AGR-2 Irradiation Test Final As-Run Report

Technical Report · Fri Aug 01 04:00:00 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
• Country of Publication: United States
• Language: English

Related Subjects

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