Analysis on hydrogen risk mitigation in severe accidents for Pressurized Heavy Water Reactor
Creators
- 1. School of Mechanical Engineering, Shanghai Jiao Tong University, 800, Dong Chuan Rd., Shanghai, 200240 (China)
Description
Highlights: •Hydrogen risk for HPWR is assessed using the mechanical analytical code. •Two typical severe accident sequences induced by SBO and LLOCA are selected. •Thermal hydraulic and hydrogen source term are studied. •Hydrogen mitigation with igniters is investigated. -- Abstract: Hydrogen source term and hydrogen mitigation under severe accidents is evaluated for most nuclear power plants (NPPs) after Fukushima Daiichi accident. Two units of Pressurized Heavy Water Reactor (PHWR) are under operating in China, and hydrogen risk control should be evaluated in detail for the existing design. The distinguish feature of PHWR, compared with PWR, is the horizontal reactor core surrounded by moderator in calandria vessel (CV), which may influence the hydrogen source term. Based on integral system analysis code of PHWR, the plant model including primary heat transfer system (PHTS), calandria, end shield system, reactor cavity and containment has been developed. Two severe accident sequences have been selected to study hydrogen generation characteristic and the effectiveness of hydrogen mitigation with igniters. The one is Station Blackout (SBO) which represents high-pressure core melt accident, and the other is Large Break Loss of Coolant Accident (LLOCA) at reactor outlet header (ROH) which represents low-pressure core melt accident. Results show that under severe accident sequences, core oxidation of zirconium–steam reaction will produce hydrogen with deterioration of core cooling and the water in CV and reactor cavity can inhibits hydrogen generation for a relatively long time. However, as the water dries out, creep failure happens on CV. As a result, molten core falls into cavity and molten core concrete interaction (MCCI) occurs, releasing a large mass of hydrogen. When hydrogen igniters fail, volume fraction of hydrogen in the containment is more than 15% while equivalent amount of hydrogen generate from a 100% fuel clad-coolant reaction. As a result, hydrogen risk lies in the deflagration–detonation transition area. When igniters start at the beginning of large hydrogen generation, hydrogen mixtures ignite at low concentration in the compartments and the combustion mode locates at the edge of flammable area. However, the power supply to igniters should be ensured.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.pnucene.2014.12.011Additional details
Identifiers
- DOI
- 10.1016/j.pnucene.2014.12.011;
- PII
- S0149197014003539;
Publishing Information
- Journal Title
- Progress in Nuclear Energy
- Journal Volume
- 80
- Journal Page Range
- p. 128-135
- ISSN
- 0149-1970
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51027492
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FUKUSHIMA DAIICHI NUCLEAR POWER STATION; HAZARDS; HEAT TRANSFER; LOSS OF COOLANT; MITIGATION; PHWR TYPE REACTORS; PWR TYPE REACTORS; REACTOR CORES; STATION BLACKOUT; STEAM; THERMAL HYDRAULICS; ZIRCONIUM
- Descriptors DEC
- ACCIDENTS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; HYDRAULICS; MECHANICS; METALS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR SITES; REACTORS; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Copyright © 2014 Elsevier Ltd. All rights reserved.