Jump to main content

yr 〜
yr

Search results 30

POLIDENT, a module for generating continuous-energy cross sections from ENDF resonance data [microform] / prepared by M.E. Dunn, N.M. Greene ; prepared for Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission

POLIDENT, a module for generating continuous-energy cross sections from ENDF resonance data [microform] / prepared by M.E. Dunn, N.M. Greene ; prepared for Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
Microform図書
2000<YCA-Y 3.N 88:25/6694>
National Diet Library

SCAMPI: A code package for cross-section processing CONF-960415-31 DE96 008672

SCAMPI: A code package for cross-section processing CONF-960415-31 DE96 008672
PaperMicroform規格・テクニカルリポート類
Parks, C. V, Petrie, L. M, Bowman, S. M, Broadhead, B. L, Greene, N. M1996<LS-DE96/008672>
National Diet LibraryOther Libraries in Japan

Production and testing of the VITAMIN-B6 fine group and the BUGLE-93 broad-group neutron/photon cross-section libraries derived from ENDF/B-VI nuclear data NUREG/CR-6214 TI95 005715 ORNL-6795

Production and testing of the VITAMIN-B6 fine group and the BUGLE-93 broad-group neutron/photon cross-section libraries derived from ENDF/B-VI nuclear data NUREG/CR-6214 TI95 005715 ORNL-6795
Microform規格・テクニカルリポート類
Ingersoll, D. T, White, J. E, Wright, R. Q, Hunter, H. T, Slater, C. O, Greene, N. M, Roussin, R. W, MacFarlane, R. E1995<LS-TI95/005715>
National Diet Library

LAW Library -- A multigroup cross-section library for use in radioactive waste analysis calculations ORNL/TM-12370 DE94 017317

LAW Library -- A multigroup cross-section library for use in radioactive waste analysis calculations ORNL/TM-12370 DE94 017317
Microform規格・テクニカルリポート類
Greene, N. M, Arwood, J. W, Wright, R. Q, Parks, C. V1994<LS-DE94/017317>
National Diet Library

SCALE: A MODULAR CODE SYSTEM FOR PERFORMING STANDARDIZED COMPUTER ANALYSES FOR LICENSING EVALUATION. FUNCTIONAL MODULES F1-F8 - VOLUME ... (NUREG ; NUREG-CR-0200-VOL.2-PT.1-REV.4)

SCALE: A MODULAR CODE SYSTEM FOR PERFORMING STANDARDIZED COMPUTER ANALYSES FOR LICENSING EVALUATION. FUNCTIONAL MODULES F1-F8 - VOLUME ... (NUREG ; NUREG-CR-0200-VOL.2-PT.1-REV.4)
Paper図書
GREENE, N.M.NUREG (U.S. Nuclear Regulatory Commission)(NUREG (U.S. Nuclear Regulatory Commission))1995.
Other Libraries in Japan
  • Author HeadingGREENE, N.M.

LAW LIBRARY - A MULTIGROUP CROSS-SECTION LIBRARY FOR USE IN RADIOACTIVE WASTE ANALYSIS CALCULATIONS. (ORNL ; ORNL/TM-12370)

LAW LIBRARY - A MULTIGROUP CROSS-SECTION LIBRARY FOR USE IN RADIOACTIVE WASTE ANALYSIS CALCULATIONS. (ORNL ; ORNL/TM-12370)
Paper図書
GREENE, N.M.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1994.
Other Libraries in Japan
  • Author HeadingGREENE, N.M.

New SCALE-4 features related to cross-section processing (CONF ; CONF-9109217-10; DE92017128)

New SCALE-4 features related to cross-section processing (CONF ; CONF-9109217-10; DE92017128)
Paper図書
Petrie, L.M., Landers, N.F., Greene, N.M. [et al.]Oak Ridge National Lab.1991.12.31.
Other Libraries in Japan
  • Author HeadingPetrie, L.M. Landers, N.F. Greene, N.M. Parks, C.V.

AMPX-77: A modular code system for generating coupled multigroup neutron-gamma cross-section libraries from ENDF/B-IV and/or ENDF/B-V (ORNL ; ORNL/CSD/TM-283)

AMPX-77: A modular code system for generating coupled multigroup neutron-gamma cross-section libraries from ENDF/B-IV and/or ENDF/B-V (ORNL ; ORNL/CSD/TM-283)
Paper図書
N.M. Greene [et al.]1992
Other Libraries in Japan
  • Author HeadingGreene, N.M. Ford, W.E. III Petrie, L.M. A...

PRODUCTION AND TESTING OF THE VITAMIN-B6 FINE-GROUP AND THE BUGLE-93 BROAD-GROUP NEUTRON/PHOTON CROSS-SECTION LIBRARIES DERIVED FROM ENDF/B-VI NUCLEAR DATA (CONF ; CONF-930809-13)

PRODUCTION AND TESTING OF THE VITAMIN-B6 FINE-GROUP AND THE BUGLE-93 BROAD-GROUP NEUTRON/PHOTON CROSS-SECTION LIBRARIES DERIVED FROM ENDF/B-VI NUCLEAR DATA (CONF ; CONF-930809-13)
Paper図書
INGERSOLL, D.T.// WHITE, J.E.// WRIGHT, R.Q.// HUNTER, H.T.// SLATER, C.O.// GREENE, N.M.// MACFARLANE, R.E. (OAK RIDGE NATIONAL LAB., TN (UNITED STATES))1993.
Other Libraries in Japan
  • Author HeadingINGERSOLL, D.T. WHITE, J.E. WRIGHT, R.Q. HUNTER, H.T. SLATER, C.O. GREENE, N.M. MACFARLANE, R.E.

LAW (LIBRARY TO ANALYZE WASTE) LIBRARY: A MULTIGROUP CROSS SECTION LIBRARY FOR USE IN RADIOACTIVE WASTE ANALYSIS CALCULATIONS (CONF ; CONF-891103-21)

LAW (LIBRARY TO ANALYZE WASTE) LIBRARY: A MULTIGROUP CROSS SECTION LIBRARY FOR USE IN RADIOACTIVE WASTE ANALYSIS CALCULATIONS (CONF ; CONF-891103-21)
Paper図書
GREENE, N.M.//PARKS, C.V.//ARWOOD, J.W. (OAK RIDGE NATIONAL LAB., TN (USA))1989.
Other Libraries in Japan
  • Author HeadingGREENE, N.M. PARKS, C.V. ARWOOD, J.W.

Sequence Coding and Search System for licensee event reports: user's guide. Volume 1, Revision 1 (ORNL/NSIC ; ORNL/NSIC-223-VOL.1-REV.1)

Sequence Coding and Search System for licensee event reports: user's guide. Volume 1, Revision 1 (ORNL/NSIC ; ORNL/NSIC-223-VOL.1-REV.1)
Paper図書
Oak Ridge National Lab., TN (USA); JBF Associates, Knoxville, TN (USA); Science Applications International Corp., Oak Ridge, TN (USA)(Oak Ridge National Lab., TN (USA); JBF Associates, Knoxville, TN (USA); Science Applications International Corp., Oak Ridge, TN (USA))1985.
Other Libraries in Japan
  • Author HeadingGreene, N.M. Johnson, M.P. Mays, G.T.

SACRD: A DATA BASE FOR FAST-REACTOR SAFETY COMPUTER CODES - VERSION 81. (ORNL ; ORNL/CSD-86)

SACRD: A DATA BASE FOR FAST-REACTOR SAFETY COMPUTER CODES - VERSION 81. (ORNL ; ORNL/CSD-86)
Paper図書
GREENE, N.M.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1982.
Other Libraries in Japan
  • Author HeadingGREENE, N.M.

BONAMI-S: response self-shielding by the Bondarenko method. Volume 2. Functional studies (NUREG ; NUREG/CR-0200-Vol.2; ORNL/NUREG/CSD-2-V2; DE82016031; TRN: 83-010283)

BONAMI-S: response self-shielding by the Bondarenko method. Volume 2. Functional studies (NUREG ; NUREG/CR-0200-Vol.2; ORNL/NUREG/CSD-2-V2; DE82016031; TRN: 83-010283)
Paper図書
Greene, N.M.Oak Ridge National Lab.1981.10.
Other Libraries in Japan
  • Author HeadingGreene, N.M.

SACRD: A DATA BASE FOR FAST REACTOR SAFETY COMPUTER CODES, CONTENTS AND GLOSSARY OF VERSION 1 OF THE SYSTEM. (ORNL ; ORNL-5477/V2)

SACRD: A DATA BASE FOR FAST REACTOR SAFETY COMPUTER CODES, CONTENTS AND GLOSSARY OF VERSION 1 OF THE SYSTEM. (ORNL ; ORNL-5477/V2)
Paper図書
GREENE, N.M.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1979.
Other Libraries in Japan
  • Author HeadingGREENE, N.M.

SACRD: A DATA BASE FOR FAST REACTOR SAFETY COMPUTER CODES, GENERAL DESCRIPTION. (ORNL ; ORNL-5477/V1)

SACRD: A DATA BASE FOR FAST REACTOR SAFETY COMPUTER CODES, GENERAL DESCRIPTION. (ORNL ; ORNL-5477/V1)
Paper図書
GREENE, N.M.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1979.
Other Libraries in Japan
  • Author HeadingGREENE, N.M.

AMPX: A MODULAR SYSTEM FOR MULTIGROUP CROSS SECTION GENERATION AND MANIPULATION. (TID ; TID-28576)

AMPX: A MODULAR SYSTEM FOR MULTIGROUP CROSS SECTION GENERATION AND MANIPULATION. (TID ; TID-28576)
Paper図書
GREENE, N.M.(et al.)1977.
Other Libraries in Japan
  • Author HeadingGREENE, N.M.

AMPX: A MODULAR CODE SYSTEM FOR GENERATING COUPLED MULTIGROUP NEUTRON-GAMMA LIBRARIES FROM ENDF/B. (ORNL ; ORNL-TM-3706)

AMPX: A MODULAR CODE SYSTEM FOR GENERATING COUPLED MULTIGROUP NEUTRON-GAMMA LIBRARIES FROM ENDF/B. (ORNL ; ORNL-TM-3706)
Paper図書
GREENE, N.M.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1976.
Other Libraries in Japan
  • Author HeadingGREENE, N.M.

XLACS: A PROGRAM TO PRODUCE WEIGHTED MULTIGROUP NEUTRON CROSS SECTIONS FROM ENDF/B. (ORNL ; ORNL-TM-3646)

XLACS: A PROGRAM TO PRODUCE WEIGHTED MULTIGROUP NEUTRON CROSS SECTIONS FROM ENDF/B. (ORNL ; ORNL-TM-3646)
Paper図書
GREENE, N.M.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1972.
Other Libraries in Japan
  • Author HeadingGREENE, N.M.

EVALUATION AND COMPILATION OF THE FISSION AND CAPTURE CROSS SECTIONS OF PU-239 IN THE ENERGY RANGE 25 KEV TO 15 MEV. (ORNL ; ORNL-TM-2797)

EVALUATION AND COMPILATION OF THE FISSION AND CAPTURE CROSS SECTIONS OF PU-239 IN THE ENERGY RANGE 25 KEV TO 15 MEV. (ORNL ; ORNL-TM-2797)
Paper図書
GREENE, N.M.(et al.)Oak Ridge National Laboratory(Oak Ridge National Laboratory)1970.
Other Libraries in Japan
  • Author HeadingGREENE, N.M.

XSDRN: A DISCRETE ORDINATES SPECTRAL AVERAGING CODE. (ORNL ; ORNL-TM-2500)

XSDRN: A DISCRETE ORDINATES SPECTRAL AVERAGING CODE. (ORNL ; ORNL-TM-2500)
Paper図書
GREENE, N.M.Oak Ridge National Laboratory(Oak Ridge National Laboratory)1969.
Other Libraries in Japan
  • Author HeadingGREENE, N.M.
RSS