Support for Fuel Fabrication and Characterization
Program Document
·
OSTI ID:1556094
- Idaho National Laboratory
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) 2018, the activities for the INL ART TDO fuel development are focused on final characterization to support 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.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- DOE-NE
- DOE Contract Number:
- AC07-05ID14517;
- OSTI ID:
- 1556094
- Report Number(s):
- INL/MIS-12-27311-Rev010
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
+
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
AGR-1
AGR-2
Burn
Core
Deep
Denver
Examination
Fission
Fuel
FY10
Graphite
High
HTM
Irradiation
Kernel
Materials
Meeting
Methods
NGNP
Pebble-Bed
PIE
Post-irradiation
Preparations
Product
QA
Qualification
R&D
Review
Safety
TDO
Technical
Temperature
Testing
TRISO
V&V
VHTR
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
AGR-1
AGR-2
Burn
Core
Deep
Denver
Examination
Fission
Fuel
FY10
Graphite
High
HTM
Irradiation
Kernel
Materials
Meeting
Methods
NGNP
Pebble-Bed
PIE
Post-irradiation
Preparations
Product
QA
Qualification
R&D
Review
Safety
TDO
Technical
Temperature
Testing
TRISO
V&V
VHTR