Published December 1984 | Version v1
Report

Multivent effects in a large scale boiling water reactor pressure suppression system

  • 1. Lawrence Livermore National Lab., CA (USA)
  • 2. GKSS-Forschungszentrum Geesthacht G.m.b.H., Geesthacht-Tesperhude (Germany, F.R.)

Description

The steam-driven GKSS pressure suppression test facility, which contains 3 full scale vent pipes, has been used for 5 years to investigate the postulated loss-of-coolant accident in a Mark II and Type 69 BWR. Using the rsults from several of these tests, wetwell boundary load data (peak pressures and spectral power) during the chugging stage, have been evaluated for ''sparse'' pool response (one and two vents in the three vent pool) and for ''full'' pool response (one, two, or three vent operation in pools of constant wetwell pool area per vent). The ''sparse'' pool results indicate the pool-system, chug event boundary loads are strongly dependent on wetwell pool area per vent, with the load increasing with decreasing area. The ''full'' pool results show a substantial increase in the pool-system, chug event boundary loads upon a change from single cell to double cell operation; only minor change occurs in going from double to triple cell operation. (orig./HP)

Additional details

Publishing Information

Imprint Title
5th international meeting on thermal nuclear reactor safety. Proceedings. Vol. 3
Imprint Pagination
736 p.
Journal Page Range
p. 1859-1866.
Report number
KFK--3880/3

Conference

Title
5. international meeting on thermal nuclear reactor safety.
Dates
9-13 Sep 1984.
Place
Karlsruhe (Germany, F.R.).

INIS

Country of Publication
Germany
Country of Input or Organization
Germany
INIS RN
16068365
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BLOWDOWN; BWR TYPE REACTORS; CONTAINMENT; DYNAMIC LOADS; LOSS OF COOLANT; PRESSURE SUPPRESSION; REACTOR SAFETY EXPERIMENTS
Descriptors DEC
ACCIDENTS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS