Published February 2015 | Version v1
Journal article Metadata-only

TRACE thermal hydraulic model development of Qinshan nuclear power plant phase II PWR

Creators

  • 1. Nuclear and Radiation Safety Center, MEP, Beijing (China)
  • 2. Third Qinshan Nuclear Power Plant, Haiyan (China)

Description

In order to improve nuclear power plant safety review work, NNSA imported reactor thermal hydraulic best estimate code TRACE from NRC. In this paper, the NPQJVC two-loop PWR thermal hydraulic model is setup and LBLOCA is simulated using TRACE code and engineering modeling assistant code SNAP. The results of simulation are reasonable. (authors)

Additional details

Publishing Information

Journal Title
Nuclear Power Engineering
Journal Volume
36
Journal Issue
1
Journal Page Range
p. 124-126
ISSN
0258-0926

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
48083740
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COMPUTERIZED SIMULATION; ENGINEERING; LOSS OF COOLANT; NUCLEAR POWER PLANTS; QINSHAN-2-1 REACTOR; QINSHAN-2-2 REACTOR; SAFETY ANALYSIS; T CODES; THERMAL HYDRAULICS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HYDRAULICS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
1 fig., 3 tabs., 3 refs.