Radiation Safety Information Computational Center
Oak Ridge National Laboratory
Phone No. 423-574-6176
A hero is no braver than an ordinary man, but he is brave five minutes
longer.--Ralph Waldo Emerson
The abstracts in our collection are searchable; you may narrow your selection of codes/data libraries for a particular need by scanning the abstract and the electronic notebook.
When you encounter difficulty implementing or running a code, you might find the answer in the "Electronic Notebook," a new addition to our web page. Its implementation was driven by the "DOE2000 Electronic Notebook Project." The notebook is arranged by code/data library name and each notebook is searchable. You are encouraged to use the notebook and to post your suggestions and questions.
You will find other helpful links at our web site such as links to professional groups, other
laboratories in the U.S. and abroad, and a link to a searchable bibliographic database. A quick
analysis of web use by our clients over the last three months reveals even usage over the period
with the exception of a dip during the last week of March and the first week of April.
Our aim is to make the web site useful to our clients. Let us know how we can do it better.
Date: Mon, 22 Jun 1998 070938 -0600 From: Brian D Harlow <HARLBD@inel.gov> Subject: Why Low-Level Radiation Can?t Cause Cancer To: email@example.com I just finished reading the May newsletter from the Radiation Safety Information Computational and was interested in the article "Why Low-Level Radiation Can't Cause Cancer." However, looking at the numbers presented in the article, an error seemingly appeared. It stated that about 99.99% of the DNA alterations are repaired in the metabolic case, and about 1 in 500 in the radiation case. That would mean that 499 in 500 DNA alterations are not repaired in the radiation case. However, in the subsequent table "Number of Events Occurring Daily in Each Cell of the Body" the number 1 in 500 un/misrepaired alterations (DNA alterations not repaired) is used instead of the actual number of 499 in 500 DNA alterations not repaired as stated in the text. This would change the final ratio of mutation, radiation to metabolism to about 1 to 2,000. This is still a substantial ratio between the two types of mutation sources but is substantially less than the printed 1 to 10,000,000. Brian D. Harlow, Sr. Scientist Idaho National Engineering and Environmental Laboratory P.O. Box 1625 Idaho Falls, ID 83415-2202 phone (208)533-4307 fax (208)533-4369 e-mail firstname.lastname@example.org ++++++++++++++++++++++++++++++++++++++++++++++++ Reply Date: Mon, 22 Jun 1998 180324 -0400 From: Ted Rockwell <email@example.com> To: "Kirk, Bernadette Lugue (BLK)" <firstname.lastname@example.org> Subject: ReFWWhy Low-Level Radiation Can?t Cause Cancer Bernadette et al. When I write something, it's nice to know that it's not only read, but read carefully and with understanding. You have caught a clear disconnect between the table and the words. Thanks for pointing that out. The table is correct. I originally described all this in exponential form, and then tried to simplify it by talking about percentages. I shouldn't have. It's 1 in 10,000 single breaks that fail to repair properly, and 1 in 500 for the double breaks. As you pointed out, the words said it backwards for the double breaks. I hope your readers found this paper helpful. As you noted, even if the words were right and the table wrong, the basic point would still hold, though less dramatically. Thanks again for the feedback. Ted Rockwell
Please file this ......
The following is a repeat of an article published in the November 1996 RSIC Newsletter.
With the great increase in electronic correspondence it has become necessary to remind our
clients that we need essential information included with any correspondence (fax or email) that
may not include your company letterhead. The following are some examples of our dilemma.
The following email addresses, as email addresses tend to be, are rather cryptic and require
additional detective work to find where they belong.
From: Erin Rogozinski <email@example.com> From: "Wang,Steve" <SWANG@cerner.com> From: "WM Symposia, Inc." <firstname.lastname@example.org> From: Adam Bradbury <email@example.com> From: BURROWS@bnlnd2.dne.bnl.gov From: Ralph Kenning <firstname.lastname@example.org> From: Enfir <email@example.com> From: Gianni Reffo <firstname.lastname@example.org>
The following example is an improvement, but it could be better:
Adam Bradbury Stonewell Consultants Ltd (01524) 811260 (Is it a phone number or mail code?) email@example.com
The following examples are excellent and most mail systems will allow the user to append a "signature" to outgoing mail. Please do our staff a kindness and include the information in your email message that would ordinarily appear on your company letterhead if you had to write a letter to communicate.
Stephen E. Binney Professor of Nuclear Engineering 116 Radiation Center Oregon State University Corvallis, OR 97331-5902 Phone: (541)737-7068 Fax: (541)737-0480 Internet: firstname.lastname@example.org
Insoo Jun, Ph.D. Hughes Space and Communications Building S25, M/S C372 P.O. Box 92919 Los Angeles, CA 90009 Tel)310-364-8584 Fax)310-416-3088
Though many of our email correspondents are known by their first-names our information
retrieval system is indexed by company name. Please help us out by using the signature in your
email software. If we do not have all the information we need your request could be delayed.
Include all means of contacting you; phone, fax, and email.
and.... Fax Revisited
Fax machines are great for sending and receiving information quickly, and our user community
makes liberal use of them. However, we too often get the same information a few days later in
the mail, which increases the cost of doing business for you and for us. If you send a
request/response to us via fax it is not necessary to send the same information in the regular mail.
Every item gets handled in some way, and duplicates mean someone on the staff is handling the
information more than once. Keep your original for your files and save the postage. This also
applies to e-mail.
Argonne National Laboratory contributed a newly frozen version of this code system to calculate site-specific residual radioactive material guidelines and radiation dose and excess cancer risk to an on-site resident. The revised package includes RESRAD 5.82 and RESRAD-BUILD 2.36.
RESRAD 5.82 requires a Windows operating system and is compatible with Windows95, WindowsNT, or Windows 3.1. The primary modifications in this 4/30/98 release include:
1) Allows plot data to be exported to tab-delimited text file,
2) Corrected an installation problem on Windows 3.1,
3) Corrected a plotting problem for soil guidelines.
RESRAD-BUILD Version 2.36 is a pathway analysis model designed to evaluate the potential
radiological dose incurred by an individual who works or lives in a building contaminated with
radioactive material. The radioactive material in the building structure can be released into the
indoor air by mechanisms such as diffusion (radon gas), mechanical removal (decontamination
activities), or erosion (removable surface contamination). Features in Version 2.36 include:
1) Corrected a problem with simultaneously changing number of wall regions and their
2) Added an OK button to uncertainty window,
3) Made sure first uncertainty variable is added on first try.
The Lahey F77L3/EM-32 and Microsoft Visual Basic compilers were used to create most
RESRAD executables included in the package. The RESPLOT executable was created with
Lahey and MicroGlyph SCIPLOT 5.0. The new RESRAD and RESRAD-BUILD executables run
under Windows 3.1, Windows95 and Windows NT 4.0. Note that the source files are not
included. The package is distributed on five DS/HD 3.5-in. (1.44 MB) diskettes in
self-extracting compressed DOS files. Reference: ANL/EAD/LD-2 (Sept. 1993) and
ANL/EAIS-8 (April 1993), ANL/EAD/LD-3 (Nov. 1994). Fortran 77 and BASIC; PC 386 or 486
Sandia National Laboratories, Albuquerque, New Mexico, advised RSICC of a correction to the MELCOR Accident Consequence Code System designated MACCS2, which was developed to estimate the potential impacts to the surrounding public of severe accidents at nuclear power plants. The principal phenomena considered in MACCS are atmospheric transport and deposition under time-variant meteorology, short-term and long-term mitigative actions and exposure pathways, deterministic and stochastic health effects, and economic costs of mitigative actions. Two defect notifications M2V1-12A and M2V1-12B describe the defects and the methods to avoid involving them in a calculation. The notifications are available on the WWW and are being added to the RSICC package documentation. No changes to the software are being made at this time, but these defects will be corrected in the next release of MACCS2. A release date for the new version is not known at this time. For those users with access the web the corrections can be found at maccnote.pdf.
MACCS2 runs on IBM compatible 80486 or Pentium PC with 8 MB of RAM under DOS,
Windows95 or WindowsNT. The Lahey F77L3/EM-32 Version 5.2 compiler was used to create
the executables included in the package, which is transmitted on nine 1.44 MB 3.5-in. DOS
formatted diskettes in self-extracting archive files. References:
SAND97-0594 (March 1997). Fortran 77, PC based 80486 or
Pentium processor (C00652/PC486/00).
Los Alamos National Laboratory, Los Alamos, New Mexico, contributed a new code system to determine alpha,n; spontaneous-fission; and beta-n delayed neutron sources and spectra due to the decay of radionuclides in homogeneous media. The code also calculates alpha,n sources and spectra in interface problems where the alpha source material is in one region and the (alpha,n) target material is in an adjacent region. Spontaneous-fission spectra are calculated with evaluated half-life, spontaneous-fission branching and Watt spectrum parameters for 43 actinides. The (alpha,n) spectra are calculated using an assumed isotropic neutron angular distribution in the center-of-mass system with a library of 89 nuclide decay alpha spectra, 24 sets of measured and/or evaluated (alpha,n) cross sections and product nuclide level branching fractions, and functional alpha stopping cross sections for Z < 106.
SOURCES3A runs on Sun, IBM RS/6000 and personal computers. The package is transmitted
on one diskette and includes the Fortran source, PC executable, data libraries, and test cases in
both DOS and tar formats. References: LAUR 97-4365 (October 1997), LA-UR-96-3869
(Revised July 1997), and LA-8869 MS (June 1981). Fortran 77; Sun and PC
Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a minor correction to this multidimensional, finite-difference heat conduction analysis code system. HEATING can solve steady-state and/or transient heat conduction problems in one-, two-, or three-dimensional Cartesian, cylindrical, or spherical coordinates. Both HEATING 7.2i and HEATING7.3 are distributed in this package. The correction was made to Subroutine H7MAP in HEATING 7.2i and in Subroutine H73MAP in HEATING 7.3, and the H73MAP executable was recompiled. The change impacts output for 1-dimensional problems. If the number of nodes is large enough that the output exceeds one page in length, only part of the output is displayed. The output from the first few temperatures is repeated, and the rest of the output is never printed.
HEATING7.2i runs on several Unix systems including IBM RS/6000, Sun, DEC, DEC Alpha,
HP and Cray. Fortran 77 and C compilers are required. For the PC version, a Fortran compiler
and DOS extender software are needed to create new executables or to compile and load
user-supplied subroutines. The Microway NDP Fortran 386 4.2.1 compiler was used to create
7.2i executables included in package. HEATING 7.3 is written in Fortran 77 but includes some
Fortran 90 features. HEATING 7.3 PC executables were created using Microsoft Powerstation
v4.0. Visual Basic 4.0 was used to create the graphical front end for the program. Windows95 or
WindowsNT is required to use the GUI version of HEATING 7.3, though a non-GUI version is
included in the package that may be run in a DOS window of Windows95 or WindowsNT.
HEATING7.3 for Unix was tested only on IBM RS/6000 and requires the XLF 3.2 compiler.
Included are the referenced document and one CD-ROM which contains source, PC executables,
script files, and sample cases. The Unix versions are written in compressed Unix tar files.
References: ORNL/TM-12262 (February 1993). HEATING 7.2i: Fortran 77 and C; UNIX
Workstation or Mainframe; Fortran 77; 386 or 486 PC; HEATING 7.3: Fortran 90; 486PC and
IBM RS/6000 (P00199/MNYCP/01)
The Second International Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp'98) is sponsored by the Accelerator Applications Technical Group of the American Nuclear Society (ANS), and is hosted by the Oak Ridge-Knoxville, Tennessee, Section of the ANS. It will be held in Gatlinburg, Tennessee, during the week of September 20-23, 1998, at the Park Vista Hotel & Conference Center.
AccApp'98 will provide a forum for discussion of the uses of particle accelerator technology for nuclear applications. It will focus on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, production or destruction of radionuclides significant to energy, medicine, defense, or other endeavors, as well as imaging and diagnostics.
Papers are solicited in the following areas: applications, design, R&D needs, analytical methods,
tools and databases, economics, safety and licensing. The Call For Papers with all relevant
information and points of contact is located at http://www.engr.utk.edu/org/ans/AccApp98.
The language of the meeting will be English with no simultaneous translation provided. Those
who wish to present a paper at the meeting should send an abstract of the paper, as soon as
possible, but not later than August 1, 1998. Further information about the meeting is available
from Dr. José Rubens Maiorino, Chairman 1998-RERTR Meeting, Comissão Nacional de
Energia Nuclear, Instituto de Pesquisas Energéticas e Nucleares, Diretoria de Reatores, Travessa
R 400 - Cidade Universitária- CEP: 05508-900, São Paulo - SP - Brazil (phone (55-11)
816-9111, fax (55-11) 816-9432, email: email@example.com), or please visit the webpage at url
Abstracts of 400 words should be sent by the end of January 1999. Notification of acceptance
will be made by the end of March 1999. A full paper should to be sent to Program Secretary by
the end of July 1999. Manuscripts for both abstracts and papers should be sent via Web or as an
electronic file with attached text files. The proceedings will be distributed on CD at the
conference. Detailed information about the conference may be obtained from Yujiro Ikeda, Japan
Atomic Energy Research Institute, Tokai Research Establishment, Neutron Science Research
Center, Spallation Neutronics Laboratory, Tokai-mura, Naka-gun, Ibaraki-ken 319-11 Japan
(phone 81-29-282-6074, fax 81-29-282-5709, email firstname.lastname@example.org) or from the
web page at http://icrs9.tokai.jaeri.go.jp.
The focus of the meeting will be the role of the National Laboratories in ionizing radiation
measurements and standards. The National Laboratories play pivotal roles in standards
development and implementation and in the development of state-of-the-art technologies for
ionizing radiation measurements and standardization. Sessions will include medical applications,
occupational radiation protection, public and environmental radiation protection, and industrial
applications and materials effects, each session addressing the subject of one of the CIRMS
Science and Technology Subcommittees. For more information contact Katy Nardi, (770)
622-0026, email <KatyNardi@aol.com>.
The Symposium theme is dosimetry for the assessment of irradiated reactor materials and reactor
experiments, featuring radiation metrology techniques, databases and standardization. Under this
theme, papers are solicited for presentation in the following areas:
Papers in these and other areas are expected to cover such applications as fission and fusion energy research and test and research reactor experiments.
Inquiries and requests to be added to the mailing list should be sent to one of the of the following:
|North and South America, East and Southeast
Dr. David W. Vehar
Phone: 1-505-845-3414, Fax: 1-505-844-0798
|Europe, Africa, Asia (other), and Australia: |
Dr. Hamid Ait Abderrahim
Radiation Oncology Resident's Review in Radiation Oncology Physics and Radiation Biology,
May 11-15, 1998, a continuing education course offered by the University of Texas at San
Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing
Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491;
Physicist's Review in Radiation Oncology Physics, May 11-15, 1998, a continuing education
course offered by the University of Texas at San Antonio. Contact: The University of Texas
Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San
Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).
Computational Methods in Reactor Analysis and Shielding, May 18-22, 1998, 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 (phone
423-974-2525; email email@example.com).
Nuclear Criticality Safety, May 18-22, 1998, 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 (phone 423-974-2525; email firstname.lastname@example.org).
Monte Carlo Analysis, May 18-22, 1998, 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 (phone 423-974-2525; email email@example.com).
Radiation Safety Officer's Course, May 18-22, 1998, a continuing education course offered by
the University of Texas at San Antonio. Contact: The University of Texas Health Science Center
at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX
78284-7980 (phone 210-567-4491; fax 210-567-6964).
Practical MCNP for the HP, May 18-22, 1998, University of New Mexico-Los Alamos Campus.
Contact Dick Olsher, 505-667-3364, e-mail: firstname.lastname@example.org.
SAMO 98: Second International Symposium on Sensitivity Analysis of Model Output, May
19-22, 1998, University of Venice, Dorsoduro 3825, 30123 Venezia, Italy. Contact: Mrs. Dorit
Schlittenhardt, Public Relations and Publications Unit - JRC Ispra Site, TP 020, 21020 Ispra
(VA) Italy (phone 39 332 789370, fax: 39 332 785409, email email@example.com, web
Methodologies For Particle Transport Simulation and Their Application to Reactor Dosimetry/
Shielding, May 25-29, 1998, SCK/CEN, Mol, Belgium. Contact: Prof. Ali Haghighat, Penn State
University, Nucl. Eng. Dept., 231 Sackett Building, University Park, PA 16802 (phone
814-865-0039, fax 814-865-8499, email: http://firstname.lastname@example.org/).
Radiation Safety Officer, June 8-12, Las Vegas, Nevada, a Technical Short Course offering of
Nevada Technical Associates. Contact: Nevada Technical Associates, Inc., P.O. Box 90748,
Henderson, NV 89009 (phone 702-564-2798; fax 702-558-7672).
3rd International Meeting of Physicists in the Inca Region, June 15-20, 1998, Cusco, Peru.
Contact: Jon Broadway, Internatl. Corps on Environment (ICE), Auburn University, 75
Technacenter Drive, Montgomery, AL 36117-6035 (phone: 334-242-2777; fax: 334-242-2755;
ICENES '98, Emerging Nuclear Energy Systems, June 28-July 2, 1998, Tel-Aviv, Israel. Contact:
Conference Secretariat, Dan Knassim Ltd., P.O. Box 1931, Ramat Gan 52118, Israel (phone
972-3-6133340, fax 972-3-6133341, email email@example.com, web
CINDER'90 June 30 - July 1, and again July 1415, 1998, Los Alamos National Laboratory.
Contact: W. B. Wilson, Nuclear Theory and Applications Group (T-2), Theoretical Division, Los
Alamos National Laboratory, PO Box 1663, MS:B243, Los Alamos, NM 87545 (phone
505-667-7749, fax: 505-667-9671, or firstname.lastname@example.org).
Health Physics Society Annual Meeting, July 12-16, 1998, Minneapolis, Minnesota. Contact:
Health Physics Society, Suite 402, 1313 Dolley Madison Blvd., McLean, VA 22101-3926 (phone
703-790-1745; fax 703-790-2672; email: email@example.com).
The 1998 IEEE International Conference on Nuclear and Space Radiation Effects, July 20-24,
Newport Beach, California. Contact: James R. Schwank, Sandia National Laboratories, P.O Box
5800, MS 1083, Albuquerque, NM 87185-1083 (phone 505-844-8376, fax: 505-844-2991, email
AccApp'98, Sept. 20-23, 1998, Gatlinburg, Tennessee, sponsored by the Oak Ridge-Knoxville,
TN, USA Section of the ANS. Contact: Dr. John Haines, Chairman, AccApp '98 Technical
Program Committee, Oak Ridge National Laboratory, Oak Ridge, TN 37831-8071, USA (phone
423-574-0966, fax 423-576-7926, email: firstname.lastname@example.org, or url
Training Course on the Use of MCNP in Radiation Protection and Dosimetry, Sept. 28-1 Oct.
1998, at the Imperial College of Science, Technology and Medicine, London. Contact: Robert
Alan Price, Imperial College of Science, Technology and Medicine, T. H. Huxley School of the
Environment, Earth Sciences and Engineering, Applied Modelling and Computation Group,
Centre for Environmental Technology, Room 405, Royal School of Mines Building, Prince
Consort Rd, London SW7 2BP, UK (phone 44 171 594 9323, fax 44 171 594 9341, url
4th Annual Workshop on Monte Carlo Simulation of Radiotherapy Treatment Sources using the
OMEGA/BEAM Code System, Oct. 5-8, 1998, 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 email@example.com; url:
Radiation Safety Officer, Nov. 2-6, 1998, Las Vegas, Nevada, a Technical Short Course offering
of Nevada Technical Associates. Contact: Nevada Technical Associates, Inc., P.O. Box 90748,
Henderson, NV 89009 (phone 702-564-2798; fax 702-558-7672).
First Latin American Symposium on Nuclear Tracks and Radiation, April 5-9, 1999, Caracas,
Venezuela, Institute for Advanced Studies, Convention Centre. Contact: Professor Laszlo Sajo,
Universidad Simon Bolivar, FE-1, Apdo 89000, Caracas, Venezuela, (phone 58-2- 906- 3590,
fax 58- 2 -906-3712, email: firstname.lastname@example.org)
Conference on Radionuclide Metrology and its Application, June 7-11, 1999, Prague. Contact:
Pavel Dryák, Czech Metrological Institute, Radiova 1, CZ 102 00 Prague, Czech Republic
(phone: +420 2 67008244, fax: +420 2 67008466, email: email@example.com).
Health Phys., 74, 594-601 . . . Comparison of the LLNL and JAERI Torso Phantoms Using Ge Detectors and Phoswich Detectors. . . . Kramer, G.H.; Hauck, B.M.; Allen, S.A. . . . May 1998 . . . Human Monitoring Laboratory, Ontario, Canada; Department of Compliance and Licensing, Ontario, Canada.
Health Phys., 74, 608-609 . . . Worker Dose Analysis Based on Real Time Dosimetry. . . . McElroy, N.L. . . . May 1998 . . . Stanford University, Stanford, CA.
Health Phys., 74, 613-618 . . . A Joint HML-KAERI Project - Comparison of the LLNL and JAERI Torso Phantoms Using Four 50 mm Ge Detectors. . . . Kramer, G.H.; Lee, T.Y.; Kim, J.S. . . . May 1998 . . . Human Monitoring Laboratory, Ontario, Canada; Korea Atomic Energy Research Institute, Taejon, Korea.
Health Phys., 74, 639-643 . . . History of the Health Physics Society. . . . Morgan, K.Z. . . . June 1998.
Health Phys., 74, 644-645 . . . History of the International Radiation Protection Association. . . . Morgan, K.Z. . . . June 1998.
Health Phys., 74, 647-672 . . . Soil Ingestion By Humans: A Review of History, Data, and Etiology with Application to Risk Assessment of Radioactively Contaminated Soil. . . . Simon, S.L. . . . June 1998 . . . National Research Council, Washington, DC.
Health Phys., 74, 673-676 . . . Multifractal Analysis of the 137Cs Fallout Pattern in Austria Resulting from the Chernobyl Accident . . . Pausch, G.; Bossew, P.; Hofmann, W.; Steger, F. . . . June 1998 . . . University of Salzburg, Salzburg, Austria; Austrian Research Center Seibersdorf, Seibersdorf, Austria.
Health Phys., 74, 677-686 . . . Geographical Distribution of Radiation Risks in The Netherlands. . . . Janssen, M.P.M.; Blaauboer, R.O.; Pruppers, M.J.M. . . . June 1998 . . . National Institute of Public Health and the Environment, Bilthoven, The Netherlands.
Health Phys., 74, 687-697 . . . Environmental Contamination and Assessment of Doses from Radiation Releases in the Southern Urals. . . . Kryshev, I.I.; Romanov, G.N.; Sazykina, T.G.; Isaeva, L.N.; Trabalka, J.R.; Blaylock, B.G. . . . June 1998 . . .Institute of Experimental Meteorology, Obninsk, Russia; Experimental Research Station of the Mayak Nuclear Materials Production Complex, Chelyabinsk, Russia; Chelyabinsk Hydrometeorological Center, Chelyabinsk, Russia; Oak Ridge National Laboratory, Oak Ridge, TN; SENES Oak Ridge Inc., Oak Ridge, TN.
Health Phys., 74, 698-706 . . . Calculation of the Effective Dose and Its Variation from Environmental Gamma Ray Sources. . . . Saito, K.; Petoussi-Henss, N.; Zankl, M. . . . June 1998 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan; GSF-National Research Center for Environment and Health, Neuherberg, Germany.
Health Phys., 74, 707-713 . . . Dose Reconstruction for Residents Living in 60Co-Contaminated Rebar Buildings. . . . Tung, C.J.; Chao, T.C.; Chen, T.R.; Hsu, F.Y.; Lee, I.T.; Chang, S.L.; Liao, C.C.; Chen, W.L . . . June 1998 . . . National Tsing Hua University, Hsinchu, Taiwan; Atomic Energy Council, Taipei, Taiwan.
Nucl. Sci. Eng., 129, 1-14 . . . Neutronic Analysis of Critical Configurations in Geologic Respositories - II: Highly Enriched Uranium. . . . Vujic, J.; Greenspan, E. . . . May 1998 . . . University of California, Berkeley, Berkeley, CA.
Nucl. Sci. Eng., 129, 51-60 . . . One-Dimensional Beam Transport - Revisited. . . . Anderson, D.; Fulop, T.; Lisak, M.; Wising, F.; . . . May 1998 . . . Chalmers University of Technology, Goteborg, Sweden.
Nucl. Sci. Eng., 129, 81-87 . . . Measurements of Tritium and 14C Production Cross Sections for 14.7-MeV Neutrons on 17O and 18O. . . . Verzilov, Y.M.; Ikeda, Y.; Maekawa, F.; Oyama, Y.; Smith, D.S. . . . May 1998 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan; Argonne National Laboratory, Argonne, IL.
Nucl. Sci. Eng., 129, 88-96 . . . A Hierarchical Domain Decomposition Boundary Element Method Applied to the Multiregion Problems of Neutron Diffusion Equations. . . . Purwadi, M.D.; Tsuji, M.; Narita, M.; Itagaki, M. . . . May 1998 . . . Hokkaido University, Sapporo, Japan.
Nucl. Technol., 122, 125-131 . . . RETRAN-03 Simulation of a Multiple Failure Event at KORI Unit 2. . . . Kim, K.; Chang, W.P.; Yoo, K.J.; Lee, S.H.; Lee, C.B. . . . May 1998 . . . Korea Atomic Energy Research Institute, Taejon, Korea; Korea Electric Power Company, Pusan, Korea.
Nucl. Technol., 122, 132-145 . . . The RETRAN-3D Code; Pressurized Water Reactor Multidimensional Neutron Kinetics Applications. . . . Gose, G.C.; Shatford, J.G.; Agee, L.J. . . . May 1998 . . . Computer Simulation & Analysis, Inc., Idaho Falls, ID; Electric Power Research Institute, Palo Alto, CA.
Nucl. Technol. 122, 146-157 . . . RETRAN Benchmarks of Lasalle Units 1 and 2 Startup Tests. . . . Beaumont, E.T.; Jacobs, R.H. . . . May 1998 . . . Commonwealth Edison Company, Downers Grove, IL.
Nucl. Technol., 122, 170-178 . . . A Probabilistic Approach for the Evaluation of Reactivity Insertion Accident Effects. . . . Ramos, J.C.; Agee, L.J.; Dias, A.F. . . . May 1998 . . . Instituto de Investigaciones Electricas, Morelos, Mexico; Electric Power Research Institute, Palo Alto, CA; S. Levy Inc.; Campbell, CA.
Nucl. Technol., 122, 179-195 . . . Design and Development of Fast Breeder Reactor Passive Reactivity Control Systems: LEM and LIM. . . . Kambe, M.; Uotani, M. . . . May 1998 . . . Central Research Institute of the Electric Power Industry, Tokyo, Japan.
Nucl. Technol., 122, 211-221 . . . Calculation of Radiation Dose Rates in a Water Layer in Contact with Used Candu UO2 Fuel. . . . Sunder, S. . . . May 1998 . . . Atomic Energy of Canada Ltd., Whiteshell Labs., Manitoba, Canada.
Radiat. Prot., 5, 341-348 . . . A Simple Method of Calculating Neutron Energy Spectrum. . . . Yisheng L.; Yong, G.; Yuanming, S.; et al. . . . May 1997 . . . Beijing Institute of Radiation Medicine, Beijing, China. . . . In Chinese.
Radiat. Prot., 6, 434-439 . . . Calibration and Performance Test of Thermoluminescent Neutron Dosemeters for Personal Neutron Dose Monitoring. . . . Keqin, Z.; Ruxin, Z. . . . June 1997 . . . National Institute of Metrology, Beijing, China. . . . In Chinese.
Radiat. Prot., 6, 440-448 . . . Inhalation Dose Coefficients of Some Radionuclides for Members of the Public. . . . Yongzeng, Z. . . . June 1997 . . . China Institute for Radiation Protection, Taiyuan, China. . . . In Chinese.
Radiat. Prot. 6, 454-457 . . . Ionometric Determination of Absorbed Dose in Water for Cobalt-60 Gamma Rays. . . . Jiacheng, H.; Qiuxing, Q. . . . June 1997 . . . National Institute of Metrology, Beijing, China; Beijing Municipal Research Institute of Environmental Protection, Beijing, China. . . . In Chinese.
DOE-HDBK-1113-97 . . . Radiological Safety Training for Uranium Facilities. . . . February 1998.
NEA/COM(98)1 . . . The Nuclear Energy Agency Reviews Safety Research Needs for Russian-Designed Reactors. . . . March 1998.
NEA/COM(98)3 . . . Radioactive Waste Management in OECD/NEA Member Countries. . . . May 1998 . . . OECD Publications Distributors.
NEA/COM(98)4 . . . Nuclear Power and Climate Change.. . . May 1998.
ORNL/TM-13567 . . . Neutronics Benchmark for the Quad Cities-1 (Cycle 2) Mixed-Oxide Assembly Irradiation. . . . Fisher, S.E.; Difilippo, F.C. . . . April 1998 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
ORNL/TM-13584 . . . ARP: 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. . . . April 1998 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Book . . . Table of Isotopes, Eighth Edition. . . . Firestone, R.B., ed.; Shirley, V.S., ed. . . . 1998.