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与能本 泰介; 峯尾 英章; 村山 洋二; 芳原 新也*; 中島 健*; 中塚 亨; 上坂 充*
日本原子力学会誌ATOMO
, 63(1), p.73 - 77, 2021/01
研究炉等が長期にわたり運転を停止していることは原子力人材の育成等に大きな影響を与えている。本報告ではグレーデッドアプローチを適用した適切な規制対応方法を整備し実践するための課題を分析し抽出するとともに、解決のための取組みを関係組織に提言する。
小野田 雄一; 栗坂 健一; 堺 公明
Journal of Nuclear Science and Technology, 53(11), p.1774 - 1786, 2016/11
被引用回数：3 パーセンタイル：26.09(Nuclear Science & Technology)The accident categories of severe accidents (SAs) for prototype Sodium-cooled Fast Reactor (SFR) which need proper measures were investigated through the internal event PRA and event tree analysis for the external event and six accident categories, ULOF, UTOP, ULOHS, LORL, PLOHS and SBO, were identified. Fundamental safety strategy against these accidents is studied and clearly stated considering the characteristics and existing accident measures of prototype SFR, and concrete measures based on this safety strategy are investigated and organized. The sufficiency of these SA measures is confirmed by comparing the evaluated Core Damage Frequency (CDF) and Containment failure frequency (CFF) to the target value, 1
10
and 110
per plant operating year, respectively, which were selected based on the IAEA's safety target. However, the target value of CDF and CFF should be satisfied considering all the SAs caused by both internal and external events. External event PRA for prototype SFR is now under evaluation and we set out to satisfy the target value of CDF and CFF considering both internal and external events.
小野田 雄一; 栗坂 健一; 堺 公明
Proceedings of 10th International Topical Meeting on Nuclear Thermal Hydraulics, Operation and Safety (NUTHOS-10) (USB Flash Drive), 12 Pages, 2014/12
The accident sequences beyond design basis to be considered for the prototype Sodium-cooled Fast Reactor (SFR), which is now under development in Japan Atomic Energy Agency (JAEA), are identified in order to confirm the effectiveness of the measures against severe accidents. Internal and external events are considered as potential initiator of severe accidents. Earthquake and tsunami are focused on as the external events in light of the accident at the Fukushima Dai-ichi Nuclear Power Station. Probabilistic Risk Assessment (PRA) and/or its alternative approach are taken for the comprehensive analyses of the accident sequences. At first, four important accident sequence groups are identified; anticipated transient without scram, loss of reactor sodium level, protected loss of heat sink and loss of all alternating current power sources. Then accident sequence to be evaluated is extracted from corresponding accident sequence group. Severe accident measures which are composed of installing hardware or constructing emergency operator procedure, and which are intended to minimize the risk of radioactive release, are also identified for each accident sequence. In order to confirm the effectiveness of those severe accident measures prepared for prototype SFR, deterministic safety evaluations of those accident sequences should be carried out.
