Direct measurement of multi-noncondensable and steam mixture under an accident condition of a Passive Containment Cooling System (PCCS)
- 1. Toshiba Corporation (Japan)
- 2. GE Nuclear Energy, San Jose, CA (United States)
Description
The Passive Containment Cooling System (PCCS) has a function to remove the long-term decay heat following an accident by condensation. As an extension of the PCCS development program, its heat removal capability under a severe accident condition has been tested. The effect of the lighter noncondensable than steam on the PCCS heat transfer characteristics was clarified. Helium gas was used to simulate hydrogen gas which can be generated by metal-water reaction. In the final stage, multi-noncondensables (i.e. both nitrogen and helium) were simultaneously confined. The GIRAFFE measurement system was accordingly modified so that noncondensable gas concentration was directly measured. Due to installation of direct measurement system of noncondensable, the noncondensable transport mechanism was modeled so that the analytical code might be remarkably improved. (author)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the OECD/CSNI specialist meeting on advanced instrumentation and measurement techniques
- Imprint Pagination
- 752 p.
- Journal Page Range
- p. 55-66
- Report number
- NUREG/CP--0160
Conference
- Title
- OECD/CSNI specialist meeting on advanced instrumentation and measurement techniques
- Dates
- 17-20 Mar 1997
- Place
- Santa Barbara, CA (United States)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 35095781
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- AFTER-HEAT REMOVAL; ANALYTICAL SOLUTION; COMPUTER CALCULATIONS; CONTAINMENT SYSTEMS; COOLING SYSTEMS; EXPERIMENTAL DATA; HEAT TRANSFER; HELIUM; INTERSTITIAL HYDROGEN GENERATION; REACTOR ACCIDENTS
- Descriptors DEC
- ACCIDENTS; CONTAINMENT; DATA; ELEMENTS; ENERGY SYSTEMS; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; FLUIDS; GASES; INFORMATION; MATHEMATICAL SOLUTIONS; NONMETALS; NUMERICAL DATA; PHYSICAL RADIATION EFFECTS; RADIATION EFFECTS; RARE GASES; REMOVAL
Optional Information
- Notes
- 16 refs, 24 figs, 2 tabs
- Secondary number(s)
- INIS-XA-N--001