Support for Fuel Fabrication and Characterization
Oak Ridge National Laboratory (ORNL) has participated in the Advanced Gas Reactor (AGR) program for the Next Generation Nuclear Plant (NGNP) and the transition to the Idaho National Laboratory (INL) Advanced Reactor Technologies (ART) Technology Development Office (TDO) since the inception of the program. In this effort, ORNL has fabricated tristructural isotropic (TRISO) fuel and fuel compacts for AGR-1, AGR-2, and AGR-3/4 experiments, provided matrix only components for AGC-2, AGC-4, and AGR 3/4 experiments and for university studies, and provided characterization, coating, and compaction support for INL and BWX Technologies Nuclear Operations Group (BWXT). In fiscal year (FY) 2017, the activities for the INL ART TDO fuel development are focused on preparations for the AGR-5/6/7 experiments and technical support to the Generation-IV International Forum (GIF) pre-irradiation leach-burn-leach (LBL) round robin effort with China and South Korea. With the successful transfer of fuel fabrication technology to BWXT, ORNL’s involvement has shifted toward transferring fuel characterization methods, providing technical support, verification of BWXT laboratory results, and fabricating surrogate fuel materials for university collaborations. ORNL will also provide analytical support to BWXT and INL for uranium dispersion analysis and confirmatory fuel characterization analyses as needed.
- 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:
- 1476312
- Report Number(s):
- INL/MIS-12-27311-Rev011
- Country of Publication:
- United States
- Language:
- English
Similar Records
Support for Fuel Fabrication and Characterization
AGR-5/6/7 Fuel Fabrication Report
Related Subjects
NGNP + TDO + VHTR + R&D + Fuel + AGR-1 + AGR-2 + Irradiation + Fission + Product + Graphite + High + Temperature + Materials + HTM + FY10 + Technical + Review + Meeting + Denver + Kernel + QA + Deep + Burn + TRISO + Pebble-Bed + Core + Qualification + PIE + Post-irradiation + Examination + Safety + Testing + Preparations + Methods + V&V +