Published October 2014
| Version v1
Journal article
Sensitivity analysis of ship reactor compartment model during LOCA
Creators
- 1. Department of Nuclear Science and Engineering, Naval University of Engineering, Wuhan (China)
Description
In view of the remarkable difference between ship reactor compartment (SRC) and nuclear power plant containment in space layout and structure size, the SRC pressure and temperature variations are more serious and relied on the dimension of SRC thermal-hydraulic model. Using RELAP5/MOD3.2 code, six SRC control volume models were established, including two-dimensional and three-dimensional models in space, and the variations of SRC pressure and temperature under supposed LOCA were analyzed. The characters of different models were studied and an optimized model was established. The result can be a reference in ship reactor SRC safety evaluation and thermal-hydraulics character analysis during LOCA. (authors)
Additional details
Publishing Information
- Journal Title
- Atomic Energy Science and Technology
- Journal Volume
- 48
- Journal Issue
- suppl
- Journal Page Range
- p. 376-380
- ISSN
- 1000-6931
INIS
- Country of Publication
- China
- Country of Input or Organization
- China
- INIS RN
- 48072390
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPARTMENTS; CONTAINMENT; CONTROL; LOSS OF COOLANT; R CODES; SAFETY ANALYSIS; SENSITIVITY ANALYSIS; SHIP PROPULSION REACTORS; SPACE DEPENDENCE; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; TWO-DIMENSIONAL CALCULATIONS; VARIATIONS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; PROPULSION REACTORS; REACTOR ACCIDENTS; REACTORS
Optional Information
- Notes
- 5 figs., 3 tabs., 5 refs.