Published 1997 | Version v1
Miscellaneous Metadata-only

TRACG post-test analysis of panthers prototype tests of SBWR passive containment condenser

Creators

  • 1. GE Nuclear Energy (United States)
  • 2. S. Levy, Inc, 3425 S. Bascom Ave., Campbell (United States)
  • 3. ENEA ERG FISS, Via Martiri di Sole n.4 (Italy)

Description

As part of the validation effort for application of the TRACG code to the Simplified Boiling Water Reactor (SBWR), calculations have been performed for the various test facilities which are part of the SBWR design and technology certification program. These calculations include post-test calculations for tests in the PANTHERS Passive Containment Condenser (PCC) test program. Sixteen tests from the PANTHERS/PCC test matrix were selected for post-test analysis. This set includes three steady-state pure-steam tests, nine steady-state steam-air tests, and four transient tests. The purpose of this paper is to present and discuss the results of the post-test analysis. The author includes a brief description of the PANTHERS/PCC test facility and test matrix, a description of the PANTHERS/PCC post-test TRACG model and the manner in which the various types of tests in the post-test evaluation were simulated, and a presentation of the results of the TRACG simulation

Part of:
Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety

Additional details

Publishing Information

Imprint Title
Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety
Imprint Pagination
1493 p.
Journal Page Range
p. P4.1.P4.6

Conference

Title
5. international topical meeting on nuclear thermal hydraulics, operations and safety
Dates
14-18 Apr 1997
Place
Beijing (China)

INIS

Country of Publication
China
Country of Input or Organization
China
INIS RN
29048844
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature, Numerical Data
Descriptors DEI
BENCH-SCALE EXPERIMENTS; BWR TYPE REACTORS; CONDENSER COOLING SYSTEMS; CONTAINMENT; CONTAINMENT SYSTEMS EXPERIMENT; EXPERIMENTAL DATA; MATHEMATICAL MODELS; MODIFICATIONS; NUCLEAR POWER PLANTS; STEADY-STATE CONDITIONS; T CODES; TEST FACILITIES; TRANSIENTS
Descriptors DEC
AUXILIARY SYSTEMS; AUXILIARY WATER SYSTEMS; COMPUTER CODES; COOLING SYSTEMS; DATA; ENRICHED URANIUM REACTORS; INFORMATION; NUCLEAR FACILITIES; NUMERICAL DATA; POWER PLANTS; POWER REACTORS; REACTOR SAFETY EXPERIMENTS; REACTORS; THERMAL POWER PLANTS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information