THERMAL HYDRAULIC ANALYSIS OF A GAS TEST LOOP SYSTEM
Conference
·
OSTI ID:911625
This paper discusses thermal hydraulic calculations for a Gas Test Loop (GTL) system designed to provide a high intensity fast-flux irradiation environment for testing fuels and materials for advanced concept nuclear reactors. To assess the performance of candidate reactor fuels, these fuels must be irradiated under actual fast reactor flux conditions and operating environments, preferably in an existing irradiation facility [1]. Potential users of the GTL include the Generation IV Reactor Program, the Advanced Fuel Cycle Initiative and Space Nuclear Programs.
- Research Organization:
- Idaho National Lab. (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- DOE - NE
- DOE Contract Number:
- DE-AC07-99ID-13727
- OSTI ID:
- 911625
- Report Number(s):
- INL/CON-05-00446; TRN: US0800048
- Resource Relation:
- Conference: ANS 2005 Winter Meeting,Washington, DC,11/13/2005,11/17/2005
- Country of Publication:
- United States
- Language:
- English
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