ATHLET-CD analysis of water injection into a partly-damaged BWR core for accident management improvement
- 1. Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen (Germany)
Description
The present work is aimed at investigating the influence of water injection into a partly-damage core as a result of hypothetical multiple failures of the safety systems during a small break (SB) LOCA in a boiling water reactor (BWR). The work is carried out in the frame of the research project WASA-BOSS (Weiterentwicklung und Anwendung von Severe Accident Codes – Bewertung und Optimierung von Störfallmaßnahmen) funded by the German Federal Ministry of Economics and Technology which is devoted to the analysis of severe accident scenarios for the assessment of the safety of German nuclear power plants. The reference power plant is a generic 72-type BWR with a thermal power of 3840 MW. According to probabilistic safety analyses, a SBLOCA scenario at one of the steam lines inside the containment was defined for this work. Calculations have been carried out with the thermal-hydraulic system code ATHLET-CD up to 2 hours after reactor SCRAM, corresponding to a configuration where about half of the core material is molten in case of no water injections. The coolability of a partly-damaged core has been investigated by assuming the recovery of the safety systems operation at different core damage states. The results of the present calculations show that injection of water at different points in time has a significant impact on the produced hydrogen and on the accident progression. This study represents the starting point for further analysis, which may include reflooding at different core damage states as well as simulation of the interaction between molten material and lower plenum, and provides useful information for the improvement of the accident management measures. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the 23th international conference on nuclear engineering (ICONE-23)
- Imprint Pagination
- [3737 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- 23. international conference on nuclear engineering
- Acronym
- ICONE-23
- Dates
- 17-21 May 2015
- Place
- Chiba (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 48051229
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- ACCIDENT MANAGEMENT; BWR TYPE REACTORS; ECCS; FEEDWATER; HEAT TRANSFER; LOSS OF COOLANT; REACTOR CORE DISRUPTION; REACTOR VESSELS; RHR SYSTEMS; STEAM LINES; THERMAL HYDRAULICS
- Descriptors DEC
- ACCIDENTS; CONTAINERS; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; HYDROGEN COMPOUNDS; MANAGEMENT; MECHANICS; OXYGEN COMPOUNDS; PIPELINES; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as DVD-ROM Data in PDF format. Folder Name: FullPaper; Paper ID: ICONE23-1244.pdf; 7 refs., 10 figs.