A two-phase pressure drop calculation code based on a new method with a correction factor obtained from an assessment of existing correlations
Creators
- 1. Korea Advanced Inst. of Science and Technology, Cheong Ryang, Seoul (Republic of Korea)
Description
Although the average exit enthalpy of a current generation PWR core under normal operation does not exceed the saturation value, bulk boiling can occur in a hot channel. Moreover, in the event of a reactor transients, such as a small or a large break LOCA, bulk boiling can occur throughout the core. For both steady and transient conditions it is necessary to predict the pressure loss as accurately as possible for a two-phase mixture since pressure drop not only influences flow distribution and pumping power requirements but also the hot channel is limiting from DNB considerations. Various approaches for two-phase flow pressure drop predictions have been proposed during the past two decades. Idsinger et al. compared a large number of existing correlations against data for conditions representing transient as well as steady-state BWR operation, and showed that the correlations which had the least RMS error overall for the normal BWR operation conditions is the Armand-Treschev Correlation. Also, they reported that the correlations which have shown the best overall performance were, homogeneous theory, the Thorn correlation, and the Baroczy correlation. The purpose of this paper is first, to present the results of an assessment of existing correlations for their applicability to PWR conditions; and secondly, to present the outlines of a computer code entitled K-TWOPD for two-phase pressure drop calculation
Additional details
Publishing Information
- Publisher
- Clean Energy Research Inst. University of Miami.
- Imprint Place
- Coral Gables, FL (USA)
- Imprint Title
- The 5th Miami international symposium on multi-phase transport and particulate phenomena (Condensed Papers)
- Imprint Pagination
- 181 p.
- Journal Page Range
- p. 16.
Conference
- Title
- 5. Miami international symposium on multi-phase transport and particulate phenomena.
- Dates
- 12-14 Dec 1988.
- Place
- Miami Beach, FL (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21014222
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; FLOW MODELS; HYDRAULICS; K CODES; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR COOLING SYSTEMS; REACTOR CORES; TWO-PHASE FLOW
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; FLUID FLOW; MATHEMATICAL MODELS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-881202--.