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NEA-1768 ZZ-MCJEFF3.1NEA.

ZZ MCJEFF3.1NEA, MCNP Neutron Cross Section Library based on JEFF3.1

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-MCJEFF3.1NEA.
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2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
ZZ-MCJEFF3.1NEA0300K NEA-1768/01 Tested 23-JUN-2006
ZZ-MCJEFF3.1NEA0400K NEA-1768/02 Tested 23-JUN-2006
ZZ-MCJEFF3.1NEA0500K NEA-1768/03 Tested 23-JUN-2006
ZZ-MCJEFF3.1NEA0600K NEA-1768/04 Tested 23-JUN-2006
ZZ-MCJEFF3.1NEA0700K NEA-1768/05 Tested 23-JUN-2006
ZZ-MCJEFF3.1NEA0800K NEA-1768/06 Tested 23-JUN-2006
ZZ-MCJEFF3.1NEA0900K NEA-1768/07 Tested 23-JUN-2006
ZZ-MCJEFF3.1NEA1000K NEA-1768/08 Tested 23-JUN-2006
ZZ-MCJEFF3.1NEA1200K NEA-1768/09 Tested 23-JUN-2006
ZZ-MCJEFF3.1NEA1800K NEA-1768/10 Tested 23-JUN-2006
ZZ-MCJEFF3.1NEATHERM NEA-1768/12 Tested 02-MAY-2007

Machines used:

Package ID Orig. computer Test computer
NEA-1768/01 Many Computers PC Windows
NEA-1768/02 Many Computers PC Windows
NEA-1768/03 Many Computers PC Windows
NEA-1768/04 Many Computers PC Windows
NEA-1768/05 Many Computers PC Windows
NEA-1768/06 Many Computers PC Windows
NEA-1768/07 Many Computers PC Windows
NEA-1768/08 Many Computers PC Windows
NEA-1768/09 Many Computers PC Windows
NEA-1768/10 Many Computers PC Windows
NEA-1768/12 Many Computers PC Windows
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3. DESCRIPTION OF PROGRAM OR FUNCTION

Continuous energy neutron cross-section data library for the Monte Carlo program MCNP based on the JEFF-3.1 evaluated nuclear data library (ACE format).
  
FORMAT: ACE
  
NUMBER OF GROUPS: Continuous energy
  
NUCLIDES (381): 1-H-1, 1-H-2, 1-H-3, 2-He-3, 2-He-4, 3-Li-6, 3-Li-7, 4-Be-9, 5-B-10, 5-B-11, 6-C-0, 7-N-14, 7-N-15, 8-O-16, 8-O-17, 9-F-19, 11-Na-22, 11-Na-23, 12-Mg-24, 12-Mg-25, 12-Mg-26, 13-Al-27, 14-Si-28, 14-Si-29, 14-Si-30, 15-P-31, 16-S-32, 16-S-33, 16-S-34, 16-S-36, 17-Cl-35, 17-Cl-37, 18-Ar-36, 18-Ar-38, 18-Ar-40, 19-K-39, 19-K-40, 19-K-41, 20-Ca-40, 20-Ca-42, 20-Ca-43, 20-Ca-44, 20-Ca-46, 20-Ca-48, 21-Sc-45, 22-Ti-46, 22-Ti-47, 22-Ti-48, 22-Ti-49, 22-Ti-50, 23-V-0, 24-Cr-50, 24-Cr-52, 24-Cr-53, 24-Cr-54, 25-Mn-55, 26-Fe-54, 26-Fe-56, 26-Fe-57, 26-Fe-58, 27-Co-58, 27-Co-58m, 27-Co-59, 28-Ni-58, 28-Ni-59, 28-Ni-60, 28-Ni-61, 28-Ni-62, 28-Ni-64, 29-Cu-63, 29-Cu-65, 30-Zn-0, 31-Ga-0, 32-Ge-70, 32-Ge-72, 32-Ge-73, 32-Ge-74, 32-Ge-76, 33-As-75, 34-Se-74, 34-Se-76, 34-Se-77, 34-Se-78, 34-Se-79, 34-Se-80, 34-Se-82, 35-Br-79, 35-Br-81, 36-Kr-78, 36-Kr-80, 36-Kr-82, 36-Kr-83, 36-Kr-84, 36-Kr-85, 36-Kr-86, 37-Rb-85, 37-Rb-86, 37-Rb-87, 38-Sr-84, 38-Sr-86, 38-Sr-87, 38-Sr-88, 38-Sr-89, 38-Sr-90, 39-Y-89, 39-Y-90, 39-Y-91, 40-Zr-90, 40-Zr-91, 40-Zr-92, 40-Zr-93, 40-Zr-94, 40-Zr-95, 40-Zr-96, 41-Nb-93, 41-Nb-94, 41-Nb-95, 42-Mo-92, 42-Mo-94, 42-Mo-95, 42-Mo-96, 42-Mo-97, 42-Mo-98, 42-Mo-99, 42-Mo-100, 43-Tc-99, 44-Ru-96, 44-Ru-98, 44-Ru-99, 44-Ru-100, 44-Ru-101, 44-Ru-102, 44-Ru-103, 44-Ru-104, 44-Ru-105, 44-Ru-106, 45-Rh-103, 45-Rh-105, 46-Pd-102, 46-Pd-104, 46-Pd-105, 46-Pd-106, 46-Pd-107, 46-Pd-108, 46-Pd-110, 47-Ag-107, 47-Ag-109, 47-Ag-110, 47-Ag-111, 48-Cd-106, 48-Cd-108, 48-Cd-110, 48-Cd-111, 48-Cd-112, 48-Cd-113, 48-Cd-114, 48-Cd-115, 48-Cd-116, 49-In-113, 49-In-115, 50-Sn-112, 50-Sn-114, 50-Sn-115, 50-Sn-116, 50-Sn-117, 50-Sn-118, 50-Sn-119, 50-Sn-120, 50-Sn-122, 50-Sn-123, 50-Sn-124, 50-Sn-125, 50-Sn-126, 51-Sb-121, 51-Sb-123, 51-Sb-124, 51-Sb-125, 51-Sb-126, 52-Te-120, 52-Te-122, 52-Te-123, 52-Te-124, 52-Te-125, 52-Te-126, 52-Te-127, 52-Te-128, 52-Te-129, 52-Te-130, 52-Te-132, 53-I-127, 53-I-129, 53-I-130, 53-I-131, 53-I-135, 54-Xe-124, 54-Xe-126, 54-Xe-128, 54-Xe-129, 54-Xe-130, 54-Xe-131, 54-Xe-132, 54-Xe-133, 54-Xe-134, 54-Xe-135, 54-Xe-136, 55-Cs-133, 55-Cs-134, 55-Cs-135, 55-Cs-136, 55-Cs-137, 56-Ba-130, 56-Ba-132, 56-Ba-134, 56-Ba-135, 56-Ba-136, 56-Ba-137, 56-Ba-138, 56-Ba-140, 57-La-138, 57-La-139, 57-La-140, 58-Ce-140, 58-Ce-141, 58-Ce-142, 58-Ce-143, 58-Ce-144, 59-Pr-141, 59-Pr-142, 59-Pr-143, 60-Nd-142, 60-Nd-143, 60-Nd-144, 60-Nd-145, 60-Nd-146, 60-Nd-147, 60-Nd-148, 60-Nd-150, 61-Pm-147, 61-Pm-148, 61-Pm-148, 61-Pm-149, 61-Pm-151, 62-Sm-144, 62-Sm-147, 62-Sm-148, 62-Sm-149, 62-Sm-150, 62-Sm-151, 62-Sm-152, 62-Sm-153, 62-Sm-154, 63-Eu-151, 63-Eu-152, 63-Eu-153, 63-Eu-154, 63-Eu-155, 63-Eu-156, 63-Eu-157, 64-Gd-152, 64-Gd-154, 64-Gd-155, 64-Gd-156, 64-Gd-157, 64-Gd-158, 64-Gd-160, 65-Tb-159, 65-Tb-160, 66-Dy-160, 66-Dy-161, 66-Dy-162, 66-Dy-163, 66-Dy-164, 67-Ho-165, 68-Er-162, 68-Er-164, 68-Er-166, 68-Er-167, 68-Er-168, 68-Er-170, 71-Lu-175, 71-Lu-176, 72-Hf-174, 72-Hf-176, 72-Hf-177, 72-Hf-178, 72-Hf-179, 72-Hf-180, 73-Ta-181, 73-Ta-182, 74-W-182, 74-W-183, 74-W-184, 74-W-186, 75-Re-185, 75-Re-187, 76-Os-0, 77-Ir-191, 77-Ir-193, 78-Pt-0, 79-Au-197, 80-Hg-196, 80-Hg-198, 80-Hg-199, 80-Hg-200, 80-Hg-201, 80-Hg-202, 80-Hg-204, 81-Tl-0, 82-Pb-204, 82-Pb-206, 82-Pb-207, 82-Pb-208, 83-Bi-209, 88-Ra-223, 88-Ra-224, 88-Ra-225, 88-Ra-226, 89-Ac-225, 89-Ac-226, 89-Ac-227, 90-Th-227, 90-Th-228, 90-Th-229, 90-Th-230, 90-Th-232, 90-Th-233, 90-Th-234, 91-Pa-231, 91-Pa-232, 91-Pa-233, 92-U-232, 92-U-233, 92-U-234, 92-U-235, 92-U-236, 92-U-237, 92-U-238, 93-Np-235, 93-Np-236, 93-Np-237, 93-Np-238, 93-Np-239, 94-Pu-236, 94-Pu-237, 94-Pu-238, 94-Pu-239, 94-Pu-240, 94-Pu-241, 94-Pu-242, 94-Pu-243, 94-Pu-244, 94-Pu-246, 95-Am-241, 95-Am-242, 95-Am-242m, 95-Am-243, 95-Am-244, 95-Am-244m, 96-Cm-240, 96-Cm-241, 96-Cm-242, 96-Cm-243, 96-Cm-244, 96-Cm-245, 96-Cm-246, 96-Cm-247, 96-Cm-248, 96-Cm-249, 96-Cm-250, 97-Bk-247, 97-Bk-249, 97-Bk-250, 98-Cf-249, 98-Cf-250, 98-Cf-251, 98-Cf-252, 98-Cf-254, 99-Es-253, 99-Es-254, 99-Es-255, 100-Fm-255
  
Isotopes in isomeric state (library at 300K): 27-Co-58M, 47-Ag-110M, 48-Cd-115M, 52-Te-127M, 52-Te-129M, 61-Pm-148M, 95-Am-242M, 95-Am-244M
  
TEMPERATURES: 300 K, 400 K, 500 K, 600 K, 700 K, 800 K, 900 K, 1000 K, 1200 K and 1800 K (the package is separated as separate entity for each temperature to facilitate handling)
  
THERMAL SCATTERING  
- Hydrogen bound in polyethylene, 293.6 K, 350 K
- Hydrogen bound in water, 293.6 K, 323.6 K, 373.6 K,  423.6 K, 473.6 K, 523.6 K, 573.6 K, 623.6 K, 647.2 K, 800 K, 1000 K
- Hydrogen bound in ZrH, 293.6 K, 400 K, 500 K, 600 K, 700 K, 800 K 1000 K, 1200 K
-  Graphite, 293.6 K, 400 K, 500 K, 600 K, 700 K, 800 K 1000 K, 1200 K, 1600 K, 2000 K, 3000 K
- D bound in D2O, 293.6 K, 323.6 K, 373.6 K,  423.6 K, 473.6 K, 523.6 K, 573.6 K, 643.6 K,
- Be(metal), 293.6 K, 400 K, 500 K, 600 K, 700 K, 800 K 1000 K, 1200 K
- Be in BeO, 293.6 K, 400 K, 500 K, 600 K, 700 K, 800 K 1000 K, 1200 K
  
ORIGIN: JEFF3.1
  
WEIGHTING SPECTRUM:
NEA-1768/01
ACE library for 300 K

NEA-1768/02
ACE library for 400 K

NEA-1768/03
ACE library for 500 K

NEA-1768/04
ACE library for 600 K

NEA-1768/05
ACE library for 700 K

NEA-1768/06
ACE library for 800 K

NEA-1768/07
ACE library for 900 K

NEA-1768/08
ACE library for 1000 K

NEA-1768/09
ACE library for 1200 K

NEA-1768/10
ACE library for 1800 K

NEA-1768/12
ACE library for Thermal Scattering Data
An error has been introduced when processing the H-HZr file with the THERM module (NATOM=2 instead of  NATOM=1). The file at the same 8 different temperatures with the correct NJOY input has been processed again. The corresponding processed thermal scattering library is included in this version.
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4. METHODS

This library was generated with the NJOY-99.90 nuclear data processing system plus some specific updates required for correct processing. The library has undergone strict QA procedures. All inputs used for processing JEFF3.1 with NJOY99.90 and the documented derived version are provided. The validations made, using benchmark experiments for criticality (ICSBEP) and shielding (SINBAD) are documented in the report.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS AND INFORMATION

PRPR: Fortran 77 pre-processor source.
MAKXSF: Prepares the MCNP Cross-Section Libraries.
These programs are distributed with the Monte Carlo code package MCNP-4C2 (CCC-0701), PREPRO2002 Endf-6 files preprocessing codes (IAEA1379).
NJOY99 Data Processing System of Evaluated Nuclear Data Files ENDF Format (PSR-0480).
  
Requesters for MCJEFF3.1NEAttttK libraries (tttt is the temperature) should request also the THER data for thermal neutron applications.
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9. STATUS
Package ID Status date Status
NEA-1768/01 23-JUN-2006 Screened
NEA-1768/02 23-JUN-2006 Screened
NEA-1768/03 23-JUN-2006 Screened
NEA-1768/04 23-JUN-2006 Screened
NEA-1768/05 23-JUN-2006 Screened
NEA-1768/06 23-JUN-2006 Screened
NEA-1768/07 23-JUN-2006 Screened
NEA-1768/08 23-JUN-2006 Screened
NEA-1768/09 23-JUN-2006 Screened
NEA-1768/10 23-JUN-2006 Screened
NEA-1768/12 02-MAY-2007 Screened
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10. REFERENCES

- Trkov, A., ACELST code, December 2002.
-D. Lopez Aldama and A. Trkov, A test library for Accelerator Driven Systems, ADS-Lib/V1.0 , IAEA, 2005.
- M.S. Abdelrahman, N. Abdurrahman, Cross Section Libraries for Studies of Plutonium Disposition in Light Water Reactors. ANRCP-1999-28, October 1999.
- W. Haeck, B. Verboomen, ALEPH-DLG 1.1.0 Creating Cross Section Libraries for MCNP(X). SCK, CEN-BLG-1002 Rev. 0. February, 2006.
- J. Perrot, O. Meplan, ENDF2ACE User Guide, http://lpsc.in2p3.fr/gpr/MURE/html/ENDF2ACE_User_Guide/
- S. C. FRANKLE, Experience with ENDF60 and QA of a Continuous-Energy Library, XTM:SCF-96-363, Los Alamos National Laboratory, USA (1996)
- J. Blair Briggs (ed.), International Handbook of Evaluated Criticality Safety Benchmark Experiments, NEA/NSC/DOC(95)03/I, Nuclear Energy Agency, Paris (September 2005 Edition)
- S.C. van der Marck, Shielding benchmark calculations with MCNP-4C3 using JEFF-3.1 data, NRG-Petten, October 2005, JEFDOC-1106.
- S.C. van der Marck, Criticality safety benchmark calculations with MCNP-4C3 using JEFF-3.1 data, NRG-Petten, October 2005, JEFDOC-1107.
- NEA/OECD; The JEFF-3.1 project: Complete content of the JEFF-3.1 evaluated nuclear data library, June 2, 2005, NEA#06071 (on CDROM)
- Robert C. Little, Robert E. MacFarlane, ENDF/B-VI Neutron Library for MCNP with Probabity Tables, LANL, LA-UR-98-5718, Dec. 1998
- Russell D. Mosteller, Comparison of ENDF/B-VI and Initial ENDF/B-VII Results for the MCNP Criticality Validation Suite, LA-UR-05-8430, 2005.
- R. C. LITTLE, R. E. MacFARLANE, .ENDF/B-VI Neutron Library for MCNP with Probability Tables., LA-UR-98-5718, Los Alamos National Laboratory, USA (1998)
- M. C. WHITE, J. M. CAMPBELL, S. C. FRANKLE, R. C. LITTLE, Processing of Nuclear Data for Applications., LA-UR-02-1235, Los Alamos National Laboratory, USA (2002)
- J. M. CAMPBELL, S. C. FRANKLE, R. C. LITTLE, .ENDF66: A Continuous-Energy Neutron Data Library Based on ENDF/B-VI Release 6., LA-UR-03-0954, Los Alamos National Laboratory, USA (2003)
- J. D. Court, R.C. Brockhoff, and J.S. Hendricks Lawrence Livermore Pulsed Sphere Benchmark Analysis of MCNP ENDF/B-VI, LA-12885 (1994)
- Briesmeister, J. F., MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C, Los Alamos National Laboratory, LA-13709-M, 2000
- M. Mattes and J. Keinert, Thermal Neutron Scattering Data for the Moderator materials H2O, D2O and ZrHx in ENDF-6 Format and as ACE library for MCNP(X) Codes, INDC(NDS)-0470, April 2005
- MacFarlane, R.E., Muir, D.M., NJOY-99.0: Code System for Producing Pointwise and Multigroup Neutron and Photon Cross Sections from ENDF/B data, Los Alamos National Laboratory, PSR-480, 2000.
- R. E. MacFARLANE, .up90 - NJOY version 99.90., Los Alamos National Laboratory, USA (2003)
- R. E. MacFARLANE, .up112 - NJOY version 99.112., Los Alamos National Laboratory, USA (2005)
- Cullen, D.E., PREPRO 2004: 2004 ENDF/B Pre-processing codes, IAEA-NDS-39, Rev. 12, November 22, 2004.
- Sinbad data base, NEA (2005).
- Trkov, A., UpdXSDIR code, December 2002.
- F.A. Alpan, M.E. Dunn, Yummy: The Yucca Mountain MCNP-Library, ORNL/TM-2204/124, June 2004.
NEA-1768/01, included references:
- Processing of the JEFF-3.1 Cross Section Library into a Continuous Energy
Monte Carlo Radiation Transport and Criticality Data Library, OECD NEA Data
Bank, May 2006, prepared by O. Cabellos, NEA/NSC/DOC(2006)18
NEA-1768/02, included references:
- Processing of the JEFF-3.1 Cross Section Library into a Continuous Energy
Monte Carlo Radiation Transport and Criticality Data Library, OECD NEA Data
Bank, May 2006, prepared by O. Cabellos, NEA/NSC/DOC(2006)18
NEA-1768/03, included references:
- Processing of the JEFF-3.1 Cross Section Library into a Continuous Energy
Monte Carlo Radiation Transport and Criticality Data Library, OECD NEA Data
Bank, May 2006, prepared by O. Cabellos, NEA/NSC/DOC(2006)18
NEA-1768/04, included references:
- Processing of the JEFF-3.1 Cross Section Library into a Continuous Energy
Monte Carlo Radiation Transport and Criticality Data Library, OECD NEA Data
Bank, May 2006, prepared by O. Cabellos, NEA/NSC/DOC(2006)18
NEA-1768/05, included references:
- Processing of the JEFF-3.1 Cross Section Library into a Continuous Energy
Monte Carlo Radiation Transport and Criticality Data Library, OECD NEA Data
Bank, May 2006, prepared by O. Cabellos, NEA/NSC/DOC(2006)18
NEA-1768/06, included references:
- Processing of the JEFF-3.1 Cross Section Library into a Continuous Energy
Monte Carlo Radiation Transport and Criticality Data Library, OECD NEA Data
Bank, May 2006, prepared by O. Cabellos, NEA/NSC/DOC(2006)18
NEA-1768/07, included references:
- Processing of the JEFF-3.1 Cross Section Library into a Continuous Energy
Monte Carlo Radiation Transport and Criticality Data Library, OECD NEA Data
Bank, May 2006, prepared by O. Cabellos, NEA/NSC/DOC(2006)18
NEA-1768/08, included references:
- Processing of the JEFF-3.1 Cross Section Library into a Continuous Energy
Monte Carlo Radiation Transport and Criticality Data Library, OECD NEA Data
Bank, May 2006, prepared by O. Cabellos, NEA/NSC/DOC(2006)18
NEA-1768/09, included references:
- Processing of the JEFF-3.1 Cross Section Library into a Continuous Energy
Monte Carlo Radiation Transport and Criticality Data Library, OECD NEA Data
Bank, May 2006, prepared by O. Cabellos, NEA/NSC/DOC(2006)18
NEA-1768/10, included references:
- Processing of the JEFF-3.1 Cross Section Library into a Continuous Energy
Monte Carlo Radiation Transport and Criticality Data Library, OECD NEA Data
Bank, May 2006, prepared by O. Cabellos, NEA/NSC/DOC(2006)18
NEA-1768/12, included references:
- Processing of the JEFF-3.1 Cross Section Library into a Continuous Energy
Monte Carlo Radiation Transport and Criticality Data Library, OECD NEA Data
Bank, May 2006, prepared by O. Cabellos, NEA/NSC/DOC(2006)18
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11. HARDWARE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
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13. SOFTWARE REQUIREMENTS
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

This work was carried out for the OECD/NEA Data Bank
12, boulevard des Iles
92130 Issy-les-Moulineaux
France
by Oscar Cabellos
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16. MATERIAL AVAILABLE
NEA-1768/01
- JEFF3.1 Continuous energy  cross sections in ACE format for transport and
criticality calculations at 300K (381 isotopes)
- NEA/NSC/DOC(2006)18
- Patches to NJOY99.90
- NJOY99.90 inputs used for processing JEFF3.1

NEA-1768/02
- JEFF3.1 Continuous energy  cross sections in ACE format for transport and
criticality calculations at 400K (381 isotopes)
- NEA/NSC/DOC(2006)18
- Patches to NJOY99.90
- NJOY99.90 inputs used for processing JEFF3.1

NEA-1768/03
- JEFF3.1 Continuous energy  cross sections in ACE format for transport and
criticality calculations at 500K (381 isotopes)
- NEA/NSC/DOC(2006)18
- Patches to NJOY99.90
- NJOY99.90 inputs used for processing JEFF3.1

NEA-1768/04
- JEFF3.1 Continuous energy  cross sections in ACE format for transport and
criticality calculations at 600K (381 isotopes)
- NEA/NSC/DOC(2006)18
- Patches to NJOY99.90
- NJOY99.90 inputs used for processing JEFF3.1

NEA-1768/05
- JEFF3.1 Continuous energy  cross sections in ACE format for transport and
criticality calculations at 700K (381 isotopes)
- NEA/NSC/DOC(2006)18
- Patches to NJOY99.90
- NJOY99.90 inputs used for processing JEFF3.1

NEA-1768/06
- JEFF3.1 Continuous energy  cross sections in ACE format for transport and
criticality calculations at 800K (381 isotopes)
- NEA/NSC/DOC(2006)18
- Patches to NJOY99.90
- NJOY99.90 inputs used for processing JEFF3.1

NEA-1768/07
- JEFF3.1 Continuous energy  cross sections in ACE format for transport and
criticality calculations at 900K (381 isotopes)
- NEA/NSC/DOC(2006)18
- Patches to NJOY99.90
- NJOY99.90 inputs used for processing JEFF3.1

NEA-1768/08
- JEFF3.1 Continuous energy  cross sections in ACE format for transport and
criticality calculations at 1000K (381 isotopes)
- NEA/NSC/DOC(2006)18
- Patches to NJOY99.90
- NJOY99.90 inputs used for processing JEFF3.1

NEA-1768/09
- JEFF3.1 Continuous energy  cross sections in ACE format for transport and
criticality calculations at 1200K (381 isotopes)
- NEA/NSC/DOC(2006)18
- Patches to NJOY99.90
- NJOY99.90 inputs used for processing JEFF3.1

NEA-1768/10
- JEFF3.1 Continuous energy  cross sections in ACE format for transport and
criticality calculations at 1800K (381 isotopes)
- NEA/NSC/DOC(2006)18
- Patches to NJOY99.90
- NJOY99.90 inputs used for processing JEFF3.1

NEA-1768/12
- JEFF3.1 Continuous energy  cross sections in ACE format for transport and
criticality calculations -Thermal scattering data for 7 important moderator
materials at different temperatures
- NEA/NSC/DOC(2006)18
- Patches to NJOY99.90
- NJOY99.90 inputs used for processing JEFF3.1
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17. CATEGORIES
  • Z. Data.

Keywords: Monte Carlo method, continuous energy, cross sections.