SPACE code ECCX Component Model and Comparisons with RELAP5/Mod 3.3 Code Predictions
- 1. Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)
Description
During the loss of coolant accident, especially when the break is considered a large break, in the nuclear power plant system, an emergency core cooling (ECC) injection is activated once the pressure has decreased sufficiently. The ECCS provides the process of the reestablishment of liquid/fuel contact by refilling, reflooding and quenching of the heated fuel rod cladding. The performance of the ECC injection at its initial stage is affected by the process of mixing of a jet of a cold water injected into a two-phase and the resulting steam condensation that follows. SPACE code incorporates a special component ECCX to account for the mixing and condensation phenomena near the ECC injection. This paper outlines the implemented models and assessment results of the ECCX component
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Daejeon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS spring meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2012 spring meeting of the KNS
- Dates
- 16-18 May 2012
- Place
- Jeju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 43073582
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CLADDING; ECCS; FUEL RODS; INJECTION; LOSS OF COOLANT; NUCLEAR POWER PLANTS; R CODES; S CODES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; DEPOSITION; ENGINEERED SAFETY SYSTEMS; FUEL ELEMENTS; INTAKE; NUCLEAR FACILITIES; POWER PLANTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR PROTECTION SYSTEMS; SURFACE COATING; THERMAL POWER PLANTS
Optional Information
- Notes
- 2 refs, 5 figs