NEA-1818 ZZ-KASHIL-E70.

1. NAME OR DESIGNATION:  ZZ-ZZ-KASHIL-E70.

3. DESCRIPTION

  
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  FORMAT: MATXS, 204 nuclides processed with NJOY99.245
  
  NUMBER OF GROUPS: 199 neutron-, 42 photon-groups
  
  204 NUCLIDES including 8 thermal scattering law data: H-1, H-2, H-3, He-3, He-4, Li-6, Li-7, Be-9, Be-9, Be-9, B-10, B-11, C-nat, C-nat, N-14, N-15, O-16, O-17, F-19, Na-23, Mg-24, Mg-25, Mg-26, Al-27, Si-28, Si-29, Si-30, P-31, S-32, S-33, S-34, S-36, Cl-35, Cl-37, K-39, K-40, K-41, Ca-40, Ca-42, Ca-43, Ca-44, Ca-46, Ca-48, Sc-45, Ti-46, Ti-47, Ti-48, Ti-49, Ti-50, V-nat, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, Ga-69, Ga-71, Y-89 , Zr-90, Zr-91, Zr-92, Zr-94, Zr-96, Nb-93, Mo-92, Mo-94, Mo-95, Mo-96, Mo-97, Mo-98, Mo-100 , Pd-102, Pd-104, Pd-105, Pd-106, Pd-108, Pd-110, Ag-107 , Ag-109, Cd-106, Cd-108, Cd-110, Cd-112, Cd-113, Cd-114, Cd-116, In-113, In-115, I-127, Xe-124, Xe-126, Xe-128, Xe-129, Xe-130, Xe-131, Xe-132, Xe-134, Xe-136, Cs-133, Ba-138, Pr-141, Nd-143, Nd-145, Nd-146, Nd-148, Nd-150, Pm-147, Sm-147, Sm-151, Sm-152, Eu-151, Eu-152, Eu-153, Eu-154, Eu-155, Gd-152, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158, Gd-160, Dy-164, Ho-165, Lu-175, Lu-176, Hf-174, Hf-176, Hf-177, Hf-178, Hf-179, Hf-180, Ta-181, Ta-182, W-182, W-183, W-184, W-186, Re-185, Re-187, Ir-191, Ir-193, Au-197, Pb-206, Pb-207, Pb-208, Bi-209, Th-230, Th-232, Pa-231, Pa-233, U-232, U-233, U-234, U-235, U-236, U-237, U-238, Np-237, Np-238, Np-239, Pu-236, Pu-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Pu-243, Pu-244, Am-241, Am-242, Am-242m, Am-243, Cm-241, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248, Bk-249, Cf-249, Cf-250, Cf-251, Cf-252, Cf-253, Es-253
  
  ORIGIN: ENDF/B-VII.0
  
  WEIGHTING SPECTRUM: 300, 600, 1000, 2100 K
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The KASHIL-E70 is a MATXS-format, 199-group neutron and 42-group photon cross section library for shielding applications based on ENDF/B-VII.0. The library contains 204 nuclide data including 8 thermal scattering law data processed by the NJOY99.259 code patched with NEA024. The library can be utilized to generate the problem-dependent group constants for neutron and/or photon transport calculations through the DANTSYS, DOORS, or PARTISN code systems.

4. METHODS

The KASHIL-E70 was generated at 300, 600, 1000, and 2100 K. It contains the self-shielded cross sections for 5 to 8 background cross sections depending on the nuclides. The infinite diluted cross sections for H-1, H-2, C-nat, and Be-9 are included at temperatures given in the thermal scattering law data. The Legendre orders of scattering are P7 for light nuclides (up to Cu-65) and P5 for the remainder of the nuclides. This library has a VITAMIN-B6 energy group structure, i.e. 199 groups for the neutron and 42 groups for the photon. The group structure can be useful for a broader range of applications such as a variety of reactor design and shielding problems including thermal and fast reactor systems. The neutron and photon weighting functions are of the form typically used for fission reactor shielding problems. For the neutron, the weighting function is composed of a smoothly varying combination of a Maxwellian thermal spectrum, a 1/E slowing down spectrum, and a fission spectrum (IWT=4 in GROUPR module of NJOY). For the photon, the function is composed of a 1/E spectrum, with a roll-off at lower energies and a similar drop-off at higher energies (IWT=3 in GAMINR module of NJOY). The library has been validated through the shielding benchmark experiments such as PCA-REPLICA, NESDIP-2, Winfrith Iron 88, Winfrith Graphite, etc.

8. RELATED OR AUXILIARY PROGRAMS

DANTSYS 3.0 (CCC-0547): One-, Two-, and Three-Dimensional, Multigroup, Discrete Ordinate Transport Code System

DOORS-3.2 (CCC-0650): One-, Two-, and Three-Dimensional Discrete Ordinates Neutron/Photon Transport Code System

PARTISN 4.00 (CCC-0707): Time-Dependent, Parallel Neutral Particle Transport Code System

TRANSX 2.15 (PSR-0317): Code System to Produce Neutron, Photon, and Particle Transport Tables for Discrete-Ordinates and Diffusion Codes from Cross Sections in MATXS Format

10. REFERENCES

C.-S Gil: ZZ KASHIL-E6, 175 N, 42 Gamma Groups Cross Sections in MATXS Format Based on ENDF/B-VI.5 for Shielding Applications, NEA-1649, OECD/NEA Data Bank, Issy-les-Moulineaux, France (2002).
C.-S. Gil, J.-D. Kim, and J. Chang: Analysis of Pressure Vessel Surveillance Dosimetry Inserted into Korean PWR, Reactor Dosimetry: Radiation Metrology and Assessment, J.G. Williams, et al., Eds., pp. 101-107, West Conshohocken, PA (2001).
D.H. Kim, C.-S. Gil, J.-D. Kim, and J. Chang: Generation and Validation of a Shielding Library Based on ENDF/B-VI.8, Radiation Protection Dosimetry, 115, 232 (2005).

11. HARDWARE REQUIREMENTS:  Hard disk space of 734 MB is required.

Tested at the NEA Data Bank on a PC with 3GHz INTEL Pentium 4 RAM 1Gb, WINDOWS XP Professional SP3, Compaq Version 6.6 (Update A).

15. NAME AND ESTABLISHMENT OF AUTHORS

Do Heon Kim
Nuclear Data Evaluation Lab.
Korea Atomic Energy Research Institute
P.O. Box 105, Yuseong, Daejeon, 305-600, Rep. of Korea
  
Choong-Sup Gil
Nuclear Data Evaluation Lab.
Korea Atomic Energy Research Institute
P.O. Box 105, Yuseong, Daejeon, 305-600, Rep. of Korea
  
Young-Ouk Lee
Nuclear Data Evaluation Lab.
Korea Atomic Energy Research Institute
P.O. Box 105, Yuseong, Daejeon, 305-600, Rep. of Korea

KASHIL-E70: MATXS-format library
INDEX-E70: Index file for KASHIL-E70