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. 416 August 1999
We would rather have one man or woman working with us than three merely
working for us.--J. Dabney Day

RSICC Hosts DOE Fellows

The RSICC staff had the pleasure of hosting two guests during the summer. All was not fun and games since they certainly participated in our code/data packaging activities.

Andrew Jones came to the center under the Historically Black Colleges and Universities Faculty Research Program administered by the Oak Ridge Institute for Science and Education through a cooperative agreement between the U. S. Department of Energy and the U.S. Nuclear Regulatory Commission. While he was here, Dr. Jones tested and compiled information on software programs that have significant impacts on nuclear regulatory specifications. Dr. Jones received his Ph.D. in Applied Mathematics from Brown University. He is going on to a professorship at Morehouse College in Atlanta. B. J. Marshall, a Nuclear Engineering student at the University of Missouri at Rolla, came to us under the Energy Research Undergraduate Laboratory Fellowships (ERULF) program. He worked on SINBAD benchmark updates and computational verification of YAYOI, a Japanese addition. Three new compilations were added from the JASPER experimental program here at ORNL this summer. They included the radial shield, axial shield, and in-vessel fuel storage measurements. Additionally, B.J.'s work on a new software update to the NRC program HABIT was completed and will be released pending QA testing later this fall.

RSICC sends thanks to our guest scholars for their concerted efforts and help these past few months. There are many opportunities for cooperative programs between the laboratory and business and educational Interests. Check the website at http://www.ornl.gov/ornlhome/work_with_us.htm for additional information.

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.
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.

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.



One change was made to the computer code collection during the month. One code system was corrected

North Carolina State University, Raleigh, North Carolina, announced a correction for a bug in the hexagonal solver of NESTLE 5.02. The RSICC master was updated. Users who already have the package may make the correction themselves. Details are available on the RSICC web site by clicking on Software then Updates and Announcements or go to url http://www-rsicc.ornl.gov/ANNOUNCE.html#Announcements.

NESTLE solves the few-group neutron diffusion equation utilizing the Nodal Expansion Method (NEM). The NESTLE code can solve the eigenvalue (criticality), eigenvalue adjoint, external fixed-source steady-state, and external fixed-source or eigenvalue initiated transient problems. NESTLE runs on Unix workstation with at least 16 megabytes of memory and has been tested on the IBM RS/6000, HP9000/700, DEC5000, and SUN platforms. A Fortran 77 compiler is required. NESTLE has run under these operating systems: AIX, HP-UX, ULTRIX, and SUN Solaris. The package is transmitted on one diskette written in tar format. References: Informal Report (August 1996). Unix Workstations; Fortran 77 (C00641MNYWS02).


One change was made to the data library collection during the month. The documentation for an existing data library was updated.

Oak Ridge National Laboratory, Oak Ridge, Tennessee, updated the documentation for this package. BUGLE-96 is a 47 neutron, 20 gamma-ray group cross section library derived from ENDF/B-VI.3 for LWR shielding and pressure vessel dosimetry applications. Initially the BUGLE-93 report which documented development of multigroup data derived from Release 2 of ENDF/B-VI was distributed with BUGLE-96. The revised report documents the BUGLE-96 data library, which is based on Release 3 of ENDF/B-VI reference data and employs self-shielding procedures different from BUGLE-93. Users may request a hard copy or download the electronic PDF file from RSICC's web site. No change was made to the data. Reference: NUREG/CR-6214, Revision 1, ORNL-6795/R1. All computers (D00185ALLCP00).


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.

SAMMY Training Course Scheduled for September 1999

Two ORNL staff members, N. M. Larson and L. C. Leal, will be presenting a workshop covering the SAMMY code, used for analysis of neutron-related data in the resolved and unresolved resonance region. The workshop, sponsored by the OECD/NEA Data Bank, will take place in NEA, Issy-les-Moulineaux, near Paris, France, from September 27 to October 1, 1999.

The workshop is intended for those who are interested in the theory of neutron cross sections in the resonance region (R-matrix formalism and approximations thereto), and in the use of the SAMMY code for analysis of experimental neutron-induced cross-section data (for extracting values and covariances for resonance parameters, to be reported in the evaluated data files). Topics include R-matrix theory, data-reduction effects, Doppler- and resolution-broadening, self-shielding and multiple-scattering corrections, the use of covariance information, techniques for performing detailed analyses, and many others.

The workshop will include several hands-on computer applications using the last released version of SAMMY (M2). Computer exercises will lead the participant through the various features of the code, beginning with simple examples and leading to realistic situations. Additional details, including registration information, are available on the web site http://www.nea.fr/html/dbdata/sammy99.htm.

N. M. Larson

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 generated.

The registration fee is $1,800 ($300 discount if you register by October 1). 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 payments. Course fees are refundable up to one month before each class. Foreign nationals must register by October 1.

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, Bldg. 6011, MS 6370
Oak Ridge, Tennessee 37831-6370
FAX : 423-574-3513
Email: x4s@ornl.gov
Phone: 423-574-9213

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. 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 http://www.quantumres.com/temps/irrma_registration.html.


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/temps/irrma.html or contact

Dr. T. S. Elleman
Nuclear Engineering Department, Box 7909
North Carolina State University
Raleigh, NC 27695-7909 USA
phone: 919-515-2302
fax: 919-515-5115
email: 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.

N'ocean 2000

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. This workshop aims to promote the utilization of nuclear power in oceans by offering information about nuclear-powered ice breakers, deep-sea research ships, high-speed carriers, radioactive materials transport ships, nuclear-power plants in oceans, other facilities concerned with oceans and the economical, environmental and scientific effects, and to seek further benefits from the utilization of nuclear energy by discussing 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
Tel: +81-422-41-3138
Fax: +81-422-41-3136
e-mail: nari@srimot.go.jp
url: http://www.srimot.go.jp/ncl/ws/index.html

ICONE-8 Call For Papers

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 sponsored by the American Society of Mechanical Engineers (ASME), Société Française de l'Energie Nucléaire (SFEN) and the Japan Society of Mechanical Engineers (JSME). Papers are invited for publication and presentation on 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:

Authors should submit a 400-word abstract with return address, phone, fax, and email information by September 15, 1999, for consideration.

Online: http://www.icone-conf.org/icone8/
E-Mail: Submit-icone8@icone-conf.org
Mail: George Bockhold, US Technical Chair, c/o PO Box 116502, Gainesville, FL 32611-6502, USA; Telephone: 1+352-392-9722; fax: 1+352-392-8656.

(Include your abstract with track number in one of the following formats: PC: MSWord, WordPerfect, postscript, pdf, or text file, MAC or UNIX: send TWO printed copies.)

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:

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 or 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
email: horst.klein@ptb.de


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 by leading experts in the field 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, 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 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:

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 87545 USA

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

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. Papers 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 http://www.ambinet.com/ans/rps2000.htm.

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. The web site can be found at: http://ev2.inel.gov/ParkCity/. Please plan to join us in Park City in October of 2000.

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 3-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 victims.

Health Physics in Radiation Accidents is a 4-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 4-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 ionizing radiation.

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 mackg@orau.gov).


Your attention is directed to the following events of interest.

September 1999

6th International Conference on Nuclear Criticality Safety, September 20-24, 1999, Versailles, France. Contact: Dominique Remacle, IPSN-DPEA, BP6, F-92265 Fontenay-aux-Roses - FRANCE (phone 33 1 46 54 71 46, fax 33 1 46 57 29 98, email dominique.remacle@ipsn.fr, url http://www.ipsn.fr/icnc99/).

Embedded Mini-Workshops on PENTRAN and A3MCNP, Sept. 26, 1999, Madrid, Spain, in conjunction with the M &C'99 International Conf., Sept. 27-30, 1999. Contact: Prof. Carol Ahnert at carol@din.upm.es or Prof. A. Haghighat at haghigha@gracie.psu.edu (phone 814-865-0039, fax 814-865-8499, url http://gracie.nuce.psu.edu/wshop99m/madrid99.html).

October 1999

4th Topical Meeting on Industrial Radiation and Radioisotope Measurement Applications IRRMA '99, Oct. 3-7, 1999, in Raleigh, North Carolina. Contact: Dr. Thomas S. Elleman, Department of Nuclear Engineering, North Carolina State University, Box 7909, Raleigh, NC 27695-7909 U.S.A. (phone 919-515-2302, fax 919-515-5115, email elleman@eos.ncsu.edu, url http://www.quantumres.com/temps/irrma.html).

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 http://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).

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).

February 2000

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 nari@srimot.go.jp, url http://www.srimot.go.jp/ncl/ws/index.html).

April 2000

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

June 2000

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 musilek@br.fjfi.cvut.cz).

July 2000

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).

September 2000

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 (url email finfrock@ambinet.com).

October 2000

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.


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

book . . . Nuclear and Radiological Safety, 1986-1998. . . . 1998 . . . IAEA, Vienna, Austria.

INDC(JPN)-184/U . . . Proceedings of the Specialists' Meeting on Delayed Neutron Nuclear Data, January 28-29, 1999, Jaeri, Tokai, Japan. . . . Jun-ichi KATAKURA (Ed.) . . . July 1999 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

Health Phys., 77, 135-141 . . . Probabilistic Approach to Derive Operational Intervention Levels for Nuclear Emergency Preparedness. . . . Lauritzen, Bent; Baverstam, Ulf . . . August 1999 . . . Riso National Laboratory, Roskilde, Denmark; Swedish Radiation Protection Institute, Stockholm, Sweden.

Health Phys., 77, 142-149 . . . Simple Model for the Reconstruction of Radionuclide Concentrations and Radiation Exposures Along the Techa River. . . . ; Vorobiova, M.I.; Degteva, M.O. . . . August 1999 . . . Urals Research Center for Radiation Medicine, Medgorodok, Chelybainsk, Russia.

Health Phys., 77, 192-195 . . . Examination Frequencies and Patient Doses from Computed Tomography Examinations in the Area of Athens, Greece. . . . Perris, A. Hourdakis, C.; Manetou, A.; Iordanou, I.; Lyra, M. . . . August 1999 . . . University of Athens, Areteion Hospital, Athens, Greece; Greek Atomic Energy Commission, Attiki, Greece; NMTS Hospital, Athens, Greece.

Health Phys., 77, 196-199 . . . Linear Attenuation Coefficients of Tissue-Equivalent Materials of Differing Compositions for Low Energy Photons. . . . Sharma, R.C.; Haridasan, T.K. . . . August 1999 . . . Bhabha Atomic Research Centre, Mumbai, India.

Health Phys., 77, 200-206 . . . Determination of Neutron Spectra in a Mox Plant for the Qualification of the BD-PN D Bubble Detector. . . . Olaerts, R.; Kockerols, P. Renard, A.; Rosenstock, W.; Koble, T.; Vanhavere, F. . . . August 1999 . . . Belgonucleaire, Dessel, Belgium and Brussels, Belgium; Fraunhofer-Int, Euskirchen, Germany, SCK/CEN Boeretang, Mol, Belgium.

Nucl. Technol., 127, 1-23 . . . Automatic Rapid Process for the Generation of Problem-Dependent SAS2H/ORIGEN-S Cross-Section Libraries. . . . Leal, L.C.; Hermann, O.W.; Bowman, S.M.; Parks, C.V. . . . July 1999 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

Nucl. Technol., 127, 88-101 . . . Dose Rate Measurements and Calculation of TN-12/2 Packages. . . . Taniuchi, H.; Matsuda, F. . . . July 1999 . . . Kobe Steel Ltd., Takasago, Japan; Transnuclear Ltd., Tokyo, Japan.

Nucl. Technol., 127, 113-122 . . . Theoretical Calculations of Proton Reaction Cross Sections in a Lead Target with Energy Ep (less than or equal to) 300 MeV. . . . Jinfeng Zhou; Qingbiao Shen; Ziuquan Sun . . . July 1999 . . . NorthWest University, Xian, China; China Institute of Atomic Energy, Beijing, China.

Nucl. Technol., 127, 123-140 . . . Uncertainty Analysis in Dupic Fuel-Cycle Cost Using a Probabilistic Simulation Method. . . . Ko, W.I.; Choi, J.W.; Lee, J.S.; Park, H.S.; Lee, K.J. . . . July 1999 . . . Korea Atomic Energy Research Institute, Taejon, Korea; Korea Advanced Institute of Science and Technology, Taejon, Korea.

J. Radiat. Res. Radiat. Prot., 16, 213-217 . . . Measuring Exposure and Calculating Dose of the Low Energy X-Ray. . . . Jin Tao; Dai Huiyin . . . November 1998 . . . Xinjiang Institute of Physics, Urumqi, China; Communication Institute of Air Force, Xi'an, China.

Radiat. Prot., 19, 1-7 . . . Development of the Practical Application of the Recommendations of the International Commission on Radiological Protection. . . . Dunster, H.J. . . . January 1999 . . . In Chinese, no English abstract.

Radiat. Prot., 19, 8-11 . . . Work of ICRP Committee 3: Radiation Protection in Medicine. . . . Harding, L.K.; Mettler, F.A. . . . January 1999 . . . In Chinese, no English abstract.

Radiat. Prot., 19, 12-22 . . . Dosimetric and Biokinetic Models of the ICRP for the Assessment of Internal Doses from Radionuclides. . . . ; Kaul, A. . . . January 1999 . . . In Chinese, no English abstract.

Radiat. Prot., 19, 23-29 . . . The Scientific Base of ICRP Recommendations, Is It Changing? Can We Strengthen It? . . . Sinclair, W.K. . . . January 1999 . . . In Chinese, no English abstract.

Radiat. Prot., 19, 30-36 . . . ICRP Commmittee 4: More Recent Activities. . . . Winkler, B.C. . . . January 1999 . . . In Chinese, no English abstract.

Radiat. Prot., 19, 37-42 . . . ICRP Recommendations: Early Advice, Publication 60, and Later Guidance. . . . Valentin, J. . . . January 1999 . . . In Chinese, no English abstract.

Radiat. Prot., 19, 43-57 . . . Calculation of Calibration Coefficients for In-Situ HPGe Y Spectrometers Using Monte Carlo Methods. . . . Xiao Xuefu . . . January 1999 . . . China Institute of Atomic Energy, Beijing, China. . . . . . . In Chinese.

Radiat. Prot., 19, 58-62 . . . Monte Carlo Calculation for the Chord Length Distributions of Particles Emitted from Disk-Shaped Source Incident Into Cylinder Sensitive Body. . . . Su Youwu; Zhu Lianfang; Jiao Dunpang; Chen Xuebing; Li Xuekuan; He Yusheng . . . January 1999 . . . Institute of Modern Physics, Lanzhou, China. . . . . . . In Chinese.

Radiat. Prot., 19, 71-76 . . . The Preliminary Investigation of 110mAg In Environmental Monitoring of Guangdong Nuclear Power Station at Daya Bay in Guangdong (GNPS). . . . Song Haiqing, Chen Zhidong, Lin Qing . . . January 1999 . . . Guangdong Research and Monitoring Center of Environmental Radiation, Guangzhou, China.

Radiat. Prot., 19, 81-87 . . . Some Issues on Nuclear and Radiological Emergency Preparedness and Response in China. . . . Pan Ziqiang . . . March 1999 . . . Scientific and Technological Commission, CAEA, Beijing, China. . . . . . . In Chinese.

Radiat. Prot., 19, 140-143 . . . Determination of Neutron Angular Distribution Induced by 75 MeV/u 12C Ion Beam in Radiobiological Experiment Area. . . . Dang Binrong; Wei Zengquan; Wang Jing; Li Wenjian; Li Qiang . . . March 1999 . . . Institute of Modern Physics, Lanzhou, China.

Radiat. Prot., 19, 149-154 . . . A Method for Rapid Estimation of Internal Dose to Members of the Public from Inhalation of Mixed Fission Products (Based on the ICRP 1994 Human Respiratory Tract Model for Radiological Protection). . . . Hou Jieli . . . March 1999 . . . Xinjiang Institute of Radiological Medicine, Wulumuqi, China.

Date Posted 08/30/1999 (afr)

Last Modified afr (09/02/1999)