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High Fidelity, Fuel-Like Thermal Simulators for Non-Nuclear Testing: Analysis and Initial Test ResultsNon-nuclear testing can be a valuable tool in the development of a space nuclear power system, providing system characterization data and allowing one to work through various fabrication, assembly and integration issues without the cost and time associated with a full ground nuclear test. In a non-nuclear test bed, electric heaters are used to simulate the heat from nuclear fuel. Testing with non-optimized heater elements allows one to assess thermal, heat transfer. and stress related attributes of a given system, but fails to demonstrate the dynamic response that would be present in an integrated, fueled reactor system. High fidelity thermal simulators that match both the static and the dynamic fuel pin performance that would be observed in an operating, fueled nuclear reactor can vastly increase the value of non-nuclear test results. With optimized simulators, the integration of thermal hydraulic hardware tests with simulated neutronic response provides a bridge between electrically heated testing and fueled nuclear testing. By implementing a neutronic response model to simulate the dynamic response that would be expected in a fueled reactor system, one can better understand system integration issues, characterize integrated system response times and response characteristics and assess potential design improvements at relatively small fiscal investment. Initial conceptual thermal simulator designs are determined by simple one-dimensional analysis at a single axial location and at steady state conditions; feasible concepts are then input into a detailed three-dimensional model for comparison to expected fuel pin performance. Static and dynamic fuel pin performance for a proposed reactor design is determined using SINDA/FLUINT thermal analysis software, and comparison is made between the expected nuclear performance and the performance of conceptual thermal simulator designs. Through a series of iterative analyses, a conceptual high fidelity design is developed: this is followed by engineering design, fabrication, and testing to validate the overall design process. Test results presented in this paper correspond to a "first cut" simulator design for a potential liquid metal (NaK) cooled reactor design that could be applied for Lunar surface power. Proposed refinements to this simulator design are also presented.
Document ID
20070032700
Acquisition Source
Marshall Space Flight Center
Document Type
Conference Paper
Authors
Bragg-Sitton, Shannon M.
(NASA Marshall Space Flight Center Huntsville, AL, United States)
Dickens, Ricky
(NASA Marshall Space Flight Center Huntsville, AL, United States)
Dixon, David
(North Carolina State Univ. Raleigh, NC, United States)
Kapernick, Richard
(Los Alamos National Lab. NM, United States)
Date Acquired
August 23, 2013
Publication Date
June 24, 2007
Subject Category
Numerical Analysis
Meeting Information
Meeting: American Nuclear Society (ANS) Space Nuclear Conference (SNC) 2007
Location: Boston, MA
Country: United States
Start Date: June 24, 2007
End Date: June 28, 2007
Sponsors: American Nuclear Society
Distribution Limits
Public
Copyright
Other

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