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Yoshimura, Kazuo; Doda, Norihiro; Igawa, Kenichi*; Tanaka, Masaaki; Yamano, Hidemasa
Journal of Nuclear Engineering and Radiation Science, 9(2), p.021601_1 - 021601_9, 2023/04
Feedback reactivity automatically caused by radial expansion of the core is known as one of the inherent safety features in a sodium-cooled fast reactor (SFR). In order to validate the evaluation models of the reactivity feedback equipped in the in-house plant dynamics analysis code named Super-COPD, the benchmark analyses for the unprotected loss of heat sink (ULOHS) tests of BOP-302R and BOP-301 in an experimental SFR, EBR-II were conducted and the applicability of the evaluation method for the reactivity feedback was indicated during the ULOHS even, by comparing the numerical results and the experimental data.
Tanaka, Masaaki
no journal, ,
Japan Atomic Energy Agency (JAEA) is promoting research and development (R&D) related to fast reactors and nuclear fuel cycles as a contribution to carbon neutrality through the investigation of innovative technologies such as safety improvement. In order to maintain, develop, and provide the technological infrastructure for nuclear power plant innovation, that is the role of JAEA, an integrated evaluation method "ARKADIA" is under development to create innovative plant concepts and reform of the development process utilizing the wide range of knowledge cultivated through the development of fast reactors in JAEA. This presentation introduces the current status of development of sodium-cooled fast reactors and the ARKADIA-Design as a part of ARKADIA for design optimization support to address the R&Ds on thermal-hydraulics-related issues for design evaluation.
