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Journal Articles

Validation of decay heat evaluation method based on FPGS cord for fast reactor spent MOX fuels

Usami, Shin; Kishimoto, Yasufumi; Taninaka, Hiroshi; Maeda, Shigetaka

Proceedings of International Conference on the Physics of Reactors; Unifying Theory and Experiments in the 21st Century (PHYSOR 2016) (USB Flash Drive), p.3263 - 3274, 2016/05

The present paper describes the validation of the new decay heat evaluation method using FPGS90 code with both the updated nuclear data library and the rational extent of uncertainty, by comparing the results of the decay heat measurement of the spent fuel subassemblies in Joyo MK-II core and by comparing with the calculation results of ORIGEN2.2 code. The calculated values of decay heat (C) by FPGS90 based on the JENDL-4.0 library were coincident with the measured ones (E) within the calculation uncertainties, and the C/E ranged from 1.01 to 0.93. FPGS90 evaluated the decay heat almost 3% larger than ORIGEN2.2, and it improved the C/E in comparison with the ORIGEN2.2 code. Furthermore, The C/E by FPGS90 based on the JENDL-4.0 library was improved than that based on the JENDL-3.2 library, and the contribution of the revision of reaction cross section library to the improvement was dominant rather than that of the decay data and fission yield data libraries.

Oral presentation

Study of few-group constant generation methods with Serpent Monte Carlo code based on JOYO MK-I fast reactor data

Szogradi, M.*; Nagaya, Yasunobu

no journal, , 

A new nodal diffusion solver Ants has been developed at VTT for the development of Generation IV reactor concepts. The two-step approach where group constants are generated via Monte Carlo (MC) methods is used for the reactor core analysis. To validate this approach, the JOYO MK-I core published in the International Handbook of Evaluated Reactor Physics Benchmark Experiments was analyzed. The Serpent Monte Carlo code was used to obtain group constants of the JOYO MK-I core. The Serpent few-group cross sections were then used as input data for Ants. Calculations were also carried out with Serpent and the MVP Monte Carlo code for a full-core 3D model to assess the general performance of the code comparing neutron spectrums and power spatial distributions. Results obtained with the 3D Ants JOYO model were compared with the MC results as the first assessment of the nodal diffusion solver with fast system.

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