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Development of an Integrated Computer Code System for Analyzing Irradiation Behaviors of a Fast Reactor Fuel

Tomoyuki Uwaba, Junichi Nemoto, Masahiro Ito, Ikuo Ishitani, Norihiro Doda, Masaaki Tanaka, Satoshi Ohtsuka

Nuclear Technology | Volume 207 | Number 8 | August 2021 | Pages 1280-1289

Technical Note | doi.org/10.1080/00295450.2020.1810977

Received:July 10, 2020

Accepted:August 12, 2020

Published:August 2, 2021

Articles are hosted by Taylor and Francis Online.

Computer codes for irradiation behavior analysis of a fuel pin and a fuel pin bundle and for coolant thermal-hydraulic analysis were coupled into an integrated code system. In the system, each code provides data required by other codes, and the analyzed results are shared among them. The system allows for the synthesizing of analyses of thermal, chemical, and mechanical behaviors in a fuel subassembly under irradiation. A test analysis was made for a fuel subassembly containing a mixed oxide fuel pin bundle irradiated in a fast reactor. The results of the analysis were presented with transverse cross-sectional images of the fuel subassembly and three-dimensional images of a fuel pin and fuel pin bundle models. For detailed evaluation, various irradiation behaviors of all fuel pins in the subassembly were analyzed and correlated with irradiation conditions.