UMCP mist counterpart test
Creators
- 1. Univ. of Maryland, College Park (USA)
Description
Two Small Break LOCA transients are compared to illustrate a scaling methodology for reduced pressure integral facilities. Mapping test 3004 is conducted in the MIST full pressure, full height facility. The counter-part test MIS0317 is scaled and performed in the reduced height, reduced pressure UMCP facility. Inventory is used as the chronological scale and pressure, normalized with the initial and system saturation pressures, is used as characteristic parameter to describe the system behavior. The appropriately normalized results conclusively demonstrate that: (a) the same phenomena are observed in the two facilities; (b) the sequence of events is analogous and (c) the trends described by the normalized pressure versus inventory traces are in good quantitative agreement. Each energy transport mode traversed by the two facilities is compared and the phenomena present are described in detail. The differences between the high and reduced pressure tests are outlined. The findings clearly indicate that pressure and height can be scaled for transient where limited boundary conditions are applied (Auxiliary Feed Water only) and where the break is subcooled. A statement on sensitivity to the initial conditions is also included to define the limitations of the quantitative results
Additional details
Publishing Information
- Imprint Title
- Transactions of the seventeenth water reactor safety information meeting
- Imprint Pagination
- 186 p.
- Journal Page Range
- p. 3.11.
- Report number
- NUREG/CP--0104
Conference
- Title
- 17. water reactor safety information meeting.
- Dates
- 23-25 Oct 1989.
- Place
- Rockville, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22051895
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BOUNDARY CONDITIONS; COMPARATIVE EVALUATIONS; FEEDWATER; LOSS OF COOLANT; SCALE MODELS; SIMULATION; TEST FACILITIES; TRANSIENTS; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; EVALUATION; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTORS; STRUCTURAL MODELS; WATER
Optional Information
- Secondary number(s)
- CONF-8910222--Summs.