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NEUTRON CROSS SECTION DATA LIBRARY FOR PD-105, AG-109, XE-131 AND CS-133 원문보기

Nuclear engineering and technology : an international journal of the Korean Nuclear Society, v.37 no.1, 2005년, pp.101 - 108  

LEE Y. D. (Korea Atomic Energy Research Institute) ,  CHANG J. H. (Korea Atomic Energy Research Institute)

Abstract ▼ AI-Helper 아이콘AI-Helper

The neutron induced nuclear cross-section data for Pd-105, Ag-109, Xe-131, and Cs-133 were calculated and evaluated from an unresolved energy to 20 MeV. The energy dependent optical model potential parameters were extracted based on recent experimental data and applied up to 20 MeV. A spherical opti...

주제어

#neutron   #cross section   #evaluation   #fission products   #data library  

AI 본문요약
AI-Helper 아이콘 AI-Helper

* AI 자동 식별 결과로 적합하지 않은 문장이 있을 수 있으니, 이용에 유의하시기 바랍니다.

제안 방법

  • After merging, the NJOY [8] code was run to check the continuity and the file processing for applications. A general information file (MFI) was completed for each nucleus, including an evaluated file history, resonance evaluation, fast region information (OMP, levels, codes, parameters) and each reaction's description. Also, the general rules for the merge were established.
  • The evaluation consists of an optical model potential search followed by a complete nuclear reaction model calculation and validation for the experimental data. The optical model potential depending on the incident neutron energy is searched using a graphical interface [5] of ABA-REX [6].
  • The main utilities include masses, level densities and discrete levels, decay schemes, deformation parameters, y-ray strength functions, Reference Input Parameter Library (RIPL), and ENDF-6 formatting and plotting capabilities. The main modules are: Optical model, Multi-step Direct and compound, Pre-equilibrium exiton (DEGAS) and Monte Carlo hybrid simulation (HMS), and a full featured Hauser-Feshbach including a width fluctuation correction.

이론/모형

  • Nuclear reaction cross-sections were calculated using the recently released Empire code [7]. This code consists of several modules.
본문요약 정보가 도움이 되었나요?

참고문헌 (21)

  1. Y.D. Lee and J.H. Chang, 'Neutron Cross Section Evaluation on Pr-141, Nd-143 Nd-145, Sm-147 and Sm-149,' J, KNS, 34, 4, 370, 2002 

  2. Y.D. Lee and J.H. Chang, 'Neutron Cross Section Evaluation on Mo-95, Tc-99 Ru-101 and Rh-103 in the Fast Energy Region,' J, KNS, 34, 6, 533, 2002 

  3. S.Y.Oh and J.H.Chang, Neutron Cross Section Evaluations of Fission Products below the Fast Energy Region, BNL-NCS-67469 (KAERI/TR-1511/2000), Brookhaven Natoinal Laboratory 

  4. E.D. Arthur and P.G. Young, Symp. on Neutron Cross Sections from 10 to 50 MeV, Upton, May 1980, Brookhaven report BNL-NCS-51245 (1980). p. 731 

  5. Y. D. Lee, ABRXPL development for parameter decision of spherical optical model potential, KAERI, NDL-14/99 

  6. R.D.Lawson, ABAREX_A Neutron Spherical Optical-Statistical Model Code, in Workshop on Computation and Analysis of Nuclear Data Relevant to Nuclear Energy and Safety, pp447, Trieste, Italy 

  7. M.Herman, Empire-2: Statistical Model Code for Nuclear Reaction Calculations, IAEA, Vienna 

  8. R.E. MacFarlane, D.W. Muir, The NJOY Nuclear Data Processing System, Version 91, LA-12740-M, Oct., 1994 

  9. P. Poenitz, J.F. Whalen, 'Neutron Total Cross Section Measurements in the Energy Region from 47 keV to 20 MeV,' R, ANL-NDM-80, 1983 

  10. L. Macklin, J. Halperin, R.R. Winters, 'Pd-104,105,106, 108,110 (n, ${\gamma}$ ) Cross Sections above 2.6-KeV,' J, Nucl. Sci. Eng., 71, 182, 1979 

  11. E. Cornelis et al., 'Average Capture Cross Section of The Fission Product Nuclei Pd-104 Pd-105 Pd-106 Pd-108 Pd-110,' C, 82ANTWER, 222, 1982 

  12. R. Prasad, D.C. Sarkar, 'Measured (n, p) Reaction Cross-Sections and Their Predicted Values at 14.8 MeV,' J, NC/A, 3, (3), 467, 1971 

  13. L. L. Litvinskiy et al., 'Neutron Inelastic Cross-Section on Silver at The Energy 275 KeV,' J, YK, (4), 38, 950, 1994 

  14. W. Augustyniak et al., 'Cross Sections for The Inelastic Scattering, (n, p) and (n, 2n) Reactions on Ag-107 and Ag-109 Isotopes,' J, NP/A, 247, 231, 1975 

  15. M. V. Bokhovko, 'Neutron Radiative Capture Measurements in Silver in The Energy Range 4-400 keV,' J, YK, (2), 21, 1987 

  16. J.P. Gupta et al., 'Pre-equilibrium Emission Effect in (N,P) Reaction Cross Section at 14.8 MeV,' J, PRM, 24, 637, 1985 

  17. F. J. Vaughn et al., 'Total Neutron Cross Sections of Helium, Neon, Argon, Krypton and Xenon,' J, PR, 118, 683, 1960 

    상세보기 crossref

  18. R.A. Sigg, P.K. Kuroda, '14.6-MeV Neutron Activation Cross Sections for The Xenon Isotopes,' J, NSE, 60, 235, 1976 

  19. D.G. Foster JR, D.W. Glasgow, 'Neutron Total Cross Sections, 2.5 - 15 MeV,' J, PR/C, 3, 576, 1971 

  20. M. V. Bokhovko et al., 'Neutron Radiation Cross-Section, Neutron Transmission And Average Resonance Parameters For Some Fission Product Nuclei,' R,FEI-2168-91,1991 

  21. S.M. Qaim, 'Activation Cross-Sections for Some 14.8 MeV Neutron Induced Nuclear Reactions on Caesium, Isomer Ratio of CS-133, XE-133 and I-130,' J, JIN, 32, 1799, 1970 

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