Published 1977 | Version v1
Report Restricted

Light-water-reactor safety program. Quarterly progress report, April--June 1977

Creators

Description

The report summarizes work performed on the following water-reactor-safety problems: (1) loss-of-coolant accident research in heat transfer and fluid dynamics; (2) transient fuel response and fission-product release; (3) mechanical properties of zircaloy containing oxygen; and (4) steam-explosion studies

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS., PC A07/MF A01.

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
145 p.
Report number
ANL--77-59

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
9367793
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Progress Report
Descriptors DEI
BWR TYPE REACTORS; CRITICAL HEAT FLUX; DEFORMATION; EXPLOSIONS; FISSION PRODUCT RELEASE; FLUID FLOW; FUEL CANS; FUEL ELEMENT FAILURE; FUEL PELLETS; HEAT TRANSFER; LOSS OF COOLANT; MECHANICAL PROPERTIES; MOLTEN METAL-WATER REACTIONS; OXIDATION; PWR TYPE REACTORS; RESEARCH PROGRAMS; SIMULATION; STEAM; URANIUM DIOXIDE; ZIRCALOY 2; ZIRCALOY 4
Descriptors DEC
ACCIDENTS; ACTINIDE COMPOUNDS; ALLOYS; CHALCOGENIDES; CHEMICAL REACTIONS; CHROMIUM ADDITIONS; ENERGY TRANSFER; HEAT FLUX; IRON ADDITIONS; OXIDES; OXYGEN COMPOUNDS; REACTOR ACCIDENTS; REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS