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Title: Semiscale blowdown and Emergency Core Cooling (ECC) project test report: Test 845 (ECC Injection)

Technical Report ·
DOI:https://doi.org/10.2172/4684681· OSTI ID:4684681

This document presents the results of a decompression experiment (Test 845) performed in the Semiscale Blowdown and Emergency Core Cooling (ECC) Project as a part of the Water Reactor safety Program of the U.S. Atomic Energy Commission. The data are intended to provide a basis for assessing and measuring the maturity of analytical codes used to predict the response of pressurized water reactors to decompression and ECC injection for a hypothetical major loss-of-coolant accident. The substantial and significant differences between a large nuclear reactor and the semiscale apparatus, and the differences in the related phenomenologies during postulated loss-of-coolant accidents, make invalid any direct extrapolation of the results from this test to a reactor. This test was intended only for purposes of analysis methods development and evaluation. Semiscale Test 845 was initiated by a cold leg (inlet piping) break of a system that includes both a single operating loop and a vessel with a simulated (electrically heated) reactor core, and was the first semiscale test in which ECC was injected. The objective of this test was to obtain initial experimental information relative to the effects of ECC injection on cooling fluid availability to a heated core and on primary decompression phenomena. The purpose of this report is to present the data from Semiscale Test 845 in sufficient detail to be directly usable by those groups engaged in loss-of-coolant accident analysis for pressurized water reactors. The results presented include pressure, fluid and material temperatures, fluid density, flow rates, and fluid quality as functions of time.

Research Organization:
Aerojet Nuclear Co., Idaho Falls, ID (United States)
Sponsoring Organization:
US Atomic Energy Commission (AEC)
DOE Contract Number:
AT(10-1)-1375
NSA Number:
NSA-26-024793
OSTI ID:
4684681
Report Number(s):
ANCR-1014
Resource Relation:
Other Information: UNCL. Orig. Receipt Date: 31-DEC-72
Country of Publication:
United States
Language:
English