AGR-2 Irradiation Test Final As-Run Report

Collin, Blaise P.¹ 

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

关键词: 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;   

DOI  :  10.2172/1168618
RP-ID  :  INL/EXT--14-32277
PID  :  OSTI ID: 1168618
Others  :  Other: Rev. 1
Others  :  TRN: US1500008

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

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.