Published May 2012 | Version v1
Miscellaneous

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

Part of:
Proceedings of Korean Nuclear Society, Daejeon (KR)

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