AGR-2 Irradiation Test Final As-Run Report

Technical Report · Fri Aug 01 00:00:00 EDT 2014

DOI:https://doi.org/10.2172/1168618· OSTI ID:1168618

Collin, Blaise P. ^[1]

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1. Idaho National Lab. (INL), Idaho Falls, ID (United States). VHTR Program

This document presents the as-run analysis of the AGR-2 irradiation experiment. AGR-2 is the second of the planned irradiations for the Advanced Gas Reactor (AGR) Fuel Development and Qualification Program. Funding for this program is provided by the U.S. Department of Energy as part of the Very High Temperature Reactor (VHTR) Technology Development Office (TDO) program. The objectives of the AGR-2 experiment are to: 1. Irradiate UCO (uranium oxycarbide) and UO₂ (uranium dioxide) fuel produced in a large coater. Fuel attributes are based on results obtained from the AGR-1 test and other project activities. 2. Provide irradiated fuel samples for post-irradiation experiment (PIE) and safety testing. 3. Support the development of an understanding of the relationship between fuel fabrication processes, fuel product properties, and irradiation performance. The primary objective of the test was to irradiate both UCO and UO₂ TRISO (tristructural isotropic) fuel produced from prototypic scale equipment to obtain normal operation and accident condition fuel performance data. The UCO compacts were subjected to a range of burnups and temperatures typical of anticipated prismatic reactor service conditions in three capsules. The test train also includes compacts containing UO₂ particles produced independently by the United States, South Africa, and France in three separate capsules. The range of burnups and temperatures in these capsules were typical of anticipated pebble bed reactor service conditions. The results discussed in this report pertain only to U.S.-produced fuel.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1168618
• Report Number(s): INL/EXT-14-32277; Rev. 1; TRN: US1500008
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
VHTR REACTOR
SPENT FUELS
OXYCARBIDES
URANIUM OXIDES
URANIUM CARBIDES
URANIUM DIOXIDE
IDAHO NATIONAL LABORATORY
CAPSULES
IRRADIATION
POST-IRRADIATION EXAMINATION
EXPERIMENTAL DATA
PEBBLE BED REACTORS
PRISMATIC CONFIGURATION
ATR REACTOR
KEV RANGE 100-1000
URANIUM
HEAVY METALS
TEMPERATURE RANGE 1000-4000 K
NEUTRON FLUENCE
BURNUP
COMPACTS
GAS FLOW
MONITORS
PERFORMANCE
THERMOCOUPLES
FISSION PRODUCT RELEASE
COATED FUEL PARTICLES
FABRICATION
CHEMICAL PROPERTIES
PHYSICAL PROPERTIES
REACTOR SAFETY
TESTING
AGR
Irradiation
NGNP
VHTR
TDO