Published May 2001 | Version v1
Miscellaneous Metadata-only

Assessment of RELAP5/MOD3.3.3 beta code for the LOFT L-9-1 experiment

Creators

  • 1. KOPEC, Taejon (Korea, Republic of)
  • 2. KINS, Taejon (Korea, Republic of)
  • 3. Seoul National Univ., Seoul (Korea, Republic of)

Description

The RELAP5/MOD3.2.2 beta code was assessed on the predictability of the thermal-hydraualic phenomena in primary and secondary coolant system during the LOFT test Lp-1 test performed at the LOFT facility was an experiment to simulate a total loss of feedwater (TLOFW) accident with delayed reactor scram and no auxiliary feedwater injection. From comparisons of the code predicted results with experimental data, it was concluded that the code was capable of simulating the thermal-hydrualic behavior during the short term phase of LOFT L9-1 test. In addition, it was identified the three parameters such as the steam generator (SG) nodalization, SG U-tube heat transfer area, and loss coefficient of the pressurizer spray valve had a significant effect on the calculation results for the LOFT test L9-1

Part of:
Proceedings of the Korean Nuclear Society spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society spring meeting
Imprint Pagination
[ONE CDROM]
Journal Page Range
[11 p.]

Conference

Title
2001 spring meeting of the Korean Nuclear Society
Dates
24-25 May 2001
Place
Cheju (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
33040349
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Numerical Data, Non-conventional Literature
Descriptors DEI
EXPERIMENTAL DATA; FEEDWATER; HEAT TRANSFER; HYDRAULICS; LOSS OF FLOW; R CODES; REACTOR COOLING SYSTEMS; STEAM GENERATORS; THERMAL ANALYSIS
Descriptors DEC
ACCIDENTS; BOILERS; COMPUTER CODES; COOLING SYSTEMS; DATA; ENERGY SYSTEMS; ENERGY TRANSFER; FLUID MECHANICS; HYDROGEN COMPOUNDS; INFORMATION; MECHANICS; NUMERICAL DATA; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTOR COMPONENTS; VAPOR GENERATORS; WATER

Optional Information

Notes
4 refs, 8 figs, 1 tab