Heavy water reactor facility large-scale containment cooling test program
Creators
- 1. Westinghouse Electric Corp., Madison, PA (United States)
Description
The Heavy Water Reactor Facility (HWRF), as part of the defense-in-depth philosophy to mitigate the effect of design-basis and severe accidents, is equipped with a passive containment cooling system (PCCS). The function of the PCCS is to provide a safety-grade path to the ultimate heat sink for the removal of the reactor coolant system sensible heat and core decay heat. Ambient air enters an annular space between the steel containment shell and the surrounding concrete shield building through inlets in the shield building wall, is heated via natural convection, rises, and exits the building through a chimney located above the containment dome. A test program is in place to access parameters important to the effective operation of the PCCS. This paper focuses on the large-scale tests (LSTs). The objectives of these tests are as follows: (1) demonstrate natural circulation cooling with more prototypic cylinder and dome surface area ratios than were available in the small-scale test; (2) obtain data necessary to characterize external natural convection cooling in the air flow annulus; (3) obtain data necessary to characterize internal convection and condensation inside the simulated containment vessel; and (4) provide a basis for computer code verification and validation
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 66
- Journal Page Range
- p. 306-307.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- past, present, and future.
- Acronym
- Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction
- Dates
- 15-20 Nov 1992.
- Place
- Chicago, IL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24050861
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SYSTEMS; COOLING SYSTEMS; DATA ACQUISITION; HWLWR TYPE REACTORS; NATURAL CONVECTION; REACTOR SAFETY; TEST FACILITIES; TEST REACTORS; TESTING; THERMAL ANALYSIS
- Descriptors DEC
- CONTAINMENT; CONVECTION; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; HEAT TRANSFER; HEAVY WATER MODERATED REACTORS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; WATER COOLED REACTORS
Optional Information
- Secondary number(s)
- CONF-921102--.