|Radiation Safety Information Computational Center|
|Oak Ridge National Laboratory|
Post Office Box 2008
Oak Ridge, Tennessee 37831-6362
Lockheed Martin Energy Research Corp.
for the U.S. Department of Energy
under contract DE-AC05-96OR22464
Phone No. 423-574-6176
|No. 413||May 1999|
|When Spring unlocks the flowers to paint the laughing soil.--Reginald Heber from Seventh Sunday after Trinity.|
Feedback from developers and users on issues related to Y2000 compatibility on RSICC-distributed codes is welcome and needed! Please contact RSICC via email or post related information on our electronic notebook. Updated information about Y2K issues in RSICC packages may be found at http://www-rsicc.ornl.gov/year2000.html. The following disclaimer applies to all RSICC-distributed codes/data libraries.
|This material was prepared as an account of Government sponsored work and describes a code system or data library which is one of a series collected by the Radiation Safety Information Computational Center (RSICC). These codes/data were developed by various Government and private organizations who contributed them to RSICC for distribution; they did not normally originate at RSICC. RSICC is informed that each code system has been tested by the contributor, and, if practical, sample problems have been run by RSICC. Neither the United States Government, nor the Department of Energy, nor Lockheed Martin Energy Research Corporation, nor any person acting on behalf of the Department of Energy or Lockheed Martin Energy Research Corporation, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, usefulness or functioning of any information code/data and related material, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government, the Department of Energy, Energy Systems, nor any person acting on behalf of the Department of Energy or Lockheed Martin Energy Research Corporation.|
Several U.S. Nuclear Regulatory Commission (NRC) software packages which were transferred from the ESTSC to RSICC were incorporated into the RSICC computer code collection. Please browse the computer code abstracts available at RSICC's website for more information on these packages.
Three changes or additions were made to the computer code collection during the month. One new code system was packaged and added to the collection, one existing code system was replaced with a newly frozen version, and one code system was corrected. One change resulted from a foreign contribution.
Oak Ridge National Laboratory, Oak Ridge, Tennessee, made minor changes to this isotope generation and depletion code system. The installation procedure was simplified, and files in the sample problems directories were reorganized so that the PC output generated at ORNL is distributed in a separate subdirectory to facilitate comparison of results. These changes are cosmetic; there were NO changes to the code, executable or data files. ORIGEN2.1 is a computer code system for calculating the buildup, decay, and processing of radioactive materials. It is a revised version of ORIGEN which incorporates updates of the reactor models, cross sections, fission product yields, decay data, and decay photon data.
The Fortran source for the PC 386 and 486 was compiled and linked with the Lahey F77L-EM/32 Fortran compiler version 5.10. The executable which runs in a DOS window under either Windows 95 or Windows NT is included in the package. It also runs on VAX computers under the VMS operating system. A Fortran compiler is required to run on all computers except PC's. The package is transmitted on two diskettes with a self-extracting compressed DOS file, which contains the source code, executable for PC, data libraries, batch files, information files, and sample problem input and output. Reference: ORNL/TM-7175 (July 1980). Fortran; VAX, PC386/486 (C00371ALLCP02).
Lawrence Livermore National Laboratory, Livermore, California, contributed a newly frozen version of this code system which provides health physics personnel with a fast, field-portable calculational tool for evaluating accidents involving radioactive materials. HOTSPOT 8.03 incorporates several enhancements including an improved geographical mapping module. The new release runs on Pentium II and III correcting a problem which generated intermittent runtime errors on Pentium computers in the previous 8.0 release. HOTSPOT codes are a first-order approximation of the radiation effects associated with the atmospheric release of radioactive materials. The programs are reasonably accurate for a timely initial assessment. More importantly, HOTSPOT codes produce a consistent output for the same input assumptions and minimize the probability of errors associated with reading a graph incorrectly or scaling a universal nomogram during an emergency. HOTSPOT implements the well-established Gaussian Plume Model, which is widely used for initial emergency assessment or safety analysis planning of a radionuclide release.
HOTSPOT will run on an IBM PC with a minimum of 512 kbytes of RAM and can also be run as a DOS application within WINDOWS 3.1 or Windows 95. The BORLAND Turbo PASCAL 7.0 compiler was used to create the executables included in the package. Note that source codes are NOT distributed. The package is transmitted on one diskette in DOS format, which includes the executables and data. Reference: UCRL-MA-106315 (March 1994). PASCAL; IBM PC (C00644IBMPC02).
Unite de Developpment des Technologies du Silicium, Algiers, Algeria, contributed this Monte Carlo code system for electron (positron) dose kernel calculations. KERNEL performs dose kernel calculations for an electron (positron) isotropic point source in an infinite homogeneous medium. First, the auxiliary code PRELIM is used to prepare cross section data for the considered medium. Then the KERNEL code simulates the transport of electrons and bremsstrahlung photons through the medium until all the particles reach their cutoff energies. The deposited energy is scored in concentric spherical shells at a radial distance ranging from zero to twice the source particle range. KERNEL is based on the general purpose Monte Carlo GEPTS (Gamma, Electron and Positron Transport System) code system. Five media are considered: water, air, Al, Fe and Pb.
The Microsoft Fortran 5.1 compiler was used to create the included executable which runs on personal computers under DOS or in a DOS window of Windows 95. Included are the referenced document and one diskette on which the source, PC executable, data and test case are distributed in a self-extracting compressed DOS file. Reference: Informal report (1999). Fortran 77; IBM PC (C00672IBMPC00).
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 email@example.com 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.
The MCNP code developers will present one advanced class in London, July 5-9, 1999. The advanced class is for people who have used MCNP and want to extend their knowledge and understanding. We plan to showcase the preliminary 4C version of MCNP that will be in a pre-release status. The new features to be discussed include:
Other capabilities of MCNP to be covered are: Basic geometry and advanced geometry, Source definitions, Tallies, Data, Variance reduction, Statistical analysis, Criticality, Plotting of geometry, tallies, and particle tracks, and Neutron/photon/electron physics.
All classes provide interactive computer learning, with time 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. For more information and to register for the London class, contact Enrico Sartori, OECD/NEA, firstname.lastname@example.org.
Code Integration Group (X-CI), Los Alamos National Laboratory
Personnel from the X Division of Los Alamos National Lab have agreed to teach a four-day short course on MCNP September 29-October 2, 1999, at North Carolina State University, Raleigh, NC. The first 20 paid applicants will be accepted and the cost ($1800) will be reduced if payment is received by August 1, 1999. Registration will close on September 1, 1999. This introductory class is for people who have never used MCNP or have very limited experience with the code and will include interactive computer sessions. Time will be available to discuss individual questions and problems with MCNP experts or to pursue topics mentioned in the talks. The class will use the pre-release version 4C of MCNP. A manual will be provided for use in the classroom. As co-sponsor of the workshop, RSICC will provide a CD with the code package and the data after the class is over for a nominal cost of $300 payable to RSICC. Apply by email to Dr. T. S. Elleman, e-mail email@example.com (please copy to Dr. R. P. Gardner; e-mail firstname.lastname@example.org). Make checks or money orders payable to MCNP/IRRMA and mail to:
Dr. T. S. Elleman
Nuclear Engineering Department, Box 7909
North Carolina State University
Raleigh, NC 27695-7909 USA
It is possible to register on-line at www.quantumres.com.
Monte Carlo type calculations are ideally suited to solving a variety of problems in radiation protection and dosimetry. The Los Alamos MCNP code is a general and powerful Monte Carlo transport code for photons, neutrons, and electrons. 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. 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 by 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. 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, however to guarantee a space payment must be received prior to the registration deadline. 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 T. Seagraves, Mail Stop G761, Los Alamos, NM 87545.
DATE: October 18-22, 1999 (registration deadline October 4, 1999)
FEE: $1,650 per person (includes the MCNP code package)
PLACE: The Canyon School Complex, Los Alamos National Laboratory
Pacific Northwest National Laboratory (PNNL) is offering an MCNP visual editor training class September 13-16, 1999. The class will combine teaching on MCNP physics, along with instructions on how to use the visual editor. Computer demonstrations and exercises will focus on creating and interrogating input files with the visual editor. Demonstrations of advanced visualization work using MCNP will also be made. The class will be taught on Pentium computers running the Linux operating system. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. It is recommended that you have experience with MCNP before taking this class. Additional information is available from Randy Schwarz, Pacific Northwest National Laboratory (PNNL), Battelle Boulevard, PO Box 999, Richland, WA 99352-0999 USA (phone 509- 372-4042, fax 509-372-6421, email email@example.com).
The SCALE staff at ORNL will be offering several training courses in 1999. The courses emphasize
hands-on experience solving practical problems on PCs. The ORNL courses will have workgroups of
two persons each. No prior experience in the use of SCALE is required to attend these courses. The
registration fee for each course at ORNL is $1,500. A copy of the SCALE software and manual on CD
may be obtained at the ORNL courses for an additional fee of $300. Registrations will be accepted on
a first-come basis. Registration forms submitted directly from the Web are preferred. Registration via
FAX or e-mail is also acceptable. The registration fee must be paid by check or travelers checks. We
apologize that we are NOT able to accept credit card payments.
|Sept. 13 - 17||SCALE KENO VI
| Versailles, France - prior to
Contact Enrico Sartori (e-mail firstname.lastname@example.org )
|Oct. 25 - 29||SCALE Course
| Tokai, Japan - following ICRS
Contact Tadakazu Suzuki (e-mail tadakazu@HERO.tokai.jaeri.go.jp)
|Nov. 1 - 5||SCALE KENO V.a Course||Oak Ridge National Laboratory|
Class size is limited and courses are 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 for ORNL courses at least one month in advance. For further information, contact Kay Martin, email@example.com , 423-574-9213.
The SCALE Shielding and Source Terms Course emphasizes SAS2 and ORIGEN-ARP (depletion/source-term generation) and SAS3 and SAS4 using MORSE-SGC (3-D Monte Carlo neutron/gamma shielding). It also covers SAS1/XSDRNPM (1-D neutron/gamma shielding) and QADS/QAD-CGGP (3-D point kernel gamma shielding).
The SCALE KENO VI Criticality Course focuses on KENO VI and the associated criticality analysis sequences in CSAS6. KENO VI is the latest version of the KENO Monte Carlo criticality safety code. KENO VI differs from KENO V.a in the following ways. It contains a much larger set of geometrical bodies, including cuboids, cylinders, spheres, cones, dodecahedrons, elliptical cylinders, ellipsoids, hoppers, parallelpipeds, planes, rhomboids, and wedges. The code's flexibility is increased by allowing the following features: intersecting geometry regions; hexagonal as well as cuboidal arrays; regions, holes, arrays, and units rotated to any angle and truncated to any position; and the use of an array boundary that intersects the array. It includes the 2-D color plotting capability of KENO V.a. Users should be aware that the added geometry features in KENO VI can result in significantly longer run times than KENO V.a. A KENO VI problem that can be modeled in KENO V.a will typically run twice as long in KENO VI as in KENO V.a. Thus the new version VI is not a replacement for the existing version V.a, but an additional version for more complex geometries that could not be modeled previously.
The SCALE KENO V.a Criticality Course focuses 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 analysis code that has been in use for approximately 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.
GLOBAL '99 is the fourth conference of the GLOBAL series. It will be held August 29-September 3, 1999, at the Snow King Resort in Jackson, Wyoming. This conference emphasizes the challenges inherent in advancing the use of nuclear technologies in the next century with discussions in four specific areas: uses of nuclear technology; advanced nuclear energy concepts; fuel cycle and waste management; and nuclear resources (both human and facilities). The deadline for pre-registration is June 30. For further information contact: Todd Allen, Argonne National Laboratory - West, P. O. Box 2528, Idaho Falls, Idaho 83401-2528 (phone 208-533-7760, fax 208-533-7863, email firstname.lastname@example.org). Additional information may also be found at url http://www.anlw.anl.gov/global99/).
The Third International Conference on Isotopes (3ICI) will be held in the Renaissance Hotel in Vancouver, Canada, September 6-10, 1999. The conference will be hosted by TRIUMF, Canada's national accelerator facility and a major center for isotope production and applications in research and medicine, in conjunction with the Canadian Chapter meeting of the International Isotope Society. Persons interested in presenting an oral or poster paper should prepare a one page abstract in accord with the instructions on the web page. Further information is available from Ms. Elly M. Driessen, TRIUMF, 4004 Wesbrook Mall, Vancouver, B.C., Canada V6T 2A3 (phone 604-222-7352, fax 604-222-1074, email email@example.com, url http://www.triumf.ca/3ici/).
The Tenth International Symposium on Reactor Dosimetry will be held September 12-17, 1999, in Osaka, Japan. About every three years this symposium provides a forum for the interchange of state-of-the-art techniques, databases and standardization of radiation metrology. The Symposium will be of value to those involved in reactor dosimetry, including researchers, manufacturers and representatives from industry, utilities and regulatory agencies. The Symposium is jointly sponsored by the Atomic Energy Society of Japan (AESJ), the American Society for Testing and Materials (ASTM) and the European Working Group on Reactor Dosimetry (EWGRD). It is organized by ASTM Committee E10 on Nuclear Technology and Applications and EWGRD.
The Symposium theme is dosimetry for the assessment of irradiated reactor materials and reactor experiments, featuring radiation metrology techniques, databases and standardization. Inquiries and requests to be added to the mailing list should be sent to one of the following:
|North & South America, East & Southeast Asia:||Europe, Africa, Asia (other), and Australia:|
|Dr. David W. Vehar
ASTM Program Secretary
Sandia National Laboratories, MS-1136
P.O. Box 5800, Albuquerque, NM 87185-1136, USA
Phone: 505-845-3414, fax: 505-844-0798
|Dr. Hamid Ait Abderrahim|
EWGRD Programme Secretary
Boeretang 200, B-2400 Mol, BELGIUM
Phone: 32-14-332277, fax: 32-14-321529
The International Conference on Nuclear Criticality Safety (ICNC '99) will be held in Versailles, September 20-24, 1999, to provide an international technical forum for the nuclear criticality safety issues concerned with handling fissile material, away from nuclear reactors as well as the fuel manufacturing operations, fresh and spent fuel transportation and waste management. Additional information may be obtained at the following website: http://www.ipsn.fr/icnc99/.
The 4th Topical Meeting on Industrial Radiation and Radioisotope Measurement Applications
IRRMA '99, will be held October 3-7, 1999, in Raleigh, North Carolina. It will bring together
scientists and engineers from around the world with an interest in the use of nuclear radiation and
radioisotopes for industrial measurement applications. IRRMA '99 is sponsored by the Isotopes and
Radiation Division of the American Nuclear Society (ANS), the Eastern Carolinas Section of ANS,
the Center for Engineering Applications of Radioisotopes at North Carolina State University, and
Quantum Research Services, Inc. Presentation summaries will be published by ANS and will be
available at the meeting. Selected papers will be published in full in the journal Applied Radiation and
Isotopes, published by Elsevier Science. Additional information may be found at
http://www.quantumres.com./irrma.html or contact
Dr. Thomas S. Elleman
Department of Nuclear Engineering
North Carolina State University, Box 7909
Raleigh, NC 27695-7909 U.S.A.
"Half a Century of Radiation Shielding Research and Its Evolution into the Next Era" is the theme for the 9th International Conference on Radiation Shielding to be held October 17-22, 1999, in Tsukuba, Japan. It is sponsored and organized by the Japan Atomic Energy Research Institute and co-sponsored by the OECD-Nuclear Energy Agency-Nuclear Science Committee (NEA-NSC), Atomic Energy Society of Japan (AESJ), and the Radiation Safety Information Computational Center (RSICC). Detailed information about the conference may be obtained from Yujiro Ikeda, Japan Atomic Energy Research Institute, Tokai Research Establishment, Neutron Science Research Center, Spallation Neutronics Laboratory, Tokai-mura, Naka-gun, Ibaraki-ken 319-11 Japan (phone 81-29-282-6074, fax 81-29-282-5709, email firstname.lastname@example.org. go.jp) or from the web page at http://icrs9.tokai.jaeri.go.jp.
The 8th International Conference on Nuclear Engineering (ICONE-8) will be held in Baltimore, Maryland, April 2-6, 2000. It is sponsored by the American Society of Mechanical Engineers (ASME), Société Française de l'Energie Nucléaire (SFEN) and Japan Society of Mechanical Engineers (JSME). Papers are invited for publication and presentation on a variety of topics related to "Nuclear Energy in the New Millennium." ICONE is a comprehensive international conference on nuclear engineering which features 400-500 peer-reviewed, full-length papers in 10 technical tracks:
Two printed copies of a 400-word abstract with track number, in one of the following formats: MSWord, WordPerfect, postscript, pdf, or text file, with your return address, phone, fax, and email information should be submitted by September 15, 1999, to George Bockhold, U.S. Technical Chair, P.O. Box 116502, Gainesville, FL 32611-6502, USA (phone 1+352-392-9722, fax 1+352-392-8656, email Submitemail@example.com, url http://www.icone-conf.org/icone8/).
The 8th International Symposium on Radiation Physics (ISRP-8) will be held in Prague, the Czech
Republic, June 5-9, 2000. The Symposium, a triennial event organised by the International Radiation
Physics Society (IRPS), is devoted to current trends in radiation physics research and potential future
issues. The scientific sessions will include invited lectures and poster presentations of contributed
papers. Papers are solicited for the following proposed scientific sessions:
If you are interested in attending the symposium, please contact:
Professor Ladislav Musílek
Czech Technical University in Prague
Faculty of Nuclear Sciences and Physical Engineering
Bøehová 7, 115 19 Praha 1,
Fax: +4202 2320861, e-mail: firstname.lastname@example.org
Additional and updated information may be obtained from http://www.fjfi.cvut.cz/ISRP-8.htm.
The Plutonium Futures--The Science conference will be held at La Fonda Hotel in Santa Fe, New Mexico, July 10-13, 2000. Conference participants will examine present knowledge of the chemical and physical properties of plutonium and other actinides in complex media and materials; discuss current and emerging science (chemistry, physics, materials science, nuclear science, and environmental effects) of plutonium and actinides relevant to enhancing global nuclear security; and promote the exchange of ideas. The scientific program includes invited plenary and keynote lectures followed by presentations of invited and contributed papers in oral and poster sessions. The plenary sessions will include participation by policy makers and elected officials as well as scientific leaders. English is the official language of the conference. The extended abstracts from the conference will be published. The conference will cover scientific topics in plutonium and actinide sciences including actinides in the environment and the science underlying plutonium disposition. Conference subtopics include:
If you are interested in Plutonium Futures--The Science and wish to receive the future announcements, including the Call for Papers, complete and submit the on-line Information Request Form (http://www.lanl.gov/orgs/nmt/nmtdo/PuConf2000/2krequest.html). You may also email or write to
Plutonium Futures--The Science
Los Alamos National Laboratory
Nuclear Materials Technology Division
P.O. Box 1663
Los Alamos, NM, USA 87545
Contact: Andria Liesse
Conference E-mail: Puconf2000@lanl.gov
Your attention is directed to the following events of interest.
Executive Conference on Nuclear Power Plant Decommissioning and Spent Fuel Management, June 27-30, 1999, Traverse City, Michigan, sponsored by the ANS. Contact: Ken Powers, Big Rock Point Restoration Project, 10269 U.S. 31 N., Charelvoix, MI 49720 (phone 616-547-8388, fax 616-547-8187).
Nuclear Systems Safety:Parts I and II, Part I, July 12-16 and Part II, July 19-23, 1999, a course offered by Massachusetts Institute of Technology. Contact: MIT Professional Inst., Room 8-201, Cambridge, MA 02139 (phone 617-253-2101, fax 617-253-8042, email email@example.com).
Criticality Safety Assessments Workshop, July 13-15, 1999, University of New Mexico. Contact: firstname.lastname@example.org or 505-277-8027.
20th Annual NCS Short Course, July 19-23, 1999, University of New Mexico. Contact: email@example.com or 505-277-8027.
Workshop of Managers in Nuclear Criticality Safety, July 27-29, 1999, University of New Mexico. Contact: firstname.lastname@example.org or 505-277-8027.
Computational Methods in Reactor Analysis and Shielding, Aug. 16-20, 1999, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300 (phone 423-974-2525, fax 423-974-0668).
Nuclear Criticality Safety, Aug. 16-20, 1999, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300 (phone 423-974-2525, fax 423-974-0668).
Monte Carlo Analysis, Aug. 16-20, 1999, Knoxville, Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996-2300 (phone 423-974-2525, fax 423-974-0668).
GLOBAL '99, Aug. 29-Sept. 3, 1999, Jackson, Wyoming. Contact: email@example.com; Argonne National Laboratory - West, P. O. Box 2528, Idaho Falls, Idaho, 83401-2528 (phone 208-533-7760, fax 208-533-7863, http://www.anlw.anl.gov/global99/)
3rd International Conference on Isotopes, Sept. 6-10, 1999, Vancouver, Canada. Contact: http://www.triumf.ca/3ici/.
Tenth International Symposium on Reactor Dosimetry, Sept. 12-17, 1999, in Osaka, Japan. Contact: Dr. David W. Vehar (phone 505-845-3414, fax 505-844-0798, email firstname.lastname@example.org) or Dr. Hamid Ait Abderrahim (phone 32-14-332277, fax 32-14-321529, email email@example.com).
MCNP Visual Editor training class, Sept. 13-16, 1999, Richland, Washington. Contact: Randy Schwarz, MS K8-34, P.O Box 999, Richland, WA 99352 (phone 509-372-4042, fax 509-372-6421, email firstname.lastname@example.org).
SCALE Criticality Course (KENO V.a), Sept. 13-17, 1999, INSTN, Saclay, France. Contact: Enrico Sartori, OECD/NEA Data Bank, Le Seine-Saint Germain, 12 boulevard des Iles, F- 92130 Issy-les-Moulineaux, France (phone 33-0-1-4524-1072; fax 33-0-1-4524-1110; email email@example.com).
6th International Conference on Nuclear Criticality Safety, September 20-24, 1999, Versailles, France. Contact: http://www.ipsn.fr/icnc99/.
5th Annual Workshop on Monte Carlo Simulation of Radiotherapy Treatment Sources using the OMEGA/BEAM Code System, Oct. 4-7, 1999, Ottawa, Canada. Contact: Blake Walters, Ionizing Radiation Standards, National Research Council of Canada, Ottawa, Canada, K1A 0R6. (phone 613-993-2715, fax 613-952-9865, e-mail firstname.lastname@example.org, url www.irs.inms.nrc.ca/inms/irs/BEAM/beamhome.html)
Half a Century of Radiation Shielding Research and Its Evolution into the Next Era (ICRS-9), Oct. 17-22, 1999, Tsukuba, Japan, sponsored and organized by the Japan Atomic Energy Research Institute. Contact: Yujiro Ikeda, Japan Atomic Energy Research Institute, Tokai Research Establishment, Neutron Science Research Center, Spallation Neutronics Laboratory, Tokai-mura, Naka-gun, Ibaraki-ken 319-11 Japan (phone 81-29-282-6074, fax 81-29-282-5709, email email@example.com, url http://icrs9.tokai.jaeri.go.jp).
Practical MCNP for the Health /Medical Physicist & Rad Engineer, Oct. 18-22, 1999, Los Alamos, NM. Contact: http://drambuie.lanl.gov/~esh4/mcnp.htm.
International Mechanical Engineering Congress and Exposition, Nov. 14-19, 1999, Nashville, Tennessee. Contact: Dr. John L. Boccio, Brookhaven National Laboratory, Building 197C, Upton, New York 11973-5000 (phone 516-344-7690; fax 516-344-5266, email firstname.lastname@example.org).
8th International Conference on Nuclear Engineering (ICONE-8), April 2-6, 2000, Baltimore, Maryland, sponsored by the American Society of Mechanical Engineers (ASME), Société Française de l'Energie Nucléaire (SFEN) and Japan Society of Mechanical Engineers (JSME). Contact: George Bockhold, U.S. Technical Chair, P.O. Box 116502, Gainesville, FL 32611-6502, USA; (phone 1+352-392-9722, fax 1+352-392-8656, email Submitemail@example.com, url http://www.icone-conf.org/icone8/).
Plutonium Futures--The Science, July 10-13, 2000, Santa Fe, New Mexico. Contact: Plutonium Futures--The Science, Los Alamos National Laboratory, Nuclear Materials Technology Division, P.O. Box 1663, MS E500, Los Alamos, NM, USA 87545 (phone 505-665-5981, fax 505-667-7966, email Puconf2000@lanl.gov).
Radiation Protection for our National Priorities: Medicine, the Environment, and the Legacy, Sept. 17-21, 2000, Spokane, Washington. Contact: Harvey Goldberg, ANS-EWS, P.O.Box 941, Richland, WA 99352 (email firstname.lastname@example.org