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. 865-574-6176
FAX 865-574-6182
Internet: PDC@ORNL.GOV
WWW: http://www-rsicc.ornl.gov/rsic.html

No. 421 February 2000
Ethical living is the indispensable condition of all that is most worthwhile in the world.--Ernest Caldecott





Area Code Changes for RSICC

The area code for parts of East Tennessee changed from 423 to 865 effective November 1, 1999. The transition period will extend to April 24, 2000, during which time both area codes can be used. This period should provide enough time for the customer to make necessary changes in modems, faxes, automatic dialers, speed calling, pagers, and cellular phones for numbers dialed within the Knoxville-Oak Ridge region.



NRC Codes Made Available

Several U.S. Nuclear Regulatory Commission (NRC) software packages which were transferred from the ESTSC to RSICC were incorporated into the RSICC computer code collection. Please browse the computer code abstracts available at RSICC's www site for more information on these packages.

CCC-689/MATADOR
PSR-436/FRAPT6/MOD1 Distribution is limited to United States.
PSR-436/FRAPT6/V21 Distribution is limited to United States.
PSR-465/EVNTRE
PSR-467/SRVAL
PSR-475/SIGPI



CHANGES TO THE COMPUTER CODE COLLECTION

Four changes were made to the computer code collection during the month. One new code system was added to the collection, two code systems were replaced with newly frozen versions, and one code system was corrected. One change resulted from a foreign contribution.



Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a newly frozen version of this modular code system for performing standardized computer analyses for licensing evaluation. In its present form, the system has the capability to perform criticality, shielding, and heat transfer analyses using well-established functional modules tailored to the SCALE system. Spent fuel characteristics for these analyses can be obtained from a module that performs a depletion/decay calculation. A significant number of updates have been made to SCALE since the release of SCALE 4.4. Most of these updates were minor corrections or enhancements. Because some of these updates could be important to SCALE users, this interim release of SCALE 4.4a is being made available. Details of the changes are available in the SCALE Newsletter which can be viewed on the web: http://www.cped.ornl.gov/scale/scale-home.html.

A new Windows GUI replacement for the CSASIN input processor for the CSAS criticality sequences in SCALE called CSPAN (Criticality Safety Input Processor for Analysis) is included. The initial version of a Windows-based GUI for HEATING named Visual Heating is also included to assist the user in preparing and running the HEATING module. It includes a 3-D graphics capability for viewing the HEATING geometry model.

Fortran 90 and C compilers are required to install the Unix version of SCALE-4.4a which runs on IBM RS/6000, DEC Alpha OSF/1, SUN, and HP workstations and on Pentium personal computers running Linux. The Linux version was installed on a Pentium III under RedHat Linux 6.1 with The Portland Group, Inc. (PGI) PGF90 compiler version 3.1-3 & gcc compiler. Linux executables are included in the package. A minimum of 650 MB is required to create executables and run test cases. The Windows PC version runs on Pentium personal computers with a minimum of 32 MB RAM. Executables included in the PC windows package were created using the Lahey F90 Fortran compiler version 4.00e in a DOS window of Windows NT 4.0. Nominal hard disk requirements are 500 MB for a complete installation, including space for running sample problems. SCALE runs on Windows 95/98/NT/2000 platforms. Data libraries required to run SCALE modules under Windows are included in this distribution.

Included in the transmittal are the electronic documentation and 2 CD-ROMs with the Unix and Windows PC versions of SCALE. Reference: included in electronic (PDF) format only: NUREG/CR-0200, Rev. 6 (ORNL/NUREG/CSD-2/R6), Vols. I, II, and III (December 1999). Fortran 90 and C; DEC, IBM RS/6000, HP, and SUN Unix workstations; and PC (Pentium or later), Windows 95/98/NT (C00545/MNYCP/01).



Forschungszentrum Jülich GmbH, Germany, through the NEA DB contributed this Monte Carlo code system for high-energy radiation transport calculations. HERMES-KFA consists of a set of Monte Carlo codes used to simulate particle radiation and interaction with matter. The main codes are HETC, MORSE, and EGS. They are supported by a common geometry package, common random routines, a command interpreter, and auxiliary codes like NDEM that is used to compute a gamma-ray source from nuclear de-excitation after spallation processes.

The developers report that HERMES runs on IBM RS/6000 using AIX 4.1 and was also installed on a SunSparcstation using SunOS 4.1. The code was not successfully tested at either the NEA Data Bank or at RSICC and is being made available as it was received from the developers. Included are the referenced document and a CD-ROM which includes the HERMES source codes, scripts, and test cases in a compressed Unix tar file. Reference: JUL-2203 (May 1988). Fortran 77; IBM RS/6000 (C00687MNYWS00).



Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a correction to CRRS (Conference Room Reservation System). The scheduler functions properly in the year 2000, but the header on the "BrowseAll" feature calendar was not indicating the correct year. A corrected perl script placed in the package solved the problem. CRSS is a set of CGI scripts written in perl with a top level HTML page for this World-Wide Web-based software, which is used at ORNL to reserve conference rooms. In addition, customized versions have been constructed to reserve government vehicles and laboratory instruments. CRRS provides a calendar-based scheduler for conference rooms through the WWW and allows Laboratory employees to schedule conference rooms without calling the person who keeps a paper log. The system runs on the internal WWW server at ORNL. This machine is a DEC ALPHA with the Digital Unix 4.0 operating system running the Apache Stronghold Web server. The package is distributed as a Unix tar file on diskette. References: Informal report. PERL; DEC Alpha (P00376/DALPU/01).



The Nuclear Regulatory Commission, Washington, DC, and Lockheed Martin Idaho Technologies, Inc., Idaho Falls, Idaho, contributed newly frozen versions of this collection of programs developed for the purpose of performing those functions necessary to create and analyze a complete Probabilistic Risk Assessment (PRA). The new versions are identified as SAPHIRE 6.64 and SAPHIRE 7.06. The programs included in this suite are the Integrated Reliability and Risk Analysis System (IRRAS), the System Analysis and Risk Assessment (SARA) system, the Models And Results Database (MAR-D) system, and the Fault tree, Event tree and P&ID (FEP) editors. Previously these programs were released as separate packages. These programs allow the user to create event trees and fault trees, to define accident sequences and basic event failure data, to solve system and accident sequence fault trees, to quantify cut sets, and to perform uncertainty analysis on the results. Also included are features to allow the analyst to generate reports and displays that can be used to document the results of an analysis. Since this software is a very detailed technical tool, the user of this program should be familiar with PRA concepts and the methods used to perform these analyses. SAPHIRE 7.06 is restricted to United States distribution only.

SAPHIRE is written entirely in MODULA-2 and uses an integrated commercial graphics package to interactively construct and edit fault trees. The fault tree solving methods used are industry recognized top down algorithms. For quantification, the program uses standard methods to propagate the failure information through the generated cut sets. The package is transmitted on one CD-ROM and includes an executable which runs in a MS-DOS Window of Windows95. References for SAPHIRE 5.69: NUREG/CR-6116 Vols 1-5, 7, 8 (December 1993). Reference for SAPHIRE 6.64 and 7.06: Extensive electronic documentation. MODULA-2; IBM PC 486 (Version 6.64 P00405PC48601 and Version 7.06 P00405PC48602).



ANS Honors New Fellows at Winter Meet

The following ANS members, elected as Fellows of the society, were honored at the 1999 Winter Meeting.



Daniel T. Ingersoll (member since 1977), section leader, Nuclear Analysis and Shielding Section, Oak Ridge National Laboratory, "For leadership responsible for the development, application, and preservation of integrated technologies widely used for radiation analysis in a variety of complex applications. Prominent examples are the first publicly available 3-D Sn Code (TORT), international shielding programs at the Tower Shielding Facility (TSF), and redirection of the TSF for medical applications."

Thomas H. Row (member since 1961), senior staff assistant to the director, Oak Ridge National Laboratory, "For scientific and technical leadership in nuclear environmental impact assessments. His notable achievements include implementation of effective technical and financial management to remediate a legacy of wastes at Oak Ridge National Laboratory. He established an enduring standard for nuclear power plant environmental statements and quelled licensing disruptions. Equally compelling is his unrivaled technical program leadership of the Society."

Rusi P. Taleyarkhan (member since 1989), program manager, Oak Ridge National Laboratory, "For pioneering, directing, and developing unique methodologies and core capabilities (analytical and experimental) for assessing postulated severe accidents in non-power (research, test, and production) reactors and gaseous diffusion plants. His work has been used for analyzing/enhancing the safety of high-powered research reactors worldwide, for formulating IAEA guidelines for assessing research reactor safety, and for regulatory approval for operations of America's gaseous diffusion plants."



ANS Honors and Awards

The following members received awards for professional achievement during the Honors and Awards Luncheon at the Winter Meeting.

Rafael B. Perez (member since 1963), ANS Fellow and professor emeritus of nuclear engineering at the University of Tennessee, received the Eugene P. Wigner Reactor Physicist Award for "his 30 years' involvement and leadership in many areas of reactor physics research and education, including his pioneering work on neutron wave and pulse propagation, non-linear reactor dynamics and control, fission physics, and the application of Eugene P. Wigner's R-matrix formalism to nuclear reactor cross section theory, evaluation, and technology."

Wolf Häfele (member since 1959), ANS Fellow and retired director of the Rossendorf Research Center, Dresden, Germany, was awarded the Alvin M. Weinberg Medal given in recognition of outstanding contributions to the understanding of the social implications of nuclear technology. Häfele was nominated for the award by Weinberg himself. The citation reads "For a lifetime of achievement as a reactor physicist, leader of the German Fast Breeder Reactor Project, author of Energy in a Finite World, and philosopher of energy and its relation to human affairs."

Douglas E. Peplow (member since 1991), staff scientist, Nuclear Analysis and Shielding Section, Oak Ridge National Laboratory, received the Mark Mills Award for graduate work in nuclear science for his paper titled, "Differential Sampling Applied to Mammography Image Simulation," coauthored by his dissertation advisor, Prof. Kuruvilla Verghese. The dissertation research was funded by a NEER (Nuclear Engineering Education Research) grant from the U.S. Dept. of Energy. Peplow received his PhD. in nuclear engineering from North Carolina State University.

Dimitrios Cokinos , nuclear engineer, Brookhaven National Laboratory, received the Standards Service Award "In recognition of his tireless efforts over many years in support of the ANS Standards Program, and in particular his leadership as chair of ANS-19, the Reactor Physics Design Subcommittee. His endeavors have contributed to the development and maintenance of standards that are widely used in the nuclear industry."



Obituaries

Robert S. Wilson died January 16 in Ithaca, NY. Wilson was the first director of the Fermi National Accelerator laboratory. He headed the Manhattan Project's Experimental Nuclear Physics Division in Los Alamos during World War II. He joined the faculty at Cornell University in 1947 where he designed a series of particle accelerators that led to the construction of the Cornell Electron-Positron Storage Ring which now bears his name. In 1967 he assumed directorship of Fermilab, the world's highest-energy particle accelerator. He served there until 1978.

Harald H. Rossi died January 1 in Upper Nyack, NY. Rossi pioneered the field of microdosimetry and designed many instruments used to measure radiation, including the proportional counter, or Rossi counter, which measures the energy deposited by radiation in cells and other microscopic sites.

Michael G. Sowerby died November 15, 1999. Sowerby specialized in measurement and evaluation of nuclear data at the United Kingdom Atomic Energy Authority's Harwell site.



CONFERENCES, COURSES, SYMPOSIA

RSICC attempts to keep its users/contributors advised of conferences, courses, and symposia in the field of radiation protection, transport, and shielding through this section of the newsletter. Should you be involved in the planning/organization of such events, feel free to send your announcements and calls for papers via email to raf@ornl.gov with "conferences" in the subject line. Please include the announcement in its native format as an attachment to the message. If the meeting is on a website, please include the url.

Every attempt is made to ensure that the links provided in the Conference and Calendar sections of this newsletter are correct and live. However, the very nature of the web creates the possibility that the links may become unavailable. In that case, please call or mail the contact provided.



Practical MCNP for the Health /Medical Physicist & Rad Engineer

This course is aimed at the HP, medical physicist, and rad engineer with no prior experience with Monte Carlo techniques. The focus is almost entirely on the application of MCNP to solve a variety of practical problems in radiation shielding and dosimetry. The intent is to "jump start" the student toward using MCNP productively. Extensive interactive practice sessions are conducted on a personal computer. Topics will include overview of the MCNP code and the Monte Carlo method, basic concepts, input file preparation, geometry, source definition, standard MCNP tallies, interpretation of the output file, exposure and dose rate calculations, radiation shielding, photon skyshine, detector simulation and dosimetry.

The course fee includes a complete MCNP code package, distributed directly from the Radiation Safety Information Computational Center (RSICC). Students will also be provided with a comprehensive class manual and a diskette containing all of the practice problems. This course has been granted 32 Continuing Education Credits by the AAHP. The course is offered by the Health Physics Measurements Group at the Los Alamos National Laboratory and is co-sponsored by RSICC.

Registration is available online at http://drambuie.lanl.gov/~esh4/mcnp.htm; however, to guarantee a space payment must be received prior to the registration deadline. Make checks payable to the University of California (checks must be in U.S. dollars on a U.S. bank) and mail together with name, address, and phone number to the address above. The course is offered by Group ESH-4, Health Physics Measurements, Mail Stop G761, Los Alamos National Laboratory, Los Alamos, NM 87545 USA and is co-sponsored by RSICC.

DATES: 15-19 May 2000 (registration deadline 1 May 2000)
16-20 October 2000 (registration deadline 2 October 2000)
FEE: $1,700 per person (includes the MCNP code package)
PLACE: The Canyon School Complex, Los Alamos National Laboratory

Inquiries regarding registration and class space availability should be made to David Seagraves, 505-667-4959, fax: 505-665-6071, e-mail: dseagraves@lanl.gov. Technical questions may also be directed to Dick Olsher, 505-667-3364, e-mail: dick@lanl.gov.



MCNP and Visual Editor Training Course

Upcoming 2000 dates for the MCNP and Visual Editor Training Course are:

October 9-12 in Richland, Washington. Cost $1400

The source code package can be obtained directly from RSICC.

The class will combine teaching on MCNP physics, along with instructions on how to use the visual editor. Computer demonstrations and exercises will focus on creating and interrogating input files with the visual editor. Demonstrations of advanced visualization work using MCNP will also be made. The class will be taught on Pentium computers running the Linux operating system. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. It is recommended that you have experience with MCNP before taking this class. For additional information contact Randy Schwarz, MS K8-34, P. O. Box 999, Richland, WA 99352 (509-372-4042, fax 509-372-6421, email randy.schwarz@pnl.gov, url http://www.pnl.gov/eshs/software/ved.html).



MCNP Workshops for the Year 2000

The following is the 2000 schedule for Monte Carlo N-Particle Transport Code workshops.



Year 2000 Schedule:

10-14 April Advanced Class Imperial College, London
11 May MCNP4C Workshop Pittsburgh, PA, USA
23-26 May Introductory Class USA, Los Alamos National Laboratory
3-7 July Introductory Class University of Stuttgart, Germany
12-15 September Introductory Class Richland, WA; USA
11-15 September MCNP Topics Tokyo, Japan



Introductory classes are for people who have little or no experience with MCNP. The classes survey the features of MCNP so the beginning user will be exposed to the capabilities of the program and will have hands-on experience at running the code to solve rudimentary problems. Course topics include basic geometry, source definitions, output (tallies) specification and interpretation, advanced geometry (repeated structures specification), variance reduction techniques, statistical analysis, criticality, plotting of geometry, tallies, and particle tracks, and neutron/photon/electron physics.

Advanced classes are for people with MCNP experience who want to extend their knowledge and understanding. Most areas of MCNP operation will be discussed in detail, with emphasis on advanced geometry, advanced variance reduction techniques, perturbation enhancement & cumulative tallies. Time will be available to discuss approaches to specific problems of interest to students.

NOTE: While MCNP supports a number of platforms, class computers are usually UNIX machines. Experience with UNIX will be helpful to the student but is not essential.

Year 2000 classes will showcase the latest release of MCNP, Version 4C. Major new features that will be discussed include:

  • Macrobodies
  • Unresolved Resonance Treatment
  • Perturbation Enhancement
  • Alpha Eigenvalues
  • Cumulative Tallies

All classes provide interactive computer learning. Time will be available to discuss individual questions and problems with MCNP experts. To Register for the LANL classes via the Internet, go to http//www.solutionsbyhqc.com/mcnpinfo.html or email Bill Hamilton at bill@solutionsbyhqc.com. For registration information on the European classes, contact Enrico Sartori, OECD/NEA, Sartori@nea.fr. Contact Judi Briesmeister, email jfb@lanl.gov, for the course in Japan.





Reactor Analysis and Criticality Safety Short Courses

The Department of Nuclear Engineering at the University of Tennessee-Knoxville is offering two short courses for radiation transport specialists during Tennessee Industries Week (TIW-35), August 14-18, 2000.



Monte Carlo Analysis is often the method of choice to solve complex problems in criticality and radiation shield design. The transport analyst must often choose between Monte Carlo and deterministic methods like discrete ordinates; or the nature of the design problem may dictate that he perform a coupled (Monte Carlo/discrete ordinates) calculation. Therefore, to use Monte Carlo and other transport methods effectively, the analyst must understand the theoretical and computational fundamentals. Rather than use an existing program, it is sometimes advantageous to create a new special-purpose Monte Carlo program. The procedures that are involved in preparing a user-written Monte Carlo program will be described in terms of the classical and conceptually simple straight-ahead, one-speed, slab transmission problem.

Many advanced topics will be included that will permit optimum use of existing computer codes such as MCNP. Special attention will be given to the understanding of the adjoint calculation. Advantages and disadvantages of the adjoint mode versus the forward mode of analysis will be described. The full range of variance reduction techniques will be studied for both forward and adjoint calculations.

The Monte Carlo Method offers the expectation that the true solution to the problem as modeled can be achieved. However, this may lead to a false sense of credibility, in particular when calculations are performed by relatively inexperienced users (the majority of people who use the Monte Carlo method do so only occasionally). Monte Carlo calculations are subject to major errors and/or misinterpretations because currently used statistical measures may be insufficient. Other methods for statistically characterizing Monte Carlo methods will be described.

The relationship of the Monte Carlo method to the other transport methods such as discrete ordinates will be described, including comparisons of computational advantages and disadvantages. The MCNP computer code will be described as required to illustrate the general features of large Monte Carlo computer programs.



Nuclear Criticality Safety Engineers, scientists, and technical managers who wish to increase their knowledge and understanding of nuclear criticality safety will be interested in this intensive one-week short course. The topics covered in the course are based primarily on the experience of the six instructors which totals over 130 years of nuclear criticality safety related experience. Such a wealth of experience needs to be shared with the criticality safety community including both new professionals in the field as well as experienced professionals.

The course topics include illustrative applications using the SCALE system developed at Oak Ridge National Laboratory with emphasis on the Monte Carlo code KENO Va, standards, regulations, review of accidents, hand calculation methods, subcritical limits, code validation techniques, emergency response, process upsets and recovery actions, and transient excursion modeling.

The registration fee is $1195 per person for each course. The deadline for registration in these courses is August 1, 2000. For additional information contact Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 865-974-2525; email lutne@utk.edu). If you have access to the internet, you may also register via the website at http://www.engr.utk.edu/dept/nuclear/TIW.html.



SNA 2000

The Fourth International Conference on Supercomputing in Nuclear Applications (SNA 2000)

September 4-7, 2000, Toranomon-Pastoral, Tokyo, Japan, sponsored by Japan Atomic Energy Research Institute, cosponsored by OECD/Nuclear Energy Agency, Atomic Energy Society of Japan, Japan Nuclear Cycle Development Institute.

The objective of this conference is to present the newest research results in numerical simulations in a wide variety of scientific and engineering fields, and to promote and encourage the introduction of supercomputing technologies to numerical simulations. Contributions generally focus on large scale numerical simulations in application fields and supercomputing technologies. Papers on computational science and engineering simulations, whether they are small or large scale, are welcome.

Authors interested in contributing to the SNA 2000 are invited to submit manuscripts that report new technologies and practical experience related to numerical simulations in application fields and high performance computing and communication. Topics of interest include but are not restricted to the following:

Numerical Simulations in Application Fields

  • Reactor Engineering: Fission and fusion, Accelerator and beam, Reactor and neutron physics, Plant simulation, operation, and design.
  • Fluid Engineering: Turbulent flow, Multi-phase flow, Reactive flow, Heat transfer.
  • Structural Engineering: Thermal and structural analysis, Impact dynamics and stability, Computational fracture and damage mechanics, Fluid-structure interaction, Linear and nonlinear vibration.
  • Materials Science: Fracture, Brittle/ductile properties, Defects, Thermodynamic properties of materials.
  • Environmental Sciences: Air, marine and/or terrestrial pollution, Global climate change, Nuclear emergence response, Nuclear waste disposal.
  • Bioscience: Microdosimetry, Modeling of biological radiation effect, Dose calculation.
  • Radiation and Photon Science: Utilization of radiation fields (neutrons etc.), Laser and synchrotron radiation and their applications, Interaction of laser with matter.
  • Basic Research Fields: Computational physics and chemistry, Plasma physics, etc.

High Performance Computing and Communication

  • High Performance Computing Infrastructure: Highly parallel algorithms, Performance and benchmarking, Distributed parallel computing systems and networking, Parallel numerical libraries, Languages for high performance computing, Visualization and graphics.
  • High Performance Computing Systems: Next generation computers, Data storage systems, Special-purpose computers.

Hideo Kaburaki
Center for Promotion of Computational Science and Engineering
Japan Atomic Energy Research Institute
Tel. +81-3-5723-2513
Fax. +81-3-5723-2537
e-mail: sna2000@koma.jaeri.go.jp

http://ciscper.tokai.jaeri.go.jp/sna2k/





MC2000

The International Conference on Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications (MC2000) will be held October 23-26, 2000, in Lisbon, Portugal. At the International Conference, "Monte Carlo 2000 - Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications," all sessions will be dedicated to Monte Carlo issues. This Conference has been organized around three main categories of Monte Carlo simulations: Radiation Physics, Particle Transport Simulation and Applications involving electron-photon, neutron-gamma and hadronic codes. The following issues will be addressed:

  • Theory and methods
  • Physics and modeling issues
  • Algorithm developments
  • Computational Science
  • Basic data
  • Analysis of experiments and measurements
  • Benchmarks
  • Status of general-purpose codes
  • Tools (Graphics and Analysis)
  • Applications

The deadline for abstract submission is March 31, 2000. Inquiries regarding the conference can be addressed to: Instituto Tecnológico e Nuclear, MC2000 Conference Secretariat, Estrada Nacional 10, P-2686-953 Sacavem, Portugal (phone: +351-21-994 60 00 ext. 6154, fax +351-21-994 10 39, email mc2000@itn1.itn.pt, or Dr. Pedro Vaz, Technical and Scientific Program Co-ordinator at email vaz@nea.fr, url http://www.itn.pt/Meetings/MC2000/).



Calendar

Your attention is directed to the following events of interest.

April 2000

MCNP Advanced Class, 10-14 April, 2000, London. For registration information on the European classes, contact Enrico Sartori, OECD/NEA, sartori@nea.fr.



May 2000

PHYSOR 2000, May 7-11, 2000, Pittsburgh, Pennsylvania, sponsored by the Reactor Physics Section of the American Nuclear Society and the ANS Pittsburgh Section. Contact: Dr. Tom Congedo (phone 412-256-1084, fax 412-256-2444, email congedtv@westinghouse.com, url http://ans-pgh.commerce.wec.com/rp2000.htm).

Transport Processes in Applied Physics and Risk Analysis, A Tribute to Jacques Devooght, May 12, 2000, Brussels. Contact: Mrs. Nicole Detienne, Service de Chimie Organique, Faculté des Sciences Appliquées, Université Libre de Bruxelles, Bruxelles, Belgium (phone 32-02-6502048, fax 32-02-6503606, email ndetienn@ulb.ac.be, url http://mnsgi.ulb.ac.be/pub/pel/may12.html).

MCNP Introductory Class, 23-26 May, 2000, Los Alamos National Laboratory, New Mexico. To register for the LANL classes via the Internet, go to http://www.solutionsbyhqc.com/mcnpform.html or email Bill Hamilton at bill@solutionsbyhqc.com.



June 2000

International Workshop on Neutron Field Spectrometry in Science, Technology and Radiation Protection, June 5-8, 2000, Pisa, Italy. Contact Horst Klein, PTB, dep. 6.4 `Neutron Metrology', Bundesallee 100, D-38116 Braunschweig, Germany (phone 49-531-592-6400, fax 49-531-592-7205, email horst.klein@ptb.de).

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).

7th Workshop on Methodologies for Particle Transport Simulation of Nuclear Systems (Design, Dosimetry and Shielding), June 26-30, 2000, Penn State University, University Park, Pennsylvania. Contact: haghigha@gracie.psu.edu, or iaw@psu.edu or from the website at http://gracie.psu.edu/wshop02/wshop02.html.



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).

August 2000

Eighth International Conference on Electronic Spectroscopy and Structure (ICESS), Campus of the University of California, Berkeley, Aug. 8-12, 2000. Contact: icess@lbl.gov (url: http://www-als.lbl.gov/icess/).

Monte Carlo Analysis, Aug. 14-18, 2000, Knoxville, Tennessee, a short course by the University of Tennessee. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 865-974-2525; email lutne@utk.edu, http://www.engr.utk.edu/dept/nuclear/TIW.html.

Nuclear Criticality Safety, Aug. 14-18, 2000, Knoxville, Tennessee, a short course by the University of Tennessee. Contact: Lydia Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 865-974-2525; email lutne@utk.edu, http://www.engr.utk.edu/dept/nuclear/TIW.html).



September 2000

4th International Conference on Supercomputing in Nuclear Applications (SNA 2000), Sept. 4-7, 2000, Toranomon-Pastoral, Tokyo, Japan, sponsored by Japan Atomic Energy Research Institute, cosponsored by OECD/Nuclear Energy Agency, Atomic Energy Society of Japan, Japan Nuclear Cycle Development Institute. Contact: Hideo Kaburaki, Center for Promotion of Computational Science and Engineering, Japan Atomic Energy Research Institute (phone +81-3-5723-2513, fax +81-3-5723-2537, e-mail: sna2000@koma.jaeri.go.jp, http://ciscper.tokai.jaeri.go.jp/sna2k/).

Radiation Protection for our National Priorities: Medicine, the Environment, and the Legacy, Sept. 17-21, 2000, Spokane, Washington. Contact: Harvey Goldberg, ANS-EWS, P.O.Box 941, Richland, WA 99352 (email finfrock@ambinet.com).

SPECTRUM 2000, Chattanooga, Tennessee, Sept. 24-28, 2000. Contact: SPECTRUM 2000, University of Tennessee, Department of Nuclear Engineering, Knoxville, TN 37996-2300 (phone 865-974-5048, fax 419-828-4819, email spectrum2000@engr.utk.edu, url http://www.engr.utk.edu/spectrum/).

ICENES 2000, The 10th International Conference on Emerging Nuclear Energy Systems, Sept. 25-28, 2000, Petten, The Netherlands. Contact: Mrs. M. Hofman, Meeting Secretariat, NRG, P.O. Box 25, 1755 ZG Petten, The Netherlands (phone +31-224-56-4193, fax +31-224-56-3490, email hofman@nrg-nl.com, url http://www.nrg-nl.com/congres/icenes/).



October 2000

YUNSC 2000, Oct 2-5, 2000, Belgrade, Yugoslavia. Contact: Radojko Pavlovi, YUNSC 2000 Conference Secretary, The VINCA Institute of Nuclear Sciences, P.O.B. 522, 11001 Belgrade, Yugoslavia (phone + 381-11-453-867, fax + 381-11-455-943, email yuns@rt270.vin.bg.ac.yu).

MCNP and Visual Editor Training Course, Oct. 9-12, 2000, Richland, Washington. Contact: Randy Schwarz, MS K8-34, P. O. Box 999, Richland, WA 99352 (509-372-4042, fax 509-372-6421, email randy.schwarz@pnl.gov, url http://www.pnl.gov/eshs/software/ved.html).

2000 American Nuclear Society 14th Topical Meeting on the Technology of Fusion Energy, Oct. 15-19, 2000, Park City, Utah. Contact: url http://www.ambinet.com/ans/rps2000.htm.

4th International Workshop on Dosimetry for Radiation Processing, Oct. 22-27, 2000, San Diego, California. Contact: Dr. Harry Farrar IV, ASTM Committee E-10, 18 Flintlock Lane, Bell Canyon, CA 91307-1127 (phone 818-340-1227, fax 818-340-2132, email hfarrar4@aol.com).

International Conference on Advanced Monte Carlo for Radiation Physics, Particle Transport Simulation and Applications (MC2000), October 23-26, 2000, Lisbon, Portugal. Contact: Intituto Tecnológico e Nuclear, MC2000 Conference Secretariat, Estrada Nacional 10, P-2686-953 Sacavem, Portugal (phone: +351-21-994 60 00 ext. 6154, fax +351-21-994 10 39, email mc2000@itn1.itn.pt, or Dr. Pedro Vaz, Technical and Scientific Program Co-ordinator at email vaz@nea.fr, url http://lipulsi.lip.pt/mc2000/).



November 2000

5th Radiation Physics Conference--Atomic Energy, Radiation Protection, Challenges and Strategies, Nov. 5-9, 2000, Cairo, Egypt. Contact: Prof. Mohammad A. Gomaa, Atomic Energy Authority, 3 Ahmad Al-Zomor St., Alzohour District, Nasr City, Children Village Post Office, Postal Code 11787, Cairo, Egypt (fax 00202-287603, email ruatom@rusys.EG.net).



JANUARY ACCESSION OF LITERATURE

The following literature cited has been reviewed and placed in the RSICC Information Storage and Retrieval Information System (SARIS), now searchable on the RSICC web server (http://www-rsicc.ornl.gov/SARIS.html). This early announcement is made as a service to the shielding community. Copies of the literature are not distributed by RSICC. They may generally be obtained from the author or from a documentation center such as the National Technical Information Service (NTIS), Department of Commerce, Springfield, Virginia 22161. For literature listed as available from INIS contact INIS Clearinghouse, International Atomic Energy Agency, P.O. Box 100, A-1400 Vienna.

Radiation Shielding Literature

Health Phys., 78, 159-169 . . . A New Anthropometric Phantom for Calibrating In Vivo Measurements of Stable Lead in the Human Leg Using X-Ray Fluorescence. . . . Spitz, H.; Jenkins, M.; Lodwick, J.; Bornschein, R. . . . February 2000 . . . University of Cincinnati, Cincinnati, OH.

Health Phys., 78, 199-214 . . . Electron Absorbed Fractions and Dose Conversion Factors for Marrow and Bone By Skeletal Regions. . . . Eckerman, K.F.; Stabin, M.G. . . . February 2000 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Universidade Federal de Pernambuco, Recife, PE, Brazil.

Health Phys., 78, 215-221 . . . Effective Half-Lives for Patients Administered Radiolabeled Antibodies and Calculated Dose to the Public in Close Proximity to Patients. . . . Kaurin, D.G.L.; Carsten, A.L.; Baum, J.W. . . . February 2000 . . . Vanderbilt University Medical Center, Nashville, TN; Brookhaven National Laboratory, Upton NY.

Health Phys., 78, 226-227 . . . Anomalous Dose Assessment Associated with Film Badge Storage in a Controlled Area. . . . Hedrick, W.R.; Starchman, D.E. . . . February 2000 . . . Northeastern Ohio Universities College of Medicine, Canton, OH.

Nucl. Sci. Eng., 134, 121-134 . . . Two-Dimensional Discrete Ordinates Photon Transport Calculations for Brachytherapy Dosimetry Applications. . . . Daskalov, G.M.; Baker, R.S.; Little, R.C.; Rogers, D.W.O.; Williamson, J.F. . . . February 2000 . . . National Research Council of Canada, Ontario, Canada; Los Alamos National Laboratory, Los Alamos, NM; Washington University Medical School, St. Louis, MO.

Nucl. Sci. Eng., 134, 135-158 . . . Transport Synthetic Acceleration for Long-Characteristics Assembly-Level Transport Problems. . . . Zika, M.R.; Adams, M.L. . . . February 2000 . . . Lawrence Livermore National Laboratory, Livermore, CA; Texas A&M University , College Station, TX.

Nucl. Sci. Eng., 134, 159-170 . . . Transport Synthetic Acceleration with Opposing Reflecting Boundary Conditions. . . . Zika, M.R.; Adams, M.L. . . . February 2000 . . . Lawrence Livermore Laboratory, Livermore, CA; Texas A&M University, College Station, TX.

Nucl. Sci. Eng., 134, 171-200 . . . Neutron Activation Cross-Section Measurements from 16 to 20 MeV for Isotopes of F, Na, Mg, Al, Si, P, Cl, Ti, V, Mn, Fe, Nb, Sn, and Ba. . . . Fessler, A.; Plompen, A.J.M.; Smith, D.L.; Meadows, J.W.; Ikeda, Y. . . . February 2000 . . . Commission of the European Communities, Geel, Belgium; Argonne National Laboratory, Argonne, IL; Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

Nucl. Sci. Eng., 134, 201-207 . . . A Study of Transmitted Photon Spectra of 133Ba Through a Soil Medium. . . . Sidhu, G.S.; Singh, K.; Singh, P.S.; Mudahar, G.S. . . . February 2000 . . . Punjabi University, Patiala, India.

Nucl. Sci. Eng., 134, 208-217 . . . Attenuation Measurements in Solutions of Some Carbohydrates. . . . Singh, G.; Singh, K.; Lark, B.S.; Sahota, H.S. . . . February 2000 . . . Guru Nanak Dev University, Amritsar, India; Punjabi University, Patiala, India.

Nucl. Sci. Eng., 134, 218-226 . . . Submoment Expansion of Neutron-Scattering Sources. . . . Williams, M.L. . . . February 2000 . . . Louisiana State University, Baton Rouge, LA.

Nucl. Technol., 128, 285-299 . . . Comparisons of Calculated and Measured 237Np, 241Am, and 243Am Concentrations as a Function of the 240Pu/239Pu Isotopic Ratio in Spent Fuel. . . . Charlton, W.S.; Stanbro, W.D.; Perry, R.T.; Fearey, B.L. . . . December 1999 . . . Los Alamos National Laboratory, Los Alamos, NM.

Nucl. Technol., 128, 402-408 . . . The Effective Delayed Neutron Fraction for Bare-Metal Criticals. . . . Pearlstein, S. . . . December 1999.

KEK Preprint 99-111 . . . Improvement of Air Transport Data and Wall Transmission/Reflection Data in the SKYSHINE Code (2) Calculation of Gamma-Ray Wall Transmission and Reflection Data . . . Hayashida, Y.; Ishikawa, S.; Hayashi, K.; Hirayama, H.; Sakamoto, Y.; Harima, Y.; Nemoto, M. . . . October 1999.

KEK Preprint 99-109 . . . Application of Improved Air Transport Data and Wall Transmission/Reflection Data in the SKYSHINE Code to Typical BWR Turbine Skyshine. . . . Tayama, R.; Hirayama, H.; Sakamoto, Y.; Harima, Y.; Hayashida, Y.; Nemoto, M.; Ishikawa, S.; . . . October 1999.

KEK Preprint 99-110 . . . Improvement of Air Transport Data and Wall Transmission/Reflection Data in the SKYSHINE Code (1) Calculation of Line Beam Response Function for Gamma-Ray Skyshi . . . Nemoto, M.; Harima, Y.; Hirayama, H.; Sakamoto, Y.; Hayashi, K.; Hayashida, Y.; Ishikawa, . . . October 1999.

KEK Preprint 99-121 . . . Feasibility Studies of the Self-TOF Detector for High-Energy Neutron Measurements in Shielding Experiments. . . . Sasaki, M.; Nakao, M.; Shibata, T.; Nakao, N.; Nakamura, T. . . . October 1999 . . . Tohoku University Aoba, Miyagi, Japan; High Energy Accelerator Research Organization, Iabaraki, Japan.

ORNL/TM-13313 . . . Assessment of the Available 233U Cross-Section Evaluations in the Calculation of Critical Benchmark Experiments. . . . Leal, L.C.; Wright, R.Q. . . . October 1996 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

ORNL/TM-1999-300 . . . Evaluation of Prompt Fission Gamma Rays for Use in Simulating Nuclear Safeguard Measurements. . . . Valentine, T.E. . . . October 1999 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

JEFF Report 16 . . . Intercomparisons of Calculations Made for GODIVA and JEZEBEL. . . . . . . December 1999 . . . Nuclear Energy Agency, Issy-les-Moulineaux, France.

JEFF Report 15 . . . Light Water Reactor (LWR) Pin Cell Benchmark Intercomparisons. . . . . . . September 1999 . . . Nuclear Energy Agency, Issy-les-Moulineaux, France.

ICRU News . . . New ICRU Report on Nucelar Data for Neutron and Proton Radiotherapy and for Radiation Protection. . . . Chadwick, M.B.; DeLuca, P.M. Jr. . . . February 1999 . . . Los Alamos National Laboratory, Los Alamos, NM; University of Wisconsin - Madison, Madison, WI.

Bull. Res. Lab. Nucl. Reactor, 23, 24-25 . . . Nuclear Fuel Rod Bundle Thermal Hydraulics Analysis . . . . Ninokata, H. . . . 1999.

Bull. Res. Lab. Nucl. Reactor, 23, 26 . . . Coupling of Space-Dependent Neutron Kinetics Model with Thermal Hydraulics Analysis. . . . Ninokata, H. . . . 1999.

Bull. Res. Lab. Nucl. Reactor, 23, 28 . . . A Simple Analytical Method to Evaluate Transient Behaviors of Fast Reactors. . . . Ninokata, H.; Sawada, T. . . . 1999.

Bull. Res. Lab. Nucl. Reactor, 23, 30 . . . Study on Design of a Long Life Multipurpose Small Size Fast Reactor with Liquid Metallic-Fueled Core. . . . Ninokata, H. ;Sawada, T.; Netchaev, A. . . . 1999.

Bull. Res. Lab. Nucl. Reactor, 23, 33 . . . Fundamental Studies on Future Light Water Reactor Development. . . . Aritomi, M. . . . 1999.

Bull. Res. Lab. Nucl. Reactor, 23, 51-52 . . . Sensitivity Analysis of Nuclear Importance to One-Group Neutron Cross Sections. . . . Sekimoto, H.; Waris, A. . . . 1999.

Bull. Res. Lab. Nucl. Reactor, 23 56-57 . . . Study of the "Keff of the World" Problem in Monte Carlo Eigenvalue Calculation. . . . Obara, T.; Sekimoto, H. . . . 1999.

Bull. Res. Lab. Nucl. Reactor, 23, 81 . . . Trends Affecting Japanese and U.S. Nuclear Power Regulatory Policy and Practice and Potential Consequences. . . . Marcus, G.H. . . . 1999.

Bull. Res. Lab. Nucl. Reactor, 23, 82 . . . The Impacts of Tomeisei on Nuclear Power Regulation and Other Japanese Government Activities. . . . Marcus, G.H. . . . 1999.

Bull. Res. Lab. Nucl. Reactor, 23, 83 . . . Potential Uses of Risk Insites in Nuclear Regulation in Japan. . . . Marcus, G.H. . . . 1999.

KEK Proceedings 99-11; JHF-99-5 . . . ITER Project - Overview of EDA. . . . Seki, M. . . . August 1999 . . . JAERI, Ibaraki-ken, Japan.

KEK Proceedings 99-11, JHF-99-5 . . . ITER Project - Physics. . . . Shimada, M. . . . August 1999 . . . ITER JCT, Ibaraki-ken, Japan.

KEK Proceedings 99-11, JHF-99-5 . . . Accelerator-Driven Systems in Nuclear Power. . . . Ponomarev, L.I.; Artisyuk, V.V. . . . August 1999 . . . Russian Research Center "Kurchatov Institute"; Tokyo Institute of Technology.

KEK Proceedings 99-11, JHF-99-5 . . . Recent Results in the Experimental MCF-Study at Dubna Pasotron. . . . Ponomarev, L.I. . . . August 1999 . . . RRC "Kurchatov Institute" and MUCATEX, Moscow.

KEK Proceedings 99-11, JHF-99-5 . . . Recent uCF Research - uCF Experiment at RIKEN-RAL (1); X-Ray and Neutron Studies on Muon to Alpha Sticking in D-T uCF. . . . Ishida, K.; Nagamine, K.; Matsuzaki, T.; Nakamura, S.N.; Kawamura, N.; Sakamoto, S.; Iwasaki; Watanabe, I.; Tanase, M.; Kato, M.; Kurosawa, K.; Kudo, K.; Takeda, N.; Eaton, G.H . . . August 1999 . . . Institute of Physical and Chemical Research (RIKEN); High Energy Accelerator Research Organization (KEK-MSL); University of Tokyo (UT-MSL); Japan Atomic Energy Research Institute (JAERI); Electrotechnical Laboratory (ETL); Rutherford Appleton Laboratory (RAL).

KEK Proceedings 99-11, JHF-99-5 . . . Recent uCF Research - uCF Experiment at RIKEN-RAL (2) Measurement of the Kb/Ka Ratio for u-a Sticking X-Rays. . . Nakamura, S.N.; Nagamine, K.; Matsuzaki, T.; Ishida, K.; Kawamura, N.; Sakamoto, S.; Iwasaki; Tanese, M.; Kato, M.; Kurosawa, K.; Sugai, H.; Watanabe, I.; Kudo, K.; Takeda, N.; Eaton, G.H. . . . August 1999 . . . Institute of Physical and Chemical Research, Saitama, Japan; High Energy Accelerator Research Organization, Ibaraki, Japan; University of Tokyo, Tokyo, Japan; Japan Atomic Energy Research Institute, Ibaraki, Japan; Electrotechnical Laboratory, Ibaraki, Japan; Rutherford Appleton Laboratry, Oxon, United Kingdom.

KEK Proceedings 99-11, JHF-99-5 . . . Recent Study of Muon Catalyzed Fusions (uCF) RIKEN-RAL uCF Experiment Facility - III . . . Kawamura, N.; Nagamine, K. Matsuzaki, T.; Ishida, K.; Nakamura, S.N.; Sakamoto, S.; Tanase; Kato, M.; Kurosawa, K.; Sugai, H.; Kudo, K.; Takeda, N.; Eaton, G.H, . . . August 1999 . . . Institute of Physical and Chemical Research, Saitama, Japan; High Energy Accelerator Research Organization, Ibaraki, Japan; Japan Atomic Energy Research Institute, Ibaraki, Japan; Electrotechnical Laboratory, Ibaraki, Japan; Rutherford Appleton Laboratory, Oxon, United Kingdom.

KEK Proceedings 99-11, JHF-99-5 . . . High Purity Tritium Gas Supplied by JAERI for Muon Catalyzed Fusion Research at RIKEN-RAL Muon Facility. . . . Kato, M.; Kurosawa, K.; Sugai, H.; Tanase, M.; Matsuzaki, T.; Ishida, K. ;Nagamine, K. . . . August 1999 . . . JAERI, Ibaraki-ken, Japan; RIKEN, Saitama, Japan; High Energy Accelerator Research Organization, Ibaraki, Japan.

KEK Proceedings 99-11, JHF-99-5 . . . Comments on MuCF Experiment - Magnetized Target MuCF. . . . Takeda, T. . . . August 1999 . . . University of Electro-Communications.