Support for INL ART TDO Advanced Gas Reactor Fuel Fabrication and Characterization
Program Document
·
OSTI ID:1562932
- Idaho National Laboratory
Oak Ridge National Laboratory (ORNL) has participated in the Advanced Gas Reactor (AGR) program for the Next Generation Nuclear Plant (NGNP) since the inception of the program. In this effort, ORNL has fabricated tri-structural isotropic (TRISO) fuel and fuel compacts for AGR-1, AGR-2, and AGR-3/4 experiments, provided matrix only components for AGC-2 and AGR-3/4 experiments and for university studies, and provided characterization, coating, and compaction support for Babcock and Wilcox (B&W). In FY 2017, the activities for the Very-High Temperature Reactor (VHTR) Technology Development Office (TDO) fuel development are focused on preparations for the AGR-5/6/7 experiments. With the successful transfer of fuel fabrication technology to B&W, ORNL’s involvement has shifted toward transferring fuel characterization methods, providing support for fabricating surrogate fuel materials international collaborations. ORNL will also provide analytical support to B&W for uranium dispersion analysis and confirmatory fuel characterization analyses as needed.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC07-05ID14517;
- OSTI ID:
- 1562932
- Report Number(s):
- INL/MIS-12-27311-Rev009
- Country of Publication:
- United States
- Language:
- English
Similar Records
Support for Fuel Fabrication and Characterization
Support for Fuel Fabrication and Characterization
Support for Fuel Fabrication and Characterization
Program Document
·
Wed Sep 26 20:00:00 EDT 2018
·
OSTI ID:1476312
Support for Fuel Fabrication and Characterization
Program Document
·
Wed Sep 26 20:00:00 EDT 2018
·
OSTI ID:1556093
Support for Fuel Fabrication and Characterization
Program Document
·
Sun Dec 03 19:00:00 EST 2017
·
OSTI ID:1556094
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