphasize the AMPX modules that relate to producing multigroup data (e.g., generating weighting spectra, resonance-parameter processing, thermal-data processing, etc.). Workshop participants will gain familiarity with the different types of data that are used to provide a multigroup dataset for transport calculations. The afternoon session will be devoted to "hands-on" exercises that emphasize the course material from the first two days of instruction. Participants will have the opportunity to prepare input for producing continuous-energy and multigroup data using AMPX-2000.
Day 3 - The third day will begin with a review of the classroom exercises from Day Two followed by additional discussions on multigroup library processing as needed. New AMPX capabilities for generating probability tables and covariance matrices will be discussed in the morning session. The afternoon session will be devoted to additional classroom exercises related to generating continuous-energy and multigroup data. In addition, workshop participants will have the opportunity to generate probability tables and process ENDF/B uncertainty data with AMPX-2000.
Day 4 - The fourth day will begin with a review of the sample problems of the preceding afternoon session followed by classroom instruction for the various resonance self-shielding treatments that are provided in the AMPX system. The material will build upon the information presented on Day Two and include discussions of modules and procedures that must be used to prepare the appropriate data to be used in the treatments. The afternoon session will provide classroom exercises that make use of the course material presented in the morning session.
Day 5 - The fifth day will provide a review of the problems that were investigated on Day Four. A discussion of various AMPX-2000 utility modules will be provided. AMPX-2000 produces data in a wide variety of formats and has the capability to interface with the NJOY code system. The material covered on Day Five will focus on the utility modules that are needed to perform specialized data manipulation tasks (e.g., convert data between NJOY and AMPX, compare data libraries, constructing and maintaining a special energy boundary library for group structures, procedures for constructing specialized 1/ES t functions, AMPX installation procedures for different computer platforms, etc).
Tutorials on deterministic radiation transport codes (tentatively end of 2002). The intention is to present recently developed tools for modelling 3D problems, including automated mesh generation, (X-Y-Z), (R-THETA-Z) and the visualization of the corresponding results to facilitate interpretation and for improved documentation. Methods for 3D Sensitivity Analysis / Uncertainty Analysis should also be demonstrated. The Data Bank Executive Group has strongly recommended the development of such tools. If you are interested in participating, please fill in the form.
Workshop on Computing Radiation Dosimetry with embedded training course on MCNPX - Monte Carlo Code System for Multiparticle & High Energy Applications, to be held at the Instituto Tecnologico e Nuclear (ITN), Sacavem, Lisbon, Portugal June 22-28, 2002. During the weekend of June 22-23, a series of tutorial lectures will be held followed by a daily tutorial lecture delivered by a senior expert on a subject related to the MCNPX module(s) being taught that day. The MCNPX specific training will be delivered June 24-28. If you are interested in participating, please fill in the form.
MCNP - Introductory or Advanced Course including MCNP5 Features, March 18-22 at the Imperial College, London.
PENELOPE (electron-photon transport) workshop with tutorial, (2002, RSICC, Oak Ridge, Tennessee, USA).
Three U.S. Nuclear Regulatory Commission (NRC) software packages which were transferred from the Energy Science and Technology Software Center, Oak Ridge, Tennessee to RSICC were incorporated into the RSICC computer code collection. Please browse the computer code abstracts available at RSICC's www site for more information on these packages.
Two new packages were added to the computer code software and data collection; both are foreign contributions.
The ENEA Nuclear Data Center, Bologna, Italy, through the OECD Nuclear Energy Agency Data Bank, Issy-Les Molineaux, France, contributed this code system for 2D- and 3D- mesh generation and graphical display of geometry and results for the DOORS deterministic transport codes. Bologna Transport Analysis Pre-Post-Processors (BOT3P) provide users of the DORT and TORT deterministic transport codes (CCC-650/DOORS-3.2) some useful diagnostic tools to prepare and check their input data files. These tools were conceived to be as general as possible for a large number of applications. They were designed to overcome some difficulties in the preparation of the geometrical model entries and of the fixed neutron source entries of the DORT/TORT input files for the shielding calculations of the VENUS-1 and VENUS-3 benchmark experiments, within the framework of the activities of the OECD/NEA Task Force on Computing Radiation Dose and Modeling of Radiation-Induced Degradation of Reactor Components (TFRDD). BOT3P consists of the following six independent programs:
RVARSCL: Reads DORT/TORT "VARSCL" sequential
BOT3P programs run on DEC Alpha, Sun and IBM RS/6000 systems and are expected to run on most Unix workstations. The developer implemented BOT3P under the following UNIX systems:
DEC Alpha, OSF1 V4.0F, DIGITAL Fortran, Version
BOT3P1.0 has not been implemented under
Windows. Executables that were created at RSICC on a Pentium computer under
RedHat Linux 7 with the Portland Group, Inc. compiler are included. A Fortran
77 compiler is required to compile the codes on all other computers. At
RSICC, the codes were also tested on an IBM RS/6000 under AIX 4.2 with
XLF 126.96.36.199. The RSCORS, Sandia National Laboratory subroutine library
of graphical primitives, is required to install and run BOT. RSCORS is
distributed with the CCC-650/DOORS3.2 package. The package is transmitted
on a CD in a GNU compressed Unix tar file. The tar file contains the source
files, test cases, implementation instructions, procedures, description
of sample problem cases, and documentation. References: KT-SCG 00011 (September
5, 2001), KT-SCG 00011 (September 5, 2001), KT-SCG 00012 (September 5,
2001). Fortran 77; IBM, Sun, DEC and Linux PC (P00513/MNYWS/00).
The Safety Research Institute, Atomic Energy Regulatory Board, IGCAR Campus, Tamilnadu, India, contributed this interactive, user-friendly code system to graphically view neutron and gamma-ray cross-sections of isotopes, which are available in different data libraries. The names of isotopes for which the cross-sections are available is shown in a data base grid on the selection of a particular library. Routines have been developed in Visual Basic 6.0 to retrieve required information from each of the binary files or random access files. The present program can fetch data from:
1) ACE random access file used with MCNP code,
It is possible to compare the data of cross-sections for any isotope from selected libraries, and it is possible to extract a particular nuclear reaction cross-section from ACE library files. Context sensitive help is an attractive feature of the program and aids the novice user to extract the required data. Routines were developed to fetch the required data from binary (random access) files.
The interactive program was developed on a Pentium computer under Windows-95,98 and was tested at RSICC on a PENTIUM III 1GHz Micron running Windows 2000. The package is transmitted on a CD which contains a self-extracting compressed file that contains Visual Basic 6 source files, executable files, typical cross section library files and documentation and help files.
References: Informal reports from Safety Research
Institute (November 2001). Visual Basic 6.0; Pentium (P00514/PC586/00).
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. 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.
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, are invited to present a paper. Please visit the website www.bnl.gov/est/IMUG2002 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.
The MCNP code developers will present several
classes in 2002 in the United States and two classes in Europe. The dates
for these classes are:
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 gain depth of understanding.
The classes will be based on MCNP5, that has a tentative release date of April 2002. 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, tallies, 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.
Lead Teachers: Drs. John Hendricks, Gregg McKinney,
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.
All 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. Followup consultation for class participants will be provided.
Classes are taught directly 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 Nuclear Criticality Slide Rule Workshop will be held February 26-27, 2002, at the Oak Ridge National Laboratory, Oak Ridge, Tennessee, and is intended for criticality safety and radiation shielding engineers, health physicists, and emergency response personnel. The Slide Rule is available in working hand-held hard copy or as a Windows PC program. The workshop includes hands-on-training with both versions. Attendees must bring a laptop PC (Windows 95/NT or later) with CD-ROM drive.
Registration information: If you register by January 31, 2002, you will receive a $100 discount. Cost of the workshop is $800 registration fee, $125 for the hand-held hard copy of Slide Rule, $450 for Windows PC version of NCS Slide Rule on CD. For more information or to register online, go to www.cped.ornl.gov/sliderule.
DATE: May 6-10, 2002
Monte Carlo type calculations are ideally suited to solving a variety of problems in radiation protection and dosimetry. This course is aimed at the HP, medical physicist, and rad engineer with no prior experience with Monte Carlo techniques. The focus is almost entirely on the application of MCNP™ to solve a variety of practical problems in radiation shielding and dosimetry. The intent is to "jump start" the student toward using MCNP productively. Extensive interactive practice sessions are conducted on a personal computer. Topics will include overview of the MCNP code and the Monte Carlo method, basic concepts, input file preparation, geometry, source definition, standard MCNP tallies, interpretation of the output file, exposure and dose rate calculations, radiation shielding, photon skyshine, detector simulation and dosimetry. The course fee includes a complete MCNP code package, distributed directly from the Radiation Safety Information Computational Center (RSICC). Students will also be provided with a comprehensive class manual and a diskette containing all of the practice problems. This course has been granted 32 Continuing Education Credits by the AAHP, and 4.5 CM points by the American Board of Industrial Hygiene.
The course is offered by the Health Physics Measurements Group at the Los Alamos National Laboratory and is co-sponsored by RSICC. Registration is available online at http://drambuie.lanl.gov/~esh4/mcnp.htm Make checks payable to the University of California (checks must be in U.S. dollars on a U.S. bank) and mail together with name, address, and phone number to: Los Alamos National Laboratory, Group ESH-4, MCNP Class/David Seagraves, Mail Stop G761, Los Alamos, NM 87545.
Inquiries regarding registration and class space availability should be made to David Seagraves, 505-667-3241, fax: 505-665-6071, e-mail: email@example.com. Technical questions may also be directed to Dick Olsher, 505-667-3364, e-mail: firstname.lastname@example.org.
The 10th in a series will be held May 21-23, 2002, at the University of Michigan, Ann Arbor, MI. The program will emphasize research and recent development in ionizing radiation measurements. Proposed session topics are: radiation sources, including secondary target sources; detectors and detection systems; data acquisition and data analysis systems and methods; radiation spectroscopy; particle-induced X-ray emission and radiation-induced fluorescence; analytical standards and elemental analysis; new and unique applications of ionizing radiation; industrial radiography and tomography; nuclear methods in space exploration and planetary science.
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
Three five-day classes will be held in 2002 - March 18-22, June 17-21, and September 9-13, all in Richland, Washington. These classes 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.
These classes 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 these classes can be located at: http://www.mcnpvised.com/train.html, or by contacting Randy Schwarz (email email@example.com).
Hardened Electronics and Radiation Technology (HEART) Conference, Mar. 11-15, 2002, Monterey, CA. Contact: Thomas Stringer, chair (tel 719-599-1719, fax 719-599-1991).
Thirty-Eighth Annual Meeting of the National Council on Radiation Protection and Measurements, Apr. 10-12, 2002, Arlington, VA. Contact: William M. Beckner (tel 301-657-2652, fax 301-907-8768, url www.ncrp.com).
Back to the Future of Nuclear Technology, 2002 ANS Student Conference, Apr. 10-13, 2002, University Park, PA. Contact: Frank Buschman (tel 814-865-6351, email firstname.lastname@example.org, url www.clubs.psu.edu/ANS).
12th Biennial RPSD Topical Meeting, Apr. 14-17, 2002, Santa Fe, NM. Hosted by the ANS Trinity Section and cosponsored by the Health Physics Society, L'Organisation de cooperation et de developpement/L'Agence pour l'energie nucleaire (OECD/AEN, and RSICC. Contact: (email email@example.com, url www.lanl.gov/RPSD2002/).
International Youth Nuclear Congress 2002, Apr. 16-20, 2002, Taejon, Korea. Contact: Alexandre Tsiboulia or Han Seong Son (email firstname.lastname@example.org, email@example.com, url http://www.iync.org).
Seventh International Radiopharmaceutical Dosimetry Symposium, Apr. 17-19, 2002, Nashville, TN. Contact: Michael Stabin (email firstname.lastname@example.org, url http://www.doseinfo-radar.com/symphome.html).
MCNPX Intermediate Workshop, Apr. 18-23, 2002, Santa Fe/Los Alamos, NM. Contact Bill Hamilton (tel 505-662-9097, email email@example.com, url http://mcnpxworkshops.com for details). *We will take Sunday off (and if the RPS conference runs over, we'll start the 19th).
Radiation Transport Calculations Using the EGS Monte Carlo System, Apr. 29-May 2, 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, url www.irs.inms.nrc.ca/inms/irs/papers /egsnrc/brochure.html).
Practical MCNP for the HP, Medical Physicist, and Rad Engineer, May 6-10, 2002, Los Alamos, NM. Contact: David Seagraves (tel 505-667-3241, fax 505-665-6071, email email@example.com, url http://drambuie.lanl.gov/~esh4/mcnp.htm; technical questions to Dick Olsher, 505-667-3364, firstname.lastname@example.org).
Symposium on Radiation Measurements and Applications, May 21-23, 2002, Ann Arbor, MI. Contact: General Chair David K. Wehe (tel 734-764-6215, email email@example.com, url http://rma -symposium.engin.umich.edu/).
Topical Meeting: Industrial Radiation and Radioisotope Measurement Applications IRRMA-V A Class IV Topical, June 9-14, 2002, Bologna, Italy, co-sponsored by the American Nuclear Society. Contact: Prof. Jorge Fernandez (Chair) (e-mail firstname.lastname@example.org).
ANS Annual Meeting, The Revival of the Nuclear Power Option, June 9-13, 2002, Hollywood, FL (url http://www.ans.org/).
14th International Conference on High-Power Particle Beams and 5th International Conference on Dense Z-Pinches, June 23-28, 2002, Albuquerque, NM (email for general inquiries email@example.com, url http://www.sandia.gov/BeamsDZP).
Snowmass Fusion Summer Study, July 8-19, 2002, Snowmass Village, CO (url http://lithos.gat.com/snowmass/).
Fourth Meeting of the International MACCS Users Group (IMUG) September 6, 2002, in the Principality of Monaco (url 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, url http://www.vin.bg.ac.yu/YUNS).
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).
15th ANS Topical Meeting on the Technology of Fusion Energy, Nov. 17-21, 2002, Washington, DC. (url http://www.ans.org/).
International Conference on Supercomputing in Nuclear Applications, SNA 2003, September 22-24, 2003, Paris, France. Organizers: CEA, SFANS, co-organizer: OECD/NEA. (email SNAfirstname.lastname@example.org, url http://SNA-2003.cea.fr).
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). 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.
Health Phys., 81, 289-301 . . . Review of the ICRP Tritium and 14C Internal Dosimetry Models and Their Implementation in the GENMOD-PC Code. . . . Richardson, R.B.; Dunford, D.W. . . . September 2001 . . . AECL, Chalk River Laboratories, Chalk River, Ontario, Canada.
Health Phys., 81, 272-288 . . . Radon Exposure and the Risk of Leukemia: A Review of Epidemiological Studies. . . . Laurier, D.; Valenty, M.; Tirmarche, M. . . . September 2001 . . . Institute for Protection and Nuclear Safety, Fontenay-aux-Roses, France.
Health Phys., 81, 313-324 . . . Dose to Lung from Inhaled Tritiated Particles. . . . Richardson, R.B.; Hong, A. . . . September 2001 . . . AECL, Chalk River Laboratories, Chalk River, Ontario, Canada.
Health Phys., 81, 325-329 . . . Effective Half-Life of 131I in Thyroid Cancer Patients. . . . North, D.L.; Shearer, D.R.; Hennessey, J.V.; Donovan, G.L. . . . September 2001 . . . Rhode Island Hospital, Providence, RI; Brown University, Providence, RI.
Nucl. Eng. Design, 209, 1-22 . . . Euratom Framework Programme Research in Reactor Safety: Main Achievements of FP-4 ('94-'98), Preliminary Results of FP-5 ('98-'02) and Prospects for Beyond 2002 . . . Van Goethem, G.; Zurita, A.; Bermejo, J.M.; Lemaître, P. . . . November 2001 . . . Nuclear Fission and Radiation Protection, Brussels, Belgium.
Nucl. Eng. Design, 209, 23-28 . . . The 5th Euratom Framework Programme 1998-2002: End-User Driven Research and Training Activities. . . . Marchipont, J.F. . . . November 2001 . . . European Commission, Brussels, Belgium.
Nucl. Eng. Design, 209, 29-37 . . . Main Achievements of FP-4 Research in Reactor Safety. . . . Van Goethem, G.; Zurita, A.; Bermejo, J.M.; Lemaître, P.; Bischoff, H. . . . November 2001 . . . European Commission, Brussels, Belgium.
Nucl. Eng. Design, 209, 39-45 . . . The European Utility Requirement Document (EUR). . . . Roche, B. . . . November 2001 . . . Electricite de France-Pole Industrie, Saint Denis, France.
Nucl. Eng. Design, 209, 47-56 . . . Strategy and Research Needs for Nuclear Power Plant Development: Plant Modernization and Possible New Construction in Finland. . . . Mattila, L.; Vanttola, T. . . . November 2001 . . . VTT Energy, Espoo, Finland.
Nucl. Eng. Design, 209, 57-65 . . . Challenges Left in the Areas of Materials Ageing and Plant Modernisation. . . . Schulz, H. . . . November 2001 . . . GRS, Cologne, Germany.
Nucl. Eng. Design, 209, 67-77 . . . Reconstitution Techniques Qualification and Evaluation to Study Ageing Phenomena of Nuclear Pressure Vessel Materials (RESQUE). . . . Van Walle, E. et al. . . . November 2001 . . . SCK CEN, Mol, Belgium; VTT Energy, Espoo, Finland; Research Center Rossendorf Inc., Dresden, Germany; AEA Technology, Harwell, UK; BNFL Magnox, Berkeley, UK; Siemens, Erlangen, Germany; JRC/IAM, Petten, the Netherlands; NGR, Petten, The Netherlands.
Nucl. Eng. Design, 209, 79-85 . . . BIMET: Structural Integrity of Bi-Metallic Components. . . . Faidy, C. et al. . . . November 2001 . . . EDF-SEPTEN-RE, Villeurbanne, France.
Nucl. Eng. Design, 209, 87-96 . . . Challenges Left in the Area of In-Vessel Melt Retention. . . . Asmolov, V.; Ponomarev-Stepnoy, N.N.; Strizhov, V.; Sehgal, B.R. . . . November 2001 . . . Kurchatov Institute, Moscow, Russia; Russian Academy of Sciences, Moscow; Russia; Royal Institute of Technology, Stockholm, Sweden.
Nucl Eng. Design, 209, 97-106 . . . Severe Accident Recriticality Analyses (SARA). . . . Frid, W. et al. . . . November 2001 . . . Swedish Nuclear Power Inspectorate, Stockholm, Sweden; Riso National Laboratory, Roskilde, Denmark; VTT Energy, Espoo, Finland; Studsvik Eco & Safety AB, Nykoping, Sweden; Tellisuuden Voima Oy, Olkihuoto, Finland.
Nucl. Eng. Design, 209, 107-116 . . . Investigation of Core Degradation (COBE) . . . Shephard, I. et al. . . . November 2001 . . . Joint Research Center, Ispra, Italy; Universita deli Studi di Pisa, Italy; Technische Universitat (TUD), Dresden, Germany; Commissariat á l'Energie Atomique (CEA), Cadarache, France; Forschungszentrum Karlsruhe (FZKA), Germany; IBRAE, Moscow, Russia; Universite de Provence, Marseille, France; AEA Technology, Winfrith, UK; Ente per le Nuove Tecnologie, l'Energie e l'Ambient, Bologna, Italy; Universität Stuttgart, Germany; Universidad Politechnica de Madrid, Spain.
Nucl. Eng. Design, 209, 117-125 . . . On the Prediction of the Reactor Vessel Integrity Under Severe Accident Loadings (RPVSA) . . . Krieg, R. et al. . . . November 2001 . . . Institut fur Reaktorsicherheit, Karlsruhe, Germany; Commissariat a l'Energie Atomique, Saclay, France; Ente per le Nuove Technologie l'Energia e l'Ambiete, Roma, Italy; Joint Research Centre of the European Community, Ispra, Italy; Forschungszentrum Jülich, Germany; Paul Scherrer Institut, Villigen, Switzerland.
Nucl. Eng. Design, 209, 127-138 . . . Corium Spreading and Coolability CSC Project . . . Cognet, G. . . . November 2001 . . . CEA/DRN/DTP, Saint Paul lez Durance, France; FZK, Karlsruhe, Germany; JRC/ISIS, Ispra, Italy; Siemens, Erlangen, Germany; Royal Institute of Technology, Stockholm, Sweden; University of Stuttgart, Germany;; ENEA, Bologna, Italy; IUSTI, Marseilles, France; Framatome, Paris la Défense, France; EDF/DRD/RNE/TTA, Chatou, France; CEA/DRN/DTP, Grenoble, France.
Nucl. Eng. Design, 209, 139-146 . . . Investigations on the Phenomenology of Ex-Vessel Core Melt Behaviour (COMAS). . . . Steinwarz, W.; Alemberti, A.; Hafner, W.; Alkan, Z.; Fischer, M. . . . November 2001 . . . Siempelkamp Nuklear, und Unwelttechnik GmbH & Co., Krefeld, Germany; Ansaldo, Genoa, Italy; Battelle, Eschborn, Germany; Aachen University, Germany; Siemens, Erlangen, Germany.
Nucl. Eng. Design, 209, 147-154 . . . Prevention and Mitigation Measures to Ensure Containment Integrity. . . . DeBoeck, B. . . . November 2001 . . . Association Vincotte Nuclear, Brussels, Belgium.
Nucl. Eng. Design, 209, 155-163 . . . Containment Evaluation Under Severe Accidents (CESA): Synthesis of the Predictive Calculations and Analysis of the First Experimental Results Obtained on the Civaux Mock-Up . . . Granger, L. et al. . . . November 2001 . . . EDF-SEPTEN Division GC, Villeurbanne, France; IPSN, Paris, France; Siemens, Erlangen, Germany; ENEL, Roma, Italy; CEA, Saclay, France; ENS de Cachan, Cachan, France; LCPC, Paris, France; ISMES, Seriate, Italy; Stangenberg und Partners, Bochum, Germany; Coyne et Bellier, Paris, France; GRS, Köln, Germany; NNC Ltd., Cheshire, UK; AEA Technology, Dorset, UK.
Nucl. Eng. Design, 209, 165-172 . . . Multi-Dimensional Simulation of Hydrogen Distribution and Turbulent Combustion in Severe Accidents . . . Bielert, U. et al. . . . November 2001 . . . Institute for Nuclear and Energy Technologies, Karlsruhe, Germany; Commissariat a l'Energie Atomique, Gif-sur-Yvette, France; Institut de Protection et Súrete Nucléaire, Fontenay-aux-Roses, France; Joint Research Centre Ispra, Italy; Technical University Munich, Garching, Germany; Framatome, Erlangen, Germany.
Nucl. Eng. Design, 209, 173-181 . . . Applicability of Phebus FP Results to Severe Accident Safety Evaluations and Management Measures. . . . Schwarz, M.; Clement, B.; Jones, A.V. . . . November 2001 . . . Institut de Protection et de Sûreté Nucléaire, Saint-Paul-lez-Durance, France; Joint Research Centre, Ispra, Italy.
Nucl. Eng. Design, 209, 183-192 . . . A Risk-Based Evaluation of the Impact of Key Uncertainties on the Prediction of Severe Accident Source Terms - STU . . . Ang, M.L. et al. . . . November 2001 . . . NNC Limited, Cheshire, UK; UITESA, Madrid, Spain; Tractebel Energy Engineering, Brussels, Belgium; IVO Power Engineering Ltd., Vantaa, Finland; VTT Energy, City, Finland; Vattenfall Energisystems A.B., Stockholm, Sweden; Sydkraft Konsult A.B., Malmo, Sweden; EDF-SEPTEN, Villeurbanne, France; GRS, Cologne, Germany.
Nucl. Eng. Design, 209, 193-200 . . . Organic Iodine Chemistry. . . . Dickinson, S. et al. . . . November 2001 . . . AEA Technology plc, Dorset, UK; CEA/IPSN, Saint-Paul-Lez-Durance, France; Framatome, Erlangen, Germany; STUK, Helsinki, Finland; VTT Chemical Technology, Espoo, Finland.
Nucl. Eng. Design, 209, 201-210 . . . Role of the Man-Machine Interface in Accident Management Strategies. . . . Owre, F. . . . November 2001 . . . OECD Halden Reactor Project, Halden, Norway.
Nucl. Eng. Design, 209, 223-231 . . . The Development and Demonstration of Integrated Models for the Evaluation of Severe Accident Management Strategies - SAMEM. . . . Ang, M.L. et al. . . . November 2001 . . . NNC Limited, Cheshire, UK; GRS mbH, Koln, Germany; Fortum Engineering Ltd., Vantaa, Finland; Vattenfall Energisystem AB, Stockholm, Sweden; Sycon Energikonsult, Malmo, Sweden.
Nucl. Eng. Design, 209, 243-252 . . . TEPSS - Technology Enhancement for Passive Safety Systems . . . Hart, J. et al. . . . November 2001 . . . NRG Nuclear Research and Consultancy Group, Petten, The Netherlands; NRG Nuclear Research and Consultancy Group, Arnhem, The Netherlands; Stork Nucon V.V., Amsterdam, The Netherlands; Paul Scherrer Institute, Villigen, Switzerland; Centro Investigaciones Energeticas, Madrid, Spain; Universidad Politècnica de Valencia, Spain; Universitat Politècnica de Catalunya, Barcelona, Spain.
Nucl. Eng. Design, 209, 253-262 . . . Containment Behaviour in the Event of Core Melt with Gaseous and Aerosol Releases (CONGA). . . . Friesen, F. et al. . . . November 2001 . . . Siemens AG, Offenbach am Main, Germany; PSI, Villigen, Switzerland; CIEMAT, Madrid, Spain; Joint Research Center, Ispra, Italy; ENEL, Milan, Italy.
Nucl. Eng. Design, 210, 1-8 . . . Calcium Oxide/Carbon Dioxide Reactivity in a Packed Bed Reactor of a Chemical Heat Pump for High-Temperature Gas Reactors. . . . Kato, Y.; Yamada,M.; Kanie, T.; Yoshizawa, Y. . . . December 2001 . . . Tokyo Institute of Technology, Tokyo, Japan.
Nucl. Eng. Design, 210, 9-19 . . . Conceptual Designing of Reduced-Moderation Water Reactor with Heavy Water Coolant. . . . Hibi, K.; Shimada, S.; Okubo, T.; Iwamura, T.; Wada, S. . . . December 2001 . . . Mitsubishi Heavy Industries, Ltd.; Yokohama, Japan; JAERI, Ibaraki, Japan; Japan Atomic Power Company, Tokyo, Japan.
Nucl. Eng. Design, 210, 21-36 . . . Mechanistic Modeling for Ring-Type Boiling Water Reactor Fuel Spacer Design (3) Run-Off Effect and Model Formulation. . . . Yano, T.; Aritomi, M.; Kikura, H.; Obata, H. . . . December 2001 . . . Tokyo Institute of Technology, Tokyo, Japan; Japan Atomic Power Company, Ltd., Tokyo, Japan.
Nucl. Eng. Design, 210, 37-51 . . . Liquid-Liquid Interface Stability in Accelerating and Constant-Velocity Tube Flows. . . . Epstein, M.; Burelbach, J.P.; Fauske, H.K.; Kubo, S.; Koyama, K. . . . December 2001 . . . Fauske & Associates, Inc.; Burr Ridge, IL; Japan Atomic Power Company, Tokyo, Japan; Advanced Reactor Technology Co., Ltd., Tokyo, Japan.
Nucl. Eng. Design, 210, 53-77 . . . Liquid Entrainment By an Expanding Core Disruptive Accident Bubble - A Kelvin/Helmholtz Phenomenon. . . . Epstein, M.; Fauske, H.K.; Kubo, S.; Nakamura, T.; Koyama, K. . . . December 2001 . . . Fauske & Associates, Inc.; Burr Ridge, IL; Japan Atomic Power Company, Tokyo, Japan; Mitsubishi Heavy Industries, Ltd., Nagasaki, Japan; Advanced Reactor Technology Co., Tokyo, Japan.
Nucl. Eng. Design, 210, 95-123 . . . Assessments of the Kinetic and Dynamic Transient Behavior of Sub-Critical Systems (ADS) in Comparison to Critical Reactor Systems. . . . Schikorr, W.M. . . . December 2001 . . . Forschungszentrum Karlsruhe, Germany.
Nucl. Eng. Design, 210, 135-155 . . Interfacial Area Measurements in Subcooled Flow Boiling. . . . Bartel, M.D.; Ishii, M.; Masukawa, T.; Mi, Y.; Situ, R. . . . December 2001 . . . Purdue University, West Lafayette, IN.
Nucl. Eng. Design, 210, 157-168 . . . Water Flow Experiments and Analyses on the Cross-Flow Type Mercury Target Model with the Flow Guide Plates. . . . Haga, K.; Terada, A.; Kaminaga, M.; Hino, R. . . . December 2001 . . . JAERI, Ibaraki, Japan.
Nucl. Eng. Design, 210, 169-175 . . . Ex-Vessel Transport and Mixing of a Deborated Slug in a PWR Primary Geometry. . . . di Marzo, M. . . .December 2001 . . . University of Maryland, College Park, MD.
Nucl. Eng. Design, 210, 177-191 . . . Implementation and Assessment of the Renormalization Group (RNG), Quadratic and Cubic Non-Linear Eddy Viscosity k-e Models in GOTHIC. . . . Analytis, G.Th. . . . December 2001 . . . Paul Scherrer Institute, Villigen PSI, Switzerland.
Nucl. Eng. Design, 210, 193-224 . . . Experimental Studies of Oxidic Molton Corium - Vessel Steel Interaction. . . . Bechta, S.V. et al. . . . December 2001 . . . Scientific Research Technological Institute, Leningrad Region, Russia; SPb Electrotechnical University, St. Petersburg, Russia; GI VNIPIET, St. Petersburg, Russia; Institute of Silicate Chemistry, St. Petersburg, Russia.
Nucl. Eng. Design, 210, 225-238 . . . Modeling of Fuel Performance and Metallic Fission Product Release Behavior During HTTR Normal Operating Conditions. . . . Verfondern, K.; Sumita, J.; Ueta, S.; Sawa, K. . . . December 2001 . . . Research Center Julich, Germany; JAERI, Oarai, Japan.
Nucl. Eng. Design, 210, 239-248 . . . Measurement and Calculation of Neutron Densities in BWR High Burn-Up Fuels. . . . Tayama, R. et al. . . . December 2001 . . . Hitachi Engineering Co., Ltd., Ibaraki-ken, Japan; Nuclear Power Engineering Corp., Tokyo, Japan; Nippon Nuclear Fuel Development Co. Ltd., Ibaraki-ken, Japan.
Nucl. Eng. Design, 210, 249-258 . . . A Semiempirical Prediction of the Decay Ratio for the Boiling Water Reactors Start-Up Process. . . . Blazquez, J.; Ruiz, J. . . . December 2001 . . . CIEMAT, Madrid, Spain; National Institute of Nuclear Research, Ocoyoacac, Mexico.
Nucl. Eng. Design, 210, 259-264 . . . The Experimental Study on the Helium Circulator of HTR-10. . . . Jie Wang; Huizhong Zhou; Quanfa Tang . . . December 2001 . . . Tsinghua University, Beijing, China; Shanghai Blower Works Co. Ltd., Shanghai, China.