Current and Future Technological Issues Challenges for Nuclear Graphite Components
Conference
·
OSTI ID:2497836
- Idaho National Laboratory
Historical and current data requirements for component qualification, as-manufactured graphite material properties, Irradiated & degraded material issues, code rules – Construction & Operation, status of current ASME code rules, progress in design rules, degradation, construction vs. operation, what should we be planning, and new technical areas getting started.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- 58
- DOE Contract Number:
- DE-AC07-05ID14517
- OSTI ID:
- 2497836
- Report Number(s):
- INL/CON-24-80669-Rev000
- Resource Relation:
- Conference: INGSM, UC Berkeley, California, 09/08/2024 - 09/13/2024
- Country of Publication:
- United States
- Language:
- English
Similar Records
Draft ASME Boiler and Pressure Vessel Code Cases and Technical Bases for Use of Alloy 617 for Constructions of Nuclear Component Under Section III, Division 5
Code qualification of structural materials for AFCI advanced recycling reactors.
Technical Report
·
Mon Dec 20 00:00:00 EST 2021
·
OSTI ID:1836553
Code qualification of structural materials for AFCI advanced recycling reactors.
Technical Report
·
Thu May 31 00:00:00 EDT 2012
·
OSTI ID:1042575
+2 more