MCNP6 codes
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This paper presents the steady-state analysis results of the OECD/NEA and U.S. NRC PWR MOX/UO2 (MOX: Mixed Oxide) Core Transient Benchmark with the modern MCNP6 Monte Carlo code based on the up-to-date ENDF/B-VII.1 nuclear data library.
9p vicedric 08-02-2023 8 3 Download
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This paper presents a new design of a thermal neutron beam at the horizontal channel No.1 of the Dalat Nuclear Research Reactor by using the MCNP6 code. The thermal neutron beam is the result of installing a combination of Sapphire and Bismuth crystal filters.
6p vicedric 08-02-2023 4 3 Download
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The ADS (accelerator driven system) is recognized as a promising system to annihilate the radioactivity of nuclear waste with its inherent safety feature and waste transmutation potential. Thus, conceptual designs of ADS are widely carrying out.
10p visnape 30-01-2023 7 4 Download
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The paper presents calculation results of conceptual design for a 10-MWt highflux multi-purpose research reactor of a Research Centre for Nuclear Energy Science and Technology (RCNEST) of Viet Nam.
19p vidumbledore 06-01-2023 18 4 Download
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This paper presents the analysis of sensitivity and uncertainty for the infinite multiplication factor (kinf) for the VVR-M2 typed HEU and LEU fuel assemblies of the Dalat nuclear research reactor (DNRR) using the MCNP6.1-Whisper1.1 code.
14p vimelindagates 18-07-2022 7 2 Download
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This paper presents the steady-state analysis results of the OECD/NEA and U.S. NRC PWR MOX/UO2 (MOX: Mixed Oxide) Core Transient Benchmark with the modern MCNP6 Monte Carlo code based on the ENDF/B-VII.1 evaluated nuclear data library.
10p meyerowitz 25-12-2021 8 0 Download
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The purpose of this study is to verify the accuracy of innovative ADS core modeling by using simulation codes. The reactivity calculations of CERMET loaded fuel ADS was conducted using two Monte Carlo codes, Serpent [8] and MCNP6 [9] with ENDF/B-VII.0 library [10]. The comparison of results obtained from the two codes is analyzed and discussed in this study.
6p nguaconbaynhay11 07-04-2021 12 1 Download
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The present work aims to perform burnup calculation of the OECD VVER-1000 LEU (low enriched uranium) computational benchmark assembly using the Monte Carlo code MCNP6 and the deterministic code SRAC2006.
10p trinhthamhodang1218 14-03-2021 4 1 Download
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The paper presents the calculation results in re-design of neutron trap of the Dalat Nuclear Research Reactor (DNRR) for I-131 radioisotope production using TeO2 target. The new design permits for loading more TeO2 capsules from 9 to 12, 15 and 18 in the neutron trap.
12p trinhthamhodang1218 14-03-2021 7 1 Download