Published June 1981 | Version v1
Report Restricted

Oxide-fuel performance during operation and off-normal events

Creators

Description

An extensive irradiation program to evaluate fast reactor oxide fuel performance during both steady state and off-normal events is being conducted at HEDL. Detailed characterization of fuel pin thermal performance, dimensional stability and chemical stability from EBR-II steady state irradiations support a projection of FFTF reference pin lifetime exceeding 80 MWd/kg. Design changes for improved and advanced oxide fuels are being projected into FFTF testing. Twenty-seven TREAT reactor transient tests were conducted with EBR-II oxide pins. Tests to cladding integrity limits and tests terminated at the FFTF Secondary Plant Protective System limits provide data to validate the FFTF pin design off-normal capability

Availability note (English)

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

Files

Restricted

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

Additional details

Publishing Information

Imprint Pagination
8 p.
Report number
HEDL-SA--2237-S

Conference

Title
Topical meeting on reactor safety aspects of fuel behavior.
Dates
2 - 6 Aug 1981.
Place
Sun Valley, ID, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
13665774
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
EBR-2 REACTOR; FFTF REACTOR; FUEL PINS; MIXED OXIDE FUELS; PERFORMANCE TESTING; TREAT REACTOR
Descriptors DEC
AIR COOLED REACTORS; BREEDER REACTORS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; FUELS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; LIQUID METAL COOLED REACTORS; NUCLEAR FUELS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SODIUM COOLED REACTORS; SOLID FUELS; SOLID HOMOGENEOUS REACTORS; TEST REACTORS; TESTING; THERMAL REACTORS

Optional Information

Secondary number(s)
CONF-810803--16.