Analysis of OECD/NEA medium 1000 MWth sodium-cooled fast reactor using the Monte Carlo serpent code and ENDF/B-VIII.0 nu
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Analysis of OECD/NEA medium 1000 MWth sodium-cooled fast reactor using the Monte Carlo serpent code and ENDF/B-VIII.0 nuclear data library Fatima I. Al-Hamadi1 • Bassam A. Khuwaileh1 Donny Hartanto1
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Peng Hong Liem2,3
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Received: 19 May 2020 / Revised: 14 September 2020 / Accepted: 28 October 2020 Ó China Science Publishing & Media Ltd. (Science Press), Shanghai Institute of Applied Physics, the Chinese Academy of Sciences, Chinese Nuclear Society and Springer Nature Singapore Pte Ltd. 2020
Abstract This study presents a benchmark evaluation of the new ENDF/B-VIII.0 nuclear data library for the Organization for Economic Co-operation and Development/Nuclear Energy Agency Medium 1000 MWth sodium-cooled fast reactor (SFR). The study presented herein covers both SFR core types, i.e., metallic fueled (MET-1000) and oxide fueled (MOX-1000), simulated using the continuous-energy Monte Carlo Serpent2 code. The neutronics performances of the ENDF/B-VIII.0-based simulations were compared mainly to two libraries: ENDF/ B-VII.1 and JENDL-4.0. The comparison includes several neutronics parameters evaluated for the beginning and end of the cycle conditions. These parameters include the effective multiplication factor keff, total effective delayed neutron fraction beff, sodium void reactivity (DqNa), Doppler constant (DqDoppler), and control rod worth (DqCR). In addition, a sensitivity study was used to reveal the major isotope/reaction pairs contributing to the discrepancy
This work was supported by the Research Institute of Science and Engineering at the University of Sharjah (No. 1802040790-P). & Donny Hartanto [email protected] 1
Department of Mechanical and Nuclear Engineering, University of Sharjah, P.O. BOX 27272, Sharjah, United Arab Emirates
2
Graduate School of Engineering, Cooperative Major in Nuclear Energy, Tokyo City University (TCU), 1-28-1 Tamazutsumi, Setagaya, Tokyo, Japan
3
Scientific Computational Division, Nippon Advanced Information Service (NAIS Co., Inc.), 416 Muramatsu, Tokaimura, Ibaraki, Japan
observed in the performance of the three libraries using 33 and 44-energy-group structures. Keywords Serpent ENDF/B-VIII.0 Sodium-cooled fast reactor Sensitivity analysis
1 Introduction Under the working party of the Organization for Economic Co-operation and Development/Nuclear Energy Agency (OECD/NEA), a neutronics benchmark study of the Generation-IV sodium-cooled fast reactor (SFR) concepts has been conducted and published using different methods and codes [1–3] in conjunction with various nuclear data libraries such as ENDF/B-VII.0 [4], ENDF/BVII.1 [5], JEFF-3.1 [6], and JENDL-4.0 [7]. The benchmark consists of large 3600 MWth carbide and oxide cores as well as medium 1000 MWth metallic and oxide cores. In this study, the medium SFR cores were calculated using the new version of the nuclear data library, ENDF/B-VIII.0 [8]. The newer library has achieved improvements in many neutron cross section libraries, including the cross sections of m
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