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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2017.1
- 수록면
- 1,610 - 1,616 (7page)
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To validate the new Evaluated Nuclear Data File (ENDF)/B-VIII.0β4 library, 31 different critical cores were selected and used for a benchmark test of the important parameter keff. The four utilized libraries are processed using Nuclear Data Processing Code (NJOY2016). The results obtained with the ENDF/BVIII.
0β4 library were compared against those calculated with ENDF/B-VI.8, ENDF/B-VII.0, and ENDF/BVII.
1 libraries using the Monte Carlo N-Particle (MCNP(X)) code. All the MCNP(X) calculations of keff values with these four libraries were compared with the experimentally measured results, which are available in the International Critically Safety Benchmark Evaluation Project. The obtained results are discussed and analyzed in this paper.
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참고문헌 (10)
참고문헌 신청
/ / ENDF/B-VIII.0beta4US Evaluated Nuclear Data Library
J.B. Briggs / 2004 / International Handbook of Evaluated Criticality Safety Benchmark Experiments
J.S. Hendricks / 2008 / MCNPX 2.6.0Extensions LA-UR-08-2216 / National Laboratory and Oak Ridge National Laboratory
M. Mattes / 2005 / 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
P. Balaji / 2012 / MPICH2 Installer's Guide / Mathematics and Computer Science Division, Argonne National Laboratory
J.B. Briggs / 2004 / International Handbook of Evaluated Criticality Safety Benchmark Experiments
J.S. Hendricks / 2008 / MCNPX 2.6.0Extensions LA-UR-08-2216 / National Laboratory and Oak Ridge National Laboratory
M. Mattes / 2005 / 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
P. Balaji / 2012 / MPICH2 Installer's Guide / Mathematics and Computer Science Division, Argonne National Laboratory
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