Radiation Safety Information Computational Center
	Oak Ridge National Laboratory Post Office Box 2008 Oak Ridge, Tennessee 37831-6362 Managed by UT-Battelle, LLC for the U.S. Department of Energy under contract DE-AC05-00OR22725 Phone No. 865-574-6176 FAX 865-574-6182 Internet: PDC@ORNL.GOV http://www-rsicc.ornl.gov/rsic.html
No. 444	February 2002
"A gem is not polished without rubbing, nor a man made perfect without trials."  -- Chinese Proverb

• ANS Welcomes Abraham's Endorsement of Yucca Mountain
• Marston Responds to San Jose Newspaper
• NRC Codes Made Available
• Changes to the Computer Code and Data Collection
• TESTING THE WATERS
• CONFERENCES, COURSES, SYMPOSIA
• MACCS Meeting
• MCNP Course Announcement for 2002
• MCNPX Workshops for 2002 - UPDATE
• Practical MCNP for the HP, Medical Physicist, and RAD Engineer
• RESRAD News Update
• Radiopharmaceutical Internal Dosimetry
• Symposium on Radiation Measurements and Applications
• Visual Editor Classes
• CALENDAR
• ACCESSION of NUCLEAR SYSTEMS LITERATURE

LA GRANGE PARK, IL, January 10, 2002--Energy Secretary Spencer Abraham's endorsement of Yucca Mountain as a suitable repository for spent nuclear fuel and high-level nuclear waste is a giant step toward solving one of the most controversial issues involving nuclear energy, says the American Nuclear Society.

"We have high confidence that Yucca Mountain is a suitable site, and we applaud the Department of Energy's recommendation to proceed with the next stage of repository development, the application of a license for repository construction," said ANS Vice President/President-Elect Harold B. Ray. "The pre-closure and post-closure assessments of Yucca Mountain convince us that the combination of site and design features provide public health protection with a considerable margin of safety."

Following the adoption of the Nuclear Waste Policy Act of 1982, DOE was directed to find a site for disposing of highly radioactive materials. Many scientists have concluded that storing such material deep underground is the safest method.

The Yucca Mountain site, located about 90 miles northwest of Las Vegas, NV., is situated in a mountain range with a unique combination of rock characteristics and an extremely deep water table (800 to 1,000 feet below the level of the repository). It has undergone years of study by scientists, engineers and other nuclear experts. One such study was the Yucca Mountain Preliminary Site Suitability Evaluation (PSSE), which incorporated the most recent data from field and laboratory experiments, and examined many alternative models that have never before been explored.

Work performed by the DOE, national laboratories and other government agencies such as the U.S. Geological Survey and the Environmental Protection Agency provided an impressive comprehensive collection of interdisciplinary studies and reports. These studies concluded that the Yucca Mountain site is well suited to become the nation's first geological repository.

"We're confident that the DOE has selected and characterized a site that, with appropriate engineering design and operation, can meet with high confidence the regulatory standard for public health and safety," said Ray. "The PSSE shows that the site can meet the post-closure standard, and the analyses indicate that pre-closure health and safety protection are more than adequate."

ANS' confidence on the Yucca Mountain site is based on several factors, including:

--The project has demonstrated that the natural features of Yucca Mountain contribute very significantly to public health protection;

--The project has adopted a highly robust engineered barrier system employing multiple, independent barriers to provide long-term confinement of radionuclides; and

--DOE and the Nuclear Regulatory Commission will continue to conduct additional research and monitoring activities over the next several decades to further bolster confidence in the safety of the repository.

"We applaud the DOE for conducting such a credible interdisciplinary analysis demonstrating suitability of the Yucca Mountain site for this nation's high-level geological repository, and we are prepared to contribute to the next step of Yucca Mountain," said Ray. "It's clear the time has come for the administration to prepare a license application to the NRC for permission to construct and operate Yucca Mountain. This is an important step for the future of nuclear energy."
 

Dr. Theodore U. Marston, Vice President and Chief Nuclear Officer of EPRI located in Palo Alto, CA, wrote Brandon Bailey in response to his article "U.S. Favors Plan to Store Nuclear Waste in Nevada" published January 11, 2002, in the San Jose Mercury News.

Dear Mr. Bailey:

I would like to congratulate you on your well-balanced article on the Nuclear Waste Repository proposal. This is a very controversial topic and the public requires objective reporting so they can develop their own opinions on the subject. One fact that was not included in your article is that the proposed repository is located on the southwest boundary of the Nevada Test Site. Within a distance of 25 to 30 miles from Yucca Mountain most of the 828 underground nuclear tests were conducted. A number of the weapons tests were conducted deep in the ground at or near the water table. It is not feasible to remediate the Nevada Test Site. In contrast, the repository is located about a thousand feet above the water table.

I believe the public has the perception that Yucca Mountain is located in a pristine desert area, rather than in close proximity to where we have already impacted the ground with our nation's nuclear testing program. The addition of the used nuclear fuel in this region will have infinitesimal effect on the habitability of this area for future generations.

Thank you for your time and attention.
Very truly yours,
Ted
 
 

Four U.S. Nuclear Regulatory Commission (NRC) software packages which were transferred from the Energy Science and Technology Software Center, Oak Ridge, Tennessee 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-677/MESORAD 1.4

PSR-437/ORSMAC (U.S. distribution only)

PSR-438/PolyRes

PSR-440/FEP 4.16
 
 

A new package and a newly frozen package were added to the computer code software and data collection.

CCC-704/SlideRule 1.0
OP SYS: Windows
Language: C++
Computers: Pentium
Format: WinZip

Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed this rapid PC-based tool for estimating pertinent information needed to guide response team activities and help characterize some types of nuclear criticality accidents. The concept uses a series of sliding graphs that function similarly to a slide rule. This tool was developed with the promise that visual demonstration of trends (e.g., dose versus time or distance) are helpful to response personnel. The SlideRule provides rapid assessments for direct radiation approximations and is useful for solving for parameters that are dependent upon independent specific parameters such as variable shielding, distances, and anticipated time related radiation doses to personnel. The SlideRule is designed to provide estimates of the following:
 

• magnitude of the fission yield based on personnel or field radiation measurements,

• neutron- and gamma-dose at variable unshielded distances from the accident,

• the skyshine component of the dose,

• time-integrated radiation dose estimates at variable times/distances from the accident,

• 1-minute gamma radiation dose integrals at variable times/distances from the accident, and
• dose-reduction factors for variable thicknesses of steel, concrete, and water.

• exposure information about "accident victims,"

• estimates of potential exposures to emergency response re-entry personnel,

• estimation of future radiation field magnitudes, and

• fission yield estimates.

• low-enriched (5 wt % 235U) uranyl fluoride;

• damp, low-enriched (5 wt % 235U) UO2;

• high-enriched (93 wt % 235U) uranyl nitrate solution;

• high-enriched (93 wt % 235U) uranium metal; and

• damp, high-enriched (93 wt % 235U).

PSR-158/SAMMY-M6-Beta
OPSYS: Unix & Windows
Language: Fortran 77
Computers: Workstations & PC
Format: Unix tar & self-extracting Windows

Oak Ridge National Laboratory, Oak Ridge, Tennessee, contributed a newly frozen version of this code system for multilevel R-matrix fits to neutron and charged-particle cross-section data using Bayes' equations. SAMMY-M6-Beta, release December 2001, differs from previous versions (M5) primarily in that charged particles can be used for both incident and exit channels. The earlier release (M5) did not properly treat incident charged particles, although charged-particle final states were properly treated. SAMMY can now be used to analyze, for example, (n,alpha) or (alpha,n) reactions in addition to previously available options: transmission, elastic (both angle-integrated and differential), fission, inelastic, capture, and absorption cross sections, eta, self-indication, and certain types of integral data. Angle-differential reaction cross sections can also be treated in M6-beta.

Users should be aware that Version M6-Beta is essentially a pre-release of version M6. In order to make the incident-charged-particle version available as soon as possible, no attempt has been made to complete the update of the documentation (users' manual). Though "old" features of the code, and the new incident-charged-particle capability, have been thoroughly tested prior to this release, implementation is in preliminary stages.

The included PC executables were created on a Dell Dimension 4100 operating under Windows 2000 with Compaq Visual Fortran Professional Edition 6.5. All Unix systems require a Fortran compiler to create executables. SAMMY-M6-Beta was tested at RSICC on the following machines:

IBM RS/6000 Model 270 AIX 4.3.3 with XLF 7.1 and XLC 4.4
SUN UltraSparc 60 Solaris 2.6 using f77 V 5.0 or f90
HP B1000 under HP-UX B.10.20 using f77 10.2
DEC/Alpha 500au under Digial Unix 4.0D with Fortran 77 5.1-8
Micron P3 running Windows 2000 using included executables.

The package is transmitted on a CD with both Unix and Windows distribution files. The Unix tar file contains source codes, scripts, tutorials, and test cases for Unix and Linux users. The self-extracting compressed Windows file contains source codes, executables, batch files, and test cases for Windows PC users. Reference: ORNL/TM-9179/R5 (October 2000). Fortran; DEC Alpha (Unix and VMS), IBM RS/6000, SUN, HP, PC (P00158/IRISC/07).
 
 

The proposed courses, tutorials, etc. will be held depending on user interest and participation. For more information or support of this workshop please contact hatmakerna@ornl.gov or sartori@nea.fr.

Workshop/Tutorial (tentative) on AMPX-2000, the latest version of the AMPX cross-section processing system that is developed and maintained by the Oak Ridge National Laboratory (ORNL). AMPX-2000 processes nuclear data evaluations that conform to the Evaluated Nuclear Data File (ENDF/B) format specifications. AMPX-2000 has the capability to process ENDF/B formats through Version VI and generate continuous-energy or multigroup cross-section libraries for neutron and/or photon transport. The objective of the workshop is to introduce new and experienced users to AMPX-2000. The workshop consists of classroom instruction provided by the AMPX code developers with an emphasis on use of the code system to process nuclear data evaluations. The workshop will also provide the participants with the opportunity to use AMPX to process nuclear data evaluations. Upon completion of the workshop, participants will have an understanding of the code system and be able to use AMPX to process ENDF/B evaluations and generate cross-section data for use in radiation transport codes. The proposed Agenda for a 5-day Workshop/Tutorial follows:

Day 1 - The first day will provide an introduction to ENDF/B formats and concepts associated with cross-section data. Followed by an overview of the AMPX-2000 code system that will include a discussion of the modular design philosophy and special features associated with the code system. The history of its sponsorship, major releases, etc., will be covered. In addition, a comprehensive overview of the processing capabilities will be provided. Differences and similarities to the NJOY processing system will be reviewed as appropriate. The remaining part of the first day will be devoted to a description of the AMPX modules and procedures that are used to generate continuous-energy cross sections from ENDF/B evaluations. In addition, the AMPX modules and procedures for processing the ENDF/B collision kinematics data will be described in detail.

Day 2 - Classroom instruction for the second day will focus on the modules and procedures that are used to produce multigroup neutron and photon cross-section libraries. The morning session will emphasize the AMPX modules that relate to producing multigroup data (e.g., generating weighting spectra, resonance-parameter processing, thermal-data processing, etc.). Workshop participants will gain familiarity with the different types of data that are used to provide a multigroup dataset for transport calculations. The afternoon session will be devoted to "hands-on" exercises that emphasize the course material from the first two days of instruction. Participants will have the opportunity to prepare input for producing continuous-energy and multigroup data using AMPX-2000.

Day 3 - The third day will begin with a review of the classroom exercises from Day Two followed by additional discussions on multigroup library processing as needed. New AMPX capabilities for generating probability tables and covariance matrices will be discussed in the morning session. The afternoon session will be devoted to additional classroom exercises related to generating continuous-energy and multigroup data. In addition, workshop participants will have the opportunity to generate probability tables and process ENDF/B uncertainty data with AMPX-2000.

Day 4 - The fourth day will begin with a review of the sample problems of the preceding afternoon session followed by classroom instruction for the various resonance self-shielding treatments that are provided in the AMPX system. The material will build upon the information presented on Day Two and include discussions of modules and procedures that must be used to prepare the appropriate data to be used in the treatments. The afternoon session will provide classroom exercises that make use of the course material presented in the morning session.

Day 5 - The fifth day will provide a review of the problems investigated on Day Four. A discussion of various AMPX-2000 utility modules will be provided. AMPX-2000 produces data in a wide variety of formats and has the capability to interface with the NJOY code system. The material covered on Day Five will focus on the utility modules that are needed to perform specialized data manipulation tasks (e.g., convert data between NJOY and AMPX, compare data libraries, constructing and maintaining a special energy boundary library for group structures, procedures for constructing specialized 1/ES t functions, AMPX installation procedures for different computer platforms, etc).
 

SCALE - Criticality, Shielding, Source Term (tentative) - see the SCALE official Web page.
 

Tutorials on deterministic radiation transport codes (tentatively end of 2002). The intention is to present recently developed tools for modelling 3D problems, including automated mesh generation, (X-Y-Z), (R-THETA-Z) and the visualization of the corresponding results to facilitate interpretation and for improved documentation. Methods for 3D Sensitivity Analysis / Uncertainty Analysis should also be demonstrated. The Data Bank Executive Group has strongly recommended the development of such tools. If you are interested in participating, please fill in the form.
 

Workshop on Computing Radiation Dosimetry with embedded training course on MCNPX - Monte Carlo Code System for Multiparticle & High Energy Applications, to be held at the Instituto Tecnologico e Nuclear (ITN), Sacavem, Lisbon, Portugal, June 22-28, 2002. During the weekend of June 22-23, a series of tutorial lectures will be held followed by a daily tutorial lecture delivered by a senior expert on a subject related to the MCNPX module(s) being taught that day. The MCNPX specific training will be delivered June 24-28. If you are interested in participating, please fill in the form.
 

MCNP - Introductory or Advanced Course including MCNP5 Features, March 18-22 at the Imperial College, London.
 

PENELOPE (electron-photon transport) workshop with tutorial (2002, RSICC, Oak Ridge, Tennessee, USA).
 
 

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 alphabetically. Should you be involved in the planning/organization of such events, feel free to send your announcements and calls for papers via email to FINCHSY@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.
 
 

The Fourth Meeting of the International MACCS Users Group (IMUG) will be held on September 6, 2002, in the Principality of Monaco. The focus of the Fourth IMUG Meeting will be the exchange of technical information relating to the application of MACCS, MACCS2, and COSYMA codes to relevant problems involving atmospheric dispersion of radioactive materials and resulting consequences.

There is no fee to participate in the meeting, however for planning purposes, advance registration is requested. Everyone, including COSYMA users, are invited to present a paper. Please visit the website www.bnl.gov/est/IMUG2002 to find out about IMUG, register for the meeting or request notification of web updates. The website will be updated as additional information becomes available.
 
 

Registration: http://www-xdiv.lanl.gov/XCI/PROJECTS/MCNP/registration.html

MCNP home page: http://www-xdiv.lanl.gov/XCI/PROJECTS/MCNP/index.html

LANL contact: jfb@lanl.gov

European contact: sartori@nea.fr

The MCNP code developers will present several classes in 2002 in the United States and two classes in Europe. The dates for these classes are:
 

March 18-22	Advanced class	Imperial College of London, UK
April 9-12	Advanced class	Los Alamos, NM
May 14-17	Criticality calculations	Knoxville/Oak Ridge area
June 4-7	Introductory Class	Los Alamos, NM
July 30-August 1	Variance reduction class	Los Alamos, NM
September  (date to be decided)	Introductory class	Stuttgart, Germany

The introductory class is for people who have little or no experience with MCNP. The intermediate to advanced class will be held for people who have used MCNP and want to extend their knowledge and gain depth of understanding.

The classes will be based on MCNP5, that has a tentative release date of April 2002. The code and data package will be available through RSICC at a reduced rate to class participants. The new capabilities of version 5 will be covered.

The other capabilities on MCNP will also be covered, including: Basic geometry and advanced geometry, Source definitions, tallies, data, variance reduction, statistical analysis, criticality, plotting of geometry, tallies, and particle tracks, neutron/photon/electron physics.

All classes provide interactive computer learning. Time will be available to discuss individual questions and problems with MCNP experts or to pursue in more detail topics mentioned in the talks. Please note that other classes are offered based on MCNP. The classes mentioned here are the only ones that are taught by the people who develop and write MCNP.
 
 

Lead Teachers: Drs. John Hendricks, Gregg McKinney, Laurie Waters

Organizer: Hamilton Quality Consulting

More Information: http://mcnpxworkshops.com

Contact: bill@solutionsbyhqc.com

MCNPX homepage: http://mcnpx.lanl.gov
 

February 18-22	Introductory Workshop	Tokyo, Japan
*April 19-24 (Sun. off)	Intermediate Workshop	Santa Fe, NM
May 13-17	Introductory Workshop	Los Alamos, NM
June 24-28	Intermediate Workshop	Lisbon, Portugal

*Date changed from April 18-23

MCNPX is the LANL all-particle, all-energy (eV-TeV) Monte Carlo transport code based on MCNP4C, LAHET, CEM, etc. MCNPX has been in active development since 1995, sponsored by the particle accelerator community. It has now become an accepted tool for a broad range of applications by nuclear engineers, physicists, and scientists. The MCNPX development effort has expanded the use of the Los Alamos tools to applications such as APT, waste transmutation, accelerator shielding and health physics, particle beam cancer therapy, space shielding and cosmic ray analysis, single event effects in semiconductors, radiography, and more detailed analysis of the effects of light and heavy ions in matter. In addition, the entire functionality of MCNP4C is retained. New variance reduction and data analysis techniques, many adapted from high energy accelerator methodologies, have also been added, such as the extensive 'mesh tally' capability which allows up to 3-d plotting of particle tracks, fluence and fluence-derived quantities, energy deposition, next event estimator generation contributions and particle sources.

All workshops include hands-on instruction generally on PC Windows machines. Subject to participant export approval for the MCNPX beta test team, participants will be able to access the Fortran-90 version of MCNPX 2.4, the LA150 (150 MeV) cross-section data for over 40 isotopes for incident neutrons and protons, and 12 for photonuclear interactions, and a notebook of viewgraphs. Followup consultation for class participants will be provided.

Classes are taught directly by experienced MCNPX code developers and instructors. For more information on code versions and their capabilities, go to the MCNPX Workshops web site http://mcnpxworkshops.com.
 
 

DATE: May 6-10, 2002
FEE: $1,850 per person with the MCNP™ code package
($1,400 per person without code package)
PLACE: The Canyon School Complex, Los Alamos National Laboratory, New Mexico

Monte Carlo-type calculations are ideally suited to solving a variety of problems in radiation protection and dosimetry. 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, and 4.5 CM points by the American Board of Industrial Hygiene.

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. 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: Los Alamos National Laboratory, Group ESH-4, MCNP Class/David Seagraves, Mail Stop G761, Los Alamos, NM 87545.

Inquiries regarding registration and class space availability should be made to David Seagraves, 505-667-3241, 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.
 

This on-line course is designed to teach current techniques for calculating the radiation dose from radionuclides administered in nuclear medicine. Lectures include Internal Dose Assessment Techniques, Resources for Internal Dose Assessment in Nuclear Medicine, Kinetic Modeling, Standard Kinetic Models and Phantoms, Extrapolation of Animal Data, Bone Marrow Dosimetry, Study Design for Radiopharmaceutical Dose Assessment, Patient Specific Dosimetry, and Small Scale and Microdosimetry. Problem-solving exercises and a comprehensive on-line exam are included. Users completing the exam will receive a certificate of completion. Users may also interact with instructors by e-mail about any aspect of the course. The cost of this course is $495; access to the course is through www.internaldosimetry.com.

For questions or comments, contact either of the course instructors, Dr. Michael G. Stabin, (tel (615) 322-3190, fax (615) 322-3764, email michael.g.stabin@vanderbilt.edu) or Dr. Richard B. Sparks (tel (865) 938-4949, fax (865) 947-1550, email rsparks@creativedevelopment.com, url www.creativedevelopment.com, www.internaldosimetry.com).
 

 Argonne National Laboratory will conduct a training course on the RESRAD family of risk assessment codes. This DOE-cosponsored workshop will be conducted on March 5-8, 2002. The latest probabilistic versions of RESRAD 6.1 and RESRAD-BUILD 3.1 will be used. The tentative agenda of this workshop can be found on the RESRAD web site - http://web.ead.anl.gov/resrad/training/ AgendaMarch2002.htm. Space is limited. For more information, please visit http://web.ead.anl.gov/resrad/training/MarchWrkshp.cfm, or contact Carole Ealy at 630-252-5677 or carole_ealy@anl.gov).

The 10th in a series will be held May 21-23, 2002, at the University of Michigan, Ann Arbor. The program will emphasize research and recent development in ionizing radiation measurements. Proposed session topics are: radiation sources, including secondary target sources; detectors and detection systems; data acquisition and data analysis systems and methods; radiation spectroscopy; particle-induced X-ray emission and radiation-induced fluorescence; analytical standards and elemental analysis; new and unique applications of ionizing radiation; industrial radiography and tomography; nuclear methods in space exploration and planetary science. For more information see the website at: http://rma-symposium. engin.umich.edu/ or contact David K. Wehe at dkw@umich.edu.
 
 

The Visual Editor is a powerful visualization tool that can be used to rapidly create complex Monte Carlo N Particle (MCNP 4C2) geometry models, including lattices, universes, fills, and other geometrical transformations. The Visual Editor can:

Display MCNP 4C2 geometries in multiple plot windows.
Create surfaces and cells to build a geometry.
Create materials using the local xsdir file.
Store commonly used materials in a material library.
Sub-divide large cells into smaller cells.
Create cells containing universes and lattices.
Interactively set cell importances from the plot window.
Display source points and collision points in the plot window.

Three five-day classes will be held in 2002: March 18-22, June 17-21, and September 9-13, all in Richland, Washington. These classes will focus on the use of the visual editor, with an overview of MCNP. The fifth day is optional and will focus on using the Visual Editor and MCNP to do some example problems.

These classes will include computer demonstrations and exercises that will focus on creating and interrogating input files with the Visual Editor. Advanced visualization work using MCNP will also be demonstrated. The class will be taught on Pentium computers running the Linux operating system and Windows NT. Class attendees can use either the Linux or Windows version of the visual editor. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. Further information on these classes can be located at: http://www.mcnpvised.com/train.html, or by contacting Randy Schwarz (email randyschwarz@mcnpvised.com).
 
 

February 2002

Nuclear Criticality Slide Rule Workshop, Feb. 26-27, 2002, Oak Ridge, TN. Contact: Kay Lichtenwalter (fax 865-576-3513, email scalehelp@ornl.gov, url www.cped.ornl.gov/sliderule).

MCNPX Introductory Workshop, Feb. 18-22, 2002, Los Alamos, NM. Contact Bill Hamilton (tel 505-662-9097, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

SAMMY Workshop, Feb. 18-22, 2002, NEA, Paris, France. Contact: (Ali Nouri email ali.nouri@oecd.org or Nancy Larson email nml@ornl.gov, url www.nea.fr/html/dbdata/sammy.htm).

SAMMY Workshop, Feb. 25-Mar. 4, 2002, (exact schedule not yet available), Triste, Italy. Small part of the biannual "Workshop on Nuclear Reaction Data and Nuclear Reactors: Physics, Design and Safety," Feb 25-Mar. 28. (url http://www.ictp.trieste.it/cgi-bin/ICTPsmr/mkhtml/smr2html.pl?smr1398 /Announcement).
 

March 2002

Hardened Electronics and Radiation Technology (HEART) Conference, Mar. 11-15, 2002, Monterey, CA. Contact: Thomas Stringer, chair (tel 719-599-1719, fax 719-599-1991).

SCALE Source Terms and Shielding Course, Mar. 11-15, 2002, Oak Ridge, TN. Contact: Kay Lichtenwalter (fax 865-576-3513, email scalehelp@ornl.gov, url www.cped.ornl.gov/scale/trcourse.html).

SCALE KENO-VI Criticality Safety Course, Mar. 18-22, 2002, Oak Ridge, TN. Contact: Kay Lichtenwalter (fax 865-576-3513, email scalehelp@ornl.gov, url www.cped.ornl.gov/scale/trcourse.html).

Visual Editor Class, Mar. 18-22, 2002, Richland WA. Contact: Randy Schwarz (tel 509-372-4042, email randy.schwarz@mcnpvised.com, url http://mcnpvised.com/train.html).
 

April 2002

6th International Symposium on Fusion Nuclear Technology - ISFNT-6, Apr. 7-12, 2002, San Diego, CA. Contact Claudia Hennessy (email chennessy@vlt.ucsd.edu; url http://isfnt6.ucsd.edu).

Thirty-Eighth Annual Meeting of the National Council on Radiation Protection and Measurements, Apr. 10-12, 2002, Arlington, VA. Contact: William M. Beckner (tel 301-657-2652, fax 301-907-8768, url www.ncrp.com).

Back to the Future of Nuclear Technology, 2002 ANS Student Conference, Apr. 10-13, 2002, University Park, PA. Contact: Frank Buschman (tel 814-865-6351, email fxb129@psu.edu, url www.clubs.psu.edu/ANS).

12th Biennial RPSD Topical Meeting, Apr. 14-17, 2002, Santa Fe, NM. Hosted by the ANS Trinity Section and cosponsored by the Health Physics Society, L'Organisation de cooperation et de developpement/L'Agence pour l'energie nucleaire (OECD/AEN, and RSICC. Contact: (email rpsd2002@lanl. gov, url www.lanl.gov/RPSD2002/).

International Youth Nuclear Congress 2002, Apr. 16-20, 2002, Taejon, Korea. Contact: Alexandre Tsiboulia or Han Seong Son (email alexts@ippe.obninsk.ru,hsson@nanum.kaeri.re.kr, url http://www.iync.org).

Seventh International Radiopharmaceutical Dosimetry Symposium, Apr. 17-19, 2002, Nashville, TN. Contact: Michael Stabin (email michael.g.stabin@vanderbilt.edu, url http://www.doseinfo-radar.com/ symphome.html).

MCNPX Intermediate Workshop, Apr. 19-24, 2002, Santa Fe/Los Alamos, NM. Contact: Bill Hamilton (tel 505-662-9097, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details). *We will take Sunday off.

MCNP, EGS4 & BEAM Users Group Meeting, Apr. 22-24, 2002, Stoke-on-Trent, England. Contact: Craig Edwards (MCNEG Chairman) (tel + 44 (0) 1782 554070, fax + 44 (0) 1782 845140, email radphys@dial.pipex.com, url www.mcneg.org.uk).

International Conference on Wire System Aging, Apr. 23-25, 2002, Rockville, MD. Contact: Technical information: Jit Vora (tel 301-415-5833, fax 301-415-5151, email jpv@nrc.gov); registration information: Susan Monteleone (tel 631-344-7235, fax 631-344-3957, email susanm@bnl.gov, url http://www.bnl.gov/icwsa).

Radiation Transport Calculations Using the EGS Monte Carlo System, Apr. 29-May 2, 2002, Ottawa, Canada. Contact: Blake Walters, Ionizing Radiation Standards, National Research Council of Canada, Ottawa, Canada, K1A 0R6. (tel 613-993-2715, fax 613-952-9865, e-mail bwalters@irs.phy.nrc.ca, url www.irs.inms.nrc.ca/inms/irs/papers /egsnrc/brochure.html).
 

May 2002

Practical MCNP for the HP, Medical Physicist, and Rad Engineer, May 6-10, 2002, Los Alamos, NM. Contact: David Seagraves (tel 505-667-3241, fax 505-665-6071, email deseagraves@lanl.gov, url http://drambuie.lanl.gov/ ~esh4/mcnp.htm; technical questions to Dick Olsher, 505-667-3364, dick@lanl.gov).

MCNPX Introductory Workshop, May 13-17, 2002, Los Alamos, NM. Contact Bill Hamilton (tel 505-662-9097, email registrar@ mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

Symposium on Radiation Measurements and Applications, May 21-23, 2002, Ann Arbor, MI. Contact: General Chair David K. Wehe (tel 734-764-6215, email dkw@umich.edu, url http://rma-symposium.engin.umich.edu/).
 

June 2002

Topical Meeting: Industrial Radiation and Radioisotope Measurement Applications IRRMA-V A Class IV Topical, June 9-14, 2002, Bologna, Italy, co-sponsored by the American Nuclear Society. Contact: Prof. Jorge Fernandez, Chair (e-mail: jorge.fernandez@mail.ing.unibo.it).

ANS Annual Meeting, The Revival of the Nuclear Power Option, June 9-13, 2002, Hollywood, FL (url http://www.ans.org/).

Visual Editor Class, June 17-21, 2002, Richland WA. Contact: Randy Schwarz (tel 509-372-4042, email randy.schwarz@mcnpvised.com, url http://mcnpvised.com/train.html).

14th International Conference on High-Power Particle Beams and 5th International Conference on Dense Z-Pinches, June 23-28, 2002, Albuquerque, NM (email for general inquiries beams02@sandia.gov; url http://www.sandia.gov/BeamsDZP).

MCNPX Intermediate Workshop, June 24-28, 2002, Lisbon, Portugal. Contact Bill Hamilton (tel 505-662-9097, email registrar@ mcnpxworkshops.com, url http://mcnpxworkshops.com for details).
 

July 2002

Snowmass Fusion Summer Study, July 8-19, 2002, Snowmass Village, CO (url http://lithos.gat.com/snowmass/).
 

August 2002

Spectrum 2002, Exploring Science-Based Solutions and Technologies, 9th Biennial International Conference on Nuclear and Hazardous Waste Management, Aug. 4-8, 2002, Reno, NV. Contact: Dr. Richard Jacobsen (email jacor@inel.gov, url www.ans.org/spectrum).
 

September 2002

Fourth Meeting of the International MACCS Users Group (IMUG), September 6, 2002, in the Principality of Monaco (url http://www.bnl.gov/est/IMUG2002).

22nd Symposium on Fusion Technology - SOFT, Sept. 8-13, 2002, Helsinki, Finland. Contact: Symposium Secretary Mrs. Merja Asikainen (tel +358 9 456 6854; fax +358 9 456 7002; email: soft2002@vtt.fi; url http://www.vtt.fi/val/soft2002/).

Visual Editor Class, Sept. 9-13, 2002, Richland, WA. Contact: Randy Schwarz (tel 509-372-4042, email randy.schwarz@mcnpvised.com, url http://mcnpvised.com/train.html).

YUNSC 2002 - The 4th International Conference of Yugoslav Nuclear Society, Sept.30-Oct.3, 2002, Belgrade, Yugoslavia. Contact (tel ++381 11 454-796; fax ++381 11 444-74-57; email yuns@rt270.vin.bg.ac.yu, url http://www.vin.bg.ac.yu/YUNS).
 

October 2002

2002 International Topical Meeting on Probabilistic Safety Assessment (PSA '02), Oct. 6-10, 2002, Detroit, MI. Contact: Rebecca Steinman (phone 734-930-7500, email rls@adventengineering.com, url http://www-ners.engin.umich.edu/PSAConf/).

PHYSOR 2002, Oct. 7-10, 2002, Seoul, Korea, sponsored by the American Nuclear Society and hosted by the Korean Nuclear Society. Contact: Prof. Nam Zin Cho (tel +82-42-869-3819, fax +82-42-869-5859, email tpc@physor2002.kaist.ac.kr, url http://physor2002.kaist.ac.kr).

First Asian and Oceanic Congress for Radiation Protection (AOCRP-1), Oct. 20-24, 2002, Seoul, Korea, sponsored by the Korean Association for Radiation Protection (KARP). Contact: Dr. Myung-Jae Song (tel +82-42-870-0202, fax +82-42-870-0269, email mjsong@khnp.co.kr, url http://www.aocrp-1.com).

15th ANS Topical Meeting on the Technology of Fusion Energy, Nov. 17-21, 2002, Washington, DC. (url http://www.ans.org/).
 

November 2002

International Symposium on Standards and Codes of Practice in Medical Radiation Dosimetry, November 25-28, 2002, IAEA, Vienna. Contact: Dr. Ken R. Shortt (tel +43 1 2600 21664, fax +43 1 26007 21662, email Dosimetry@iaea.org, url http://www.iaea.org/worldatom/Meetings/ 2002/infcn96.shtml).
 

September 2003

International Conference on Supercomputing in Nuclear Applications, SNA 2003, September 22-24, 2003, Paris, France. Organizers: CEA, SFANS, co-organizer: OECD/NEA. (email SNA-2003@cea.fr, url http://SNA-2003.cea.fr).
 
 

The nuclear systems literature (shielding, safety, materials) cited below 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 nuclear sciences 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.

Ann. Nucl. Energy, 29, 645-647 . . . On the Multiplication Factor and Reactivity Definitions for Subcritical Reactor Systems. . . .Gandini, A. . . . April 2002 . . . University of Rome, Italy.

Ann. Nucl. Energy, 29, 659-671 . . . A Transverse Buckling Based Method in Core Neutronics Models Equivalence. . . . Dall'Osso, A. . . . April 2002 . . . Framatome, Paris La Defense Cedex, France.

Ann. Nucl. Energy, 29, 673-683 . . . Energetics of Core Disruptive Accident for Different Fuels for a Medium Sized Fast Reactor. . . . Singh, O.P.; Harish, R. . . . April 2002 . . . Indira Gandhi Centre for Atomic Research, Tamil Nadu, India.

Ann. Nucl. Energy, 29, 685-700 . . . Neutron Transport in Two Interacting Slabs. . . . Williams, M.M.R. . . . April 2002.

Ann. Nucl. Energy, 29, 701-716 . . . Study on the Control Rod Interaction Effect in RSG Gas Multipurpose Reactor (MPR-30). . . . Hong, L.P.; Taryo, T.; Sembiring, T.M.; Hiroshi, S.; Yoshitaka, N. . . . April 2002 . . . Indonesia National Atomic Energy Agency, Tangerang, Indonesia; Tokyo Institute of Technology, Japan; NAIS, Co. Inc., Ibaraki-ken, Japan.

Ann. Nucl. Energy, 29, 717-750 . . . Applications of an Adjoint Monte Carlo Method to the Underground Migration of Radionuclides Over Large Scales. . . . Smidts, O.F. . . . April 2002 . . . Université Libre de Bruxelles, Brussels, Belgium.

Ann. Nucl. Energy, 29, 761-766 . . . An Upgraded Version of the AMEBA PWR. . . . Novelli, A. . . . April 2002 . . . Politecnico di Milano, Milan, Italy.

Ann. Nucl. Energy, 29, 767-775 . . . An Evaluation of the Americium Insertion in Uo2 Fuel. . . . Costa, A.L.; Pereira, C. . . . April 2002 . . . UFMG, Belo Horizonte, MG, Brazil.

J. Nucl. Mater., 299, 181-198 . . . A Review of the Thermophysical Properties of MOX and UO₂ Fuels. . . . Carbajo, J.J.; Yoder, G.L.; Popov, S.G.; Ivanov, V.K. . . . December 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Kurchatov Institute, Moscow, Russian Federation.

J. Nucl. Mater., 299, 199-204 . . . New Aluminium-Rich Alkali Slag Matrix with Clay Minerals for Immobilizing Simulated Radioactive Sr and Cs Waste. . . . Qian, G.; Sun, D.D.; Tay, J.H. . . . April 2002 . . . Nanyang Technological University, Singapore.

J. Nucl. Mater., 299, 205-218 . . . Effect of Neutron Irradiation and Post-Irradiation Annealing on Microstructure and Mechanical Properties of OFHC-Copper. . . . Singh, B.N.; Edwards, D.J.; Toft, P. . . . December 2001 . . . Riso National Laboratory, Roskilde, Denmark; Pacific Northwest National Laboratory, Richland, WA.

J. Nucl. Mater., 299, 219-226 . . . The Structures of Two Sodium Uranyl Compounds Relevant to Nuclear Waste Disposal. . . . Li, Y.; Burns, P.C. . . . December 2001 . . . University of Notre Dame, IN.

J. Nucl. Mater., 299, 227-234 . . . Determination of the Defect Creation Mechanism in the Mono-Silicated Fluoroapatite. Disorder Modeling Under Repository Conditions. . . . Soulet, S.; Carpéna, J.; Chaumont, J.; Krupa, J-C.; Ruault, M-O. . . . December 2001 . . . CNRS-IN2P3, Orsay Campus, France; CEA-Cadarache, Saint-Paul-lez-Durance, France; Institut de Physique Nucleaire, Orsay, France.

J. Nucl. Mater., 29, 235-241 . . . A Working Hypothesis on Oxidation Kinetics of Zircaloy. . . . Yoo, H-I.; Koo, B-J.; Hong, J-O.; Hwang, I-S.; Jeong, Y-H. . . . December 2001 . . . Seoul National University, South Korea; Korea Atomic Energy Research Institute, Daejeon, South Korea.

J. Nucl. Mater., 299, 242-249 . . . Tritium Recovery From Nanostructured LiAlO₂. . . . Carrera, L.M. et al. . . . December 2001 . . . Instituto Nacional de Investigaciones Nucleares, Mexico; Universidad Autónoma Metropolitana, Mexico.

J. Nucl. Mater., 299, 250-259 . . . Activation Energy of UO₂ and UO_2+x Sintering. . . . Dehaudt, Ph.; Bourgeois, L.; Chevrel, H. . . . December 2001 . . . Commissariat à l'Energie Atomique, Grenoble, France.

J. Nucl. Mater., 299, 260-263 . . . Characterization of the New Uranium-Nickel Alloy U₁₀Ni₁₃. . . . Perricone, A.; Noël, H. . . . December 2001 . . . Université de Rennes, France.

J. Nucl. Mater., 299, 264-266 . . . Gibbs Free Energy of Formation of Liquid Lanthanide-Bismuth Alloys . . . Sheng, J.; Yamana, H.; Moriyama, H. . . . December 2001 . . . Kyoto University Kumatori, Osaka, Japan.

J. Nucl. Mater., 299, 267-270 . . . Hardening of Fe-Cu Alloys at Elevated Temperatures by Electron and Neutron Irradiations. . . . Tobita, T.; Suzuki, M.; Iwase, A.; Aizawa, K. . . . December 2001 . . . JAERI, Ibaraki-ken, Japan.

J. Nucl. Mater., 299, 271-273 . . . High Temperature Application of EDTA Solvents for Iron Oxide Removal. . . . Hur, D.H.; Lee, E.H.; Choi, M.S.; Chung, H.S.; Kim, U.C. . . . December 2001 . . . Korea Atomic Energy Research Institute, Daejeon, South Korea; Korea Electric Power Research Institute, Daejeon, South Korea.

J. Nucl. Mater., 299, 274-276 . . . Development of CaF₂ Special Refractory Components. . . . Ghosh, A.; Upadhyaya, D.D.; Prasad, R.; Suri, A.K. . . . December 2001 . . . Bhabha Atomic Research Centre, Mumbai, India.

Nucl. Technol., 136, 255-260 . . . Coupling Model: A Common-Cause-Failure Model with Consideration of Interpretation Uncertainties. . . . Kreuser, A.; Peschke, J. . . . December 2001 . . . Gesellschaft für Anlagen, Cologne, Germany.

Nucl. Technol., 136, 261-277 . . . Preliminary Frapcon-3Th Steady-State Fuel Analysis of ThO₂ and UO₂ Fuel Mixtures. . . . Loewen, E.P.; Wilson, R.D.; Hohorst, J.K.; Kumar, A.S. . . . December 2001 . . . Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID; Cooper Nuclear Station, Brownville, NE; University of Missouri-Rolla, MO.

Nucl. Technol., 136, 278-291 . . . BWR Reload Strategy Based on Fixing Once-Burnt Fuel Between Cycles. . . . Maag, E.M.; Knott, D. . . . December 2001 . . . The Perry Nuclear Power Plant, Perry, OH.

Nucl. Technol., 136, 292-300 . . . Development and Application of the Reactor Coolant On-Line Leakage Evaluation Model for Pressurized Water Reactors. . . . Liang, T.K.S.; Hung, H-J.; Chang, C-J. . . . December 2001 . . . Institute of Nuclear Energy Research, Lung-Tan, Taiwan.

Nucl. Technol., 136, 301-314 . . . Investigating the Stability Characteristics of Natural-Circulation Boiling Water Reactors Using Root Loci of a Reduced-Order Model. . . . Zboray, R.; De Kruuijf, W.J.M.; Van Der Hagen, T.H.J.J.; Van Dam, H. . . . December 2001 . . . Delft University of Technology, JB Delft, The Netherlands.

Nucl. Technol., 136, 315-330 . . . Numerical Methodology to Evaluate Fast Reactor Sodium Combustion. . . . Yamaguchi, A.; Takata, T.; Okano, Y. . . . December 2001 . . . Japan Nuclear Cycle Development Institute, Ibaraki, Japan.

Nucl. Technol., 136, 342-353 . . . Separation of Actinides from LWR Spent Fuel Using Molten-Salt-Based Electrochemical Processes. . . .Karell, E.J. et al. . . . December 2001 . . . Argonne National Laboratory, Argonne, IL.

Nucl. Technol., 136, 354-366 . . . Influence of Finite Absorption of Radionuclides on Radionuclide Migration in an Engineered Barrier System. . . . Matsuo, T.; Yoshida, T. . . . December 2001 . . . Power and Industrial Systems Research and Development Laboratory, Ibaraki-ken, Japan; Hitachi Ltd., Ibaraki-ken, Japan.

Nucl. Technol., 136, 367-370 . . . The Influence of Lewis Acid/Base Chemistry on the Removal of Gallium by Volatility from Weapons-Grade Plutonium Dissolved in Molten Chlorides. . . . Williams, D.F.; Del Cul, G.D.; Toth, L.M.; Collins, E.D. . . . December 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN; Electrochemical Systems, Knoxville, TN.

Nucl. Technol., 137, 1-10 . . . Feasibility Study of a Proliferation-Resistant Fuel Form for Plutonium Recycling. . . . Aghara, S.K.; Beard, C.A. . . . January 2002 . . . University of Texas, Austin, TX.

Nucl. Technol., 137, 10-27 . . . IIST and BETHSY Counterpart Tests on PWR Total Loss-of-Feedwater Transient with Two Different Bleed-and-Feed Scenarios. . . . Liu, T-J. . . . January 2002 . . . Institute of Nuclear Energy Research, Lungtan, Taiwan.

Nucl. Technol., 137, 28-46 . . . Percolation Cooling of the Three Mile Island Unit 2 Lower Head by Way of Thermal Cracking and Gap Formation. . . . Thomsen, K.L. . . . January 2002 . . . Riso National Laboratory, Roskilde, Denmark.

Nucl. Technol., 137, 47-59 . . . Transmutation of ¹²⁹I Using An Accelerator-Driven System. . . . Nishihara, K.; Takano, H. . . . January 2002 . . . JAERI, Ibaraki-ken, Japan.

Nucl. Technol., 137, 60-71 . . . Structure and Properties of Chromium- and Zinc-Oxide Layers Formed on Zircaloy-2 in High-Temperature Water. . . . Blajiew, O.L.; Matsuura, C.; Hiroishi, D.; Ishigure, K. . . . January 2002 . . . University of Tokyo, Japan.