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Journal Articles

An Investigation on the control rod homogenization method for next-generation fast reactor cores

Takino, Kazuo; Sugino, Kazuteru; Oki, Shigeo

Annals of Nuclear Energy, 162, p.108454_1 - 108454_7, 2021/11

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Journal Articles

An Investigation on the control rod homogenization method for next-generation fast reactor cores

Takino, Kazuo; Sugino, Kazuteru; Oki, Shigeo

Proceedings of Joint International Conference on Supercomputing in Nuclear Applications + Monte Carlo 2020 (SNA + MC 2020), p.92 - 96, 2020/10

JAEA Reports

Development of neutron transport calculation codes for 3-D hexagonal geometry, 2; Improvement and enhancement of the MINISTRI code

Sugino, Kazuteru; Takino, Kazuo

JAEA-Data/Code 2019-011, 110 Pages, 2020/01

JAEA-Data-Code-2019-011.pdf:3.37MB

A deterministic discrete ordinates method (SN method) transport calculation code for three-dimensional hexagonal geometry has been developed as the MINISTRI code (Ver. 7.0). MINISTRI is based on the triangle-mesh finite difference method, which can perform neutron transport calculations with high accuracy for cores of fast power reactors and assemblies of the Russian BFS critical facility. The present study has derived a proper scheme for remarkably improving the convergence of MINISTRI by investigating the issue of previous MINISTRI (Ver. 1.1), which sometimes plays a poor convergence performance in calculations for large-scale power reactor cores. The verification test of improved MINISTRI has been carried out for various cores by setting the reference result as the multi-group Monte-Carlo calculation with the same cross-sections as used in MINISTRI. As a result, it is found that the agreements are within 0.1% for eigenvalues and within 0.7% for power distributions. Thus, the satisfying accuracy of MINISTRI has been confirmed. In order to reduce the calculation time, the initial diffusion calculation scheme and the parallel processing have been implemented. As a result, the calculation time is reduced to the approximately one tenth compared with previous MINISTRI. Furthermore, adoption of the treatment of the anisotropic cell streaming effect, preparation of the perturbation calculation tool, implementation of the function for specification of the triangle-mesh-wise material and merging of the hexagonal-mesh calculation code MINIHEX have been carried out. Thus, the versatility of MINISTRI has been enhanced.

Journal Articles

Investigation of the core neutronics analysis conditions for evaluation of burn-up nuclear characteristics of next-generation fast reactors

Takino, Kazuo; Sugino, Kazuteru; Yokoyama, Kenji; Jin, Tomoyuki*; Oki, Shigeo

Proceedings of 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) (CD-ROM), p.1214 - 1220, 2018/04

Journal Articles

The Investigation of the new multipurpose research reactor succeeding to JRR-3

Takino, Kazuo; Arai, Masaji; Murayama, Yoji

Proceedings of International Topical Meeting on Research Reactor Fuel Management and Meeting of the International Group on Reactor Research (RRFM/IGORR 2016) (Internet), p.667 - 676, 2016/03

Our working group has started to investigate basic concepts of the new research reactor which foresaw twenty years later. The aim of this project is to build up the design of new multipurpose research reactor which is constructed instead of JRR-3 for utilization of the neutron beam, irradiation, training and so on.

Oral presentation

The Basic design concept of the new multipurpose research reactor succeeding to JRR-3

Arai, Masaji; Takino, Kazuo

no journal, , 

The Department of Research Reactor and Tandem Accelerator began to discuss basic design concept of the new multipurpose research reactor succeeding to JRR-3.

Oral presentation

The Investigation of the core for the new multipurpose research reactor succeeding to JRR-3, 1; Design of Fuel and core

Arai, Masaji; Tsumura, Takashi; Takino, Kazuo

no journal, , 

no abstracts in English

Oral presentation

The Investigation of the core for the new multipurpose research reactor succeeding to JRR-3, 3; Thermal margin

Tsumura, Takashi; Arai, Masaji; Takino, Kazuo

no journal, , 

no abstracts in English

Oral presentation

An Investigation of the core neutronics analysis conditions for evaluation of burnup nuclear characteristics of next-generation fast reactors

Takino, Kazuo; Sugino, Kazuteru; Yokoyama, Kenji; Jin, Tomoyuki*; Oki, Shigeo

no journal, , 

no abstracts in English

Oral presentation

An Investigation on the control rod homogenization method for next-generation fast reactor cores

Takino, Kazuo; Sugino, Kazuteru; Oki, Shigeo

no journal, , 

no abstracts in English

13 (Records 1-13 displayed on this page)
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