PWR low pressure natural circulation and loss of all AC power
Creators
- 1. Univ. of Ljubljana (Slovenia). Jozef Stefan Inst.
Description
First phase of the specific PWR nuclear power plant transient analysis in area of low pressure phenomena, where no special possibilities of interventions exist, has been done. Such transients may be initiated by hypothetical loss of all plant AC power due to different causes during cold or hot shutdown. Complete transient has not been analyzed yet, because of the errors in results calculated by the RELAP5/MOD2 and RELAP5/MOD3 programs. The analysis has shown, that the stable decay heat removal with single phase primary coolant natural circulation is achieved but not preserved in the case where the initial reactor coolant system pressure is 1 bar. After some 5.5 hours into the transient voids start to form in the upper section of steam generators U-tubes and two phase natural circulation appears. On the other hand the stable decay heat removal with single phase primary natural circulation is preserved if initial reactor coolant system pressure is 10 bar. The duration of such stable heat removal is limited by steam generator secondary coolant inventory. RELAP5/MOD2 predictions at 1 bar initial pressure were acceptable despite troubles that appeared after first void formation. RELAP5/MOD3 calculations were performed without any difficulties but results produced are unacceptable due to significant numerical mass error which caused unacceptable primary mass decrease of 8% in the first 10 hours of transient time. Mass error appeared also during the calculations at initial pressure of 10 bar performed by RELAP5/MOD2. It caused significant variations of the secondary coolant mass
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0636-7
- Imprint Title
- 2nd ASME-JSME international conference on nuclear engineering -- 1993
- Imprint Pagination
- 770 p.
- Journal Page Range
- p. 221-227.
Conference
- Title
- 2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering.
- Dates
- 21-24 Mar 1993.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25058804
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- AFTER-HEAT REMOVAL; COMPUTER CALCULATIONS; NATURAL CONVECTION; OUTAGES; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR SHUTDOWN; SECONDARY COOLANT CIRCUITS; THEORETICAL DATA; TRANSIENTS
- Descriptors DEC
- CONVECTION; COOLING SYSTEMS; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; HEAT TRANSFER; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; REMOVAL; SHUTDOWN; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-930352--.