| Radiation Safety Information Computational Center | |
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Oak Ridge National Laboratory Post Office Box 2008 Oak Ridge, Tennessee 37831-6362 Managed by Lockheed Martin Energy Research Corp. for the U.S. Department of Energy under contract DE-AC05-96OR22464 Phone No. 423-574-6176 |
| No. 398 | February 1998 |
RSICC DOCUMENTS GO ELECTRONIC
In an effort to better serve the community, RSICC has initiated a new project. Documentation for software and data libraries, which existed only on paper in the past, is now scanned and made available in Adobe Portable Data Format (PDF). Because RSICC has over 1000 computer packages, the project will be handled as time and funding permit. We are pleased to inform our users that about 40 such documents are now available on the web (http://www-rsicc.ornl.gov/DOCUMENTS.html), in addition to the others which are in Microsoft Word, WordPerfect and postscript formats.
CHANGES TO THE COMPUTER CODE COLLECTION
Three changes were made to the computer code collection during the month. An existing code package was enhanced with additions or corrections to the software, and two existing code packages were replaced with newly frozen versions.
CCC-638/TART97 OP SYS:Unix and DOS LANGUAGE:Fortran 77 COMPUTERS:many FORMAT:Unix and DOS |
Lawrence Livermore National Laboratory, Livermore, California, contributed a newly frozen version of this coupled neutron-photon, three-dimensional, combinatorial geometry, Monte Carlo transport code system. TART97 can calculate 1) static reactivity problems, 2) dynamic reactivity problems, 3) source problems involving any combination of neutron and/or photon sources. |
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The package includes both ENDL and ENDF/B-VI data as well as several auxiliary codes: TARTCHEK, EPICSHOW, PLOTTAB, plus several utility programs. TART97 uses the latest ENDF/B-VI, Release 4, neutron data and Evaluated Photon Data Library ‘97 (EPDL97). TART97 is very fast and completely supersedes all older versions of TART. The developer strongly recommends that all users acquire the most recent version and its data files.
This is a complete system to assist with input preparation, run Monte Carlo calculations, and facilitate analysis of output results. TART97, which runs on almost any modern computer, was tested on Cray, IBM RS/6000, HP, Sun, and DEC Alpha under Unix operating systems. It also runs on IBM PC’s and Power MAC. It is written in 100% Fortran 77. A Fortran 77 compiler is required for Unix systems, and executables are included for IBM PC. The package is transmitted on a CD-ROM. References: UCRL-ID-126455, Rev. 1 (Nov. 1997). Fortran 77; Many Computers (C00638/MNYCP/02). |
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CCC-660/MCNP4B2 OP SYS:Unix and DOS LANGUAGE:Fortran 77 COMPUTERS:workstations and PC FORMAT:Unix and DOS |
In October 1997, Los Alamos National Laboratory, Los Alamos, New Mexico contributed a correction for MCNP4B2 which supports Linux and Lahey Fortran 90 on PC’s, a fix for PVM, and corrects a potentially significant problem which affects all repeated structures/lattice geometry problems with closely spaced surfaces. |
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At that time executables were not updated, so they corresponded to the initial MCNP4B release. In the January 1998 update, all MCNP4B executables were deleted; and a new MCNP4B2 executable for personal computers created with the F77L3-EM/32 version 5.2 compiler was added to the package. MCNP4B is a general-purpose, continuous-energy, generalized geometry, time-dependent, coupled neutron-photon-electron Monte Carlo transport code system.
MCNP4B includes a test library of cross sections for running the sample problems; but all cross sections are included in the new DLC-189/MCNPXS code package, which is distributed with the code. MCNP4B is operable on Cray computers under UNICOS using CFT77 6.0.4.1, IBM RS/6000 under AIX 3.2.5 and AIX 4.2, SunSparc under SOLARIS 2.4 using F77 4.0, DEC Alpha under Digital UNIX V3.2, HP with HP F77 9.16, SGI under IRIX 4.0.2, Linux, and all computers in general with at least 150 megabytes of hard disk. Executable files for the PC version are provided for running on 32MB memory on either a Pentium or 80486 computer with a coprocessor. The PC executables included in the package were created with the Lahey Fortran F77L3-EM/32 version 5.2 compiler. They run in a DOS window of either Windows95 or WindowsNT 4.0. Compilation of MCNP under Unix requires both FORTRAN77 and ANSI C standard compilers. PVM is required for multiprocessing on a cluster of workstations. Scripts are provided for installation on both PC and Unix systems. Included are the referenced documents and the source codes, test problems, executables, and installation scripts available on a UNIX tar format cartridge tape or CD-ROM for use on both Unix and DOS platforms. Users who received MCNP4B from RSICC may contact us to get the updated install.fix and PC executables on diskette. References: LA-12625-M (1997), LA-13181 (August 1996), and LA-13138 (April 1996). Fortran 77 and C; Unix workstations, Intel-based PC, and Cray (C00660/ALLCP/02). |
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CCC-647/DRAGON3.02 OP SYS:Unix LANGUAGE:Fortran 77 COMPUTERS:many FORMAT:Unix tar |
The Ecole Polytechnique de Montreal of Canada contributed this lattice cell code system called DRAGON, which is a collection of models to simulate the neutronic behavior of a unit cell or a fuel assembly in a nuclear reactor. |
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It includes all of the functions that characterize a lattice cell code, namely: interpolation of microscopic cross sections supplied by means of standard libraries; resonance self-shielding calculations in multidimensional geometries; multigroup and multidimensional neutron flux calculations which can take into account neutron leakage; transport-transport or transport-diffusion equivalence calculations as well as editing of condensed and homogenized nuclear properties for reactor calculations; and finally isotopic depletion calculations.
This release, DRAGON3.02, has seen a large number of changes. Most of them are related to the treatment of the microscopic cross section libraries while others were implemented to simplify the input file. Some changes include the capability to read WIMSD4 formatted microscopic cross section libraries, the capability to generate ISOTXS format microscopic cross section libraries in addition to GOXS format macroscopic cross section libraries, and the addition of the new EXCELL module. The execution of DRAGON is controlled by the generalized GAN driver which is modular and can be interfaced easily with other production codes.
The user must supply cross sections. DRAGON can access directly standard microscopic cross-section libraries in the following formats: DRAGON, MATXS (TRANSX-CTR), WIMSD4, WIMS-AECL, and APOLLO. It has the capability of exchanging macroscopic cross-section libraries with a code such as PSR-206/TRANSX-CTR or PSR-317/TRANSX-2 by the use of the GOXS format files. Macroscopic cross sections can also be read in DRAGON via the input data stream.
DRAGON runs on IBM RS/6000, HP9000/700, SUN SparcStations, and DEC Alpha under Unix operating systems. The package is transmitted on either a CD-ROM or tape cartridge as a compressed Unix tar file which contains installation instructions, the user’s guide, Fortran source, installation scripts, and test cases. Reference: IGE-174 Rev. 3 (December 1997). Fortran 77; IBM RS/6000, HP9000, SUN, DEC (C00647/MNYWS/01). |
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PERSONAL ITEMS
In serving a specialized area of scientific endeavor, it seems important that we note significant events or changes in the activities of people concerned with radiation protection, transport, and shielding in the nuclear industry. We, therefore, continue to carry personal items as they are brought to our attention.
RSICC Mourns the Passing of a Friend and Scientist
On February 4, 1998, Dr. Fran Alsmiller, ORNL physicist and contributor to RSICC, died in Oak Ridge. Fran is well-known for her many contributions in physics, and in particular, for the work she had done with the High Energy Transport Code (HETC). She is survived by her husband, Dr. R. G. (Tut) Alsmiller, and brother, Dr. Ed Shipley. Both Fran and Tut have dedicated their life to working at ORNL. Although Tut and Fran retired in 1993, they stayed active in research.
It is always sad to lose a friend and colleague. From my perspective, the passing was even sadder. My first experiences at ORNL are associated with Fran during the summer of 1963. I was a callow undergraduate student with little experience. Both Fran and Tut helped me that summer and for that I will be extremely grateful. That summer represented one of those few milestones that you have in life. Fran will be remembered and missed by me and by all of her associates.—Tony Gabriel, ORNL
In RSICC's early days, a considerable effort was made under NASA sponsorship to support space and high energy shielding. The Alsmillers (Fran and Tut) reviewed the literature and all computational aspects for the RSICC data banks in interaction with other international research teams. Their work gave
essential support to the early space programs - pre-Apollo and later exploratory programs. In addition, they collaborated in producing high-energy data and other information that continues to be at the forefront of the state-of-the-art. Fran will be missed by all those who worked with and called her 'friend'.
—Betty F. Maskewitz, Retired RSIC Director
CONFERENCES, COURSES, SYMPOSIA
RSICC attempts to keep its users/contributors advised of conferences, courses, and symposia in the field of radiation protection, transport, and shielding through this section of the newsletter. Should you be involved in the planning/organization of such events, feel free to send your announcements and calls for papers via email to raf@ornl.gov.
Technologies for the New Century
The 1998 ANS Radiation Protection and Shielding Division Topical Conference, "Technologies for the New Century" will be held in Nashville, Tennessee, April 19–23, 1998. The General Chairman is Robert W. Roussin (rwr@ornl.gov) and the Technical Chairman is D. T. Ingersoll (dti@ornl.gov). Information about the conference can be found at http://www-rsicc.ornl.gov/RPS98/rps98.htm.
DORT and TORT Workshop
A two-day workshop on ORNL's neutral particle transport codes DORT (2D) and TORT (3D) will be conducted April 24-25, 1998, in Nashville immediately following the 1998 RP&S Topical Meeting. The focus of the workshop will be on using the codes, especially the TORT code. Detailed descriptions will be given on all input parameters and output files, and numerous examples will be offered.
In addition, the novice will be introduced briefly to neutron transport methods, especially those based on the discrete ordinates approximation. Also, an overview will be given of the Discrete Ordinates of Oak Ridge System (DOORS), within which DORT and TORT are bundled. Other DOORS codes which perform auxiliary functions will be discussed with particular emphasis on how they can be utilized in complex analyses.
In order to open DOORS (so to speak!) to more advanced usage of these codes, world-recognized experts will be invited to share their expertise and cite examples of how they employ DOORS codes to solve their problems. The last half-day of the workshop will be a hands-on computer lab where participants will get the opportunity to construct an input file, run the codes, and examine the output to verify proper execution under the supervision of experts. Complete details about the workshop program may be found on the web at http://www-rsicc.ornl.gov/RPS98/workshop.html.
Criticality Safety Assessments Workshop
A two and a half-day workshop designed for criticality safety personnel with some experience doing assessments (evaluations) and some computer code experience (KENO, MCNP, MONK, DANTSYS) will be held July 7-9, 1998. The participants will be divided into groups of three to four. Each group will be given an operation/process which is to be evaluated and for which limits and controls are to be determined. Each group will have a faculty observer/facilitator who will act as the "operations" representative. The group will be responsible for interviewing operations, identifying normal and off-normal conditions, parameters to be controlled, how the parameters will be controlled, limits, estimates of the k-effectives of different configurations, a summary of the assessment, and example postings and procedures. Each group will present their assessment to the faculty who will provide a critique of the results. The participants will have a chance to use handbooks, reports, manuals, and computer codes to evaluate the neutronics of the process and determine the sensitivity of k-effective to various parameters such as mass, concentration, reflection, etc. A tentative outline of the workshop includes: Tuesday morning - presentation of problem and data gathering; Tuesday afternoon - groups identify normal/off-normal conditions, parameters, and non-computer estimates of the k-effectives. Each group will provide an interim report to be evaluated by the faculty over night. Wednesday morning - computations and sensitivity studies, iterations with operations, and QA on models; Wednesday afternoon - limits, postings, procedures, and a summary of the assessment which will be reviewed by the faculty over night. Thursday morning - presentations of the assessments with critiques.
The basic fee for the Assessments Workshop is $750.00 which covers tuition, access to the computer codes, all other course materials and lunch each day. The workshop will be held at the UNM Continuing Education Center. Additional information may be obtained by contacting Cheryl at cbrozena@unm.edu or Bob at busch@unm.edu or by calling 505-277-2225.
The Second International Topical Meeting on Nuclear Applications of Accelerator Technology (AccApp'98) is sponsored by the Accelerator Applications Technical Group of the American Nuclear Society (ANS), and is hosted by the Oak Ridge-Knoxville, Tennessee, USA Section of the ANS. It will be held in Gatlinburg, Tennessee, during the week of September 20-23, 1998, at the Park Vista Hotel & Conference Center.
AccApp'98 will provide a forum for discussion of the uses of particle accelerator technology for nuclear applications. It will focus on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, production or destruction of radionuclides significant to energy, medicine, defense, or other endeavors, as well as imaging and diagnostics.
Papers are solicited in the following areas: applications, design, R&D needs, analytical methods, tools and databases, economics, safety and licensing.
First Announcement and Call for Papers
The Ministry of the Russian Federation for Nuclear Energy, Institute of Physics and Power Engineering, Association of the Radiological Problems of Russia with participation of the Russian Nuclear Society announce the Call for Papers for the Seventh Russian Scientific Conference on "Radiation Shielding of Nuclear Installation" to be held in Obninsk, Kaluga region, Russia, September 22-25, 1998. Papers are requested on the following topics:
For more information, please contact the organizing committee: Prof. Anatoliy V. Zrodnikov - Head, Institute of Physics and Power Engineering, Bondarenko Sq. 1, Obninsk, Kaluga region, RUSSIA or Prof. Ernest E. Petrov - Deputy Head, Institute of Physics and Power Engineering, Bondarenko Sq. 1, Obninsk, Kaluga region, RUSSIA.
Calendar
Your attention is directed to the following events of interest.
March 1998
April 1998
May 1998
June 1998
July 1998
August 1998
September 1998
November 1998
December 1998
June 1999
Package Name: Package ID:
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Authorized to accept and accepted for the licensee:
Name: Signature:
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Licensee:
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Date:
Prompt return of this form with the original signature and proper payment will expedite your request. Thank you.
RSICC
P.O. Box 2008
Oak Ridge, TN 37831-6362
phone: 423-574-6176
fax: 423-574-6182
REQUEST FOR COMPUTER PROGRAMS/DATA LIBRARIES
Name of Requester:
Organization:
Return Address:
Telephone: FAX:
Email:
MATERIAL REQUESTED
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MEDIA
Necessary tapes and cartridges are provided by the requester; 3½- or 5¼-inch diskettes are provided by RSICC.
diskettes (ds/hd)
3½ inch
5¼ inch
cartridges
QIC-80 (DOS only)
DC 6150
8 mm
4 mm
CD-ROM
Return to: Radiation Safety Information Computational Center
Oak Ridge National Laboratory
Bethel Valley Road
P.O. Box 2008
Oak Ridge, TN 37831-6362
Telephone: 423/574-6176
FAX: 423/574-6182
Internet: PDC@ORNL.GOV
