Parametric Analyses of Planned Flowing Uranium Hexafluoride Critical Experiments
Conference
·
OSTI ID:1973476
- United Technologies Research Center, East Hartford, CT (United States)
Analytical investigations were conducted to determine preliminary design and operating characteristics of flowing uranium hexafluoride (UF6) gaseous nuclear reactor experiments in which a hybrid core configuration comprised of UF6 gas and a region of solid fuel will be employed. The results indicate that confined flow tests of a gaseous UF6-uranium fuel element hybrid core configuration appear feasible. A preliminary design is described for an argon buffer gas confined, UF6 flow loop system for future use in flowing critical experiments. Flowing gaseous UF6 would be confined within the cavity core Canister by Tangential Injection of Argon Buffer Gas to Produce a Radial Inflow Vortex Flow Pattern.
- Research Organization:
- United Technologies Research Center, East Hartford, CT (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- OSTI ID:
- 1973476
- Report Number(s):
- CONF-760646
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
Cavity Core Canister
Gaseous Nuclear Reactor Experiments
Hybrid Core Configuration
Nuclear Criticality Safety Program (NCSP)
Radial Inflow Vortex Flow Pattern
Solid Fuel Elements
Uranium Plasma Core Reactors
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
Cavity Core Canister
Gaseous Nuclear Reactor Experiments
Hybrid Core Configuration
Nuclear Criticality Safety Program (NCSP)
Radial Inflow Vortex Flow Pattern
Solid Fuel Elements
Uranium Plasma Core Reactors