Structural analysis of fuel assembly clads for the Upgraded Transient Reactor Test Facility (TREAT Upgrade)
Description
The Upgraded Transient Reactor Test Facility (TREAT Upgrade) is designed to test full-length, pre-irradiated fuel pins of the type used in large LMFBRs under accident conditions, such as severe transient overpower and loss-of-coolant accidents. In TREAT Upgrade, the central core region is to contain new fuel assemblies of higher fissile loadings to maximize the energy deposition to the test fuel. These fuel assemblies must withstand normal peak clad temperatures of 8500C for hundreds of test transients. Due to high temperatures and gradients predicted in the clad, creep and plastic strain effects are significant, and the clad structural behavior cannot be analyzed by conventional linear techniques. Instead, the detailed elastic-plastic-creep behavior must be followed along the time-dependent load history. This paper presents details of the structural evaluations of the conceptual TREAT Upgrade fuel assembly clads
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE86006452.Files
18002749.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 20 p.
- Report number
- CONF-860724--1
Conference
- Title
- safe and reliable nuclear power plants.
- Acronym
- ASME/ANS bi-annual nuclear power conference
- Dates
- 20-23 Jul 1986.
- Place
- Philadelphia, PA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18002749
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- EVALUATION; FUEL ASSEMBLIES; FUEL CANS; FUEL PINS; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; TESTING; TRANSIENT OVERPOWER ACCIDENTS; TREAT REACTOR
- Descriptors DEC
- ACCIDENTS; AIR COOLED REACTORS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.