Published November 7, 1986 | Version v1
Report Restricted

Relocation of zircaloy-clad uranium dioxide under severe accident conditions

Creators

Description

The mechanisms affecting the relocation of zircaloy-clad UO2 fuel rods during severe accidents in pressurized water reactors are discussed. Results from two integral in-pile tests and from the damaged Three Mile Island Unit-2 reactor core are presented. The thermal hydraulic conditions that influence fuel relocation are identified and chemical interactions between the fuel and the control rod material are addressed as they relate to material relocation

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE87004536.

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
18 p.
Report number
EGG-M--36186

Conference

Title
IAEA technical committee meeting on water reactor fuel behaviour and fission products release in off-normal and accident conditions.
Dates
10-13 Nov 1986.
Place
Vienna (Austria).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
18065870
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FUEL CANS; FUEL RODS; HEAT TRANSFER; HYDRAULICS; NUCLEAR FUELS; PWR TYPE REACTORS; REACTOR ACCIDENTS; URANIUM DIOXIDE; ZIRCALOY
Descriptors DEC
ACCIDENTS; ACTINIDE COMPOUNDS; ALLOYS; CHALCOGENIDES; ENERGY SOURCES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; FUELS; MATERIALS; OXIDES; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Notes
Portions of this document are illegible in microfiche products.
Secondary number(s)
CONF-8611109--1.