Radiation Safety Information Computational Center
Oak Ridge National Laboratory
Post Office Box 2008
Oak Ridge, Tennessee 37831-6171

Managed by
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for the U.S. Department of Energy
under contract DE-AC05-00OR22725

Phone No. 865-574-6176
FAX 865-241-4046


No. 468 February 2004
"The bigger a man's head gets, the easier it is to fill his shoes." -- Henry A. Courtney

Kal Shure is in Failing Health

RSICC has been informed that Kal Shure, a pioneer in the shielding community at large, and previously a very active member of the radiation protection and shielding division (and a supporter of RSICC), is currently in failing health. He is now 78 years old. If you know Kal in person or by reputation, please send him and his wife Mina a card with best wishes. Kal is in a nursing home, but cards can be sent to him in care of his wife to: Kal and Mina Shure, 5903 Fifth Ave., Apt. B204, Pittsburgh, PA 15232.


Hugh C. Paxton passed away in Albuquerque on December 25, 2003. He was 94. Hugh enjoyed a life filled with many diverse experiences. His interests ranged from his work with colleagues in the field of nuclear physics to bird watching excursions with friends, observing wildlife, writing, photography, and treasured reunions with his brothers and sister and their extended families. Growing up in California, Hugh was awarded an A.B. degree from UCLA in 1930 and in 1937 earned his doctorate at UC Berkeley under Professor E.O. Lawrence. He married his sweetheart, Jean Nellis Thomson, soon after. Hugh's early work in nuclear physics included cyclotron technology at the College of France in Paris and Columbia University. Following were jobs involving wartime support in New York, Oak Ridge and Philadelphia. In 1948 he accepted a position as leader of the critical assemblies group at Los Alamos Scientific Laboratory where he worked until his retirement in 1976. His responsibilities involved development of peaceful uses of nuclear energy and nuclear reactor safety standards. Hugh is survived by his wife of 66 years, Jean; son Alan and wife Merideth; daughter, Susan and husband Joseph Gomez; granddaughter Jennifer and husband Gustav Verhulsdonck; granddaughter Carrie. Memorial contributions may be made to the Academic Scholarship Program; American Nuclear Society; 555 North Kensington Ave.; LeGrange Park, IL 60526. (Taken from the December 28, 2003, Albuquerque Journal.)

Changes to the Computer Code and Data Collection

There were no changes to the computer code and data collection this month.

Monthly Code Focus

As years have gone by many different codes and applications have been sent to RSICC for stewardship. We currently have over 1700 analytical code and data packages and distribute as many each year to 73 countries in the world. To help 'categorize' each package, we have developed a database of 'Subject Categories' to attach applications to the packages at RSICC. Doing so requires investigation into each code package, user feedback from end use statements, and extensive RSICC staff experience and analysis so that we can deliver useful information each month on the 30 different categories we have identified thus far. Links to the package abstracts are embedded into the WWW version of the RSICC Newsletter. Feedback from our Newsletter community is very valuable so please direct your comments and/or suggestions to PDC@ORNL.GOV. February's code focus is Human Factors Engineering.



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 FINCHSY@ornl.gov with "conferences" in the subject line by the 20th of each month. 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. Below is a condensed list of the conferences only listed chronologically. More details (if available) are listed alphabetically following the table.

Condensed Table of Conferences

Name of Conference Date and


Web Site Abstract/Paper Due Date
40th Annual Meeting of the National Council on Radiation Protection and Measurements Apr. 14-15, 2004

Arlington, Virginia

http://www.ncrp.com n/a
PHYSOR 2004 Apr. 25-29, 2004

Chicago, Illinois

www.physor2004.anl.gov passed
Current Topics in Monte Carlo Treatment Planning May 3-5, 2004

Montreal, Canada

http://mctp.medphys.mcgill.ca passed
International Conference on Radiation Shielding (ICRS-10) and Topical Mtg. on Radiation Protection & Shielding (RPS 2004) May 9-14, 2004

Funchal, Madeira Island (Portugal)

5th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids May 16-20, 2004

Dubrovnik, Croatia

ANS Annual Summer Meeting June 13-17, 2004

Pittsburgh, Pennsylvania


students call for papers

1st International Symposium on Radionuclide Therapy and Radiopharmeceutical Dosimetry Sept. 4-8, 2004

Helsinki, Finland

12th International Conference on the Physics of Highly Charged Ions Sept. 6-10, 2004

Vilnius, Lithuania

http://www.itpa.lt/hci2004/ Apr. 15, 2004
16th American Nuclear Society Topical Meeting on the Technology of Fusion Energy Sept. 14-16, 2004

Madison, Wisconsin

http://fti.neep.wisc.edu/tofe May 1, 2004
International Conference on Nuclear Data for Science and Technology "ND2004" Sept. 26-Oct. 1, 2004

Santa Fe, New Mexico

http://t16web.lanl.gov/nd2004/ paper:

Sept. 26, 2004

5th International Conference of Yugoslav Nuclear Society (YUNS) Sept. 27-30, 2004

Belgrade, Serbia & Montenegro

June 1, 2004
11th International Congress on Neutron Capture Therapy (ISNCT-11) Oct. 11-15, 2004

Boston, Massachusetts

future site
ANS Annual Winter Meeting and Nuclear Technology Expo Nov. 14-18, 2004

Washington, D.C.

Monte Carlo 2005 Topical Meeting Apr. 17-21, 2005

Chattanooga, Tennessee

call for papers
Twelfth International Symposium on Reactor Dosimetry May 8-13, 2005

Gatlinburg, Tennessee

announcement / call for papers in pdf
ANS Annual Summer Meeting June 5-9, 2005

San Diego, California


2004 Conferences

Current Topics in Monte Carlo Treatment Planning

This workshop will be held at McGill University, Montreal, Canada, from May 3-5, 2004, and aims to bring together medical physicists and researchers to discuss development, clinical implementation and clinical evaluation of Monte Carlo treatment planning techniques in radiotherapy. The meeting will have both invited speakers and proffered contributions and is designed to have plenty of opportunity for informal and in-depth discussions.

For details regarding registration, program, invited speakers, abstract submission, etc, please consult the workshop website: http://mctp.medphys.mcgill.ca. Early registration is encouraged as the number of participants will be limited to around 100.

1st International Symposium on Radionuclide Therapy and Radiopharmaceutical Dosimetry

The 1st International Symposium on Radionuclide Therapy and Radiopharmaceutical Dosimetry will take place in conjunction with the annual European Association of Nuclear Medicine (EANM) congress in Helsinki, Finland, September 4-8, 2004.

The format of the meeting has evolved from a series of seven interesting and important radiopharmaceutical and dosimetry symposia held approximately every 5 years since 1970, with distribution of published proceedings. The last meeting ("7th International Radiopharmaceutical Dosimetry Symposium") was held in Nashville, Tennessee in 2002.

The decisions of the scientific committee and the set-up of the program for Helsinki will be coordinated by the EANM Task Group on Dosimetry and EANM Therapy Committee. All organisational matters will be handled by the EANM.

A call for abstracts (also electronic) will go out in a few months, with authors notified of outcome in approximately May 2004. Contributors will be asked either to bring an electronic version of their manuscript to the meeting in September 2004 or to submit it within two months after the meeting; early plans are to have extended peer-reviewed abstracts published as a supplement to a journal.

Michael Lassmann Val Lewington

Chair T/G Dosimetry EANM Chair Therapy Committee EANM Lassmann@nuklearmedizin.uni-wuerzburg.de vjlewington@hotmail.com


5th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids

The 5th International Conference on Nuclear Option in Countries with Small and Medium Electricity Grids will be held in Dubrovnik, Croatia, May 16-20, 2004.

In view of the good response and success of the previous Dubrovnik conferences devoted to the needs and interests of countries with small or medium nuclear systems and electricity grids, the Dubrovnik 2004 conference will serve the same general purpose, with concentration on the topics which invited most interest in the previous conference. The Conference will consider the nuclear option from the point of view of resources, costs, technological, organizational and educational requirements, and environmental advantages. It will also focus on matters related to operational safety, fuel cycle, waste management and decommissioning.

The important goal of the Dubrovnik 2004 conference is to serve as a forum to promote regional co-operation and exchange of experience in the use of nuclear power and fuel cycle facilities among the small or medium European countries interested in the nuclear option.

For updated information please visit the Conference website http://hnd.zvne.fer.hr/ Dubrovnik2004, or contact the Conference secretariat at hnd2004@fer.hr.

5th International Conference of Yugoslav Nuclear Society (YUNS) - 2004

The Conference will be held September 27-30, 2004, at the Chamber of Commerce of the Republic of Serbia, Belgrade, Serbia & Montenegro. For more information visit http://www.vin.bg.ac.yu/YUNS/Yunsc2004.html.

12th International Conference on the Physics of Highly Charged Ions

HCI-2004 will be the 12th conference in an international series taking place every two years around the world. This years will be in Vilnius, Lithuania, September 6-10, 2004. Born in Stockholm in 1982, HCI became a major forum for the presentation and discussion of important new research results in the physics of the Highly Charged Ions. The conference will continue to emphasize basic, fundamental science at the atomic and molecular level, and its applications to important technology challenges. The opportunity will be given to provide insights in other disciplines where HCI-physics have strong impact like Nuclear Physics, Material Science, Radiation Chemistry, Radiobiology, etc.

Some important dates are: Second Announcement and call for papers January 2004; deadline for abstracts April 15, 2004; deadline for grant applications April 15, 2004; student housing reservation May 15, 2004; early registration deadline May 15, 2004. For more information, please email hci2004@itpa.lt or see the website: http://www.itpa.lt/hci2004/.

16th American Nuclear Society Topical Meeting on the Technology of Fusion Energy

The ANS Topical Meeting on the Technology of Fusion Energy will be held September 14-16, 2004, in Madison, Wisconsin. You are cordially invited to submit one-page abstract(s) describing work that is new, significant, and relevant to both magnetic and inertial fusion technologies. A Microsoft Word template that can be used to create the abstract is available on the TOFE website: http://fti.neep.wisc.edu/tofe.

The 16th Topical Meeting on the Technology of Fusion Energy (TOFE) will continue the tradition of stand-alone topical meetings originated in the early 1970's, continued through the 80's, and re-established in the year 2000 in Park City, Utah. The scope of the TOFE meeting is to provide a forum for sharing the exciting new progress that has been made in fusion research as well as presenting the future of the national and worldwide fusion program.

The two and a half day program of the 16th TOFE meeting will have plenary, oral, and poster sessions, including a mix of invited oral papers and a significant number of contributed oral and poster papers. Key deadlines follow: one-page abstracts (May 1, 2004); nominations for ANS-FED awards (May 31, 2004); notification to authors (June 1, 2004); early registration deadline (August 10, 2004); hotel reservation cutoff date (August 10, 2004); full papers due at the meeting (September 14, 2004).

21st Zurich Short Courses on Modeling and Computation of Multiphase Flows

Multiphase flows and heat transfer with phase change are of interest to researchers and engineers working in power, nuclear, chemical-process, oil-and-gas, cryogenic, space, micro-technology, and other industries. Courses similar to this one have been offered in the past at Stanford University, at the University of California-Santa Barbara and for 20 years now at ETH-Zurich; over 1200 participants attended the Zurich courses. These courses will be offered March 22-26, 2004, and hosted by the Swiss Federal Institute of Technology (ETH) in Zurich. You will find detailed information about the course, as well as a registration form, at http://www.lkt.mavt.ethz.ch/courses/multiphase/Short-Course.html.

Training Course on Decontamination and Decommissioning

Argonne National Laboratory (ANL) is offering this training course March 8-12, 2004, in Las Vegas, Nevada. The purpose of the course is to provide information on the basic steps in the decommissioning process and also to impart lessons learned from past experience in decommissioning. Elements learned at this training course will assist in decision-making, planning, and implementation associated with decommissioning. Moreover, a major objective of this training course is to demonstrate the need for early and complete project planning to achieve safe and cost-effective decommissioning. A registration fee of $1095.00 is required. A course description and registration form are available at http://www.td.anl.gov/D&D. Applicants are encouraged to register electronically. Early registration is highly recommended due to the limited class size.

International Conference on Nuclear Data for Science and Technology "ND2004"

The International Conference on Nuclear Data for Science and Technology will be held September 26-October 1, 2004, in Santa Fe, New Mexico. This is an OECD-Nuclear Energy Agency Conference, which is held approximately every 3 years. Recent conferences in this series were in Antwerp (1982), Santa Fe (1985), Mito (1988), Jüelich (1991), Gatlinburg (1994), Trieste (1997) and Tsukuba (2001). This International Conference focuses on nuclear data, their production, dissemination, testing and application. The data are produced through both experiment and theoretical models; they are compiled and evaluated to form data libraries for use in applications; and they are tested through benchmark experiments and a very wide range of applications. This Conference includes all of these activities with the goal of improving nuclear data for applications including fission and fusion energy, accelerator driven systems, accelerator technology, spallation neutron sources, nuclear medicine, environment, space, non-proliferation, nuclear safety, astrophysics and cosmology, and basic research. Please see the web site for more information: http://t16web.lanl.gov/nd2004/.

International Conference on Radiation Shielding (ICRS-10) and Topical Meeting on Radiation Protection & Shielding (RPS 2004)

The Tenth International Conference on Radiation Shielding (ICRS-10) and the Thirteenth Topical Meeting of the Radiation Protection and Shielding Division of the American Nuclear Society (RPS 2004) will be held May 9-14, 2004, in Funchal, Madeira Island (Portugal).

The local organization has been assigned to ITN (the Nuclear and Technological Institute, in Lisbon), a laboratory of the Portuguese Ministry of Science and Higher Education. At the international level, the joint organization is co-sponsored by the Nuclear Energy Agency (NEA) of the Organization for Economic Co-operation and Development (OECD), the Radiation Protection and Shielding Division (RPSD) of the American Nuclear Society (ANS), and the Radiation Safety Information Computational Center (RSICC, Oak Ridge National Laboratory).

It is anticipated that this will be the most important event in the areas of Radiation Shielding and Radiation Protection during 2004. For further information please refer to the Conference website at the following URL http://www.itn.mces.pt/ICRS-RPS. Please don't hesitate to contact the Conference Secretariat at icrs-rps@itn.mces.pt.

In addition, if you would be interested in serving on the Scientific Program Committee, and contribute to the success of the meeting by either submitting or encouraging colleagues to submit papers, and participating in the technical review process, please contact the Conference Secretariat at the above email and provide your name, organization, email and topics of interest or expertise. The Organizing Committee welcomes your comments and suggestions to make your meeting a success.

ICCR 2004

The ICCR 2004 meeting will be held May 10-13, 2004, in Seoul, Korea. Your active participation and contribution will make this conference successful. Additional information is available from the ICCR 2004 conference secretariat at Hanjin Travel Service Co., Ltd. (tel +82-2-726-5554, fax +82-2-778-2514, email jssong@hanjinpco.com, url http://www.iccr.info).

MCNP Courses

Registration: http://www-xdiv.lanl.gov/x5/MCNP/registration.html

MCNP home page: http://www-xdiv.lanl.gov/x5/MCNP/index.html

LANL contact: selcow@lanl.gov

European contact: sartori@nea.fr

Apr. 19-23 Intermediate/Advanced Tokyo, Japan
June TBA Introductory Los Alamos, NM

Introductory classes are for people who have little or no experience with MCNP. This class surveys the features of MCNP so the beginning user will be introduced to the capabilities of the program, and will have hands-on experience at running the code to solve simple 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.

The intermediate to advanced class will be held for people who have used MCNP and want to extend their knowledge and understanding of the code system.

The class will be based on MCNP5 and will cover the new capabilities of version 5. Attendees may elect to receive the new package. If you have previously received an older registered version of MCNP from RSICC, you may request that the MCNP5 package be sent to you at no charge. If you have not received an older version of MCNP from RSICC, you will be charged the applicable transmittal fee.

he other capabilities of MCNP will also be covered, including basic and advanced geometry, source definitions, tallies, data, variance reduction, statistical analysis, criticality, plotting of geometry, and particle tracks, neutron/photon/electron physics.

All classes provide interactive computer instruction. 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.

MCNP Visual Editor Classes

The Visual Editor is a powerful visualization tool that can be used to rapidly create complex Monte Carlo N Particle (MCNP5) geometry models, including lattices, universes, fills, and other geometrical transformations. The Visual Editor can:

Display MCNP5 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, and

Display source points and collision points in the plot window.

Training class is scheduled March 15-19, 2004, in Richland, Washington. The class 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.

The class combines 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 Windows 2000. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. For a more detailed description of this course, click here. Further information on this class can be located at: http://www.mcnpvised.com/train.html, or by contacting Randy Schwarz (email randyschwarz@mcnpvised.com).

MCNPX Workshops

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

Organizer: HQC Professional Services

Contact: bill@solutionsbyhqc.com

More Information: http://mcnpxworkshops.com

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

March 8-12 Intermediate Santa Fe, NM
May 3-7 Intermediate Lisbon, Portugal
June 14-18 Intermediate Houston, TX
July 12-16 Introductory Santa Fe, NM

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.

The 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. Follow-up consultation for class participants will be provided.

Classes are taught by experienced MCNPX code developers and instructors. More information on code versions and capabilities is available at MCNPX Workshops web site http://mcnpxworkshops .com.


The Chicago Section of the American Nuclear Society is pleased to announce that it will host the PHYSOR-2004 Topical Meeting, April 25-29, 2004, in Chicago, Illinois. The meeting is co-sponsored by the Reactor Physics Division of the ANS, OECD Nuclear Energy Agency, European Nuclear Society, Canadian Nuclear Society, and the Brazilian National Atomic Energy Commission. The conference will be held at the Hyatt Regency in downtown Chicago.

The title for the meeting is "The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments." The technical program will cover more than 15 topical focus areas. You are invited to visit the meeting website at www.physor2004.anl.gov to obtain updated information and to download a copy of the meeting announcement. Contact: Ray Klann, Technical Program Co-Chair, at 630-252-4305 or klann@anl.gov.

Practical MCNP for the HP, Medical Physicist, and Rad Engineer

DATES: June 7-11, 2004

FEE: $1,450 per person

PLACE: The MESA Complex, Room 130, University of New Mexico-Los Alamos Campus

Monte Carlo type calculations are ideally suited to solving a variety of problems in radiation protection and dosimetry. This course is aimed at the health physicist, 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 an overview of the MCNP code and the Monte Carlo method, 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. Students will 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 HSR-4, MCNP Class, David Seagraves, Mail Stop J573, Los Alamos, NM 87545.

Inquiries regarding registration and class space availability should be made to David Seagraves, 505-667-4959, fax: 505-665-7686, e-mail: dseagraves@lanl.gov. Technical questions may also be directed to Dick Olsher, 505-667-3364; e-mail: dick@lanl.gov.

Please note that this course is separate from and independent of the courses being offered by the MCNP and MCNPX Teams at LANL.

Short Course on "Introduction to Monte Carlo Treatment Planning"

Course Director: Charlie Ma, Ph.D. ; Course Coordinator: Jinsheng Li, Ph.D.

Contact information: Tel 215-728-5665, Fax: 215-728-4789; Email: js_li@fccc.edu

Webpage: http://www.fccc.edu/clinical/radiation_oncology/monte_carlo_course.html

Venue: Radiation Oncology, FCCC, Philadelphia, PA

Date: April 8-10, 2004

The course registration fee is $1600, which covers the course materials, two lunches, two dinners and refreshments. A set of software is free for the attendee. Discounts for students are available. Hotel information is available upon request.

The short course is designed to train future Monte Carlo RTP users and researchers in the use of Monte Carlo treatment planning software. The course will include didactic instruction and hands-on workshops. The course is specially suited for previous EGS4 and OMEGA/BEAM course participants, who want to expand their research into clinical RTP. A working knowledge of a Unix-based system is expected to run the Monte Carlo RTP software.

Enrollment will be limited to 20 people to facilitate instruction at the hands-on labs. So please register early. Registration will be strictly on a first-come basis. Please contact Dr. Jinsheng Li, at js_li@fccc.edu or see the website: http://www.fccc.edu/clinical/radiation_oncology/ monte_carlo_course.html.

2005 Conferences

Monte Carlo 2005 Topical Meeting

Monte Carlo 2005 will be held April 17-21, 2005, (Sunday-Thursday). The theme of the conference will be "The Monte Carlo Method: Versatility Unbounded in A Dynamic Computing World".

The conference site is the Chattanooga Marriott and Convention Center in Chattanooga, Tennessee. The conference will be hosted by the American Nuclear Society (ANS) Oak Ridge/Knoxville Section, with ANS Radiation Protection and Shielding Division (RPSD) as the sponsoring division and Mathematics and Computations Division (MCD) as a co-sponsor. Co-sponsors will also include Oak Ridge National Laboratory (ORNL), Radiation Safety Information Computational Center (RSICC) and the Organization for Economic Cooperation and Development (OECD) Nuclear Energy Agency Data Bank (NEADB).

The Monte Carlo method and its applications have been frequently addressed at several major conferences and workshops organized in recent years in the area of nuclear applications. Monte Carlo topics have included radiation shielding, radiation physics, medical physics, and high energy physics. Significant developments have taken place in computational and data issues, resulting in state-of-the-art computer codes and tools. Monte Carlo 2005 is the next in a series devoted to the topic, following Monte Carlo 2000 which was held in Lisbon, Portugal in October 2000.

Conference topics will include: Methods Advancements (Physics) (proton transport, neutron transport, gamma transport, electron transport, heavy ion transport); Nuclear Data Advancements (proton transport, neutron transport, gamma transport, electron transport, heavy ion transport); Mathematical and Computational Advances (experiments & benchmarks, mathematical advances, computational advances, visualization); Applications (reactor, medical, accelerator, neutron science, dosimetry, shielding, fuel cycle, waste management, space & aviation, fusion, criticality safety, non-nuclear applications).

The website is http://MonteCarlo2005.org. Full papers are due September 10, 2004. For information contact Bernadette Kirk (kirkbl@ornl.gov, 865-574-6176), General Chair, or Jeff Johnson (johnsonjo@ornl.gov, 865-574-5262), Technical Chair.


March 2004

MCNPX Intermediate Workshop, Mar. 8-12, 2004, Santa Fe, NM. Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops. com, url http://mcnpxworkshops.com).

Decontamination and Decommissioning Training Course, Mar. 8-12, 2004, Las Vegas, NV. Contact: Linda Legerski (tel 603-252-4836, fax 630-252-5287, email lindal@anl.gov, url http://www.td.anl.gov/D&D/).

Visual Editor for MCNP, Mar.15-19, 2004, Richland, WA. Contact: Randy Schwarz (email randyschwarz@ mcnpvised.com, url http://www.mcnpvised.com/ train.html).

21st Zurich Short Courses on Modeling and Computation of Multiphase Flows, Mar. 22-26, 2004, Zurich. Contact: Prof. G. Yadigaroglu (tel + 41 1 632 46 15, fax + 41 1 632 11 66, e-mail yadi@ethz.ch, url http://www.lkt.mavt.ethz.ch/courses/ multiphase/Short-Course.html).

April 2004

PHYSOR 2004 Reactor Physics Topical Meeting, Apr. 25-29, 2004, Chicago, IL. Jointly sponsored by the Reactor Physics Division of the ANS and the Nuclear Energy Agency of the OECD and others. Contact: Ray Klann (tel 630-252-4305, email klann@anl.gov, url http://www.physor2004.anl.gov/).

9th Workshop on Monte Carlo Simulation of Radiotherapy Treatment Sources Using the BEAM Code System, Apr. 26-29, 2004, Ottawa, Canada. Contact: Dave Rogers (tel 613-520-2600 x4374, fax 613-520-4061, email drogers@physics.carleton.ca, url www.physics.carleton.ca/~drogers/BEAM/course/brochure.html).

May 2004

Current Topics in Monte Carlo Treatment Planning, May 3-5, 2004, McGill University, Montreal, Canada. Contacts: Jan Seutjens and Frank Verhaegen (tel 514-934-8052, url http://mctp.medphys.mcgill.ca).

MCNPX Intermediate Workshop, May 3-7, 2004, Lisbon, Portugal Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

International Conference on Radiation Shielding (ICRS-10) and Topical Mtg. on Radiation Protection & Shielding (RPS 2004), May 9-14, 2004, Funchal, Madeira Island (Portugal). Contact: Conference Secretariat (email icrs-rps@itn.mces.pt, url http://www.itn.mces.pt/ICRS-RPS).

5th Intl. Conference on Nuclear Option in Countries with Small and Medium Electricity Grids, May 16-20, 2004., Dubrovnik, Croatia, Contact Prof. Nenad Debrecin (tel +385- 1-6312-399, email hnd2004@fer.hr, url http://hnd.zvne.fer.hr/Dubrovnik2004).

June 2004

Practical MCNP for the HP, Medical Physicist, and Rad Engineer, June 7-11, 2004, Univ. of New Mexico, Los Alamos Campus. Contact: David Seagraves, (tel 505-667-4959, fax 505-665-7686, e-mail dseagraves@lanl.gov. Technical questions may also be directed to Dick Olsher, 505-667-3364; e-mail dick@lanl.gov, url http://drambuie.lanl.gov/~esh4/mcnp.htm).

MCNPX Intermediate Workshop, June 14-18, 2004, Houston, TX. Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

July 2004

MCNPX Introductory Workshop, July 12-16, 2004, Santa Fe, NM. Contact: Bill Hamilton (tel 505-455-0312, email registrar@mcnpxworkshops.com, url http://mcnpxworkshops.com for details).

September 2004

1st International Symposium on Radionuclide Therapy and Radiopharmaceutical Dosimetry, Sept. 4-8, 2004, Helsinki, Finland. Contact: Michael Lassmann or Val Lewington, (emails lassmann@ nuklearmedizin.uni-wuerzburg.de; vjlewington@ hotmail.com).

16th American Nuclear Society Topical Meeting on the Technology of Fusion Energy, Sept. 14-16, 2004, Madison, WI. (url http://fti.neep.wisc.edu/tofe).

International Conference on Nuclear Data for Science and Technology "ND2004", Sept. 26-Oct. 1, 2004, Santa Fe, NM. (Contact: http://t16web.lanl.gov/nd2004/).

5th International Conference of Yugoslav Nuclear Society (YUNS) - 2004, Sept. 27-30, 2004, Belgrade, Serbia & Montenegro. Contact: Dr. Milan Pesic, (tel 381-11-245-82-22/ext. 681, email mpesic@vin.bg.ac.yu, url http://www.vin.bg.ac.yu/YUNS/index.htm).

October 2004

11th World Congress on Neutron Capture Therapy (ISNCT-11), Oct. 11-15, 2004, Boston, MA. Contact: Robert G. Zamenhof (tel 617-636-1681, fax 617-636-5867, email rzamenhof@tufts-nemc.org, url http://meetingsandconferences.com/ISNCT-11/).

April 2005

Monte Carlo 2005 Topical Meeting, Apr. 17-21, 2005, Chattanooga, TN. Contact: Bernadette Kirk (tel 865-574-6176, fax 865-241-4046, email kirkbl@ornl.gov, url http://meetingsandconference.com /MonteCarlo2005).


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). We now include medical physics in addition to material science, radiation dosimetry, radiation safety, reactor dynamics, reactor safeguards, risk assessment, waste management, fuel cycle, fusion and plasmas, high energy particle transport, and shielding. 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.

Ann. Nucl. Energy, 30, 1821-1828. . . Cross-Section Measurements for the 97Mo (n,p) 97mNb Reaction at the Neutron Energies from 13.6 to 14.9 MeV. . . .Bostan, M. et al. . . . December 2003. . . Istanbul University, Turkey; Cekmece Nuclear Research & Training Center, Istanbul, Turkey.

Ann. Nucl. Energy, 30, 1829-1845. . . Introducing the Migration Mode Method for the Solution of the Space and Energy Dependent Diffusion Equation. . . .Dall-Osso, A. . . . December 2003. . . Framatome ANP, Cedex, France.

Ann. Nucl. Energy, 30, 1847-1862. . . Measurements of the (n,np+d) Activation Cross Sections with 13.4-14.9 MeV Neutrons Using a Fusion Neutronics Source/JAERI. . . .Sakane, H. et al. . . . December 2003. . . Nagoya University, Japan; JAERI, Ibaraki-ken, Japan.

Ann. Nucl. Energy, 30, 1879-1898. . . Improved Performances of the Fast Reactor Calculational System ERANOS-ERALIB1 Due To Improved A Priori Nuclear Data and Consideration of Additional Specific Integral Data. . . .Fort, E. et al. . . . December 2003. . . Commissariat a l'Energie Atomique, St.-Paul-Lez-Durance, France; AEA Technology, Dorset, UK; Electricite de France, Villeurbanne, France; Framatome, Lyon Cedex, France.

Ann. Nucl. Energy, 30, 1899-1903. . . Immobilization of 137Cs and 60Co in Concrete Matrix. . . .Plecas, I. . . . December 2003. . . None listed.

Ann. Nucl. Energy, 30, 1905-1917. . . On the Use of Silicon as Thermal Neutron Filter. . . .Adib, M. et al. . . . December 2003. . . NRC, AEA, Cairo, Egypt; Ain Shames University, Cairo, Egypt.

Ann. Nucl. Energy, 30, 1921. . . Erratum to: An Application of the Wiener-Hopf Method to the One-Speed Flat-Flux Problem in a Half-Space [Ann. Nucl. Energy, 30 (2003) 1333-1345]. . . .Cassell, J.S. et al. . . . December 2003. . . London Metropolitan University, UK; Imperial College of Science , London, UK.

Ann. Nucl. Energy, 31, 9-23. . . Proof of the Formula for the Ideal Gas Scattering Kernel for Nuclides with Strongly Energy Dependent Scattering Cross Sections. . . .Rothenstein, W. . . . January 2004. . . Technion-Israel Institute of Technology, Haifa, Israel.

Ann. Nucl. Energy, 31, 25-42. . . Some Aspects of Random Geometry and Absorption in Multiplying Systems and the Pulsed Neutron Problem. . . .Williams, M.M.R. . . . January 2004. . . Imperial College of Science, London, UK.

Ann. Nucl. Energy, 31, 43-53. . . Heuristic Derivation of the Rossi-Alpha Formula for a Pulsed Neutron Source. . . .Baeten, P, . . . January 2004. . . SCK-CEN, Mol, Belgium.

Ann. Nucl. Energy, 31, 55-69. . . The Fuzzy Clearing Approach for a Niching Genetic Algorithm Applied to a Nuclear Reactor Core Design Optimization Problem. . . .Sacco, W.F. et al. . . . January 2004. . . Universidade Federal do Rio de Janeiro, Brazil; Comissao Nacional de Energia Nuclear, Rio de Janeiro, Brazil.

Ann. Nucl. Energy, 31, 71-86. . . Analytic Derivation of the Correction Factor for the Improved Coarse Mesh Method. . . .Yamamoto, A. . . . January 2004. . . Nagoya University, Japan.

Ann. Nucl. Energy, 31, 87-96. . . Feasibility Study of Iridium Production at ETRR-2. . . .Abou-Zaid, A.A. et al. . . . January 2004. . . AEA, Cairo, Egypt.

Ann. Nucl. Energy, 31, 97-106. . . Experimental Studies on Measurements of Mass Attenuation Coefficients of Boric Acid at Different Concentration. . . .Icelli, O. et al. . . . January 2004. . . Ataturk University, Erzincan, Turkey.

Ann. Nucl. Energy, 31, 107-115. . . Effects Analysis Fuzzy Inference System in Nuclear Problems Using Approximate Reasoning. . . .Guimaraes, A.C.F. et al. . . . January 2004. . . Instituto de Engenharia Nuclear, Rio de Janeiro, Brazil.

Ann. Nucl. Energy, 31, 117-133. . . Theoretical Derivation of the Interaction Effects with Expansion Effects to Bubbly Two-Phase Flows. . . .Espinosa-Paredes, G. et al. . . . January 2004. . . Universidad Autonoma Metropolitana-Iztapalapa, Mexico; Instituto Mexicano del Petroleo, Mexico.

Ann. Nucl. Energy, 31, 135-149. . . Neutronics and Thermal Effects of Graphite Foams in the Performance of Nuclear Energy Systems. . . .Difilippo, F.C. . . . January 2004. . . Oak Ridge National Laboratory, Oak Ridge, TN.

Ann. Nucl. Energy, 31, 151-161. . . BWR Fuel Reloads Design Using a Tabu Search Technique. . . .Castillo, A. et al. . . . January 2004. . . Instituto Nacional de Investigaciones Nucleares, Edo. de Mexico, Mexico; Universidad Nacional Autonoma de Mexico, Mexico; Instituto Politecnico Nacional, Mexico.

Ann. Nucl. Energy, 31, 163-172. . . Experimental Investigation of Variance-To-Mean Formula for Periodic and Pulsed Neutron Source. . . .Kitamura, Y. et al. . . . January 2004. . . Nagoya University, Japan; Kyoto University, Osaka, Japan.

Ann. Nucl. Energy, 31, 173-196. . . The Burnup Capabilities of the Deep Burn Modular Helium Reactor Analyzed by the Monte Carlo Continuous Energy Code MCB. . . .Talamo, A. et al. . . . January 2004. . . Royal Institute of Technology, Stockholm, Sweden; Los Alamos National Laboratory, Los Alamos, New Mexico.

Ann. Nucl. Energy, 31, 197-212. . . Theoretical and Experimental Investigations of Reactor Parameters in a U-233 Fueled Research Reactor. . . .Mohapatra, D.K. et al. . . . January 2004. . . Indira Gandhi Centre for Atomic Research, Kalpakkam, India.

Ann. Nucl. Energy, 31, 213-225. . . Transport-Burnup Code Systems and Their Applications for IAEA ADS Benchmark. . . .Xiaofeng Jiang et al. . . . January 2004. . . Xi'an Jiaotong University, Shaanxi, China.

Ann. Nucl. Energy, 31, 231-253. . . Discrete Formulation for Two-Dimensional Multigroup Neutron Diffusion Equations. . . .Vosoughi, N. et al. . . . February 2004. . . Sharif University of Technology, Tehran, Iran; Atomic Energy Organization of Iran, Tehran, Iran; University

of Trieste, Italy; Shahid Beheshti University, Tehran, Iran.

Ann. Nucl. Energy, 31, 255-275. . . Effects of Dispersed Flow Interfacial Area/Shear Modeling and Node Size in the Core on TRAC-BF1 Rod Surface Temperature (RST) Histories of Separate-Effect and System Calculations. . . .Analytis, G. Th. . . . February 2004. . . Paul Scherrer Institute, Villigen, Switzerland.

Ann. Nucl. Energy, 31, 277-301. . . Sensitivity Analysis and Fuzzy Modelling for Passive Systems Reliability Assessment. . . .Zio, E. et al. . . . February 2004. . . Polytechnic of Milan, Italy.

Ann. Nucl. Energy, 31, 303-309. . . A PHWR With Slightly Enriched Uranium. About the First Core. . . .Notari, C. . . . February 2004. . . AEC of Argentina, Buenos Aires, Argentina.

Ann. Nucl. Energy, 31, 311-322. . . Fuzzy Inference System for Evaluating and Improving Nuclear Power Plant Operating Performance. . . .Guimaraes, A.C.F. et al. . . . February 2004. . . Instituto de Engenharia Nuclear, Rio de Janeiro, Brazil.

Ann. Nucl. Energy, 31, 323-329. . . Indications of the Validity of the Liquid Drop Model for Spontaneous Fission Half-Lives. . . .Ronen, Y. . . . February 2004. . . Ben-Gurion University of the Negev, Beer-Sheva, Israel.

Ann. Nucl. Energy, 31, 331-341. . . Measurement of the Syrian MNSR Delayed Neutron Fraction and Neutron Generation Time By Noise Analysis. . . .Khamis, I. et al. . . . February 2004. . . Atomic Energy Commission of Syria, Damascus, Syria.

Ann. Nucl. Energy, 31, 343-356. . . Development of BWR Control Rods Pattern Design System Based on Fuzzy Logic and Knowledge. . . .Francois, J-L. et al. . . . March 2004. . . Universidad Nacional Autonoma de Mexico, Mor., Mexico.

Ann. Nucl. Energy, 31, 357-373. . . Liquid Velocity in Upward and Downward Air-Water Flows. . . .Sun, X. et al. . . . March 2004. . . Purdue University, West Lafayette, IN.

Ann. Nucl. Energy, 31, 375-397. . . Identification Method of Stochastic Nonlinear Dynamics Using Dynamical Phase Analysis-Application to Forsmark Data. . . .Watanabe, F. et al. . . . March 2004. . . Tepco Systems Corp., Tokyo, Japan; University of Tsukuba, Ibaraki, Japan; Toshiba Corp., Yokohama-City, Japan.

Ann. Nucl. Energy, 31, 399-411. . . Beam Optimization: Improving Methodology. . . .Quinteiro, G.F. . . . March 2004. . . Comision Nacional de Energia Atomica, Buenos Aires, Argentina.

Ann. Nucl. Energy, 31, 413-429. . . A Comparative Physics Study of Alternative Long-Term Strategies for Closure of the Nuclear Fuel Cycle. . . .Cometto, M. et al. . . . March 2004. . . Paul Scherrer Institute, Villigen, Switzerland; Swiss Federal Institute of Technology, Lausanne, Switzerland; Huttenacherstrasse, Oberrohrdorf, Switzerland.

Ann. Nucl. Energy, 31, 431-457. . . Genetic Algorithms and Artificial Neural Networks for Loading Pattern Optimisation of Advanced Gas-Cooled Reactors. . . .Ziver, A.K. et al. . . . March 2004. . . Imperial College of Science, London, UK; British Energy Generation, Ltd., Gloucester, UK.

Ann. Nucl. Energy, 31, 459-480. . . Minimizing the Gamma Radiation Effects to Spent Fuel Pool Walls.' . . .Tippayakul, C. et al. . . . March 2004. . . Penn. State University, PN; Exelon Corp. USA.

Ann. Nucl. Energy, 31, 481-516. . . Probabilistic Safety Analysis of a Greek Research Reactor. . . .Aneziris, O.N. et al. . . . March 2004. . . National Center for Scientific Research, Aghia Paraskevi, Greece.

Ann. Nucl. Energy, 31, 517-540. . . Development, Assessment and Application of TRAC-BF1/v2001.2 for Beyond Design Basis BWR LOCA Transients. . . .Analytis, G. Th. et al. . . . March 2004. . . Paul Scherrer Institute, Villigen, Switzerland.

Ann. Nucl. Energy, 31, 541-576. . . Minimum Critical Mass and Flat Flux in a 2-Group Model. . . .Lewins, J. . . . March 2004. . . University of Cambridge, UK.

Ann. Nucl. Energy, 31, 577-582. . . The Photon Attenuation Coefficients of Barite, Marble and Limra. . . .Akkurt, I. et al. . . . March 2004. . . Suleyman Demirel University, Isparta, Turkey.

Nucl. Eng. & Design, 226, 83-96. . . Reference Stress Based Fracture Mechanics Analysis for Circumferential Through-Wall Cracked Pipes: Experimental Validation. . . .Kim, Y-J. et al. . . . December 2003. . . Sungkyunkway University, Kyonggi-do, South Korea.

Nucl. Eng. & Design, 226, 97-105. . . Friction and Wear of Inconel 690 and Inconel 600 for Steam Generator Tube in Room Temperature Water. . . .Lim, M-K. et al. . . . December 2003. . . Sungkyunkwan University, Kyung-Gi-Do, South Korea.

Nucl. Eng. & Design, 226, 107-118. . . The 3D Surface Crack-Front Constraints in Bimaterial Joints. . . .Lee, H. . . . December 2003. . . Sogang University, Seoul, South Korea.

Nucl. Eng. & Design, 226, 119-125. . . Dynamic Material Property Characterization by Using Split Hopkinson Pressure Bar (SHPB) Technique. . . .Lee, O.S. et al. . . . December 2003. . . InHa University, Incheon, South Korea.

Nucl. Eng. & Design, 226, 127-140. . . The Effects of the Stainless Steel Cladding in Pressurized Thermal Shock Evaluation. . . .Jang, C. et al. . . . December 2003. . . Korea Institute of Nuclear Safety, Daejeon, South Korea; Korea Electric Power Research Institute, Daejeon, South Korea.

Nucl. Eng. & Design, 226, 141-154. . . Round Robin Analysis of Pressurized Thermal Shock for Reactor Pressure Vessel. . . .Jhung, M.J. et al. . . . December 2003. . . Korea Institute of Nuclear Safety, Daejeon, South Korea.

Nucl. Eng. & Design, 226, 155-164. . . Numerical and Experimental Investigations into Life Assessment of Blade-Disc Connections of Gas Turbines. . . .Issler, S. et al. . . . December 2003. . . University of Stuttgart, Germany.

Nucl. Eng. & Design, 226, 165-182. . . Risk-Based Inspection and Maintenance in Power and Process Plants in Europe. . . . Jovanovic, A. . . . December 2003. . . MPA Stuttgart, Germany.

Nucl. Eng. & Design, 226, 183-191. . . Transient Analysis of Thick-Walled Piping Under Polynomial Thermal Loading. . . .Segall, A.E. . . . December 2003. . . Penn. State University, University Park, PA.

Nucl. Eng. & Design, 226, 193-204. . . Crack Opening Displacement of a Through-Wall Crack in a Plate Subjected to Bending Load. . . .Machida, H. et al. . . . December 2003. . . TEPCO Systems Corp., Tokyo, Japan; Japan Nuclear Cycle Development Institute, Ibaraki, Japan.

Nucl. Eng. & Design, 226, 221-230. . . Multi-Damping Earthquake Design Spectra-Compatible Motion Histories. . . .Choi, D-H. et al. . . . December 2003. . . Hanyang University, Seoul, South Korea; Korea Power Engineering Co., Gyeonggi-do, South Korea.

Nucl. Eng. & Design, 226, 231-241. . . Comparison of Pressure Vessel Integrity Analyses and Approaches for VVER 1000 and PWR Vessels for PTS Conditions. . . .Gulol, O.O. et al. . . . December 2003. . . Turkish Atomic Energy Authority, Ankara, Turkey; Hacettepe University, Ankara, Turkey.

Nucl. Eng. & Design, 226, 243-254. . . Identification of Damping Mechanism of TRR-II Reactor Control Rod During Free Fall Insertion. . . .Wang, S.K. et al. . . . December 2003. . . I-Shou University, Kaohsiung, Taiwan; National Central University, Chung-Li, Taiwan; Institute of Nuclear Energy Research, Lung-Tan, Taiwan.

Nucl. Eng. & Design, 226, 255-265. . . Three-Dimensional Analysis of Flow Characteristics on the Reactor Vessel Downcomer During the Late Reflood Phase of a Postulated LBLOCA. . . .Kwon, T-S. et al. . . . December 2003. . . KAERI, Daejeon, South Korea.

Nucl. Eng. & Design, 226, 267-275. . . Development of a Thermal-Hydraulic Analysis Code for Annular Fuel Assemblies. . . .Han, K.H. et al. . . . December 2003. . . Korea Advanced Institute of Science and Technology, Daejeon, South Korea.

Nucl. Eng. & Design, 226, 277-292. . . One-Dimensional Critical Heat Flux Concerning Surface Orientation and Gap Size Effects. . . .Kim, Y.H. et al. . . . December 2003. . . Seoul National University, Seoul, South Korea.

Nucl. Eng. & Design, 226, 311-336. . . The Analytic Hierarchy Process as a Systematic Approach to the Identification of Important Parameters for the Reliability Assessment of Passive Systems. . . .Zio, E. et al. . . . December 2003. . . Polytechnic of Milan, Milano, Italy.

Nucl. Eng. & Design, 226, 337-349. . . Improvement of HYCA3D Code and Experimental Verification in Rectangular Geometry. . . .Choi, Y-S. et al. . . . December 2003. . . Seoul National University, South Korea.

Nucl. Eng. & Design, 226, 351-373. . . Cost and Performance Design Approach for GTHTR300 Power Conversion System. . . .Yan, X. et al. . . . December 2003. . . JAERI, Ibaraki-ken, Japan; Mitsubishi Heavy Industries, Japan.

Nucl. Eng. & Design, 226, 375-385. . . The Removal of the Pertechnetate Ion and Actinides from Radioactive Waste Streams at Hanford, Washington, USA and Sellafield, Cumbria, UK: The Role of Iron-Sulfide-Containing Adsorbent Materials. . . .Watson, J.H.P. et al. . . . December 2003. . . University of Southhampton, UK.