Neutron nuclear data evaluation of actinide nuclei for CENDL-3.1

CHEN Guo-Chang; CAO Wen-Tian; YU Bao-Sheng; TANG Guo-You; SHI Zhao-Min; TAO Xi

doi:10.1088/1674-1137/36/9/005

Chinese Physics C> 2012, Vol. 36> Issue(9) : 823-826 DOI: 10.1088/1674-1137/36/9/005

Neutron nuclear data evaluation of actinide nuclei for CENDL-3.1

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Abstract：
New evaluations for several actinide nuclei of the third version of Chinese Evaluated Nuclear Data Library for Neutron Reaction Data (CENDL-3.1) have been completed and released. The evaluation is for all neutron induced reactions with uranium, neptunium, plutonium and americium in the mass range A=232-241, 236-239, 236-246 and 240-244, respectively, and cover the incident neutron energy up to 20 MeV. In the present evaluation, much more effort was devoted to improving the reliability of the evaluated nuclear data for available new measured data, especially scarce or absent experimental data. A general description for the evaluation of several actinides' data is presented.

References

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GE Z G et al. J. Korean Physical Society, 2011, 59(2): 1052-1056[2] Chinese Nuclear Data Center. CENDL-2, The Chinese Evaluated Nuclear Data Library for Neutron Reaction Data, Report IAEA-NDS-61, Rev. 3 (1996). International Atomic Energy Agency, Vienna, Austria[3] Nakagawa T et al. J. Nucl. Sci. Technol., 1995, 32: 1259[4] Cross Section Evaluation Working Group, ENDF/B-VI Summary Documentation, Report BNL-NCS-17541 (ENDF-201) (1991). edited by Rose P F. National Nuclear Data Center, Brookhaven National Laboratory, Upton, NY, USA, 1991[5] Morogovskij G B, Bakhanovich L A. Resolved Resonance Parameters for 236Np, INDC(CCP)-432. 2002, 35[6] Nichols A L, Aldama D L, Verpelli M. Handbook of Nuclear Data for Safeguards, INDC(NDS)-0502. 2007[7] Nichols A L, Aldama D L, Verpelli M. Handbook of Nuclear Data for Safeguards: Database Extensions, INDC(NDS)-0534, 2008[8] SHEN Qing-Biao. APOM94 Code. Private Communication, 2003[9] Raynal J. Notes on ECIS94, Centre d'Etudes Nucleaires (Saclay), CEA-N-2772. 1994[10] ZHANG Jing-Shang, User Manual of FUNF Code for Fissile Material Data Calculation, CNIC-01782. 2005[11] Chadwick M B, Oblozinsky P, Herman M et al. Nucl. Data Sheets, 2006, 107: 2931

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CHEN Guo-Chang, CAO Wen-Tian, YU Bao-Sheng, TANG Guo-You, SHI Zhao-Min and TAO Xi. Neutron nuclear data evaluation of actinide nuclei for CENDL-3.1[J]. Chinese Physics C, 2012, 36(9): 823-826. doi: 10.1088/1674-1137/36/9/005

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Received: 2011-09-16
Revised: 1900-01-01

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沈阳化工大学材料科学与工程学院沈阳 110142

Neutron nuclear data evaluation of actinide nuclei for CENDL-3.1

Corresponding author: CHEN Guo-Chang,

Corresponding author: CAO Wen-Tian,

Received Date: 2011-09-16
Accepted Date: 1900-01-01
Available Online: 2012-09-05

Abstract: New evaluations for several actinide nuclei of the third version of Chinese Evaluated Nuclear Data Library for Neutron Reaction Data (CENDL-3.1) have been completed and released. The evaluation is for all neutron induced reactions with uranium, neptunium, plutonium and americium in the mass range A=232-241, 236-239, 236-246 and 240-244, respectively, and cover the incident neutron energy up to 20 MeV. In the present evaluation, much more effort was devoted to improving the reliability of the evaluated nuclear data for available new measured data, especially scarce or absent experimental data. A general description for the evaluation of several actinides' data is presented.