Published August 1971 | Version v1
Journal article

Experimental studies of the effect of flow restrictions in a small rod bundle under emergency core coolant injection conditions

Creators

  • 1. Idaho Nuclear Corp., Idaho Falls (USA)

Description

AbstractA nine-pin array of electrical heaters was used to study the effects of partial flow blockage on the capability of cooling the array through injection of water under simulated reactor decay heat power conditions. The array was placed in a transparent tube and tests were conducted with six different blockage configurations.Tests were conducted by slowly heating the array until the temperature at the midelevation of the center pin was 1100°F. Full power (1 kW/ft) was then applied, until a midelevation temperature of either 1600 or 1800°F was reached. Bottom flooding was then initiated at a flow rate of 2 in./sec. Tests were conducted at both temperatures for each configuration. Temperatures were recorded at selected locations on one row of three heaters and high-speed motion pictures were taken.These tests, conducted for a variety of blockage geometries, demonstrated that severe flow blockage of a small fuel pin array does not result in significant reduction in the effectiveness of cooling the array by emergency cooling flooding.

Additional details

Identifiers

Publishing Information

Journal Title
Nuclear Technology
Journal Volume
11
Journal Issue
4
Series
Nucl. Technol.
Journal Page Range
551-556
ISSN
0029-5450

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
3016025
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
No Abstract
Descriptors DEI
CONFIGURATION; DEFORMATION; ECCS; FUEL PINS; HEATING; LOSSES; PERFORMANCE; PRESSURIZED WATER REACTORS; REACTOR ACCIDENTS; WATER COOLANT
Descriptors DEC
ACCIDENTS; FUEL ELEMENTS; REACTOR SAFETY; RODS; WATER COOLED REACTORS

Optional Information

Notes
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