Published January 1980 | Version v1
Journal article Metadata-only

Effect of intrasubassembly incoherencies on the fast test reactor unprotected transient overpower accident

Creators

  • 1. Hanford Engineering Development Lab., Richland, WA

Description

Intrasubassembly incoherencies affecting the fuel pin failure pattern within a fast test reactor (FTR) subassembly during an unprotected transient overpower/hypothetical core disruptive accident have been investigated using the COBRA-III/MELT code. Two dominant intrasubassembly incoherencies in an FTR subassembly were studied, namely, (a) the hydraulic effect, or the variation in pin-power-to-effective-coolant ratio between pins in the inner region and those in the outer region of the subassembly, and (b) the power skew, or variation in pinwise power density for pins throughout the subassembly

Additional details

Publishing Information

Journal Title
Nucl. Technol.
Journal Volume
47
Journal Issue
1
Series
Nucl. Technol.
Journal Page Range
23-38
ISSN
0029-5450

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
11541339
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COMPUTER CALCULATIONS; FFTF REACTOR; FUEL ELEMENT FAILURE; FUEL PINS; HEAT TRANSFER; HYDRAULICS; POWER DENSITY; REACTOR CORE DISRUPTION; REACTOR SAFETY; TRANSIENT OVERPOWER ACCIDENTS
Descriptors DEC
ACCIDENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SODIUM COOLED REACTORS; TEST REACTORS