Published 2016 | Version v1
Miscellaneous Metadata-only

Heat Transfer Analysis of Microscale UO2 Particle-Graphite System in TREAT Fuel

Creators

  • 1. Argonne National Laboratory, 9700 South Cass Ave, Argonne, IL 60439 (United States)

Description

The Transient Reactor Test Facility (TREAT) at Idaho National Laboratory in the United States is now being prepared to restart its operation and perform transient testing to assist with advanced fuel development. In parallel with TREAT restart preparations, a program is underway to develop a low-enriched uranium core to replace the current highly-enriched uranium core. In this study, heat transfer simulation of UO2 particle- graphite systems in highly-enriched and low-enriched fuels for TREAT was performed using the finite element method (FEM). The irradiation degradation of both UO2 particles and graphite was taken into account in the simulation. The UO2 particle size limits for both HEU and LEU fuels were discussed based on the FEM simulation. In addition, a prototypical particle-distribution model was developed to evaluate the effect of size and spatial distribution of UO2 particles within the graphite. (author)

Part of:
European Research Reactor Conference (RRFM) 2016: Conference Proceedings

Additional details

Identifiers

URL
https://www.euronuclear.org/meetings/rrfm2016/transactions/rrfm2016-transactions.pdf;

Publishing Information

Publisher
European Nuclear Society
Imprint Place
Brussels (Belgium)
ISBN
978-92-95064-25-6
Imprint Title
European Research Reactor Conference (RRFM) 2016: Conference Proceedings
Imprint Pagination
1154 p.
Journal Page Range
p. 862-868
Report number
INIS-BE--16M5704

Conference

Title
20. international topical meeting on Research Reactor Fuel Management (RRFM)
Acronym
RRFM 2016
Dates
13-17 Mar 2016
Place
Berlin (Germany)

INIS

Country of Publication
Belgium
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
49023281
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FINITE ELEMENT METHOD; GRAPHITE; HEAT TRANSFER; HIGHLY ENRICHED URANIUM; PARTICLE SIZE; RADIATION EFFECTS; REACTOR OPERATION; SPATIAL DISTRIBUTION; TREAT REACTOR; URANIUM DIOXIDE
Descriptors DEC
ACTINIDE COMPOUNDS; ACTINIDES; AIR COOLED REACTORS; CALCULATION METHODS; CARBON; CHALCOGENIDES; DISTRIBUTION; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HOMOGENEOUS REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; MATHEMATICAL SOLUTIONS; METALS; MINERALS; NONMETALS; NUMERICAL SOLUTION; OPERATION; OXIDES; OXYGEN COMPOUNDS; REACTOR LIFE CYCLE; REACTORS; RESEARCH AND TEST REACTORS; SIZE; SOLID HOMOGENEOUS REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; URANIUM; URANIUM COMPOUNDS; URANIUM OXIDES

Optional Information

Notes
© European Nuclear Society, 2003; 5 refs., 7 figs., 1 tab.; This record replaces 48058216
Secondary number(s)
RRFM2016--A0090