Uncertainty Estimation of Henry-Fauske Critical Flow Model Considering Thermal-nonequilibrium Constant and Discharge Coefficient in MARS-KS
Creators
- 1. Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)
Description
It is very important to evaluate critical flow in the safety assessment such as LOCA, MSLB etc. There are several models (HEM; Homogeneous Equilibrium Model, HFM; Homogeneous Frozen Model, Ransom Trapp, Henry Fauske Model) to simulate the critical flow in computer codes to analyze safety of the nuclear power plants. The default critical flow model in MARS-KS 1.4 used by KINS as independent regulatory assessment is the Henry-Fauske model, it is important to consider that the actual vapor quality is below the equilibrium quality due to thermal-nonequilibrium. Based on the Marviken experiment CFT-15 and 24 data, the uncertainty of Henry-Fauske critical flow model was evaluated. For the long nozzle (CFT-15, L/D=3.6), there was no range of uncertainty in the MARS-KS that could cover experimental data depending on the discharge coefficient and thermal non-equilibrium constant. In the case of the short nozzle (CFT-24, L/D=0.3), the uncertainty range of discharge coefficient 0.98 ⁓ 1.08 was derived for the region where the nozzle inlet pressure was greater than 3.3 MPa and the uncertainty range of thermal-nonequilibrium 0.1 ⁓ 0.3 was derived for the region above 3.1 MPa.
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS 2017 Spring Meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [3 p.]
Conference
- Title
- 2017 Spring Meeting of the KNS
- Dates
- 17-19 May 2017
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 49050363
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data, Non-conventional Literature
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRITICAL FLOW; EQUILIBRIUM; EXPERIMENTAL DATA; LOSS OF COOLANT; M CODES; NOZZLES; SAFETY ANALYSIS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DATA; FLUID FLOW; INFORMATION; NUMERICAL DATA; REACTOR ACCIDENTS; SIMULATION
Optional Information
- Notes
- 3 refs, 5 figs