Published August 1977 | Version v1
Report Restricted

In-plant safety/relief valve discharge load test, Monticello Plant. Final report

Creators

Description

This document reports the results of the test program of safety/relief valve (SRV) discharge load phenomena through a ramshead discharge device, and the effects upon the Mark I primary containment torus structure of the Monticello Nuclear Power Plant. The objectives were to provide a data base for verifying/improving bubble pressure, water reflood and piping load analytical models, and to measure the structural response of the torus, SRV piping, supports and acceleration of the basement and pedestal

Availability note (English)

MF available from INIS under the Report Number; General Electric Co., San Jose, CA.

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The record is publicly accessible, but files are restricted to users with access.

Additional details

Publishing Information

Imprint Pagination
v p.
Report number
NEDC--21581

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
9365854
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CONTAINMENT SYSTEMS; MONTICELLO REACTOR; TESTING; VALVES
Descriptors DEC
BWR TYPE REACTORS; CONTAINMENT; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; FLOW REGULATORS; POWER REACTORS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS