Study on initiating phase of core disruptive accident. Identification of important phenomena in initiating phase of unprotected transient overpower accident
Creators
- 1. Japan Atomic Energy Agency, Fast Reactor Cycle System Research and Development Center, Oarai, Ibaraki (Japan)
Description
In the safety study of sodium cooled fast reactor, it is important to appropriately evaluate the event progression of Core Disruptive Accident (CDA). In previous studies, the reliability and validity of the evaluation method of the early stage of CDA, which is named Initiating Phase (IP), was significantly enhanced by applying Phenomena Identification and Ranking Table (PIRT) approach to the Unprotected Loss of Flow (ULOF). In this study, PIRT approach was applied to Unprotected Transient over Power (UTOP), which was one of the most important and typical events in CDA as well as ULOF, and physical phenomena relating to UTOP were ranked in order of the degree of importance. As a result, 8 key phenomena were identified. Compared UTOP with ULOF, both rankings were almost same, however it was clarified in this study that the ranking of the physical phenomena related to the coolant in UTOP was lower than that in ULOF, since in UTOP primary flow remains constant and coolant behavior doesn't cause large reactivity changes. (author)
Availability note (English)
Available from DOI: https://doi.org/10.1299/jsmepes.2021.25.A132Abstract (Japanese)
ナトリウム冷却高速炉のシビアアクシデント研究では炉心損傷事故(CDA)の適切な評価が重要となる。CDAの初期の段階である起因過程の評価手法に関しては、これまでにCDAの代表的な事象である流量喪失時炉停止失敗事象(ULOF)に対してPIRT手法を適用し、評価手法の信頼性向上が図られている。本研究ではULOFと同様に代表的な事象である過出力時炉停止失敗事象(UTOP)に対してPIRT手法を適用し、16の物理現象を抽出するとともに、それらの物理現象にランク付けを行って8つの重要現象を抽出した。また、反応度変化に係る物理現象は主に冷却材のボイド化と燃料の移動によるものであるため、燃料の破損後の物理現象としては、ULOFとUTOPとで事象進展が異なっているにもかかわらずランク付けは同じとなるが、燃料の破損に至るまでの冷却材に関する物理現象のランクは、定格流量の冷却材が流れていることによりUTOPの方がULOFよりも低い結果となることが分かった。(著者)Additional details
Additional titles
- Original title (Japanese)
- ナトリウム冷却高速炉の炉心損傷初期過程の研究.過出力時炉停止失敗事象の起因過程における重要現象の同定
Identifiers
Publishing Information
- Journal Title
- Doryoku, enerugi gijutsu no saizensen koen ronbunshu (Online)
- Journal Volume
- 25
- Series
- 雑誌名:動力・エネルギー技術の最前線講演論文集 : シンポジウム; Proceedings of the National Symposium on Power and Energy Systems
- Journal Page Range
- 4 p.
- ISSN
- 2424-2950
Conference
- Title
- 25. national symposium on power and energy systems. Online
- Acronym
- SPES 2021
- Dates
- 26-27 Jul 2021
- Place
- Japan (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 54021897
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ATWS; FAST REACTORS; FUEL-COOLANT INTERACTIONS; LOSS OF FLOW; MELTDOWN; REACTIVITY; REACTIVITY INSERTIONS; REACTOR CORE DISRUPTION; SODIUM COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; EPITHERMAL REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS; SEVERE ACCIDENTS
Optional Information
- Notes
- This symposium was held online; 3 refs., 1 fig., 1 tab.