| Radiation Safety Information Computational Center | |
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Oak Ridge National Laboratory Phone No. 423-574-6176 |
| No. 396 | December 1997 |
Every man is his own ancestor, and every man his own heir. He devises his own future, and he
inherits his own past.--H. F. Hedge
 |
Oak Ridge National Laboratory, Oak Ridge, Tennessee,
contributed corrections to this one-, two- and three-dimensional
discrete ordinates neutron/photon transport code system. The
changes incorporated when updating DOORS 3.1 to DOORS 3.2
include: the addition of an edit control variable to reduce the
volume of print to standard output; the initialization of the
convergence map file; the elimination of the need to perform an
extra iteration to save the directional fluxes when the user input
time limit is reached; and the update to circumvent TORT's inability to obtain the correct system
time charges from UNICOS during multitasking. Several other corrections and enhancements
were made which improve portability among computing platforms.
DOORS 3.2 includes the most recent versions of CCC-543/TORT-DORT, CCC-254/ANISN-ORNL, CCC-628/GBANISN and CCC-351/FALSTF. It also includes the ISOPLOT code from PSR-155/DOGS and various utility programs previously included in the TORT-DORT package: GIP, ALC, RTFLUM, BNDRYS, GRTUNCL, VISA, TORSED and TORSET. ISOPLOT was modified to use the Sandia National Laboratory RSCORS graphical system. Sandia National Laboratory's CMP system for code maintenance is used to build the Fortran source files for the target computer. Both RSCORS and CMP are distributed with the system.
TORT calculates the flux or fluence of particles due to particles incident upon the system from extraneous sources or generated internally as a result of interaction with the system in two- or three-dimensional geometric systems, and DORT is used in one- or two-dimensional geometric systems. The principal application is to the deep-penetration transport of neutrons and photons. Certain reactor eigenvalue problems can also be solved.
Users of either DOORS 3.0 or 3.1 may download the update via anonymous ftp
(infosrv1.ctd.ornl.gov/pub/rsic/doors; filenames ibmout32.tar.Z and update32.tar.Z). Test case
results may also be downloaded. The entire package is transmitted as a UNIX tar file written on
either CD-ROM, 4-mm DAT (8 GB), or 8-mm (2.3 GB) cartridge tapes. The tar file contains the
Fortran and C source files, test cases, implementation instructions, procedures, description of
sample problem cases, and much of the referenced documentation. References:
ORNL/TM-13221 (October 1997), ORNL/TM-11778 (March 1992), K-1693 (March 1967),
NAA-SR-10951 (March 1966), ORNL/TM-12675 (Jan. 1996), ORNL/TM-8362 (September
1982), ORNL/TM-12246 (January 1993), ORNL/TM-12359 (August 1993), ORNL/TM-4015
(December 1972), SAND85-0825 (April 8, 1991), SAND99-XXXX (October 19, 1991). Fortran
and C; Cray Unicos, IBM AIX, Sun, DEC OSF/1, SGI and Hewlett Packard
(C00650/MFMWS/02).
The ANSWERS Software Service, AEA Technology, Winfrith,
the United Kingdom, and the OECD Nuclear Energy Agency
Data Bank, Issy-les Molineaux, France, contributed a new
version of the Winfrith improved multigroup scheme (WIMS)
code system for reactor lattice cell calculations on a wide range
of reactor systems. In particular, the code will accept rod or
plate fuel geometries in either regular arrays or in clusters. The
treatment of resonances is based on the use of equivalence
theorems with a library of accurately evaluated resonance integrals for equivalent homogeneous
systems at a variety of temperatures. The collision theory procedure gives accurate spectrum
computations in the 69 groups of the library for the principal regions of the lattice using a
simplified geometric representation of complicated lattice cells. The computed spectra are then
used for the condensation of cross-sections to the number of groups selected for solution of the
transport equation in detailed geometry. Solution of the transport equation is provided either by
use of the Carlson DSN method or by collision probability methods. Leakage calculations,
including an allowance for streaming asymmetries, may be made using either diffusion theory or
the more elaborate B1-method. The output of the code provides eigenvalues for the cases where a
simple buckling mode is applicable or cell-averaged parameters for use in overall reactor
calculations. Various reaction rate edits are provided for direct comparison with experimental
measurements.
For the included 1986 library, 14 nuclides were processed from JEF-1. Other data were derived primarily from the UKAEA Nuclear Data Library. The energy group structure was chosen primarily for thermal calculations in this basic library, which was processed with 14 fast groups, 13 resonance groups and 42 thermal groups. This group structure offers the user the choice of accurate solutions in many groups or rapid calculations in few groups. Temperature dependent thermal scattering matrices for a variety of scattering laws are included in the library for the principal moderators which include hydrogen, deuterium, graphite, beryllium and oxygen. WIMSD5 is a successor of WIMS-D4 (CCC-576).
WIMSD5 runs on DEC Alpha under OSF/1 and on Sun under Solaris using Fortran 90
compilers. It is also expected to run on IBM under MVS, VAX under VMS, and on a PC with
compilers which are allowed to use extended memory. The package is transmitted in a tar file on
CD-ROM or cartridge tape. References: NEA-1507/02: ANSWERS Software Service, AEA
Technology report (June 1997) and AEEW-R 2133 (September 1986). DEC Alpha and Sun
(C00656/MNYWS/00).
One new data library contributed by the Republic of Korea was added to the collection.
The Korean Atomic Energy Research Institute, Yusung, Taejon,
Republic of Korea, through the OECD NEA Data Bank,
contributed a WIMS 69 energy-group cross section library for
thermal reactor applications with either CCC-576/WIMS-D4 or
CCC-656/WIMSD5. The library was produced using LANL's
NJOY code system by processing nuclides from ENDF/B-V or
IV and JENDL-2 (Rev.1), and from ENDL-84, where data were
not available in ENDF/B. Transport cross sections were
computed using a P1 scattering matrix. Within-group weighting
fluxes for actinides were computed on an ultra-fine group basis for accurate intermediate
resonance self-shielding. A more explicit representation was adapted for the fission-product
chain. Within-group weighting fluxes were computed.
The following nuclides are included: H-1, H-1 (in H2O), H-1 (in ZrH), H-2, H-2 (in D2O), He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C, C (in graphite), N-14, O-16, F, Na, Al, Si, P-31, S-32, K, Ti, V, Cr, Mn-55, Fe, Co-59, Ni, Cu, Cu-63, Zr, Zircaloy-2, Nb-93, Mo, Mo-92, Mo-94, Mo-95, Mo-96, Mo-97, Mo-98, Mo-99, Mo-100, Ag-107, Ag-109, Cd, In-113, In-115, Sn, Gd, Dy-164, Er-166, Er-167, Lu-176, Hf, Hf-174, Hf-176, Hf-177, Hf-178, Hf-179, Hf-180, Ta-181, Au-197, Pb. The following fission products are included: Kr-83, Mo-95, Tc-99, Ru-101, Ru-103, Rh-103, Rh-105, Pd-105, Pd-108, Ag-109, Cd-113, In-115, I-127, I-135, Xe-131, Xe-135, Cs-133, Cs-134, Cs-135, Nd-143, Nd-145, Pm-147, Pm-148g, Pm-148m, Pm-149, Sm-147, Sm-148, Sm-149, Sm-150, Sm-151, Sm-152, Eu-153, Eu-154, Eu-155, and Gd-157. The following actinides are included: Th-232, Pa-233, U-233, U234, U-235, U-236, U-237, U-238, Np-237, Np-238, Np-239, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-242g, Am-242m, Am-243, Cm-242, Cm-244.
No retrieval code is included in the package as these data are intended for use with the WIMS
code system. The card-image data are transmitted in a 44 MB Unix tar file on either CD-ROM or
cartridge tape. References: IAEA-NDS-92, Rev. 0 (August 1990), Journal of the Korean Nuclear
Society, Volume 21, Number 4 (December 1989). Many computers (D00193/MNYCP/00).
The beginning class assumes no knowledge of Monte Carlo nor any experience with MCNP. The advanced class requires some knowledge and experience with MCNP, but the level of that class is adjusted to the interests of the particular people attending. The beginning class covers all aspects of the code including:
The goal of these classes is to provide the student with a general knowledge of the capabilities of MCNP. Within that framework, any specific application can be addressed. Emphasis is placed on gaining hands-on experience. About half the class time is spent working on computers doing exercises developed to provide true understanding of the concepts being discussed. There is ample opportunity to discuss your particular application with the MCNP experts who are the lecturers.
The registration fee includes the latest MCNP manual, CD with the installation files for all the machines we support, CD containing the data libraries for all platforms, a notebook of all the materials presented during the class, course banquet, coffee breaks, snacks, and a commemorative certificate of attendance.
For further information, contact Judi Briesmeister, email: jfb@lanl.gov or phone: 505-667-7277. A more detailed announcement will be provided to you concerning cost, registration dates, etc.
We would like to use this forum to announce that the MCNP Monte Carlo code development team is now in Group XCI and is no longer part of Group XTM within the Los Alamos National Laboratory. Our web address has changed to the following: http://www-xdiv.lanl.gov/XCI/PROJECTS/MCNP/index.html. We have been repeatedly asked if we are affiliated with the MCNP classes being offered by Group ESH-4 of LANL and we have no participation in nor association with these two classes.
Judi Briesmeister
The number of registrants for the course is limited to 24. Registrations will be accepted on a
first-come basis. Hotel rooms are available at the Garden Plaza Hotel (423-481-2468).
Additional information can be obtained by FAX (423-576-3513 ) or e-mail
(scalehelp@ornl.gov).
Monday, April 27
Introduction to CSAS6
Resonance Self-Shielding
Standard Composition Library
Unit Cell Types
KENO-VI Parameters
KENO-VI Geometry
KENO-VI Plot Data
Problem Session 1
Tuesday, April 28
Review of Problem Session 1
Geometry Modification Data
(Chords/Rotate/Translate)
Media/Holes
Media/Arrays
Problem Session 2
Wednesday, April 29
Review of Problem Session 2
KENO-VI Output - How to Read It
Start Data
Bias Data
Boundary Data
Mixing Table
Problem Session 3
Thursday, April 30
Review of Problem Session 3
Monte Carlo Uncertainties
Code & Data Validation Issues
Problem Session 4 (Bring your own problems)
Steve Bowman
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 1923, 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.
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. The Call For Papers with all relevant
information and points of contact is attached to the end of this newsletter.
Calendar
Your attention is directed to the following events of interest.
January 1998
Radiation Safety Officer's Course, Jan. 19-23, 1998, a continuing education course offered by the
University of Texas at San Antonio. Contact: The University of Texas Health Science Center at
San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980
(phone 210-567-4491; fax 210-567-6964).
February 1998
Health Physics Society Midyear Topical Meeting, Feb. 8-11, 1998, Mobile, Alabama. Contact:
Health Physics Society, Suite 402, 1313 Dolley Madison Blvd., McLean, VA 22101-3926 (phone
703-790-1745; fax 703-790-2672; email: hpsburkmgt@aol.com).
Radiation Safety Officer, Feb. 9-13, Las Vegas, Nevada, a technical short course offering of
Nevada Technical Associates. Contact: Nevada Technical Associates, Inc., P.O. Box 90748,
Henderson, NV 89009 (phone 702-564-2798; fax 702-558-7672).
Medical Dosimetry Review, Feb. 23-27, 1998, a continuing education course offered by the
University of Texas at San Antonio. Contact: The University of Texas Health Science Center at
San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980
(phone 210-567-4491; fax 210-567-6964).
March 1998
Introduction to Radiation, March 2-6, 1998, a continuing education course offered by the
University of Texas Health Science Center at San Antonio. Contact: University of Texas Health
Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Drive, San
Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).
April 1998
34th Annual Meeting of the National Council on Radiation Protection and Measurements, Apr.
1-2, 1998, Arlington, VA. Contact: National Council on Radiation Protection and Measurements,
Suite 800, 7910 Woodmont Ave., Bethesda, MD 20814-3095 (phone 301-657-2652).
Transportation and Packaging of Radioactive Materials, April 13-14, 1998, Las Vegas, Nevada,
a technical short course offering of Nevada Technical Associates. Contact: Nevada Technical
Associates, Inc., P.O. Box 90748, Henderson, NV 89009 (phone 702-564-2798; fax
702-558-7672).
Technologies for the New Century, 1998 ANS Radiation Protection and Shielding Division
Topical Conference, Apr. 19-23, 1998, Nashville, Tennessee. Contact: Dan T. Ingersoll, Oak
Ridge National Laboratory, P.O. Box 2008, Oak Ridge, TN 37831-6363 (fax 423-574-9619,
http://wwwrsicc.ornl.gov/RPS98/rps98.htm).
May 1998
Radiation Oncology Resident's Review in Radiation Oncology Physics and Radiation Biology,
May 11-15, 1998, a continuing education course offered by the University of Texas at San
Antonio. Contact: The University of Texas Health Science Center at San Antonio, Continuing
Medical Education, 7703 Floyd Curl Dr., San Antonio, TX 78284-7980 (phone 210-567-4491;
fax 210-567-6964).
Physicist's Review in Radiation Oncology Physics, May 11-15, 1998, a continuing education
course offered by the University of Texas at San Antonio. Contact: The University of Texas
Health Science Center at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San
Antonio, TX 78284-7980 (phone 210-567-4491; fax 210-567-6964).
Computational Methods in Reactor Analysis and Shielding, May 18-22, 1998, Knoxville,
Tennessee, a short course offered by the University of Tennessee-Knoxville. Contact: Lydia
Salmon, Dept. of Nuclear Engineering, University of Tennessee, Knoxville, TN 37996 (phone
423-974-2525; email lsalmon@utk.edu).
Nuclear Criticality Safety, May 18-22, 1998, Knoxville, Tennessee, a short course offered by the
University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering,
University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email lsalmon@utk.edu).
Monte Carlo Analysis, May 18-22, 1998, Knoxville, Tennessee, a short course offered by the
University of Tennessee-Knoxville. Contact: Lydia Salmon, Dept. of Nuclear Engineering,
University of Tennessee, Knoxville, TN 37996 (phone 423-974-2525; email lsalmon@utk.edu).
Radiation Safety Officer's Course, May 18-22, 1998, a continuing education course offered by
the University of Texas at San Antonio. Contact: The University of Texas Health Science Center
at San Antonio, Continuing Medical Education, 7703 Floyd Curl Dr., San Antonio, TX
78284-7980 (phone 210-567-4491; fax 210-567-6964).
Practical MCNP for the HP, May 18-22, 1998, University of New Mexico-Los Alamos Campus.
Contact Dick Olsher, 505-667-3364, e-mail: dick@lanl.gov.
June 1998
Radiation Safety Officer, June 8-12, Las Vegas, Nevada, a technical short course offering of
Nevada Technical Associates. Contact: Nevada Technical Associates, Inc., P.O. Box 90748,
Henderson, NV 89009 (phone 702-564-2798; fax 702-558-7672).
3rd International Meeting of Physicists in the Inca Region, June 15-20, 1998, Cusco, Peru.
Contact: Jon Broadway, Internatl. Corps on Environment (ICE), Auburn University, 75
Technacenter Drive, Montgomery, AL 36117-6035 (phone: 334-242-2777; fax: 334-242-2755;
email: broadway@strudel.aum.edu).
July 1998
Health Physics Society Annual Meeting, July 12-16, 1998, Minneapolis, Minnesota. Contact:
Health Physics Society, Suite 402, 1313 Dolley Madison Blvd., McLean, VA 22101-3926 (phone
703-790-1745; fax 703-790-2672; email: hpsburkmgt@aol.com).
August 1998
Practical MCNP for the HP, Aug. 10-14, 1998, University of New Mexico-Los Alamos Campus.
Contact Dick Olsher, 505-667-3364, e-mail: dick@lanl.gov.
September 1998
Transportation and Packaging of Radioactive Materials, Sept. 15-16, 1998, Las Vegas, Nevada,
a technical short course offering of Nevada Technical Associates. Contact: Nevada Technical
Associates, Inc., P.O. Box 90748, Henderson, NV 89009 (phone 702-564-2798; fax
702-558-7672).
AccApp'98, Sept. 20-23, 1998, Gatlinburg, Tennessee, sponsored by the Oak Ridge-Knoxville,
TN, USA Section of the ANS. Contact: Dr. John Haines, Chairman, AccApp '98 Technical
Program Committee, Oak Ridge National Laboratory, Oak Ridge, TN 37831-8071 , USA (phone
423-574-0966 Fax: 423-576-7926, email: hainesjr@ornl.gov), or
http://www.engr.utk.edu/org/ans/AccApp98.
November 1998
Radiation Safety Officer, Nov. 2-6, 1998, Las Vegas, Nevada, a technical short course offering
of Nevada Technical Associates. Contact: Nevada Technical Associates, Inc., P.O. Box 90748,
Henderson, NV 89009 (phone 702-564-2798; fax 702-558-7672).
Radioactive Waste Management, Nov. 10-11, 1998, Las Vegas, Nevada, a technical short course
offering of Nevada Technical Associates. Contact: Nevada Technical Associates, Inc., P.O. Box
90748, Henderson, NV 89009 (phone 702-564-2798; fax 702-558-7672).
NOVEMBER ACCESSION OF LITERATURE
The following literature cited has been reviewed and placed in the RSICC Information Storage
and Retrieval Information System (SARIS), now searchable on the RSICC web server
(http://www-rsicc.ornl.gov/rsic.html). This early announcement is made as a service to the
shielding community. Copies of the literature are not distributed by RSICC. They may
generally be obtained from the author or from a documentation center such as the National
Technical Information Service (NTIS), Department of Commerce, Springfield, Virginia 22161.
For literature listed as available from INIS contact INIS Clearinghouse, International Atomic
Energy Agency, P.O. Box 100, A-1400 Vienna.
Health Phys., 71, 286-289 . . . The Determination of Radioisotope Levels in Municipal Sewage Sludge. . . . ; Miller, W.H.; Kunze, J.F.; Banerji, S.K.; Li, Y.C.; Graham, C.; Stretch, D. . . . September 1996 . . . University of Missouri-Columbia, Columbia, MO; Union Electric Company, Fulton, MO.
Health Phys., 71, 290-299 . . . Plutonium in the Savannah River Site Environment. . . . Carlton, W.H.; Murphy Jr., C.E.; Evans, A.G. . . . September 1996 . . . Westinghouse Savannah River Company, Aiken, SC.
Health Phys., 71, 300-306 . . . Calculation of Absorbed Energy in the Gastrointestinal Tract. . . . Poston Jr., J.W.; Kodimer, K.A.; Bolch, W.E.; Poston, Sr. J.W. . . . September 1996 . . . Argonne National Laboratory, Idaho Falls, ID; Texas A&M University, College Station, TX; University of Florida, Gainesville, FL.
Health Phys., 71, 307-314 . . . A Revised Model for the Calculation of Absorbed Energy in the Gastrointestinal Tract. . . . Poston, Jr.; J.W.; Kodimer, K.A.; Bolch, W.E.; Poston, Sr., J.W. . . . September 1996 . . . Argonne National Laboratory, Idaho Falls, ID; Texas A&M University, College Stations, TX; University of Florida, Gainesville, FL.
Health Phys., 71, 315-319 . . . On Residual Dose Rate Within Particle Accelerator Enclosures. . . . Cossairt, J.D. . . . September 1996 . . . Fermi National Accelerator Laboratory, Batavia, IL.
Health Phys., 71, 340-346 . . . 137Cs Concentration in Soil Samples from an Early Survey of Hiroshima Atomic Bomb and Cumulative Dose Estimation from the Fallout. . . . Shizuma, K.; Iwatani, K.; Hasai, H.; Hoshi, M.; Oka, T.; Okano, M. . . . September 1996 . . . Hiroshima University, Hiroshima, Japan; Kure University, Kure, Japan; Radiation Effects Association, Tokyo, Japan.
Health Phys., 71, 384-394 . . . Environmental Monitoring for a Low-Level Radioactive Waste Management Facility: Incinerator Operations. . . . Tries, M.A.; Ring, J.P.; Chabot, G.E. . . . September 1996 . . . University of Massachusetts, Lowell, MA; Harvard University, Cambridge, MA.
Health Phys., 71, 395 . . . Book Reviewed: Radiobiological Consequences of Nuclear Accidents: Contamination, Radioecology, Radiobiology and Health. . . . Hamilton, I.S. . . . September 1996 . . . Texas A&M University, College Station, TX.
Health Phys., 71, 396 . . . Book Reviewed: Human Reliability Analysis in Probabilistic Safety Assessment for Nuclear Power Plants, A Safety Practice. . . . Miller, I. . . . September 1996.
Health Phys., 71, 396 . . . Book Reviewed: Principles of Nuclear Medicine Second Edition. . . . Royal, H.D. . . . September 1996.
Health Phys., 71, 397 . . . Book Reviewed: Health Effects of Exposure to Low-Level Ionizing Radiation. . . . Musolino, S.V. . . . September 1996.
Health Phys., 71, 634-640 . . . One Decade After Chernobyl: Summing Up the Consequences. . . . Kaul, A.; Landfermann, H.; Thieme, M. . . . November 1996 . . . Bundesamt fuer Strahlenschutz, Salzgitter; Bundesministerium fuer Umwelt, Bonn; Bundesamt fuer Strahlenschutz, Oberschleissheim, Germany.
Health Phys., 71, 644-660 . . . Technical Basis for EPA's Proposed Regulation on the Cleanup of Sites Contaminated with Radioactivity. . . . Wolbarst, A.B.; Mauro, J.; Anigstein, R.; Back. D.; Bartlett, J.W.; Beres, D.; Chan, D.; Cla . . . November 1996 . . . U.S. Environmental Protection Agency, Washington, DC; S. Cohen & Associates, Inc.; McLean, VA.
Health Phys., 71, 692-699 . . . Shielding Design of a Treatment Room for an Accelerator-Based Epithermal Neutron Irradiation Facility for BNCT. . . . Evans, J.F.; Blue, T.E. . . . November 1996 . . . Ohio State University, Columbus, OH.
Health Phys., 71, 770-772 . . . Use of Large Gamma-Ray Detector to Measure 131I in Milk and Water at Low Levels. . . . Rosson, R.; Garcia, R.; Kahn, B. . . . November 1996 . . . Georgia Institute of Technology, Atlanta, GA; EG&G ORTEC, Oak Ridge, TN; Canberra Industries, Inc.; Meriden, CT.
Health Phys., 71, 786-794 . . . Radiation Protection Systems for the Final Focus Test Beam at SLAC. . . . Rokni, S.H.; Benson, E.C.; Burke, D.L.; Jenkins, T.M.; Liu, J.C.; Nelson, G.; Nelson, W.R.; . . . November 1996 . . . Stanford Linear Accelerator Center, Stanford University, Stanford, CA.
Health Phys., 71, 847-862 . . . Radiological Environmental Impact of the Nuclear Industry in China. . . . Pan Ziqiang; Wang Zhibo; Chen Zhuzhou; Zhang Yongxing; Xie Jianlun . . . December 1996 . . . Bureau of Safety, Protection, Environment and Health, China National Nuclear Corp., China; Institute of Atomic Energy, Beijing, China.
Health Phys., 72, 186-194 . . . Historical Dose Reconstruction Project: Estimating the Population at Risk. . . . Rogers, J.F.; Killough, G.G. . . . February 1997 . . . Centers for Disease Control and Prevention, Atlanta, GA; Hendecagon Corp., Oak Ridge, TN; Radiological Assessments Corp., Neeses, SC.
Health Phys., 72, 313-317 . . . Computer Model Generated Density Correction Factors for Gamma Spectroscopy Counting. . . . Darman, J.J.; Aldana, J.P. . . . February 1997 . . . NES, Inc., Danbury, CT.
Nucl. Sci. Eng., 124, 1-17 . . . Linear Transport in Correlated Stochastic Media. . . . Devooght, J. . . . September 1996 . . . Universite Libre de Bruxelles, Brussels, Belgium.
Nucl. Sci. Eng., 124, 18-30 . . . The Effectiveness of P2 and Simplified P2 Synthetic Accelerations in the Solutions of Discrete Ordinates Transport Equations. . . . Noh, T.; Miller, Jr., W.F. . . . September 1996 . . . Hong Ik University, Seoul, Korea; Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Sci. Eng., 124, 31-62 . . . Analysis of Inherent Oscillations in Multidimensional Sn Solutions of the Neutron Transport Equation. . . . Petrovic, B.G.; Haghighat, A. . . . September 1996 . . . Pennsylvania State University, University Park, PA.
Nucl. Sci. Eng., 124, 63-71 . . . Discrete Transport Model Eigenfunctions. . . . Germogenova, T.A. . . . September 1996 . . . Russian Academy of Sciences, Moscow, Russia.
Nucl. Sci. Eng., 124, 72-81 . . . A Diffusion-Accelerated Solution Method for the Nonlinear Characteristic Scheme in Slab Geometry. . . . Wareing, T.A.; Walters, W.F.; Morel, J.E. . . . September 1996 . . . Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Sci. Eng., 124, 82-88 . . . Accounting for Strong Localized Heterogeneities and Local Transport Effect in Core Calculation. . . . Ruggieri, J.M.; Boyer, R.; Doriath, J.Y.; Finck, P.J. . . . September 1996 . . . CISI, Saint-Paul-les-Durance, France; Universite de Provence, Marseille, France; Commissariat a l'Energie Atomique, Saint-Paul-les-Durance, France.
Nucl. Sci. Eng., 124, 89-96 . . . Particle Transport in the Presence of Parametric Noise. . . . Prinja, A.K.; Gonzalez-Aller, A. . . . September 1996 . . . University of New Mexico, Albuquerque, NM.
Nucl. Sci. Eng., 124, 97-110 . . . Efficient Higher Order Nodal Finite Element Formulations for Neutron Multigroup Diffusion Equations. . . Hennart, J.P.; Malambu, E.M.; Mund, E.H.; del Valle, E. . . . September 1996 . . . Universidad Nacional Autonoma de Mexico, Mexico, D.F., Mexico; SCK-CEN Mol, Mol, Belgium; Universite Libre de Bruxelles, Brussels, Belgium; Universite Catholique de Louvain, Louvain-la-Neuve, Belgium; Instituto Politecnico Nacional, Mexcio, D.F., Mexico.
Nucl. Sci. Eng., 124, 160-166 . . . Incorporation of a New Spectral History Correction Method into Local Power Reconstruction for Nodal Methods. . . . Lee, C.H.; Kim, Y.J.; Song, J.W.; Park, C.O. . . . September 1996 . . . Korea Atomic Energy Research Institute, Taejon, Korea.
Nucl. Sci. Eng., 124, 167-177 . . . On the Neutron Noise Diagnostics of Pressurized Water Reactor Control Rod Vibrations - IV: Application of Neural Networks. . . . Pazsit, I.; Garis, N.S.; Glockler, O. . . . September 1996 . . . Chalmers University of Technology, Goteborg, Sweden; Ontario Hydro Nuclear, Ontrario, Canada.
Nucl. Sci. Eng., 124, 178-187 . . . Multiobjective Pressurized Water Reactor Reload Core Design by Nondominated Genetic Algorithm Search. . . . Parks, G.T. . . . September 1996 . . . Cambridge University, Cambridge, United Kingdom.
Nucl. Sci. Eng., 124, 188-196 . . . Fuel Management Optimization Using Genetic Algorithms and Expert Knowledge. . . . DeChaine, M.D.; Feltus, M.A. . . . September 1996 . . . Pennsylvania State University, University Park, PA.
Nucl. Sci. Eng., 124, 197-209 . . . Monte Carlo Calculation of Point-Detector Sensitivities to Material Parameters. . . . Perel, R.L.; Wagschal, J.J.; Yeivin, Y. . . . September 1996 . . . Hebrew University of Jerusalem, Jerusalem, Israel.
Nucl. Sci. Eng., 125, 1-11 . . . Error Estimations and Their Biases in Monte Carlo Eigenvalue Calculations. . . . Ueki, T.; Mori, T.; Nanagawa, M. . . . January 1997 . . . University of Michigan, Ann Arbor, MI; Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.
Nucl. Sci. Eng., 125, 12-18 . . . Post-Convergence Automatic Differentiation of Iterative Schemes.
. . . Azmy, Y.Y. . . . January 1997 . . . Oak Ridge National Laboratory, Oak Ridge, TN.
Nucl. Sci. Eng., 125, 19-23 . . . Perturbation of General Boundary Condition for an Eigenvalue Change in the Neutron Boltzmann Transport Equation. . . . Yamamoto, T. . . . January 1997 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.
Nucl. Sci. Eng., 125, 24-50 . . . The Suite of Analytical Benchmarks for Neutral Particle Transport in Infinite Isotropically Scattering Media. . . . Kornreich, D.E.; Ganapol, B.D. . . . January 1997 . . . Los Alamos National Laboratory, Los Alamos, NM; University of Arizona, Tucson, AZ.
Nucl. Sci. Eng., 125, 101-106 . . . A New Variational Functional for Space-Time Neutronics. . . . Favorite, J.A.; Stacey, Jr., W.M. . . . January 1997 . . . Georgia Institute of Technology, Atlanta, GA.
Nucl. Sci. Eng., 125, 111-127 . . . Response Functions for Neutron Skyshine Analysis. . . . Gui, A.A.; Shultis, J.K.; Faw, R.E. . . . February 1997 . . . Kansas State University, Manhattan, KS.
Nucl. Sci. Eng., 125, 128-170 . . . A New Weight-Dependent Direct Statistical Approach Model. . . . Burn, K.W. . . . February 1997 . . . ENEA, Bologna, Italy.
Nucl. Sci. Eng., 125, 171-177 . . . The Generalized Pn Synthetic Acceleration Method for Linear Transport Problems with Highly Anisotropic Scattering. . . . Khattab, K.M. . . . February 1997 . . . Atomic Energy Commission, Damascus, Syria.
Nucl. Sci. Eng., 125, 178-187 . . . Resonance Calculations Using the Multiband Method and Interface Currents. . . . Tatsumi, M.; Ito, T.; Takeda, T.; Yamasaki, M.; Yamamoto, A.; Takayasu, M. . . . February 1997 . . . Osaka University, Osaka, Japan; Nuclear Fuel Industries, Ltd., Osaka, Japan.
Nucl. Sci. Eng., 125, 188-195 . . . A Geometry-Independent Fine-Mesh-Based Monte Carlo Importance Generator. . . . Liu, L.; Gardner, R.P. . . . February 1997 . . . North Carolina State University, Raleigh, NC.
Nucl. Sci. Eng., 125, 196-204 . . . Study of Gamma Radiation from the Interaction of 14.6-MeV Neutrons with 27Al. . . . Hlavac, S.; Dostal, L.; Turzo, I.; Pavlik, A.; Vonach, H. . . . February 1997 . . . Slovak Academy of Sciences, Bratislava, Slovakia; Unviersitat Wien, Vienna, Austria.
Nucl. Sci. Eng., 125, 205-217 . . . Measurement of Neutron Energy Spectrum Below 10 keV in an Iron Shield Bombarded by Deuterium-Tritium Neutrons and Benckmark Test of Evaluated Nuclear Data From . . . Maekawa, F.; Oyama, Y. . . . February 1997 . . . Japan Atomic Energy Research Institute, Ibaraki-ken, Japan.
Nucl. Sci. Eng., 125, 243-247 . . . Validation of Neutron Fluence Calculation Methodology for VVER-440 Vessel. . . . Ilieva, K.; Apostolov, T.; Belousov, S.; Penev, Iv.; Popova, I. . . . February 1997 . . . Bulgarian Academy of Sciences, Sofia, Bulgaria.
Nucl. Sci. Eng., 127, 1-21 . . . Multidimensional Electron-Photon Transport with Standard Discrete Ordinates Codes. . . . Drumm, C.R. . . . September 1997 . . . Sandia National Laboratories, Albuquerque, NM.
Nucl. Sci. Eng., 127, 22-35 . . . Automatic Variance Reduction for Three-Dimensional Monte Carlo Simulations by the Local Importance Function Transform - I: Analysis. . . . Turner, S.A.; Larsen, E.W. . . . September 1997 . . . Los Alamos National Laboratory, Los Alamos, NM; University of Michigan, Ann Arbor, MI.
Nucl. Sci. Eng., 127, 36-53 . . . Automatic Variance Reduction for Three-Dimensional Monte Carlo Simulations by the Local Importance Function Transform - II: Numerical Results. . . . Turner, S.A.; Larsen, E.W. . . . September 1997 . . . Los Alamos National Laboratory, Los Alamos, NM; University of Michigan, Ann Arbor, MI.
Nucl. Sci. Eng., 127, 54-77 . . . Confidence Interval Procedures for Monte Carlo Transport Simulations. . . . Pederson, S.P.; Forster, R.A.; Booth, T.E. . . . September 1997 . . . Georgia Institute of Technology, Atlanta, GA; Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Sci. Eng., 127, 78-88 . . . Difficulties in Vector-Parallel Processing of Monte Carlo Codes. . . . Higuchi, K.; Asai, K. . . . September 1997 . . . Japan Atomic Energy Research Institute, Tokyo, Japan; Research Organization for Information Science and Technology, Ibaraki, Japan.
Nucl. Sci. Eng., 127, 89-103 . . . Effect of a 0.3-eV Resonance Cross Section for Plutonium on the Coolant Void Reactivity in a Heavy Water Lattice. . . . Kowata, Y.; Fukumura, N. . . . September 1997 . . . Power Reactor and Nuclear Fuel Development Corp., Ibaraki-ken, Japan.
Nucl. Sci. Eng., 127, 245-261 . . . Experimental and Calculated Scandium Threshold Reaction Cross Sections Averaged Over a 235U Fission Neutron Spectrum. . . . Suarez, P.M.; Arriberre, M.A.; Guevara, S.R.; Kestelman, A.J. . . . November 1997 . . . Centro Atomico Bariloche e Instituto Balseiro, Bariloche, Argentina.
Nucl. Sci. Eng., 127, 262-291 . . . Neutronic Analysis of Critical Configurations in Geologic Respositories: I - Weapons-Grade Plutonium. . . . Greenspan, E.; Vujic, J.; Burch, J. . . . November 1997 . . . University of California, Berkeley, CA.
Nucl. Sci. Eng., 127, 317-337 . . . Numerical Evaluation of the Three-Dimensional Searchlight Problem in a Half-Space. . . . Kornreich, D.E.; Ganapol, B.D. . . . November 1997 . . . Los Alamos National Laboratory, Los Alamos, NM; University of Arizona, Tucson, AZ.
Nucl. Sci. Eng., 127, 338-345 . . . Exponential Convergence on a Continuous Monte Carlo Transport Problem. . . . Booth, T.E. . . . November 1997 . . . Los Alamos National Laboratory, Los Alamos, NM.
Nucl. Sci. Eng., 127, 346-357 . . . Mixed Integer Programming for Pressurized Water Reactor Fuel-Loading-Pattern Optimization. . . . Kim, T.K.; Kim, C.H. . . . November 1997 . . . Seoul National University, Seoul, Korea.
Nucl. Technol., 119, 38-47 . . . Modeling Gamma-Ray Dose Rate From A Spent Pressurized Water Reactor Fuel Assembly. . . . Bozkurt, A.; Tsoulfanidis, N. . . . July 1997 . . . University of Missouri-Rolla, Rolla, MO.
INDC(CCP)-406 . . . The LIPAR-5 Resonance Parameter Library. . . . Abagyan, L.P. . . . August
1997 . . . Kurchatov Institute Russian Science Centre, Russia. . . . . . . Translated by the IAEA.
Next MCNP Course in Europe
QUESTIONNAIRE
Should you not be interested in the course, but your colleagues, please pass on to them a copy of
this message.
I am interested in participating in the course on MCNP-4B to be held from 23-27 March 1997 at
the University of Stuttgart.
My preference would be to attend the following course:
1. "Introduction to MCNP" for those who have never run the code or have just some experience
This class would cover: basic geometry, sources, tallies, output, criticality, materials, repeated
structures, variance reduction, graphics
2. "Advanced MCNP" for intermediate users who have run MCNP but want help with more advanced features
This class would cover: repeated structures, lattices, sources and tallies in repeated structures,
statistical assessment of tally quality, physics, variance reduction, graphics, criticality, photons,
electrons, data libraries, multi-group/adjoint, tutorials
I wish to participate and acknowledge that the participation fee is of 3000 DM
I confirm that my knowledge of English is adequate for following the course
Name:
Address:
Phone:
Fax:
e-mail address:
please return this questionnaire to E. Sartori at sartori@nea.fr or fax it to +33 (1) 45241110
DEADLINE for reply: 10 January 1998
Comments:
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www.engr.utk.edu/org/ans/AccApp98