|Radiation Safety Information Computational Center|
|Oak Ridge National Laboratory
Post Office Box 2008
Oak Ridge, Tennessee 37831-6362
Phone No. 865-574-6176
|No. 428||October 2000|
|"Unless each man produces more than he receives, increases his output, there will be less for him and all the others" -- Bernard M. Baruch|
The following information was cited in the August issue of the ANS Nuclear News. We congratulate each of the awardees. Their contributions to the nuclear community are appreciated.
U.S. Rep. Ron Packard received a Presidential Citation for "his commitment and leadership in advancing the cause of nuclear science and technology. He has been a key proponent for the nuclear science professional with his support for research and development aimed at fulfilling the promise of nuclear technology as outlined by President Eisenhower in his Atoms for Peace speech in 1953."
Emmy L. A. Roos, communications and marketing consultant and ANS member since 1996, received a Presidential Citation for "her extraordinary dedication to the advancement of all aspects of nuclear science and technology -- especially for the younger generation." She is also chair of the ANS Public Information Committee and of the ANS Colorado Section -- changing the latter from near extinction to the best small section in 1999.
The Eastern Carolinas Section received a Presidential Citation in recognition of its "revitalization ... and its renewed commitment to the goals and objectives of the American Nuclear Society." The section has increased membership from 44 members in 1995-96 to 260 members currently.
William E. Kastenberg, professor of nuclear engineering at the University of California-Berkeley and ANS fellow and member since 1967, received the Arthur Holly Compton Award in Education for "excellence in classroom teaching and supervision of graduate students and in the development of innovative curricula in nuclear engineering, and for outstanding achievements in nuclear engineering academia leadership."
Gerald Woodcock, principal engineer at Fluor Daniel Hanford and ANS member since 1988, received the Public Communication Award for "his years of effort in gently defending the simple truth in accordance with the aims and goals of the American Nuclear Society."
Paul C. Williams, consultant and ANS member since 1972, received the PEP (Public Education Program) Service Award for "his strenuous, well organized, and foresighted efforts to establish, coordinate, and oversee the extensive series of teacher workshops being held in the 10 counties of northern Ohio."
ANS President James A. Lake presented the President's Plaque of Appreciation to out-going President Andrew C. Kadak in recognition of "his leadership and his extraordinary energy for moving the Society into the 21st century."
James J. Laidler, senior scientist in the Chemical Technology Division at Argonne National Laboratory, was honored for leading "the successful U.S. effort to develop high-burnup fuels for advanced liquid metal reactors."
Pierre Lecocq, senior vice president and technical manager in the Engineering and Construction Division at Electricité de France, was honored for "major technical leadership in French power plant unit achievement and in the EPR basic design."
Harry P. "Pete" Planchon, associate director in the Engineering Division at Argonne National Laboratory - West, was honored for "his leadership of the team that successfully conducted the Inherent Safety Demonstration test in EBR II, which also became valuable to the subsequent development of the IFR concept."
Mohamed E. Sawan, senior scientist in the Engineering Physics Department at the University of Wisconsin, was honored for "his national and international leadership and contributions in radiation transport, shielding, and activation analysis for fusion reactor studies, including magnetic confinement technology test reactors, tandem mirrors, stellarators, tokamak power reactors, and heavy ion, light ion and laser-driven ICF power reactors."
Daniel R. Wilkins, assistant
general manager for TRW Environmental Safety Systems, was honored "for
his significant contributions in all phases of the development of safe,
efficient nuclear power reactors in both new and operating plants."
Argonne National Laboratory, Environmental Assessment Division, Argonne, Illinois, contributed a newly frozen version of this radiological risk assessment code system for spent nuclear fuel transportation. RISKIND estimates potential radiological consequences and health risks to individuals and the collective population from exposures associated with the transportation of spent nuclear fuel or other radioactive materials by truck or rail. It offers a user-friendly Windows™ point-and-click interface for problem entry. Numeric methods are used to calculate routine (incident-free) exposure to spent nuclear fuel or other radioactive material shipments. Plume dispersion models are used to determine dose consequences from accidental releases for individuals or a local population group.
RISKIND runs on personal computers
under Windows 95 and Windows 98 but will fail on WindowsNT and Windows2000.
The executables included in the package were created with Lahey Fortran
F77L, Visual Basic, and Borland C compilers. Source files are not included.
The package is transmitted on one DS/HD 3.5-inch (1.4 MB) diskette which
contains executables and sample cases written in a self-extracting compressed
DOS file. Reference: ANL/EAD-1 (November 1995). Lahey Fortran F77L, Visual
Basic 4, Borland C4.0; IBM PC and compatibles. (C00623IBMPC01).
The IAEA, Vienna, Austria, through the OECD NEA Data Bank, Issy-les-Moulineaux, France, contributed a new statistical mode system for calculating nuclear reactions in the frame of combined optical, multistep direct (TUL), multistep compound (NVWY) and statistical (Hauser-Feshbach) models. Incident particle can be a nucleon or any nucleus (heavy ion). Isomer ratios, residue production cross sections and emission spectra for neutrons, protons, alpha-particles, gamma-rays, and one type of light ion can be calculated. The energy range starts just above the resonance region for neutron induced reactions and extends up to several hundreds of MeV for the heavy ion induced reactions.
This current release of EMPIRE
runs under Linux Red Hat 6.1 using g77 compiler. The full functionality
requires: Fortran 77 or 90 compiler, C compiler (if not integrated with
the Fortran compiler), gnuplot, grep, awk (or gawk), bash shell, and Tcl/Tk.
Basic calculations should be possible on any operating system on which
a Fortran 77 compiler is available. The referenced document, scripts, and
test problems are transmitted on a CD in a GNU compressed tar file. Reference:
Informal report (April 5, 2000). Fortran 77 and C; Linux PC systems (P00497/PC586/00).
Oak Ridge National Laboratory, Oak Ridge, Tennessee, and the OECD NEA Data Bank, Issy-les-Moulineaux, France, contributed a newly frozen version of this shielding integral benchmark archive and database. A culmination of nearly 10 years of effort between several contributing authors resulted in the final stylization and formats for the 41 benchmark experiments contained in SINBAD 2000. This release includes a large set of 29 fission shielding benchmarks, ten fusion shielding benchmarks, and two intermediate-energy accelerator benchmarks. Work on follow-up versions of SINBAD will provide more benchmarks in fission, fusion, and accelerator shielding with new additions in radioactive waste and medical applications. The current version supplies example models and computational input for the user's benefit. Included are many benchmarks with their reference documents scanned into a searchable Adobe Acrobat® pdf format.The SINBAD retrieval system is an html indexed and hyperlinked table, sorted alphabetically by shield material, year of publication, laboratory, shield-type, and filename. Each of the table entries are linked to their html formatted abstract in the subdirectories of SINBAD 2000 data. The abstract is hyperlinked to the experimental html document within each of the subdirectories. Included in most benchmark subdirectories are computational data and original documents that have been scanned in Acrobat® pdf format.
The data are provided in HTML
3.1 format compatible with most UNIX, Microsoft® Windows™, and Apple®
platforms. The HTML browsers that are compatible with these platforms open
the data files. The size of each benchmark may range from a few hundred
kilobytes to over a megabyte depending on the number of associated graphical
and tabular files. The total disk space requirement is approximately 200
MB. Reference: SINBAD 2000 help files and examples. HTML; UNIX Workstations,
PC, MAC (D00191ALLCP02).
Yankee Atomic Electric Company, Bolton, Massachusetts, through the OECD NEA Data Bank, Issy-les-Moulineaux, France, contributed this axial burnup profile database for pressurized water reactors. The data were obtained directly from utilities whose reactors represent the range of commercial PWR fuel lattices. The work was performed by Yankee Atomic Electric for Sandia National Laboratory. All axial burnup profiles were calculated from 3-D depletion analyses of the core configuration. The organizations and utilities providing axial burnup profiles for the database used different model codes for the 3D-depletion calculations. The model codes used were: SIMULATE-3, NEMO, ANC, and PRESTO-II. Cross-section inputs describing the assemblies are derived from assembly lattice calculations. SIMULATE and NEMO used CASMO-3 to generate cross sections, ANC used PHOENIX, and PRESTO-II used RECORD. The nodal calculations were performed typically in a quarter core symmetric configuration using 12 to 25 nodes to describe the axial direction and one to four nodes to describe the radial direction of each assembly. The data cover a range of burnup from slightly over 3 GWd/MTU to 55.3 GWd/MTU and an enrichment range of 1.24 w/o to 4.75 w/o U-235. Fuel designs contain different poison absorbers such as borosilicate glass, B4C, Integral Fuel Burnable Absorber (IFBA), erbium and gadolinium. The database consists of 3169 computed axial burnup profiles, covering 106 cycles of operation.
The data may be opened with Microsoft
Excel-97. They are transmitted on a CD which includes the database and
report written in a self-extracting compressed DOS file. Reference: YAEC-1937
(May 1997). ASCII/Excel (D00201MNYCP00).
Harwell Laboratory, Oxfordshire, United Kingdom, through the OECD NEA Data Bank, Issy-les-Moulineaux, France, contributed this collection of data for use in radiochemical modeling work. The data base includes thermodynamic data (the log formation constant and the enthalpy of formation for the chemical species) for the actinides U, Th, Pu, Np, Am and Cm and for fission products including Cs, Ru, Tc and Sr. HATCHES was created using the Microsoft® Access Software on a MS Windows computer, and does not require the proprietary Access software. Output options are provided to convert the contents of the database into the format required by the PICKER/PHREEQE programs or to create the components of a data file for use with the EQ3/6 program.
At present the database has only
been compiled for use at 25 degrees C. In a limited number of cases, the
enthalpy data required for calculations at other temperatures are included;
but these data were not used at Harwell. Statistical error analyses of
the measurements are included. The package is transmitted on a CD written
in DOS format. Reference: User Manual (March 1999). Microsoft® Access
executable, Personal Computer (D00206PC48600).
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.
Class size is limited and course
is subject to cancellation if minimum enrollment is not obtained one month
prior to the course. Course fees are refundable up to one month before
each class. Classes are cosponsored by RSICC. Foreign nationals must register
at least six weeks in advance. For further information, contact Kay at
865-574-9213 or see http://www.cped.ornl.gov/scale/trcourse.html.
|7-10 November..........Advanced Class..........Oak Ridge, Tennessee|
|Advanced classes are for
people with MCNP experience who want to extend their knowledge and gain
depth of understanding. Most areas of MCNP operation will be discussed
in detail, with emphasis on Advanced Geometry, Advanced Variance Reduction
Techniques, and other advanced features of the program. Time will be available
to discuss approaches to specific problems of interest to students.
NOTE: While MCNP supports a number of platforms, class computers are usually Unix machines. Experience with Unix will be helpful to the student but is not essential.
Year 2000 classes will showcase
the latest release of MCNP, Version 4C. Major new features that will be
All classes provide interactive
computer learning. Time will be available to discuss individual questions
and problems with MCNP experts. To register for the U.S. classes via the
Internet, go to
or email Bill Hamilton at firstname.lastname@example.org.
International Symposium on Radiation Technology in Emerging Industrial Applications, Nov. 6-10, 2000, Beijing, China, sponsored by the International Atomic Energy Agency. Contact: IAEA, P.O. Box 100, Vienna International Centre, A-1400 Vienna, Austria (tel + 43 1 2600 21275, fax + 43 1 2600 29610, email email@example.com, url www.iaea.org).
First International Symposium on Supercritical Water-Cooled Reactors, Design, and Technology, Nov. 7-8, 2000, Tokyo, Japan, sponsored by the University of Tennessee Nuclear Engineering Research Laboratory and others. Contact: Mami Yamashita, email firstname.lastname@example.org.
2000 ANS/ENS International Meeting and Technology Exhibit, Nov. 12-16, 2000, Washington, D.C. Contact: Clyde Jupiter, general chair (tel 301-946-8088, fax 301-946-6539, email email@example.com, url www.ans.org).
Embedded Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp2000), Nov. 12-16, 2000, Washington, D.C., (held in conjunction with ANS/ENS International Meeting and Technology Exhibit), sponsored by the ANS Accelerator Applications Technical Group. Contact: ANS Meetings Department (tel 708-352-6611, fax 708-352-6464, email firstname.lastname@example.org).
International Seminar on Implementation of Systems to Prevent and Detect Unauthorized Uses of Nuclear and Radioactive Materials, Nov. 13-17, 2000, Vienna, Austria, sponsored by the International Atomic Energy Agency. Contact: IAEA, Wagramerstrasse 5, P.O. Box 100, A-1400 Vienna, Austria (tel + 43 1 26000, fax + 43 1 26007, email email@example.com, url www.iaea.org).
Fifth International CANDU Maintenance Conference, Nov. 19-21, 2000, Toronto, Ontario, Canada, sponsored by the Canadian Nuclear Society. Contact: CNS, 480 University Ave., Suite 200, Toronto, Ontario, Canada; (tel 416-977-7620, fax 416-977-8131, email firstname.lastname@example.org).
Radiation 2000, Nov. 26-28, 2000, Lucas Heights, Australia, sponsored by the Australian Institute of Nuclear Science and Engineering. Contact: Irene Parker, Radiation 2000, PMB 1, Menai NSW 2234 Australia (tel + 02 9717 3436, fax + 02 9717 9268, email email@example.com, url www.ainse.edu.au/ainse/index.html).
18th Nuclear Particle Physics Conference, Dec. 10-15, 2000, Adelaide, Australia, sponsored by the Australian Institute of Nuclear Science and Engineering. Contact: Irene Parker, AINSE, PMB 1, Menai NSW 2234 Australia (tel + 02 9717 3436, fax +02 9717 9268, email firstname.lastname@example.org, url www.ainse.edu.au).
International Conference of National Regulatory Authorities with Competence in the Safety of Radiation Sources and the Security of Radioactive Materials, Dec. 11-15, 2000, Buenos Aires, Argentina, sponsored by the International Atomic Energy Agency. Contact: IAEA, IAEA-CN-84, Vienna International Centre, P.O. Box 100, Wagramerstrasse 5, A-1400 Vienna, Austria; (tel +43 1 2600, fax +43 1 26007, email email@example.com; url www.iaea.org/worldatom/.)
Symposium Science with Radioactive
Beams (PACIFICHEM 2000), Dec. 14-19, 2000, Honolulu, Hawaii, sponsored
by the American Chemical Society and others. Contact: Congress Secretariat,
ACS, (tel 800-227-5558, fax 202-872-6128, email firstname.lastname@example.org,
Fire and Safety 2001: Fire Protection and Prevention in Nuclear Facilities, Feb. 12-14, 2001, London, England, sponsored by Nuclear Engineering International. Contact: Julie Rossiter, Wilmington Publishing, Ltd., Wilmington House, Church Hill, Wilmington, Dartford, Kent, DA2 7EF, U.K. (tel +44 1322 394706, fax +44 1322 276 743, email email@example.com).
21st Century Biodosimetry: Quantifying the Past and Predicting the Future, Feb. 22, 2001, Arlington, VA, sponsored by the National Council on Radiation Protection and Measurements, Contact: William M. Beckner (tel 301-657-2652, fax 301-907-8768, url www.ncrp.com.)
Waste Management 2001 Symposium, Feb. 25-Mar. 1, 2001, Tucson, AZ, sponsored by WM Symposia, Inc. Contact: LOI, Inc. (tel 520-292-5652, fax 520-292-9080, email firstname.lastname@example.org, url www.wmsym.org).
Fourth Urals Seminar on Radiation
Damage Physics, Feb. 25-Mar. 3, 2001, Snezhinsk, Russia, sponsored
by the Institute of Metal Physics. Contact: C.M. Elliott, foreign secretary
(tel 217-244-7725, fax 217-244-4293, email email@example.com,
Health Phys., 79, 251-256 . . . New Approach for Dose Reconstruction: Application to One Case of Localized Irradiation with Radiologial Burns. . . . Bottollier-Depois, J-F.; Gaillard-Lecanu, E.; Roux, A.; Chau, Q.; Trompier, F.; Voisin, P.; . . . September 2000 . . . Institute for Protection and Nuclear Safety, Fontenay-aux-Roses Cedex, France.
Health Phys., 79, 266-273 . . . Ingestion Pathway Model Developed for Use with an Acute Atmospheric Dose Model at the Savannah River Site. . . . Simpkins, A.A.; Marx, D.R.; Hamby, D.M. . . . September 2000 . . . Westinghouse Savannah River Co., Aiken, SC; Oregon State University, Corvallis, OR.
Health Phys., 79, 274-281 . . . Derivation of Indoor Gamma Dose Rate From High Resolution In Situ Gamma Ray Spectra. . . . Clouvas, A.; Xanthos, S.; Antonopoulos-Domis, M. . . . September 2000 . . . Aristotle University of Thessaloniki, Greece.
Health Phys., 79, 282-285 . . . Are Public Dose Limits Necessary? . . . Jensen, P.H. . . . September 2000 . . . Riso National Laboratory, Roskilde, Denmark.
Nucl. Sci. Eng., 136, 1-14 . . . The Screened Rutherford Pencil Beam Problem with Heterogeneities. . . . Pomraning, G.C. . . . September 2000 . . . University of California, Los Angeles, CA.
Nucl. Sci. Eng., 136, 15-33 . . . Higher-Order Boundary Condition Perturbation Theory. . . . McKinley, M.S.; Rahnema, F. . . . September 2000 . . . Georgia Institute of Technology, Atlanta, GA.
Nucl. Sci. Eng., 136, 34-58 . . . Some Aspects of Neutron Transport in Spatially Random Media. . . . Williams, M.M.R. . . . September 2000.
Nucl. Sci. Eng., 136, 59-84 . . . Adjoint Sensitivity Analysis of the RELAP5/MOD3.2 Two-Fluid Thermal-Hydraulic Code System -- I: Theory. . . . Cacuci, D.G.; Ionescu-Bujor, M. . . . September 2000 . . . University of Karlsruhe and Forschungszentrum Karlsruhe, Karlsruhe, Germany.
Nucl. Sci. Eng., 136, 85-121 . . . Adjoint Sensitivity of the RELAP5/MOD3.2 Two-Fluid Thermal-Hydraulic Code System -- II: Applications. . . . Ionescu-Bujor, M.; Cacuci, D.G. . . . September 2000 . . . University of Karlsruhe and Forschungszentrum Karlsruhe, Karlsruhe, Germany.
Nucl. Sci. Eng., 136, 122-139 . . . A Synthetic Acceleration for a Two-Dimensional Characteristic Method in Unstructured Meshes. . . . Sanchez, R.; Chetaine, A. . . . September 2000 . . . Commissariat a l'Energie Atomique de Saclay, Saclay, France.
Nucl. Sci. Eng., 136, 140-149 . . . The Transport of Neutral Hydrogen Atoms in a Hydrogen Plasma. . . . Garcia, R.D.M.; Siewert, C.E. . . . September 2000 . . . HSH Scientific Computing, Sao Jose dos Campos, SP, Brazil; North Carolina State University, Raleigh, NC.
Nucl. Technol., 131, 279-296 . . . Temperature Reactivity Effects in Pebbles of a High-Temperature Reactor Fueled with Reactor-Grade Plutonium. . . . Bende, E.E. . . . September 2000 . . . NRG, Petten, The Netherlands.
Nucl. Technol., 131, 297-318 . . . Loca with Consequential or Delayed Loop: Modeling of Accident Sequences and Associated Core Damage Frequency. . . . Martinez-Guridi, G.; Samanta, P.; Chu, T-L.; Yang, J-W. . . . September 2000 . . . Brookhaven National Laboratory, Upton, NY.
Nucl. Technol., 131, 319-331 . . . Analysis of Kuosheng Large-Break Loss-of-Coolant Accident with Melcor 1.8.4. . . . Wang, T-C.; Wang, S-J.; Chien, C-S. . . . September 2000 . . . Institute of Nuclear Energy Research, Chiaan Village Lungtan, Taiwan.
Nucl. Technol., 131, 332-336 . . . Formulas Giving Buildup Factor for Double-Layered Shields. . . . Guvendik, M.; Tsoulfanidis, N. . . . September 2000 . . . University of Missouri-Rolla, Rolla, MO.
Nucl. Technol., 131, 337-353 . . . Effect of Depleted-Uranium Dioxide Particulate Fill on Spent-Nuclear-Fuel Waste Packages. . . . Forsberg, C.W. . . . September 2000 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Technol., 131, 354-378 . . . The Remodeling and Basic Characteristics of the Heavy Water Neutron Irradiation Facility of the Kyoto University Research Reactor, Mainly for Neutron Capture Therapy . . . Kobayashi, T.; Sakurai, Y.; Kanda, K.; Fujita, Y.; Ono, K. . . . September 2000 . . . Kyoto University Research Reactor Institute, Osaka, Japan.
Nucl. Technol., 131, 379-384 . . . University Research Reactors: Issues and Challenges. . . . Bernard, J.A.; Hu, L-W. . . . September 2000 . . . Massachusetts Institute of Technology, Cambridge, MA.
Nucl. Technol., 131, 385-394 . . . The Physics of Plutonium Fuels - A Review of Organization for Economic Cooperation and Development/Nuclear Energy Agency Activities. . . . Hesketh, K.; Delpech, M.; Sartori, E. . . . September 2000 . . . BNFL Research and Technology, Preston, United Kingdom; Commissariat a l'Energie Atomique, St-Paul-lez-Durance, France; Organization for Economic Cooperation and Development/Nuclear Energy Agency, Issy-les-Moulineaux, Paris, France.
ICRU Report 63 . . . Nuclear Data for Neutron and Proton Radiotherapy and for Radiation Protection. . . . March 2000 . . . International Commission on Radiation Units and Measurements, Bethesda, MD.
KEK Proceedings 99-24 . . . e+e- Factories '99. . . . Akai, D.; Kikutani, E.; eds. . . . February 2000 . . . KEK, High Energy Accelerator Research Organizaiton, Ibaraki-ken, Japan. . . . . . . Proceedings of International Workshop on Performance Improvement of Electron-Positron Collider Particle Factories, September 21-24, 1999, KEK in Tsukuba, Japan.
ORNL/TM-2000/212 . . . R-Matrix Evaluation of 16O Neutron Cross Sections Up to 6.3 MeV. . . . Sayer, R.O.; Leal, L.C.; Larson, N.M.; Spencer, R.R.; Wright, R.Q. . . . August 2000 . . . Oak Ridge National Laboratory, Oak Ridge, TN.