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. 402

June 1998

A hero is no braver than an ordinary man, but he is brave five minutes
longer.--Ralph Waldo Emerson

On the Web?

Have you added http://www-rsicc.ornl.gov/rsic.html to your web bookmarks? It's not glitzy but it's to the point. You may find the information you want about a code/data library in the abstract or in the documents available on-line in the Electronic Documents room. These documents have been posted based on the popularity of the code. The top 170 + have been posted; those that remain are being added in the reverse order of their appearance in the RSICC collection or as needed.

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.

Rockwell Revisited

You may recall that the newsletter included a reprint of the Ted Rockwell address to the 1998 ANS Radiation Protection and Shielding Division Topical Conference, held in Nashville, Tennessee. As the editor who assembles this newsletter monthly, I occasionally get evidence that the material is read. One of our readers read Rockwell's statement very thoroughly and noted a discrepancy between the text and the table. The email exchange of information is given below and will be linked to the web page.


Date: Mon, 22 Jun 1998 070938 -0600
From: Brian D Harlow <HARLBD@inel.gov>
Subject: Why Low-Level Radiation Can?t Cause Cancer
To: rsic@ornl.gov

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 harlbd@inel.gov
Date: Mon, 22 Jun 1998 180324 -0400
From: Ted Rockwell <tedrock@cpcug.org>
To: "Kirk, Bernadette Lugue (BLK)" <blk@ornl.gov>
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

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 <erin@sq.com>
From: "Wang,Steve" <SWANG@cerner.com>
From: "WM Symposia, Inc." <wmsym@basix.com>
From: Adam Bradbury <adam@sanstone.demon.co.uk>
From: BURROWS@bnlnd2.dne.bnl.gov
From: Ralph Kenning <rkenning@atl.mindspring.com>
From: Enfir <enfir@iprj.uerj.br>
From: Gianni Reffo <reffo@nudace.arcoveggio.enea.it>

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?)

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
Insoo Jun, Ph.D.
Hughes Space and Communications
Building S25, M/S C372
P.O. Box 92919
Los Angeles, CA 90009

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.


Four changes or additions were made to the computer code collection during the month. One new code system was packaged and added to the collection, one code system was replaced with a newly frozen version, the documentation was updated on an existing code package and an existing code package was corrected.

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 parameters,
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 (C00552/PC386/05).

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 (C00661/MNYCP/00).

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)


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.

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.

21st RERTR, Call For Papers

The 21st International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR) will be held October 18-23, 1998, in São Paulo, Brazil. Information will be exchanged on the progress of national and international programs to develop low enriched fuels for research and test reactors and to convert the reactors to such fuels. This meeting is organized by the Institute of Research and Development Directorate of the Brazilian Nuclear Energy Commission (CNEN) (IPEN) in cooperation with the International Atomic Energy Agency, Argonne National Laboratory, the Brazilian Nuclear Energy Commission, the Brazilian Association for Nuclear Energy (ABEN), and other sectors of the Brazilian nuclear energy industry. Topics to be covered during the meeting are:

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: rertr98@net.ipen.br), or please visit the webpage at url http://www.ipen.br/r/rertr/rertr.html).

"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). Participants in the conference explore the scientific, technological and engineering issues associated with radiation shielding in broad nuclear energy systems, accelerator facilities, space and general environments. The conference topics are:
  • Fission Reactor Shielding
  • Accelerator and Target Shielding
  • Fusion Reactor Shielding
  • Aircraft and Spacecraft Shielding
  • Radioactive Waste
  • Radiation Protection & Safety
  • Fuel Cycle Facility Shielding
  • Transportation and Storage of Radioactive Materials
  • Decontamination and Decommissioning
  • Impact of Radiation and Radioactivity to Environment
  • Radiation Applications in Medical and Industrial Uses
  • Shielding Calculation--Monte Carlo Methods, Deterministic Methods, Point Kernel and Other Analytical Methods
  • Shielding Experiment--Benchmark Experiments, Integral and Mockup Experiments
  • Shielding Design
  • Methods Verification and Validation
  • Visualization and User Interface
  • Source Term Evaluation
  • Skyshine and and Streaming
  • Nuclear Data for Shielding
  • Field Characterization
  • Radiation Dosimetry
  • Radiation Detection and Measurement
  • Shielding Materials and Irradiation Effects
  • Activation and Induced Radioactivity
  • Exposure Evaluation and Protection

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 keda@fnshp.tokai.jaeri.go.jp) or from the web page at http://icrs9.tokai.jaeri.go.jp.


The Seventh Annual Meeting of the Council on Ionizing Radiation Measurements and Standards (CIRMS) will be held at the National Institute of Standards and Technology, Gaithersburg, Maryland, October 19-21, 1998. CIRMS is a non-profit, U.S. Council, with representation from academic, professional and industrial associations and organizations, government agencies and interested individuals. CIRMS provides an opportunity for open discussion of current issues concerning ionizing radiation and future directions of measurements and standards.

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>.

Tenth International Symposium on Reactor Dosimetry

The Tenth International Symposium on Reactor Dosimetry will be held September 12-17, 1999, in Osaka, Japan. This Symposium, held about every three years, provides a forum for the interchange of state-of-the-art techniques, databases and standardization of radiation metrology. The Symposium will be of value to those involved in reactor dosimetry, including researchers, manufacturers and representatives from industry, utilities and regulatory agencies. The Symposium is jointly sponsored by the Atomic Energy Society of Japan (AESJ), the American Society for Testing and Materials (ASTM) and the European Working Group on Reactor Dosimetry (EWGRD). It is organized by ASTM Committee E10 on Nuclear Technology and Applications and EWGRD.

The Symposium theme is dosimetry for the assessment of irradiated reactor materials and reactor experiments, featuring radiation metrology techniques, databases and standardization. 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 Asia:

Dr. David W. Vehar
ASTM Program Secretary
Sandia National Laboratories, MS-1136
P.O. Box 5800, Albuquerque, NM 87185-1136, USA

Phone: 1-505-845-3414, Fax: 1-505-844-0798
E-mail: dwvehar@sandia.gov

Europe, Africa, Asia (other), and Australia:

Dr. Hamid Ait Abderrahim
EWGRD Programme Secretary
Boeretang 200, B-2400 Mol, BELGIUM

Phone: +32 14 332277, Fax: +32 14 321529


Your attention is directed to the following events of interest.

May 1998

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; fax 210-567-6964).

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 lsalmon@utk.edu).

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 lsalmon@utk.edu).

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 lsalmon@utk.edu).

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: dick@lanl.gov.

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 dorit.schlittenhardt@jrc.org, web http://www.jrc.org/isis/sa/events/samo98/).

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://haghigha@transport.nuce.psu.edu/).

June 1998

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; email: broadway@strudel.aum.edu).

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 congress@mail.inter.net.il, web http://icenes98.simplenet.com/).

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 wbw@lanl.gov).

July 1998

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: hpsburkmgt@aol.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 schwanjr@sandia.gov).

September 1998

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: hainesjr@ornl.gov, or url http://www.engr.utk.edu/org/ans/AccApp98)

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 http://wrench.et.ic.ac.uk/courses/).

October 1998

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 bwalters@irs.phy.nrc.ca; url: www.irs.inms.nrc.ca/inms/irs/BEAM/ beamhome.html)

November 1998

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).

April 1999

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: lsajo@fis.usb.ve)

June 1999

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: pdryak@cmi.cz).


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/rsic.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

Health Phys. 74, 545-553 . . . Evaluating the Risk of Death Via the Hematopoietic Syndrome Mode for Prolonged Exposure of Nuclear Workers to Radiation Delivered at Very Low Rates. . . . Scott, B.R.; Lyzlov, A.F.; Osovets, S.V. . . . May 1998 . . . Lovelace Respiratory Research Institute, Albuquerque, NM; Ozyorsk Technological Institute of Moscow Physical Engineering Institute, Chelyabinsk, Russia.

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.