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Dynamic Response Testing in an Electrically Heated Reactor Test FacilityNon-nuclear testing can be a valuable tool in development of a space nuclear power or propulsion system. In a non-nuclear test bed, electric heaters are used to simulate the heat from nuclear fuel. Standard testing allows one to fully 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. The integration of thermal hydraulic hardware tests with simulated neutronic response provides a bridge between electrically heated testing and full 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 a relatively small fiscal investment. Initial system dynamic response testing was demonstrated on the integrated SAFE-100a heat pipe cooled, electrically heated reactor and heat exchanger hardware, utilizing a one-group solution to the point kinetics equations to simulate the expected neutronic response of the system (Bragg-Sitton, 2005). The current paper applies the same testing methodology to a direct drive gas cooled reactor system, demonstrating the applicability of the testing methodology to any reactor type and demonstrating the variation in system response characteristics in different reactor concepts. In each testing application, core power transients were controlled by a point kinetics model with reactivity feedback based on core average temperature; the neutron generation time and the temperature feedback coefficient are provided as model inputs. Although both system designs utilize a fast spectrum reactor, the method of cooling the reactor differs significantly, leading to a variable system response that can be demonstrated and assessed in a non-nuclear test facility.
Document ID
20050215607
Acquisition Source
Marshall Space Flight Center
Document Type
Conference Paper
Authors
Bragg-Sitton, Shannon M.
(NASA Marshall Space Flight Center Huntsville, AL, United States)
Morton, T. J.
(New Mexico Univ. Albuquerque, NM, United States)
Date Acquired
August 23, 2013
Publication Date
January 1, 2006
Subject Category
Nuclear Physics
Meeting Information
Meeting: STAIF-2006 Conference
Location: Albuquerque, NM
Country: United States
Start Date: February 12, 2006
End Date: February 16, 2006
Distribution Limits
Public
Copyright
Public Use Permitted.
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