Published September 1995 | Version v1
Report Restricted

Condensation during gravity driven ECC: Experiments with PACTEL

Creators

  • 1. Lappeenranta Univ. of Technology (Finland)
  • 2. Technical Research Centre of Finland, Lappeenranta (Finland)

Description

This paper provides the results of the second series of gravity driven emergency core cooling (ECC) experiments with PACTEL (Parallel Channel Test Loop). The simulated accident was a small break loss-of-coolant accident (SBLOCA) with a break in a cold leg. The ECC flow was provided from a core makeup tank (CMT) located at a higher elevation than the main part of the primary system. The CMT was pressurized with pipings from the pressurizer and a cold leg. The tests indicated that steam condensation in the CMT can prevent ECC and lead to core uncovery

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Additional details

Publishing Information

Imprint Title
Proceedings of the 7th International Meeting on Nuclear Reactor Thermal-Hydraulics NURETH-7. Volume 1, Sessions 1-5
Imprint Pagination
862 p.
Journal Page Range
p. 299-311.
Report number
NUREG/CP--0142-Vol.1

Conference

Title
7. international meeting on nuclear reactor thermal hydraulics.
Dates
10-15 Sep 1995.
Place
Saratoga, NY (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
27019770
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
DIAGRAMS; ECCS; EXPERIMENTAL DATA; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR SAFETY; TESTING
Descriptors DEC
ACCIDENTS; DATA; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-950904--Vol.1.