Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Nakayama, Shinsuke; Iwamoto, Osamu; Kimura, Atsushi
EPJ Web of Conferences, 294, p.07001_1 - 07001_6, 2024/04
Graphite is a candidate of moderator in innovative nuclear reactors such as molten salt reactors. Scattering of thermal neutrons by the moderator material has a significant impact on the reactor core design. To contribute to the development of innovative nuclear reactors, an evaluation method of thermal neutron scattering law for reactor grade graphite was studied. The inelastic scattering component due to lattice vibration was evaluated based on the phonon density of states computed with first-principles lattice dynamics simulations. The simulations were performed for ideal crystalline graphite. The coherent elastic scattering component due to crystal structure was evaluated based on neutron transmission and scattering experiments recently performed in the J-PARC/MLF facility. In comparison with the neutron transmission experiments, it was found that the quantification of small-angle neutron scattering due to structures larger than crystal, such as pores in graphite, is important. Based on the above methods, thermal neutron scattering law data for reactor-grade graphite at room temperature were evaluated.
*; *; *; *; *; Akino, Norio; Takeda, Tetsuaki; *
Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.101 - 107, 1991/00
no abstracts in English
Kondo, Tatsuo
Nihon Kinzoku Gakkai Kaiho, 17(4), p.274 - 281, 1978/04
no abstracts in English
Nakayama, Shinsuke; Iwamoto, Osamu
no journal, ,
The use of graphite and hydrogen compounds as moderators has been considered for molten salt reactors and small modular reactors. Scattering of thermal neutrons by moderators has a significant impact on reactor core design. In addition, charged-particle emission reactions on nuclides contained in molten salts and structural materials can produce nuclides that pose a problem for waste management. Therefore, accurate thermal neutron scattering law and charged-particle emission reaction cross section data for the above materials are important for the development of such innovative reactors. Based on the above, these nuclear data were evaluated and compiled as an evaluated nuclear data file in the MEXT Innovative Nuclear Research and Development Program entitled "Development of Nuclear Data Evaluation Framework for Innovative Reactor". The evaluation method of these nuclear data is outlined.
