|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
| Let us always have in mind that every attempt in the history of the world to establish a loafer's
paradise has wound up in a dictator's hell-hole.--Harold E. Stassen|
Area Code Changes for RSICC
The area code for parts of East Tennessee is changing from 423 to 865 effective
November 1, 1999. The transition period will extend to April 24, 2000, during
which time both area codes can be used. This period should provide enough
time for the customer to make all necessary changes in modems, faxes,
automatic dialers, speed calling, pagers, and cellular phones for numbers dialed
within the Knoxville-Oak Ridge region.
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 www site for more information on these packages.
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
||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.
CHANGES TO THE COMPUTER CODE COLLECTION
Three changes were made to the computer code collection during the month. One new code system was
added, an existing code package was replaced with a newly frozen version, and
one code system was corrected.
Argonne National Laboratory, Argonne, Illinois, contributed a newly frozen
version of VENTURE-PC to overcome problem size constraints caused by binary record length limits
inherent to the Fortran 90 compiler. The need for long records is detected and avoided by sub-blocking
them. Also, the latest Lahey Fortran 95 compiler offers substantial speed gains on the newest
processors. The source code was updated to be compatible with either Fortran 90 or Fortran 95. The
VENTURE program solves the usual neutronics eigenvalue, adjoint, fixed source, and criticality search
problems. It treats up to three dimensions, maps power density, and does first-order perturbation
analysis at the macroscopic cross section level. The BURNER code solves the nuclide chain equations
to estimate the nuclide concentrations and burnup at the end of an exposure time or after a shutdown
period. The principle code modules included in the VENTURE-PC system are:
- VENTURE: Multigroup neutronics finite-difference diffusion theory
- BURNER: Exposure calculation for reactor core analysis
- Other modules within VENTURE-PC are:
- DVENTR: Venture input processor
- DCRSPR: Neutron cross section processor
- DUTLIN: Control file (CNTRL) input processor
- DCMACR: Citation format cross section input processor
- CRXSPR: Cross section processor
- DENMAN: Fuel repositioning module
The system runs on any PC having 386, 486, Pentium, Pentium Pro, Pentium II, Pentium III, or Celeron
processors. The resource needs are the same as those of the Windows operating system. At least 8 MB
is required to run and 24 MB to compile. Executables were created using both Lahey Fortran 90
Version 4.50h and Lahey/Fujitsu Fortran 95 Version 5.50e. They run in a DOS window on
Windows95/98/NT systems. The instruction set used on Pentium Pro processors and later is not
compatible with earlier processors. The package is transmitted on 3 DS/HD (1.44 MB) diskettes in
self-extracting compressed DOS files, which include source, executable, sample input and output files.
References: EGG-2582, University of Cincinnati (January 1990) and Argonne National Lab memo (8
April 1997). Fortran 90 or Fortran 95 with Fortran 77 extensions; PC386, PC486, PC586, & PC686
Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a corrected
version of this code system for multilevel R-matrix fits to neutron data using
Bayes' equations. This interim release designated SAMMY-M2a is nearly
identical to SAMMY-M2 released in February of 1999. The interim release
corrects bugs found in the derivatives of capture and fission cross sections when
multiple-scattering is included in the calculation. SAMMY is used for analyses
of neutron-induced cross section data in the resolved resonance region, with new options permitting
analysis of data in the unresolved resonance region as well. In the resolved region, theoretical cross
sections are generated using the Reich-Moore approximation to R-matrix theory. Sophisticated models
are used to describe the experimental situation: data-reduction parameters (e.g. normalization,
background, or sample thickness) are included. Several options are included for both Doppler and
resolution broadening. Self-shielding and single-scattering corrections are included for analysis of
capture cross sections. Bayes' Theorem (generalized least squares) is used to find the "best fit" values of
parameters and the associated covariance matrix.
SAMMY-M2a runs on the IBM RS/6000, on DEC Alpha computers under both Open/VMS and OSF1
operating systems, and on the PC using the RedHat LINUX operating system. The system was tested
under AIX 4.2.1 using the XLF 18.104.22.168 Fortran compiler. The Linux system was installed under RedHat
Vers. 5.1 with GNU gcc Version 22.214.171.124 and g77 Vers. 0.5.21. The package is transmitted on
CD-ROM as a tar file which contains source codes, scripts, and test cases. Users who have the previous
version, SAMMY-M2, released in February 1999 (P00158IRISC04), may contact RSICC to request the
corrected source and output files if they prefer updating their existing system rather than obtaining the
entire package again. References: Informal Notes and ORNL/TM-9179/R4 (December 1998). Fortran
and C; DEC Alpha (Unix and VMS), IBM RS/6000, PC running Linux (P00158/IRISC/05).
Fluor Daniel Northwest, Richland, Washington, and the University of
Washington, Seattle, Washington, contributed this multigroup two-dimensional
(r,z) transient neutron diffusion simulator with thermal hydraulic and
computational fluid dynamics feedback for degraded-core geometry reactor
accident modeling. ATHENA_2D was written to simulate a hypothetical water
reflood of a highly-damaged light water reactor (such as the Three-Mile-Island
Unit-2 after meltdown with a packed debris bed near the center of the core) but with
insufficiently-borated reflood water. A recriticality transient may result because of the potentially more
reactive debris bed. The system solves the transient multigroup neutron diffusion equations in (r,z)
geometry. Executing in parallel with the transient neutronics is a single-phase computational fluid
dynamics (CFD) model.
A reactor lattice computer code, such as WIMS-E, is required for the creation of macroscopic cross
section libraries given pin-cell geometries. WIMS-E is a commercial product available from AEA
Technologies, England; it is not included on the ATHENA_2D distribution CD. ATHENA-2D runs on
either an IBM PC (Pentium-class) running Windows 95 or later, or Digital Equipment Corporation
Alpha workstation or Unix workstation. The IBM PC executable included on the distribution CD was
created using the Microsoft Fortran PowerStation 4.0 compiler. If color animations are desired of
results, procedure files are included on the distribution CD for the PV-Wave software from Visual
Numerics, Inc. However, this is not required to merely run ATHENA_2D. The package is transmitted
on CD-ROM as a self-extracting DOS file and as a compressed Unix tar file. References: Ph.D.
dissertation, UMI number: 9638022, University of Washington, (June 1996). Fortran 77; IBM PC, Sun,
DEC Alpha (P00431MNYCP00).
Several awards worth noting were presented during the Annual Meeting in Boston to members in the
area of radiation shielding, safety, and transport.
Thomas H. Row was awarded a Presidential Citation for his dedication and commitment to the
Society, particularly through his involvement with the Power Division. The citation reads in part, "His
tenure has been marked by extraordinary support to ANS meetings and programs, the steady expansion
of the annual Utility Working Conference, and many successful and exemplary special sessions,
including the 14 special sessions at this Boston Annual Meeting. As chair of the Publications Steering
Committee, he spearheaded Radwaste Magazine, and as a member of the Board of Directors for many
years, he was instrumental in many strategic initiatives and programs on behalf of ANS." Row is senior
staff assistant to the director, Oak Ridge National Laboratory, and has been a member of the ANS since
Harold L. Dodds was presented with the Arthur Holly Compton Award for outstanding contributions
in nuclear science and engineering education. Prof. Dodds, an ANS member since 1971, is department
head of the Nuclear Engineering Department at the University of Tennessee at Knoxville, Tennessee.
Rizwan Uddin received the Young Members Engineering Achievement Award in recognition of his
work "on the stability of two-phase flow and its chaotic dynamics, his innovative development of nodal
methods for thermal hydraulics, and his research on reactor homogenization for nodal diffusion
methods." Uddin is a nuclear engineering professor at the University of Illinois at Urbana-Champaign.
He has been a member of the ANS since 1988.
Fredric C. Olds, president, Energy Communications and ANS member since 1968, was recognized
with the Public Communications Award "For outstanding personal dedication and accomplishment
throughout his career in developing consistently top-quality documents that further the understanding of
nuclear science and technology and for public communication of noteworthy value to the nuclear
Three ANS Fellows were recognized during the 1999 ANS Annual Meeting in Boston in recognition of
"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, or outstanding efforts in the
areas of nuclear health and safety and regulation."
Bertrand Barré, director, Nuclear Reactor Division, Commissariat à l'Energie Atomique, France, for
"major technical and strategic leadership in light water reactor and fast breeder reactor development in
implementing the ambitious French nuclear power program and naval nuclear propulsion undertaking;
for his personal commitment in furthering extensively international nuclear cooperation with the United
States, European countries, Russia, and Japan; and for championing the benefits of nuclear energy in
France and abroad."
Ivan Catton, University of California-Los Angeles, for "leading the way in research on severe-accident
phenomena, notably on debris bed dry out. He has also made seminal contributions to best-estimate
accident analysis codes that have led to their acceptance in reactor regulation."
Kenneth D. Lewis, Oak Ridge National Laboratory, for "outstanding performance and contributions as
a professional nuclear engineer in several key U. S. Department of Energy projects directly impacting
national and world security, nuclear nonproliferation, and public health and safety."
Robert F. Mozley, professor emeritus of physics at Stanford University, died in May 1999 at the age of
82. A graduate of Harvard, he worked on radar technology during World War II. He received a
doctorate at the University of California at Berkeley and took part in the construction of the world's first
proton linear accelerator. He taught at Princeton and Stanford and retired in 1987. His work includes
the publication of two books: Uranium Enrichment and Other Technical Problems Relating to Nuclear
Weapons Proliferation and Politics and Technology of Nuclear Proliferation.
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 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.
SCALE KENO V.a Criticality Safety Course, November 1-5
The SCALE staff at Oak Ridge National Laboratory (ORNL) is offering a KENO V.a Criticality Safety
Training Course November 1-5, 1999. The 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
- The course will emphasize hands-on experience solving practical problems on PCs.
- No prior experience in the use of SCALE is required to attend.
- There will be workgroups of two persons each.
- The new KEN03D geometry visualization tool and the new CSPAN input GUI will be used.
The registration fee is $1,800. A copy of the SCALE software and manual on CD may be obtained for
an additional fee of $250. Classes are cosponsored by RSICC. Additional information and registration
form is available on the Web (http://www.cad.ornl.gov/cad_nea/text/trcourse.html). The registration fee
must be paid by check or travelers check. We apologize that we are NOT able to accept credit card
Class size is limited and courses are subject to cancellation if minimum enrollment is not obtained one
month prior to the course. Please mail form and registration fee payment to:
SCALE Training Course
c/o Kay Lichtenwalter
Oak Ridge National Laboratory
P.O. Box 2008
Oak Ridge, Tennessee 37831-6370
An international workshop on Utilization of Nuclear Power in Oceans, N'ocean 2000, will be held
February 21-24, 2000, Tokyo, Japan. It is sponsored and organized by Ship Research Institute,
Ministry of Transport. Economical, environmental, and scientific effects, as well as benefits from the
utilization of nuclear energy with respect to the ocean, will be discussed with international scientists,
engineers and others who are interested in these topics. In order to fully respect the workshop mission,
papers should concentrate on peaceful application of nuclear energy in oceans. The workshop is
expected to lead to international joint research. Topics will include:
- Marine Reactor
- Nuclear-Powered Ice Breaker
- Nuclear-Powered Deep-Sea Research Ship
- Nuclear-Powered High-Speed Carrier
- Concepts of Future Nuclear Ship
- Safety of Nuclear Ship
- Economy of Nuclear Ship
- Nuclear Ship Engineering Simulation System
- Barge for Nuclear Power Production, Heat Generation and Desalination
- Radioactive Materials Transport Ship
- Offshore/Undersea Nuclear Power Plant
- Radioactive Materials Storage Facility in Ocean
- Economical, Environmental and Scientific Effects
- Laws/Regulations Regarding to Nuclear Ship
- Free Navigation System of Nuclear Ship
- International Cooperation
Further details are available from
Nobuteru Nariyama (Conference Secretary)
Nuclear Technology Division
Ship Research Institute, Ministry of Transport
6-38-1, Shinkawa, Mitaka, Tokyo 181-0004, Japan
The Eighth International Conference on Nuclear Engineering, ICONE-8, will be held at the Hyatt
Regency Hotel, Baltimore, Maryland, USA, April 2-6, 2000. It is sponsored by the American Society
of Mechanical Engineers (ASME), Société Française de I'Energie Nucléaire (SFEN), and the Japan
Society of Mechanical Engineers (JSME). ICONE is a comprehensive international conference on
nuclear engineering which features peer-reviewed papers in 10 technical tracks. Further information may
be obtained from George Bockhold, US Technical Chair, c/o PO Box 116502, Gainesville, FL
32611-6502, USA (phone 352-392-9722, fax 352-392-8656, url http://www.icone-conf.org).
International Workshop on Neutron Field Spectrometry in
Science, Technology and Radiation Protection
The International Workshop on Neutron Field Spectrometry in Science, Technology and Radiation
Protection, will be held June 5-8, 2000, in Pisa, Italy. For more than 50 years neutron spectrometry has
been used in basic nuclear physics research, in fission and fusion nuclear technology, in radiation
protection and radiation therapy, and in various other applications. The dynamic range of neutron
energies and fluence rates which need to be covered in these applications has increased, and
considerable progress has been achieved in recent years both by improving conventional techniques as
well as by developing new detector systems and analyzing procedures.
The objectives of this workshop are:
- to review the state of the art in neutron spectrometry,
- to report on recent developments and improvements, and
- to demonstrate the manifold applications.
Experts dealing with neutron spectrometry in nuclear physics research, plasma diagnostics, radiation
protection and radiation therapy dosimetry, and other fields are invited to participate and to share their
experience. The aim of this workshop is to discuss all techniques used to specify spectral neutron
fluences (energy and angle dependent). Photon spectrometry in mixed neutron/photon fields is included
in the list of topics. Neutron time-of-flight spectrometry at pulsed neutron sources and in-core reactor
metrology techniques will not be dealt with because these applications are regularly discussed at other
conferences. The proceedings will be published as a special volume of Nuclear Instruments and
Methods A. Additional information may be found at http://www.ptb.de/english/org/6/neuspec/intro.htm
PTB, dep. 6.4 `Neutron Metrology'
D-38116 Braunschweig, Germany
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 organized 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 by leading experts in the field 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 Musilek
Czech Technical University in Prague
Faculty of Nuclear Sciences and Physical Engineering
Bøehová 7, 115 19 Praha 1, Czech Republic
fax +4202 2320861, email rnusiIek@br.fjfi.cvut.cz
Additional 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 will include 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:
- 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
Los Alamos, NM 87545 USA
Contact: Andria Liesse
Conference E-mail: Puconf2000@lanl.gov
Radiation Protection for Our National Priorities:
Medicine, the Environment, and the Legacy
The Radiation Protection and Shielding Division of the American Nuclear Society invites you to attend
its Year 2000 (RPS2000) topical meeting to be held in Spokane, Washington, September 17-21, 2000.
This meeting will cover issues associated with radiation protection and health physics. Paper summaries
are due December 1, 1999. RPS2000 is being organized in conjunction with the Columbia Chapter of
the Health Physics Society. In addition to the technical paper sessions there will be a full range of
classes and seminars for HPS certification credit. Spokane River Park, the site of the Expo '74 world's
fair, has been developed into an outstanding convention center with activities for everyone, from fishing
to opera, within steps of the hotel. Additional information may be obtained at
The 10th International Conference on Emerging Nuclear Energy Systems (ICENES-2000) will be held
September 25-28, 2000, Petten, The Netherlands. The main objective of the ICENES conference is to
discuss, on a broad international basis, the state of various advanced and non-conventional concepts for
nuclear energy production. The ICENES conference is held biennially. Earlier conferences were held in
Graz, Lausanne, Helsinki, Madrid, Karlsruhe, Monterey, Chiba, Obninsk and Tel-Aviv, respectively.
Both research scientists and practicing engineers are invited to attend and participate in this conference.
The meeting organization will provide ample opportunity for participants to interact in formal sessions
and informal discussions. A panel discussion "Fitting Future Nuclear Energy Systems in a Liberalized
Energy Market" is also planned. Papers can be submitted on the following topics:
- Advanced fission systems
- Accelerator driven systems
- Advanced fusion concepts
- Fusion/Fission hybrids
- Laser systems for nuclear applications
- Space nuclear power
- Exotic nuclear concepts
Deadline for abstracts is December 20, 1999. Instructions for submitting papers are available at
http://www.nrg-nl.com/congres/icenes/ or contact:
Mrs. Dr. A.I. van Heek, Organising Chairman
Phone. (+31) 224 56 4507
Mrs. M. Hofman, Meeting Secretariat
Phone: (+31) 224 56 4193
The address for both is:
P.O. Box 25
1755 ZG Petten
Fax: (+31) 224 56 3490
ANS 14th Topical Meeting on the Technology of Fusion Energy
The 2000 American Nuclear Society 14th Topical Meeting on the Technology of Fusion Energy will be
held at the Olympia Park Hotel in Park City, Utah, October 15-19, 2000. It will be an international
forum for presentation and discussion of scientific and technical information covering all aspects of
fusion technology, including the most recent developments in both inertial and magnetic confinement
fusion energy. The meeting website provides detailed information on abstract submittal, meeting
registration, lodging, and activities. Questions should be sent to Jon Carmack at firstname.lastname@example.org (phone
208-526-7576 , fax 208-526-0528). The web site can be found at: http://ev2.inel.gov/ParkCity/.
Fourth International Workshop on Dosimetry
for Radiation Processing
The American Society for Testing and Materials (ASTM) Subcommittee E10.01 Dosimetry for
Radiation Processing has announced the Fourth International Workshop on Dosimetry for Radiation
Processing to be held at the Bahia Resort Hotel in San Diego, California, October 22-27, 2000. The
symposium will be patterned on the three previous workshops in 1989 (Ste-Adèle, Québec), 1991
(University of Maryland), and 1995 (Ste-Adèle, Québec). The symposium will include a few
presentations by invited speakers, but the main emphasis will be on small informal "round table"
workshop sessions and hands-on practical exercises in which all attendees are expected to participate.
An informal poster session will be combined with an equipment and technology demonstration session.
Registration is limited to a maximum of 160 technical participants on a "first-register-first-serve" basis.
The scope of this workshop covers all aspects of dosimetry for radiation processing, including the
processing of medical products, pharmaceuticals, foods, inks, packaging, and polymers. The objective is
to improve the quality of dosimetry through a better understanding of dosimetry principles, calibration
techniques, dosimetry applications (e.g. dose mapping and routine monitoring), and the determination
and understanding of dosimetry uncertainties, all based on standards published by ASTM Subcommittee
E10.01. Other standards on process control and quality systems that may have an impact on dosimetry
practices will also be covered. The presentations and workshop sessions are expected to cover the
- Dosimetry Principles
- Selection and Calibration of Dosimetry Systems
- Dose Mapping (Gamma)
- Dose Mapping (Electron Beam and X-Ray-Bremsstrahlung)
- Influence Factors (including environmental effects) on Dosimeter Response
- Uncertainties in Absorbed Dose Measurements
- Dosimetry in Industrial Applications
- Quality Assurance and Regulatory Aspects of Dosimetry
- Mathematical Methods for Calculating Absorbed Dose in Radiation Processing Applications
A registration form is available at http://www.astm.org/COMMIT/e10workshop.htm. Additional
information may be obtained from
Dr. Harry Farrar IV, Chairman
ASTM Committee E-10
18 Flintlock Lane
Bell Canyon, CA 91307-1127 USA
Telephone: +1 (818) 340-1227
Fax: +1 (818) 340-2132
Fifth Radiation Physics Conference
The Atomic Energy Authority of Egypt is sponsoring the Fifth Radiation Physics Conference--Atomic
Energy, Radiation Protection, Challenges and Strategies. The conference will be held November 5-9,
2000, in Cairo at a site to be announced. The organizing body solicits your work in the following areas:
- Radiation sources
- Radiation effects
- Radiation detection and measurements
- Radiation dosimetry
- Radiation shielding
- Radiation protection and safety
- Applied radiation physics
- Radiation biophysics
- Medical radiation physics
- Environmental radioactivity and earth sciences
- Special topics to include:
- Atomic energy, radiation protection--challenges and strategies
- Radiation exposure of air crew
- Application of nuclear techniques (detection of land mines, etc.)
- Global air and aquatic radioactive monitoring
Further information about the conference and the proper submission of your work may be obtained from
Prof. Mohammad A. Gomaa, Atomic Energy Authority, 3 Ahmad Al-Zomor St., Alzohour District,
Nasr City, Children Village Post Office, Postal Code 11787, Cairo, Egypt (fax 00202-287603, email
REAC/TS Radiation-Accident Courses
The Radiation Emergency Assistance Center/Training Site (REAC/TS) in Oak Ridge, Tennessee, is
part of the Medical Sciences Division of the Oak Ridge Institute for Science and Education established
by the U.S. Department of Energy to undertake national and international programs in science and
engineering education, training and management systems, energy and environment systems, and medical
sciences. The REAC/TS staff offers several courses in the handling of radiation accidents. A brief
description of the courses follows.
Handling of Radiation Accidents by Emergency Personnel is a 3½-day course designed for emergency
room nurses and physicians who may need to administer initial hospital aid to a radiation accident
victim. Lectures, complemented by demonstrations, laboratory exercises, and a simulated radiation
accident drill, will emphasize the handling of the victim. Discussions include the fundamentals of
radiation, detection and measurement, prevention of the spread of contamination, dose reduction for the
victim and attending personnel, and the role of the medical physicist in caring for contaminated accident
Health Physics in Radiation Accidents is a 4½-day course for health physicists and radiation protection
technologists who may be called upon to respond to accidents involving radioactive materials and injury
to personnel. The major topics are radiological emergency procedures and the role of the health
physicist in a medical environment.
Medical Planning and Care in Radiation Accidents, a 4½-day course designed for physicians, presents
an advanced level of information on diagnosis and treatment of acute local and total body radiation
exposure, internal and external contamination, combined injuries, and multi-casualty incidents involving
The course dates and registration information may be obtained from L. Gail Mack, Registrar,
REAC/TS, MS-39, Oak Ridge Inst. for Science & Education, P.O. Box 117, Oak Ridge, TN
37831-0117 (phone 423-576-3132, email email@example.com).
Your attention is directed to the following events of interest.
SCALE KENO V.a Criticality Safety Course, Nov. 1-5, 1999, Oak Ridge, TN. Contact: Kay
Lichtenwalter, Oak Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6370 (phone
423-574-9213, fax 423-574-3513, email firstname.lastname@example.org).
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 email@example.com).
Utilization of Nuclear Power in Oceans, N'ocean 2000, Feb. 21-24, 2000, Tokyo, Japan. Contact:
Nobuteru Nariyama (Conference Secretary), Nuclear Technology Division, Ship Research Institute,
Ministry of Transport, 6-38-1, Shinkawa, Mitaka, Tokyo 181-0004, Japan (phone +81-422-41-3138,
fax +81-422-41-3136, email firstname.lastname@example.org, url www.srimot.go.jp/ncl/ws/index.html).
Radiation Transport Calculations using the EGSnrc Monte Carlo System, Feb. 29-Mar. 2, 2000,
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, email
email@example.com, url www.irs.inms.nrc.ca/inms/irs/papers/egsnrc/brochure.html).
Eighth International Conference on Nuclear Engineering, ICONE-8, April 2-6, 2000, Baltimore,
Maryland, USA. Contact: George Bockhold, US Technical Chair, c/o PO Box 116502, Gainesville, FL
32611-6502, USA (phone 352-392-9722, fax 352-392-8656, email Submitfirstname.lastname@example.org, url
International Workshop on Neutron Field Spectrometry in Science, Technology and Radiation
Protection, June 5-8, 2000, Pisa, Italy. Contact Horst Klein, PTB, dep. 6.4 `Neutron Metrology',
Bundesallee 100, D-38116 Braunschweig, Germany (phone 49-531-592-6400, fax 49-531-592-7205,
8th International Symposium on Radiation Physics (ISRP-8), June 5-9, 2000, Prague, the Czech
Republic. 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, email email@example.com).
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
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).
ICENES 2000, The 10th International Conference on Emerging Nuclear Energy Systems, Sept. 25-28,
2000, Petten, The Netherlands. Contact: Mrs. M. Hofman, Meeting Secretariat, NRG, P.O. Box 25,
1755 ZG Petten, The Netherlands (phone +31-224-56-4193, fax +31-224-56-3490, email
email@example.com, url http://www.nrg-nl.com/congres/icenes/).
2000 American Nuclear Society 14th Topical Meeting on the Technology of Fusion Energy, Oct.
15-19, 2000, Park City, Utah. Contact: url http://www.ambinet.com/ans/rps2000.htm.
4th International Workshop on Dosimetry for Radiation Processing, Oct. 22-27, 2000, San Diego,
California. Contact: Dr. Harry Farrar IV, ASTM Committee E-10, 18 Flintlock Lane, Bell Canyon, CA
91307-1127 (phone 818-340-1227, fax 818-340-2132, email firstname.lastname@example.org).
5th Radiation Physics Conference--Atomic Energy, Radiation Protection, Challenges and Strategies ,
Nov. 5-9, 2000, Cairo, Egypt. Contact: Prof. Mohammad A. Gomaa, Atomic Energy Authority, 3
Ahmad Al-Zomor St., Alzohour District,
Nasr City, Children Village Post Office, Postal Code 11787, Cairo, Egypt (fax 00202-287603, email
AUGUST ACCESSION OF LITERATURE
The following literature cited 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 shielding
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.
Radiation Shielding Literature
KEK Preprint 99-2 . . . Results of a Beam Test of the Combined Lead Glass and PWO Cells Detector
for the COMPASS Electromagnetic Calorimeter. . . . ; Dolgopolov, A.V.; Donskov, S.V.; Fujii, Y.;
Inaba, S.; Lednev, A.A.; Nakagawa, T.; Prokosh . . . April 1999 . . . Institute for High Energy Physics,
Moscow, Russia; KEK, Ibaraki, Japan; Miyazaki University, Miyazaki, Japan; Yamagata University,
Yamagata, Japan; Tohoku University, Sendai, Japan.. . . To be published in Nucl. Instr. Method.
KEK Preprint 99-33 . . . Development of a Self-TOF Detector for High-Energy Neutron
Spectrometry. . . . Sasaki, M.; Nakao, M.; Shibata, T.; Nakao, N.; Nakamura, T. . . . June 1999 . . .
Tohoku University, Sendai, Japan; High Energy Accelerator Research Organization, Ibaraki, Japan.
Health Phys., 77, 9-15 . . . Radiation Protection Information: Can You Trust the Government's Risks
or Risk the Government's Trust?: 1997 G. William Morgan Lecture. . . . Ziemer, P.L. . . . July 1999 . . .
Purdue University, West Lafayette, Indiana.
Health Phys., 77, 33-36 . . . Medical Radiation Exposures for Diagnostic Radiology in Malaysia. . . .
Ng, K-H.; Abdullah, B.J.J.; Sivalingam, S. . . . July 1999 . . . University of Malaya Medical Center,
Kuala Lumpur, Malaysia; Kuala Lumpur Hospital, Kuala Lumpur, Malaysia.
Health Phys., 77, 76-88 . . . A Non-Destructive Method to Determine the Depth of Radionuclides in
Materials In-Situ. . . . Naessens, E.P.; Xu, X.G. . . . July 1999 . . . Rensselaer Polytechnic Institute,
Troy, New York.
Nucl. Sci. Eng., 132, 155-180 . . . On the Propagation of Rays in Discrete Ordinates. . . . Mathews,
K.A. . . . June 1999 . . . Air Force Institute of Technology, Wright-Patterson Air Force Base, Ohio.
Nucl. Sci. Eng., 132, 181-193 . . . A Variational Synthesis Nodal Discrete Ordinates Method. . . .
Favorite, J.A.; Stacey, W.M. . . . June 1999 . . . Georgia Institute of Technology, Atlanta, Georgia.
Nucl. Sci. Eng., 132, 194-202 . . . Acceleration of the Analytic Function Expansion Nodal Method by
Two-Factor Two-Node Nonlinear Iteration. . . . Kap Suk Moon, Nam Zin Cho, Jae Man Noh, Ser Gi
Hong . . . June 1999 . . . Korea Advanced Institute of Science and Technology, Taejon, Korea.
Nucl. Sci. Eng., 132, 203-216 . . . A New Approximating Formula for Calculating Gamma-Ray
Buildup Factors in Multilayer Shields. . . . Assad, A.; Chiron, M.; Nimal, J.C.; Diop, C.M. . . . June
1999 . . . CEA-DRN/DMT/SERMA/LEPP, Gif-sur-Yvette Cedex, France.
Nucl. Sci. Eng., 132, 217-258 . . . Derivations of the Solid Angle Subtended at a Point by First- and
Second-Order Surfaces and Volumes as a Function of Elliptic Integrals. . . . Cramer, S.N. . . . June
1999 . . . Oak Ridge National Laboratory, Oak Ridge, Tennessee.