Radiation Safety Information Computational Center
	Oak Ridge National Laboratory Post Office Box 2008 Oak Ridge, Tennessee 37831-6362 Managed by Lockheed Martin Energy Research Corp. for the U.S. Department of Energy under contract DE-AC05-96OR22464 Phone No. 423-574-6176 FAX 423-574-6182 Internet: PDC@ORNL.GOV WWW: http://www-rsicc.ornl.gov/rsic.html
No. 413	May 1999
When Spring unlocks the flowers to paint the laughing soil.--Reginald Heber from Seventh Sunday after Trinity.

Year 2000

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.

NRC Codes Made Available

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.

PSR-383/KFIX (3D)
PSR-389/COMPBRN3
PSR-392/OCA-P
PSR-393/COMMIX-1C
PSR-406/FRANTIC3
PSR-407/IMPORTANCE
PSR-411/MORECA
PSR-412/CEMENT
PSR-413/SFHA
PSR-416/RELAP4/MOD7/101
CCC-668/RABFIN,PARTS
CCC-671/CHNSED
CCC-673/LINSED

CHANGES TO THE COMPUTER CODE COLLECTION

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).

CONFERENCES, COURSES, SYMPOSIA

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 raf@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.

MCNP Courses

Advanced Class-London

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:

• Macrobodies
• Unresolved resonance treatment
• Perturbation enhancement
• Alpha eigenvalues
• Cumulative tallies

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, sartori@nea.fr.

Judi Briesmeister
Code Integration Group (X-CI), Los Alamos National Laboratory
jfb@lanl.gov

Introduction to MCNP Short Course

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 elleman@ncsu.edu (please copy to Dr. R. P. Gardner; e-mail gardner@ncsu.edu). 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
phone 919-515-3620
fax 919-515-5115
It is possible to register on-line at www.quantumres.com.

Practical MCNP for the Health /Medical Physicist & Rad Engineer

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

MCNP and Visual Editor Training Course

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 randy.schwarz@pnl.gov).

SCALE Training Course Schedule for 1999

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.

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,  x4s@ornl.gov , 423-574-9213.

SCALE Shielding and Source Terms Course

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).

SCALE KENO VI Criticality Course

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.

SCALE KENO V.a Criticality Course

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.

International Conference on Future Nuclear
Systems Nuclear Technology--Bridging the Millennia

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 todd.allen@anl.gov). Additional information may also be found at url http://www.anlw.anl.gov/global99/).

Third International Conference on Isotopes

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 ici@triumf.ca, url http://www.triumf.ca/3ici/).

Tenth International Symposium on Reactor Dosimetry

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:

ICNC '99

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/.

IRRMA '99

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.
Telephone 919-515-2302
Fax 919-515-5115
E-mail elleman@eos.ncsu.edu

"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 ikeda@fnshp.tokai.jaeri. 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:

• Plant Operations and Maintenance
• Major Component Reliability and Materials Issues
• Structural Integrity, Dynamic Behavior and Seismic Design
• License Renewal, Life Extension, Decommissioning and Decontamination
• Safety, Reliability and Plant Evaluations
• Next Generation Systems
• Thermal Hydraulics
• Basic Nuclear Engineering Advances
• Nuclear Fuel Cycle, Spent Fuel and Radwaste Management
• Codes, Standard and Regulatory Issues

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 Submit-icone8@icone-conf.org, url http://www.icone-conf.org/icone8/).

ISRP-8

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:

• Fundamental processes in radiation physics
• Radiation sources and detectors
• Radiation in physical and material sciences
• Radiation in medicine and biology
• Radiation in space, earth and environmental sciences
• Radiation in archaeometry and the history of art
• Radiation technologies and industrial applications

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,
Czech Republic
Fax: +4202 2320861, e-mail: musilek@br.fjfi.cvut.cz

Additional and updated information may be obtained from http://www.fjfi.cvut.cz/ISRP-8.htm.

Plutonium Futures--The Science

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:

• Separations
• Matrix interactions
• Materials compatibility
• Plutonium metallurgy
• Detection and analysis
• Environmental and biosphere chemistry
• Nuclear fuels
• Novel plutonium/actinide compounds and complexes

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
MS E500
Los Alamos, NM, USA 87545

Contact: Andria Liesse
Telephone: 505-665-5981
Conference E-mail: Puconf2000@lanl.gov
Fax: 505-667-7966

Calendar

Your attention is directed to the following events of interest.

June 1999

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).

July 1999

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 professional-institute@mit.edu).

Criticality Safety Assessments Workshop, July 13-15, 1999, University of New Mexico. Contact: busch@unm.edu or 505-277-8027.

20th Annual NCS Short Course, July 19-23, 1999, University of New Mexico. Contact: busch@unm.edu or 505-277-8027.

Workshop of Managers in Nuclear Criticality Safety, July 27-29, 1999, University of New Mexico. Contact: busch@unm.edu or 505-277-8027.

August 1999

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: todd.allen@anl.gov; 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/)

September 1999

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 dwvehar@sandia.gov) or Dr. Hamid Ait Abderrahim (phone 32-14-332277, fax 32-14-321529, email haitabde@sckcen.be).

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 randy.schwarz@pnl.gov).

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 sartori@nea.fr).

6th International Conference on Nuclear Criticality Safety, September 20-24, 1999, Versailles, France. Contact: http://www.ipsn.fr/icnc99/.

October 1999

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 bwalters@irs.phy.nrc.ca, 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 ikeda@fnshp.tokai.jaeri.go.jp, 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.

November 1999

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 boccio@bnl.gov).