EPJ Web Conf.
Volume 146, 2017ND 2016: International Conference on Nuclear Data for Science and Technology
|Number of page(s)||4|
|Section||Integral Experiments, Benchmarks and Data Validation|
|Published online||13 September 2017|
Reliability assessment of MVP-BURN and JENDL-4.0 related to nuclear transmutation of light platinum group elements
1 Department of Nuclear Engineering, Graduate School of Science and Engineering, Tokyo Institute of Technology, 2-12-1-N1-9 Ookayama, Meguro-ku, Tokyo 152-8550, Japan
2 Department of Chemical Engineering and Materials Science, The Henry Samueli School of Engineering, University of California, Irvine, 916 Engineering Tower, Irvine, CA 92697-2575, USA
3 Laboratory for Advanced Nuclear Energy, Institute for Innovative Research, Tokyo Institute of Technology, 2-12-1-N1-9 Ookayama, Meguro-ku, Tokyo 152-8550, Japan
a e-mail: email@example.com
Published online: 13 September 2017
The Aprés ORIENT research program, as a concept of advanced nuclear fuel cycle, was initiated in FY2011 aiming at creating stable, highly-valuable elements by nuclear transmutation from ↓ssion products. In order to simulate creation of such elements by (n, γ) reaction succeeded by β− decay in reactors, a continuous-energy Monte Carlo burnup calculation code MVP-BURN was employed. Then, it is one of the most important tasks to con↓rm the reliability of MVP-BURN code and evaluated neutron cross section library. In this study, both an experiment of neutron activation analysis in TRIGA Mark I reactor at University of California, Irvine and the corresponding burnup calculation using MVP-BURN code were performed for validation of the simulation on transmutation of light platinum group elements. Especially, some neutron capture reactions such as 102Ru(n, γ)103Ru, 104Ru(n, γ)105Ru, and 108Pd(n, γ)109Pd were dealt with in this study. From a comparison between the calculation (C) and the experiment (E) about 102Ru(n, γ)103Ru, the deviation (C/E-1) was signi↓cantly large. Then, it is strongly suspected that not MVP-BURN code but the neutron capture cross section of 102Ru belonging to JENDL-4.0 used in this simulation have made the big di↑erence as (C/E-1) >20%.
© The Authors, published by EDP Sciences, 2017
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