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
WWW: http://www-rsicc.ornl.gov/rsic.html

No. 434 April 2001
"A life spent making mistakes is not only more honorable, but more useful than a life spent doing nothing." George Bernard Shaw


NC State Celebrates!

The following was taken from the February 2001 issue of the ANS Nuclear News.

North Carolina State University celebrated the 50th anniversary on December 2-4, 2000, of both the founding of its nuclear engineering academic program and the beginning of construction of its Raleigh research reactor. The Raleigh unit was designated in 1986 as an American Nuclear Society historical landmark in recognition of its being the first reactor in the world to be operated by a non-governmental institution.

Fifty years after the founding, NC State's academic program is now offered through the school's Department of Nuclear Engineering, and the nuclear reactor program is operating its fourth reactor, the PULSTAR, which in 1997 received a license renewal from the Nuclear Regulatory Commission, allowing it to continue operations for an additional 20 years. 

The Golden Anniversary celebration was a three-day event attended by about 100 participants. During the celebration, Carolina Power and Light Company, operator of four nuclear power plants, was recognized for its $283,000 gift to the Department of Nuclear Engineering. The Golden Anniversary concluded with a remembrance of 18 late faculty members of NC State's nuclear engineering staff and a Letter of Appreciation to Raymond Murray for his 50 years of service to the school's nuclear engineering and reactor programs.

MCNP Notice

The current release of MCNP distributed by RSICC is Version 4C. (RSICC package ID is C00700ALLCP02.) Los Alamos National Laboratory posted additional patches designated fix4c.02, which can be used to create MCNP4Ca. Users who wish to build MCNP4Ca can download the fix4c.02 changes from the MCNP web site at LANL by clicking "Resources for Users" from the following URL: 


Alternately, one can download an install.fix file that includes the fix4c.02 patches from entry 44 of the MCNP4C chapter of the electronic notebook on RSICC's website. Users can then use the distributed MCNP installation procedures to build new executables. 

Congrats to Hore-Lacy

Ian Hore-Lacy, received the Australian Nuclear Association's Annual Award for 2000, for "outstanding contributions to the provision of information on nuclear science and technology nationally and internationally."

NRC Codes Made Available

Three 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 software collection.

PSR-448/MAR-D 4.16 (distribution is limited to United States)




Three new packages were added to the computer software and data collection during the month, two of which are foreign contributions.

CCC-698/WIMS-ANL, Version 4.00

Argonne National Laboratory, Argonne, Illinois, contributed the WIMS-ANL code, which is an extension of the Winfrith WIMS-D4 code for lattice cell computations. This code has been tailored to address some of the problem areas encountered in dealing with research reactor fuels, experiment, reflector and control regions. The SUPERCELL option eliminates some of the limitations of the traditional SPECTROX solution and supports the solution of more complex geometries with a more detailed spatial mesh and multiple resonance materials. The code generates both macroscopic and microscopic cross sections in the ISOTXS format with any selected number of energy groups. The user can specify which fission product isotopes are to be explicitly included in the microscopic burnup dependent ISOTXS library. Fission product library data can be generated for use with the MCNP code and burnup dependent applications. The cross section library data provided are based on ENDF/B versions VI (69 group) and V (69 and 172 group) data. The code is variably dimensioned so that other group structures could be used. The source code and output format have been completely revised to reflect current coding practices and to permit display of the results on typical desk top monitors.

The methods of solution in WIMS-ANL remain unchanged from those used in the original WIMS-D4 code with the same resonance treatment and a choice of collision probability and DSN solutions for the simple lattice cell. The SUPERCELL option provides for the selection of supporting auxiliary cells that might represent the different elements and varying spectra of the final SUPERCELL model. The resonance treatment where applicable is carried out in the auxiliary cells. These data are combined in the detailed SUPERCELL computation, and cross section data are generated for the selected edit regions and isotopes.

The code compiled successfully on Sun Solaris; the Lahey compilers F77L, LF90 and LF95 for PC; and the g77 and GNU compilers under Linux. The package is transmitted on a CD rom and includes the source files, scripts, data library, and test cases written in both Unix and Dos formats. Reference: ANL/RERTR/TM-23 (December 2000). Fortran 77; Unix Sun and PC (Windows 95, 98, NT and Linux) (C00698MNYCP00)


The Department of Nuclear Energy System, Japan Atomic Energy Research Institute, Tokai-mura, Naka-gun, Ibaraki-ken, Japan, through the OECD NEA Data Bank, Issy-les-Moulineaux, France, contributed a three-dimensional neutron diffusion calculation code for X-Y-Z geometry. MOSRA-Light can be used in: validation of discontinuity factor for adjoint problem; benchmark on discontinuity factor (forward & adjoint cal.); DVP BWR Benchmark; and void reactivity effect benchmark; etc. MOSRA-Light is based on the 4th order polynomial nodal expansion method (NEM). As the 4th order NEM is not sensitive to mesh sizes, accurate calculation is possible by the use of coarse meshes of about 20 cm. The drastic decrease of number of unknowns in a three-dimensional problem results in very fast computation. Furthermore, it employs newly developed computation algorithm "boundary separated checkerboard sweep method" appropriate to vector computers.

MOSRA-Light was tested by the developers on several computers running Unix and Red Hat Linux 4.2. A Fortran compiler is required on all systems. A C compiler is used to get date, time, and CPU time. As they are not essential for MOSRA-Light calculations, a C compiler is not indispensable. RSICC tested MOSRA-Light on a SUN UltraSparc 60 under SunOS 5.6 with f77 version 5 and C version 5.0 compilers. No executables are provided. The package is transmitted on a DS/HD diskette in a GNU compressed tar file, which includes source, an installer, two test cases, and electronic help files. References: MAN1.TXT and Readme.txt. Fortran-77/Fortran-90; Unix workstations, and Linux PC (P00505MNYWS00).


Siemens AG Power Generation Group, and Gemeinschaftskraftwerk Neckar GmbH, Germany, through the OECD NEA Data Bank, France, contributed these measured axial burnup profiles. This package contains the following measured PWR axial burnup shapes from NeckarWestheim 1 & 2 (GKN1 and GKN2) in subdirectory PWR-AXBUPRO-GKN12 and benchmarks on the effect of axial burnup shapes in subdirectory PWR-AXBUPRO-GKN2K.

PWR-AXBUPRO-GKN1 (square pitch lattice 15X15 - thermal Power 2497 MW) contains more than 700 EOC axial shapes from cycle 18 up. PWR-AXBUPRO-GKN2 (square pitch lattice 18X18 - thermal Power 3850 MW) contains more than 500 EOC axial shapes from cycle 5 up: more than 170 shapes for an initial fuel enrichment of 3.5 wt.-% 235U, discharge burnup ranges from 16.3 to 44.4 Mwd/kg; more than 170 shapes for an initial fuel enrichment of 3.8 wt.-% 235U, discharge burnup ranges from 14.0 to 52.8 Mwd/kg; and more than 180 shapes for an initial fuel enrichment of 4.0 wt.-% 235U, discharge burnup ranges from 15.5 to 48.9 Mwd/kg.

In PWR-AXBUPRO-GKN2K, the shapes were gathered from cycles 5 through 12 of NPP Neckarwestheim 2. All the shapes refer to EOCs. The shapes are derived from in-core 3D power density distribution measurements based on flux measurements. At 28 fuel assembly positions the flux data are monitored at 32 equidistant axial nodes. Thus, one has a total of 896 measuring points.

The package is transmitted on a CD which includes documentation and a 2MB self-extracting compressed, DOS file. References: Siemens AG Power Generation Group Informal documents (May 26, 1998). ASCII format; IBM PC or other computer (D00209MNYCP00).


A. E Profio, 68, ANS member and charter RSICC member, died on February 2, 1999. Ed was a key early contributor to RSICC and the shielding and nuclear data community. Profio received his B.S. in Physics from the Massachusetts Institute of Technology (MIT) in 1953 and became a research scientist at Westinghouse Labs. He served as a Lieutenant in the U.S. Army from 1955 to 1957, working at Ft. Belvoir, Virginia. In 1957, he returned to MIT where he obtained his Ph.D. in nuclear engineering (1963) and took a postdoc for a year. Ed joined the Linac Physics Department at General Atomic in 1964 where he made many important contributions to the shielding and nuclear data communities. He joined the Chemical and Nuclear Engineering Department at the University of California at Santa Barbara (UCSB) in 1969 where he was a stellar professor and researcher. His textbooks: Experimental Reactor Physics and Radiation Shielding and Dosimetry, have played a major role in the nuclear engineering curriculum. Later in his professional life, he turned his attention to medical applications of nuclear methods and successfully developed experimental procedures to detect and treat both lung and breast cancer. Quoting the UCSB Dean of Engineering, "Ed Profio leaves a legacy of accomplishments in his publications and his books, in the students that sat in his class and worked by his side, and the many colleagues that he interacted with and whose lives he touched."

David Trubey, retired RSICC co-founder, writes "I feel a sense of loss even though I have not heard from Ed in a long time. I remember him well for his contributions to the ANS-6 benchmark problems efforts. He always followed through on any commitments. The published benchmark problems in ORNL/RSIC-25 were completed with his help."

Betty Maskewitz, former RSICC director, writes "We regret the passing of long-term friend and RSICC supporter, Edward Profio. He began interaction with RSICC in its earliest years. We always had a special relationship with graduate school students in nuclear science and engineering and continued to follow their professional careers thereafter. Ed, as we called him, discovered RSICC during his graduate and postdoctoral years at MIT. He interacted closely in the following years as a user and as a contributor in radiation transport and shielding information and methods. He was particularly active in nuclear data activities during his years at the GA Linac.

While teaching and doing research at UCSB, he and his graduate students participated in RSICC Seminar Workshops, mainly those in radiation transport and data methodology. Through his papers and textbooks and other research activities, he made important contributions to the nuclear science and engineering knowledge base.

The RSICC staff followed with interest his research in the use of radiation transport and other nuclear methods in medical applications. He was a stalwart in his field. We mourn his passing."

Profio is survived by his wife of 44 years, Janet, a son and two daughters.

John A. Swartout, ANS member since 1955, died October 28, 2000, in Atlanta, GA. He assisted in the development of the chemical separation processes for plutonium for the Manhattan Project; worked for 20 years at the Oak Ridge National Laboratory, including director of the Homogeneous Reactor Project and later became president for Union Carbide.

Paul Hart, ANS member since 1999, associate laboratory director for the National Energy Technology Laboratory in the Dept. of Energy's Office of Environmental Quality and Nuclear Security died December 18, 2000, in Morgantown, WV after a short illness. He previously served as research and development chemist for Union Carbide.

Melvin B. Gottlieb, 83, fusion scientist; served as director of the Princeton Plasma Physics Laboratory in the 1960s and 70s; oversaw construction of the Tokamak Fusion Test Reactor, which began operations in 1982 and went on to produce a record-breaking 11 MV of fusion energy; died December 1, 2000, in Haverford, PA.


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. 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.

Short Courses on Monte Carlo Analysis and Nuclear Criticality Safety

The Department of Nuclear Engineering at the University of Tennessee-Knoxville is offering two short courses for radiation transport and criticality safety specialists during Tennessee Industries Week (TIW-36), August 13-17, 2001.

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

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

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

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

Nuclear Criticality Safety specialists and technical managers who wish to increase their knowledge and understanding of nuclear criticality safety will be interested in this intensive one-week short course. The topics covered in the course are based primarily on the experience of the five instructors which totals over 120 years of nuclear criticality safety related experience. Such a wealth of experience needs to be shared with the criticality safety community including both new professionals in the field as well as experienced professionals. 

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

The registration fee is $1195 per person for each course. The deadline for registration for these courses is July 31, 2001. You may register via the website at http://www.engr.utk.edu/dept/nuclear/TIW.html. For additional information contact Kristin England, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone 865-974-5048; email kengland@utk.edu).

The XIX Autumn School on New Perspectives with Nuclear Radioactivity

Date: October 8-13, 2001

Location: Instituto Superior Tecnico, Lisbon, Portugal

Contact: Inquiries should be addressed to Ms. Sandra Oliveira, (tel +351-21-8419092, fax +351-21-8419143, email NRAD2001@CFIF.IST.UTL.PT).

The aim of the school is to bring together fundamental issues of nuclear radioactivity and nuclear astrophysics as well as some of the technological applications. The indicators show that sciences with a strong social impact will occupy a predominant position in the turn of the century. Nuclear physics is one of the branches of science that is expected to play an important role in this new era. On the other hand, astrophysics has always been an attraction to the human mind. Here, nuclear physics has an essential part. It is thus timely that the nuclear physics community participates actively, either addressing fundamental questions, or applying its knowledge to astrophysics and practical aspects of our society.

There will be a set of invited talks, addressing the most burning issues within the topics of the school, in a format that will allow the participant to get acquainted with some basic ideas, and simultaneously learn about the most recent developments. There will also be some invited seminars and selected short contributions.

A one-page abstract, in LaTex form, is required for the selection of oral contributions. It must be sent by e-mail to NRAD2001@CFIF.IST.UTL.PT. June 1 is the deadline for the submission of abstracts. The final decision will be communicated before June 30. The registration fee is 35 000 PTE. It includes coffee breaks, the welcome reception, the school banquet and a copy of the proceedings. Payment must be done on arrival. The deadline for registration is July 31. More information on the school is available on the web at: http://cfif.ist.utl.pt/~nrad2001.

MCNP™ Workshops

The following is the 2001 schedule for Monte Carlo N-Particle Transport Code Workshop. These classes are taught by the team who develops and maintains MCNP.
5-8 June Introductory Class Los Alamos Natl. Laboratory

The Introductory class is for people who have little or no experience with MCNP. The class surveys the features of MCNP so the beginning user will be exposed to the capabilities of the program, and will have hands-on experience at running the code to solve rudimentary problems. Course topics include Basic Geometry, Source Definitions, Output (Tallies) Specification and Interpretation, Advanced Geometry (repeated structures specification), Variance Reduction Techniques, Statistical Analysis, Criticality, Plotting of Geometry, Tallies, and Particle Tracks, and Neutron/Photon/Electron Physics.

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

Costs For Domestic U.S. Class: Cost for the class is $1,800. There is a $300 discount if payment is received by the close of registration/early payment deadline for each class. Radiation Safety Information Computational Center (RSICC) provides the code and data package and documentation for a reduced fee of $310 to all who complete the class and free to students employed by sponsors that fund RSICC.

The class fee includes a notebook with all class viewgraphs (over 300) and handouts. Dinner the first evening is included as part of your registration fee and snacks and refreshments are provided during class breaks. Lodging will be available for roughly $75 per night. Information will be sent by follow-up letter or email when we receive your registration information.

The class provides interactive computer learning. Time will be available to discuss individual questions and problems with MCNP experts. To register for the LANL class via the Internet, go to http://www.solutionsbyhqc.com/mcnpform.html.


DATES: May 14-18, 2001

NOTE: The previously scheduled October 2001 class has been postponed until next year, dates to be determined.

FEE: $1,700 per person (includes the MCNP™ code package). Price subject to change without notice. Payments must be received at least 45 days before class. If payment has not been received by the due date, your space may be given up to the next available person on our waiting list. Refunds are available up to 30 days before the class date. 

PLACE: The Canyon School Complex, Los Alamos National Laboratory, Los Alamos, New Mexico.

Contacts: Inquiries regarding registration and class space availability should be made to David Seagraves, 505-667-4959, fax: 505-665-6071, e-mail: dseagraves@lanl.gov. Technical questions may be directed to Dick Olsher, 505-667-3364, e-mail: dick@lanl.gov. For further information and registration on the Internet, visit: http://drambuie.lanl.gov/~esh4/mcnp.htm.

The Los Alamos MCNP code is a general and powerful Monte Carlo transport code for photons, neutrons, and electrons. MCNP can be safely described as the "industry standard" with more than 600 person-years of development effort behind it. It is supported on a variety of platforms and is now accessible to health physicists, medical physicists, and rad engineers using desktop or laptop personal computers. This 4.5 day course introduces the basic concepts of Monte Carlo, demonstrates how to put together an MCNP input file, and illustrates some health and medical physics applications of the code. No prior knowledge of Monte Carlo is assumed. 

MCNP is ideally suited to the needs of professionals interested in performing radiation shielding and skyshine calculations, detector simulation studies, or dosimetry. With a little practice and study of the examples, many will find they are able to solve problems that have, in the past, been out of reach. Problems that involve a complex geometry can be easily solved using MCNP (e.g., designing a maze entrance to a radiation room). Calculations are based on detailed physics models and very accurate cross section tables that require no energy group compromises to be made. 

A copy of the MCNP code package is included in the price of the course. Your copy of MCNP will be provided directly from the Radiation Safety Information Computational Center (RSICC) at Oak Ridge. Only RSICC is authorized to distribute licensed copies of the MCNP code package. All of the input and output files for the class demonstrations will be provided for self-study on a diskette. The course will focus on providing a practical boost toward learning the program and guiding the student toward useful applications. Extensive practice sessions are scheduled using a personal computer in class. 

The course will be taught by Dick Olsher and David Seagraves of the Health Physics Measurements Group, Los Alamos National Laboratory. Additional staff help will be provided by members of the Health Physics Measurements Group. 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.

Visual Editor Classes Offered

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

  • Display MCNP 4C 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. 
  • Full geometry capabilities including universes and lattices. 
  • Interactively set cell importances from the plot window. 
  • Display source points and collision points in the plot window. 



    A three-day class is to be held October 8-10, 2001, in Richland, Washington. This class will only focus on the use of the visual editor. Users should already be familiar with the use of MCNP. Computer demonstrations and exercises will focus on creating and interrogating input files with the Visual Editor. Demonstrations of advanced visualization work using MCNP will also be made. The class will be taught on Pentium computers running the Linux operating system or Windows NT version if it is working by then. Attendees are encouraged to bring their own input files for viewing and modifying in the visual editor. Further information on this class can be located at: http://www.pnl.gov/eshs/software/ved/class2.html, or by contacting: Randy Schwarz at 509-372-4042 or email: randy.schwarz@pnl.gov.

    SCALE Training Course Schedule

    The SCALE staff at ORNL will be offering two fall training courses this year. The courses will emphasize hands-on experience solving practical problems on PCs. There will be workgroups of two persons each. No prior experience in the use of SCALE is required to attend. The registration fee is $1800 for one course or $2700 for both spring or fall courses ($300 discount if you register at least one month before the course). A copy of the SCALE software and manual on CD may be obtained directly from RSICC for an additional fee of $310 payable to RSICC. Registrations will be accepted on a first-come basis. Registration forms submitted directly from the Web are preferred. Registration via fax (815-327-6460, yes, the fax area code is different!) or e-mailing Kay Lichtenwalter at lichtenwalsk@ornl.gov is also acceptable. The registration fee must be paid by check, traveler's checks, or credit card (VISA or MasterCard only).

    Class size is limited and courses are subject to cancellation if minimum enrollment is not obtained one month prior to the course. Course fees are refundable up to one month before each class. Classes are cosponsored by RSICC. Foreign nationals must register at least six weeks in advance. For further information, contact Kay at 865-574-9213 or visit the web, http://www.cped.ornl.gov/scale/trcourse.html.

    SCALE Shielding and Source Terms Course (October 15-19, 2001)

    The SCALE Shielding and Source Terms Course emphasizes SAS2 and ORIGEN-ARP (depletion/source-term generation) and SAS3 and SAS4 using MORSE-SGC (3-D Monte Carlo neutron/gamma shielding). It also covers SAS1/XSDRNPM (1-D neutron/gamma shielding) and QADS/QAD-CGGP (3-D point kernel gamma shielding). 

    SCALE KENO-Va Criticality Course (October 22-26, 2001) 

    The SCALE KENO V.a Criticality Course focuses on KENO V.a and the associated criticality analysis sequences in CSAS. KENO V.a is a widely used 3-D multigroup Monte Carlo criticality safety analysis code that has been in use for approximately 15 years. KENO V.a is a fast, easy-to-use code that allows users to build complex geometry models using basic geometrical bodies of cuboids, spheres, cylinders, hemispheres, and hemicylinders. Two-dimensional color plots of the geometry model can be generated. 


    May 2001

    Radiation Dose Management in the Nuclear Industry, May 14-16, 2001, Cumbria, England. Sponsored by the British Nuclear Energy Society, contact: Sue Frye, BNES (tel +44 20 7665 2315, fax +44 20 7233 1743, email frye_s@ice.org.uk). 

    The ANSWERS Software Service Reactor Physics, Radiation Shielding and Nuclear Criticality Annual Seminar, May 15-17, 2001, Bournemouth, Dorset, United Kingdom, sponsored by the AEA Technology. Contact: Simon Aplin (tel + 44 (0) 1305 203634, fax +44 (0) 1305 202746, email simon.aplin@aeat.co.uk, url www.aeat.co.uk/answers).

    June 2001

    International Joint Power Conference, June 4-7, 2001, New Orleans, LA, sponsored by the American Society of Mechanical Engineers. Contact: ASME (tel 800-843-2763, fax 212-591-7674, email infocentral@asme.org, url www.asme.org).

    MONK Nuclear Criticality Introductory Workshop (Includes code trial), June 4-8, 2001, University of New Mexico, Albuquerque. Contact: Simon Aplin, AEA Technology, ANSWERS Software Service. (tel +44 (0) 1305 203634, fax +44 (0) 1305 202746, email simon.aplin@aeat.co.uk, url www.aeat.co.uk/answers).

    ANS Annual Meeting, June 17-21, 2001, Milwaukee, WI. Contact: Michael Sellman, general chair, (tel 715-377-3302, fax 715-377-3355, email mbsellman@nmcco.com, url www.ans.org).

    Embedded Topical Meeting: Nuclear Safety Goals and Safety Culture, June 17-21, 2001, Milwaukee, WI, sponsored by the Nuclear Society of Russia and the Ministry of the Russian Federation for Atomic Energy and cosponsored by ANS. Contact: Edward Fuller, technical program co-chair (tel 408-356-3090, email efuller2039@hotmail.com, url www.ans.org).

    Annual Scientific and Technical Conference on Research Reactors: Science and High Technology, June 25-29, 2001, Dimitrovgrad, Ulyanovsk region, Russia, sponsored by the Nuclear Society of Russia and the Ministry of the Russian Federation for Atomic Energy. Contact: Nina Antoshkina (tel +7 095 196 9887, fax +7 095 882 5937, email agagarin@kiae.ru).

    EPRI 2001 International Low-Level Waste Conference and Exhibit Show, and ASME/EPRI Radwaste Workshop, June 25-29, 2001, Orlando, FL, sponsored by the Electric Power Research Institute. Contact: Vy Dang (tel 650-855-2239, email vdang@epri.com).

    August 2001

    Monte Carlo Analysis, Aug. 13-17, 2001, Knoxville, TN, a short course by the University of Tennessee. Contact: Kristin England, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (tel 865-974-5048, email utne@tennessee.edu, url http://www.engr.utk.edu/dept/nuclear/TIW.html).

    Nuclear Criticality Safety, Aug. 13-17, 2001, Knoxville, TN, a short course by the University of Tennessee. Contact: Kristin England, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (tel 865-974-5048, email utne@tennessee.edu, url http://www.engr.utk.edu/dept/nuclear/TIW.html).

    September 2001

    M&C 2001 Annual Meeting - Special Session: Variance Reduction for Monte Carlo Criticality Simulations, Sept. 9-13, 2001, Salt Lake City, UT. Contact: Dr. Bojan Petrovic, (tel 412-256-1295, fax 412-256-2444, email PetrovB@westinghouse.com, url http://www.srv.net/~ians/MC2001).

    M&C 2001 - International Meeting on Mathematical Methods for Nuclear Applications, Sept. 9-13, 2001, Salt Lake City, UT. Contact: Jeff Borkowski, technical program chair (tel 208-522-1060, fax 208-522-1187, email jeff@soa.com, url www.srv.net/~ians/MC2001/).

    November 2001

    Actinides Conference, Nov. 4-9, 2001, Hayama, Japan. Contact: Dr. T. Ogawa, Secretary for Actinides-2001 (fax +81 29 282 5922, email actq@act2001.tokai.jaeri.go.jp, url http://act2001.tokai.jaeri.go.jp/).


    The following literature cited has been reviewed and placed in the RSICC Information Storage and Retrieval Information System (SARIS), now searchable on the RSICC web server (http://www-rsicc.ornl.gov/SARIS.html). This early announcement is made as a service to the 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.

    Nuclear Systems Literature (Shielding, Safety, Materials)

    Health Phys., 80, 142-147 . . . Methodology of Radon Monitoring and Dose Estimates in Postojna Cave, Slovenia. . . . Vaupotic, J.; Csige, I.; Radolic, V.; Hunyadi, I.; Plannic, J.; Kobal, I. . . . February 2001 . . . J. Stefan Institute, Ljubljana, Slovenia; Institute of Nuclear Research of the Hungarian Academy of Sciences, Debrecen, Hungary; J. J. Strossmayer Univ., Osijek, Croatia.

    Health Phys., 80, 148-150 . . . 222Rn Emanation from Uranium-Glazed Ceramics. . . . Biagioni, R.N.; Sheets, R.W. . . . February 2001 . . . Southwest Missouri State Univ., Springfield, MO.

    Health Phys., 80, 151-156 . . . Thermodiffusion in Concrete Slab as a Driving Force of Indoor Radon Entry. . . . Minkin, L. . . . February 2001 . . . Portland Community College, Portland, OR.

    Health Phys., 80, 157-163 . . . Chromosome Aberrations Study of Pupils in High Radon Level Elementary School. . . . Bilban, M.; Vaupotic, J. . . . February 2001 . . . Institute of Occupational Safety, Ljubljana, Slovenia; J. Stefan Institute, Ljubljana, Slovenia.

    Health Phys., 80, 170-174 . . . Radon in Public Water Supplies in Migdonia Basin, Central Macedonia, Northern Greece. . . . Savidou, A.; Sideris, G.; Zouridakis, N. . . . February 2001 . . . National Centre for Scientific Research "Demokritos," Athens, Greece; GeoMentor e.e.i.g., Geotechnical Consortium, Athens, Greece.

    Health Phys., 80, 175-176 . . . Temperature Dependence of Adsorption Coefficients of 222Rn on Activated Charcoal Determined by Adsorption-Desorption Method. . . . Zikovsky, L. . . . February 2001 . . . Ecole Polytechnique, Montreal, Canada.

    J. Nucl. Mater., 288, 1-6 . . . Effect of Hydrogen on the Ducility Reduction of F82H Martensitic Steel After Different Heat Treatments. . . . Beghini, M.; Benamati, G.; Bertini, L.; Ricapito, I.; Valentini, R. . . . January 2001 . . . Univ. of Pisa, Italy; ENEA, Bologna, Italy.

    J. Nucl. Mater., 288, 7-10 . . . Nanocrystalline Thoria Powders Via Glycine-Nitrate Combustion. . . . Purohit, R.D.; Saha, S.; Tyagi, A.K. . . . January 2001 . . . Bhabha Atomic Research Centre, Navi Mumbai, India.

    J. Nucl. Mater., 288, 11-19. . .Alpha-Radiolysis Effects on UO2 Alteration in Water . . . Sattonnay, G.; Ardois, C.; Corbel, C.; Lucchini, J.F.; Barthe, M.-F.; Garrido, F.; Gossset, . . . January 2001 . . . Commissariat a l'Energie Atomique, CEA-Saclay, Gif sur Yvette, and Bagnols-sur-ceze, France; CNRS-Centre d'Etudes et de Recherches par Irradiation, Orleans, France; Univ. Paris Sud, Orsay, France.

    J. Nucl. Mater., 288, 20-28 . . . Rim Structure Formation of Isothermally Irradiated UO2 Fuel Discs. . . . Une, K.; Nogita, K.; Shiratori, T.; Hayashi, K. . . . January 2001 . . . Nippon Nuclear Fuel Development Co. Ltd., Ibaraki-ken, Japan; Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.

    J. Nucl. Mater., 288, 29-42 . . . Fission Gas Release and Swelling Model of Metallic Fast Reactor Fuel. . . . Lee, C.B.; Kim, D.H.; Jung, Y.H. . . . January 2001 . . . Korea Atomic Energy Research Institute, Taejon, South Korea.

    J. Nucl. Mater., 288, 43-56 . . . Measurement and Analysis of Fission Gas Release from BNFL's SBR MOX Fuel. . . . White, R.J.; Fisher, S.B.; Cook, P.M.A.; Stratton, R.; Walker, C.T.; Palmer, I.D. . . . January 2001 . . . British Nuclear Fuels, Cumbria and Preston, United Kingdom; Nordostschweizerische Kraftwerke, Baden, Switzerland; European Commission, Joint Research Centre, Karlsruhe, Germany.

    J. Nucl. Mater., 288, 57-65 . . . Thermal Conductivities of Irradiated UO2 and (U,Gd)O2. . . . Minato, K.; Shiratori, T.; Serizawa, H.; Hayashi, K.; Une, K.; Nogita, K.; Hirai, M.; Amaya, . . . January 2001 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan; Nippon Nuclear Fuel Development Co. Ltd., Ibaraki-ken, Japan.

    J. Nucl. Mater., 288, 66-75 . . . Phase Equilibria and Magnetism in the Mo-Si-U System. . . . Rogl, P.; Le Bihan, T.; Noel, H. . . . January 2001 . . . Institut fur Physikalische Chemie der Univ. Wien, Austria; Univ. de Rennes, I., France.

    J. Nucl. Mater., 288, 76-82 . . . Physical Properties of Thorium Oxalate Powders and Their Influence on the Thermal Decomposition. . . . Oktay, E.; Yayli, A. . . . January 2001 . . . Istanbul Univ., Avcilar-Istanbul, Turkey; Cekmece Nuclear Research and Training Center, Istanbul, Turkey. J. Nucl. Mater., 288, 83-85 . . . Bulk Thermal Expansion Studies of Th1-xCexO2 in the Complete Solid Solution Range. . . . Mathews, M.D.; Ambekar, B.R.; Tyagi, A.K. . . . January 2001 . . . Bhabha Atomic Research Centre, Mumbai, India.

    Nucl. Eng. Design, 205, 1-11 . . . Determination of Equivalent Single Crack Based on Coalescence Criterion of Collinear Axial Cracks. . . . Jin Ho Lee, Youn Won Park, Myung Ho Song, Young Jin Kim, Seong In Moon . . . March 2001 . . .

    Korea Institute of Nuclear Safety, Taejon, South Korea; Sungkyunkwan Univ., Suwon, South Korea.

    Nucl. Eng. Design, 205, 13-22 . . . Investigation of the Use of Ceramic Materials in Innovative Light Water Reactor - Fuel Rod Concepts. . . . Lippmann, W.; Knorr, J.; Noring, R.; Umbreit, M. . . . March 2001 . . . Technische Univ. Dresden, Germany.

    Nucl. Eng. Design, 205, 23-33 . . . New Leak Detection Technique Using Ceramic Humidity Sensor for Water Reactors. . . . Lee, N.Y.; Hwang, I.S.; Yoo, H.I. . . . March 2001 . . . Seoul National Univ., South Korea.

    Nucl. Eng. Design, 205, 35-51 . . . Development of the Five-Sensor Conductivity Probe Method for the Measurement of the Interfacial Area Concentration. . . . Euh, D.J.; Yun, B.J.; Song, C.H.; Kwon, T.S.; Chung, M.K.; Lee, U.C. . . . March 2001 . . . Korea Atomic Energy Research Institute, Taejon, South Korea; Seoul National Univ., South Korea.

    Nucl. Eng. Design, 205, 53-67 . . . On the Boundary Conditions of the k-E Model in 3D Coarse-Mesh Models for Containment Analysis. . . . Analytis, G.Th.; Andreani, M. . . . March 2001 . . . Paul Scherrer Institute, Villigen PSI, Switzerland.

    Nucl. Eng. Design, 205, 69-82 . . . ALE Finite Element Method for Gas-Liquid Two-Phase Flow Including Moving Boundary Based on an Incompressible Two-Fluid Model. . . . Uchiyama, T. . . . March 2001 . . . Nagoya Univ., Japan.

    Nucl. Eng. Design, 205, 83-90 . . . A Coupled RELAP5-3D/CDF Methodology with a Proof-of-Principle Calculation. . . . Aumiller, D.L.; Tomlinson, E.T.; Bauer, R.C. . . . March 2001 . . . Bechtel Bettis, Inc., Bettis Atomic Power Laboratory, West Mifflin, PA.

    Nucl. Eng. Design, 205, 91-105 . . . The Physical Mechanism of Core-Wide and Local Instabilities at the Forsmark-1 BWR. . . . Analytis, G.Th.; Hennig, D.; Karlsson, J.K.-H. . . . March 2001 . . . Paul Scherrer Institute, Villigen PSI, Switzerland; GSE Power Systems AB, Nykoping, Sweden.

    Nucl. Eng. Design, 205, 107-114 . . . A Simplified Model of the BWR Depressurization Transient. . . . di Marzo, M. . . . March 2001 . . . Univ. of Maryland, College Park, MD.

    Nucl. Eng. Design, 205, 115-121 . . . Interaction Between Periodically Arranged Beams and Fluid. . . . Zhang, R.J.; Hou, S.H.; Chan, C.K.; Wang, W.Q. . . . March 2001 . . . Tongji University, Shanghai, PR China; The Hong Kong Polytechnic Univ., Kowloon, Hong Kong.

    Nucl. Eng. Design, 205, 123-131 . . . Micro Four-Sensor Probe Measurement of Interfacial Area Transport for Bubbly Flow in Round Pipes. . . . Ishii, M.; Kim, S. . . . March 2001 . . . Purdue Univ., West Lafayette, IN.

    Nucl. Eng. Design, 205, 133-144 . . . Research and Development of a High-Efficiency One-Stage Melting Converter-Burial-Bunker Method for Vitrification of High-Level Radioactive Wastes. . . . Pioro, L.S.; Sadovskiy, B.F.; Pioro, I.L. . . . March 2001 . . . National Academy of Sciences of Ukraine, Kiev, Ukraine; Institute NIFKhI, Moscow, Russia; Univ. of Ottawa, Ont., Canada.

    Nucl. Eng. Design, 205, 145-158 . . . The One-Dimensional Two-Fluid Model with Momentum Flux Parameters. . . . Song, J.H.; Ishii, M. . . . Korea Atomic Energy Research Institute, Taejon, South Korea; Purdue Univ., West Lafayette, IN.

    Nucl Eng. Design, 205, 159-173 . . . Critical Heat Flux Under Choking Flow Conditions Part I - Outlet Pressure Fluctuations. . . . Olekhnovitch, A.; Teyssedou, A. Tye, P.; Champagne, P. . . . March 2001 . . . Institut de Genie Nucleaire, Ecole Polytechnique, Quebec, Canada.

    Nucl. Eng. Design, 205, 175-190 . . . Critical Heat Flux Under Choking Flow Conditions Part II - Maximum Values of Flow Parameters Attained Under Choking Flow Conditions. . . . Olekhnovitch, A.; Teyssedou, A.; Type, P. . . . March 2001 . . . Ecole Polytechnique, Quebec, Canada.

    Nucl Eng. Design, 205, 191-198 . . . Optimized Gadolinia Concepts for Advanced In-Core Fuel Management in PWRs. . . . Schlieck, M.; Berger, H.D.; Neufert, A. . . . March 2001 . . . Siemens Nuclear Power GmbH-Nuclear Fuel Cycle, Erlangen, Germany.

    Nucl. Eng. Design, 205, 199-204 . . . The Treatment of Dependent Failures in Availability Analyses. . . . Fischer, H.D. . . . March 2001 . . . Ruhr-Univ. Bochum, Germany.

    Nucl. Eng. Design, 205, 205-212 . . . Thermal and Mechanical Characteristics of an Instrumented Capsule for a Material Irradiation Test. . . . Lee, Y.S.; Choi, M.H.; Kang, Y.H. . . . March 2001 . . . Chungnam National Univ., Taejon, South Korea; Korea Atomic Energy Research Institute, Taejon, South Korea.

    Nucl. Sci. Eng., 137, 227-235 . . . A Generalized Fokker-Planck Model for Transport of Collimated Beams. . . . Prinja, A.K.; Pomraning, G.C. . . . March 2001 . . . Univ. of New Mexico, Albuquerque, NM; Univ. of California, Los Angeles, CA.

    Nucl. Sci. Eng., 137, 236-250 . . . Generalized Fokker-Planck Approximations of Particle Transport with Highly Forward-Peaked Scattering. . . . Leakeas, C.L.; Larsen, E.W. . . . March 2001 . . . Univ. of Michigan, Ann Arbor, MI.

    Nucl. Sci. Eng., 137, 251-280 . . . Multiple Scattering in Clouds: Insights from Three-Dimensional Diffusion/P1 Theory. . . . Davis, A.B.; Marshak, A. . . . March 2001 . . . Los Alamos National Laboratory, Los Alamos, NM; NASA's Goddard Space Flight Center, Greenbelt, MD; Univ. of Maryland, Baltimore, MD.

    Nucl. Sci. Eng., 137, 281-297 . . . Variable Eddington Factors and Flux Limiters in Radiative Transfer. . . . Su, B. . . . March 2001 . . . Univ. of Cincinnati, Cincinnati, OH.

    Nucl. Sci. Eng., 137, 298-333 . . . Discontinuous Finite Element Transport Solutions in Thick Diffusive Problems. . . . Adams, M.L. . . . March 2001 . . . Texas A&M Univ., College Station, TX.

    Nucl. Sci. Eng., 137, 352-358 . . . Time-Dependent, One-Speed Transport via Generalized Functions. . . . Corngold, N.R. . . . March 2001 . . . California Institute of Technology, Pasadena, CA.

    Nucl. Sci. Eng., 137, 359-363 . . . Exact Pn Method Solutions. . . . McCormick, N.J. . . . March 2001 . . . Univ. of Washington, Seattle, WA.

    Nucl. Sci. Eng., 137, 364-379 . . . Classical Perturbation Theory for Monte Carlo Studies of System Reliability. . . . Lewins, J.D. . . . March 2001 . . . Univ. of Cambridge, United Kingdom.

    Nucl. Sci. Eng., 137, 380-399 . . . Studies on Nodal Integral Methods for the Convection-Diffusion Equation. . . . Michael, E.P.E.; Dorning, J.; Uddin, R. . . . March 2001 . . . Univ. of Virginia, Charlottesville, VA.

    Nucl. Sci. Eng., 137, 400-410 . . . From Fourier Transforms to Singular Eigenfunctions for Multigroup Transport. . . . Ganapol, B.D. . . . March 2001 . . . Univ. of Arizona, Tucson, AZ.

    Nucl. Technol., 133, 310-324 . . . Performance of Near-Weapons-Grade Plutonium Fuel Pins in Commercial Light Water Reactors. . . . Difilippo, F.C.; Fisher, S.E. . . . March 2001 . . . Oak Ridge National Laboratory, Oak Ridge, TN.

    Nucl. Technol., 133, 346-354 . . . Generation, Testing, and Validation of a WIMS-D/4 Multigroup Cross-Section Library Based on the JENDL-3.2 Nuclear Data. . . . Rahman, M.; Takano, H. . . . March 2001 . . . Atomic Energy Research Establishment Institute of Nuclear Science and Technology, Dhaka, Bangladesh; Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.