Improving the fidelity of electrically heated nuclear systems testing using simulated neutronic feedback
- 1. Texas A and M University, Department of Nuclear Engineering, 129 Zachry Engineering Center, 3133 TAMU, College Station, TX 77843-3133 (United States)
- 2. NASA Marshall Space Flight Center, Propulsion Research, Technology Branch, ER-24, MSFC, AL 35812 (United States)
Description
Nonnuclear test platforms and methodologies can be employed to reduce the overall cost, risk and complexity of testing nuclear systems while allowing one to evaluate the operation of an integrated nuclear system within a reasonable timeframe, providing valuable input to the overall system design. In a nonnuclear test bed, electric heaters are used to simulate the heat from nuclear fuel. Standard electric test techniques allow one to fully assess thermal, heat transfer, and stress related attributes of a given system, but these approaches fail 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 testing with nuclear fuel elements installed. 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. This paper summarizes the results of initial system dynamic response testing for two electrically heated reactor concepts: a heat pipe-cooled reactor simulator with integrated heat exchanger and a gas-cooled reactor simulator with integrated Brayton power conversion system. Initial applications apply a simplified reactor kinetics model with either a single or an averaged measured state point. Preliminary results demonstrate the applicability of the dynamic test methodology to any reactor type, elucidating the variation in system response characteristics in different reactor concepts. These results suggest a need to further enhance the dynamic test approach by incorporating a more accurate model of the reactor dynamics and improved hardware instrumentation for better state estimation in application of the simulated response control loop.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2010.04.036Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2010.04.036;
- PII
- S0029-5493(10)00320-1;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 240
- Journal Issue
- 10
- Journal Page Range
- p. 2745-2754
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 4. international topical meeting on high temperature reactor technology
- Acronym
- HTR 2008
- Dates
- 28 Sep - 1 Oct 2008
- Place
- Washington, DC (United States)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 42013294
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BRAYTON CYCLE; COST; ELECTRIC HEATING; FUEL ELEMENTS; GAS COOLED REACTORS; HEAT EXCHANGERS; HEAT TRANSFER; PERFORMANCE TESTING; REACTOR KINETICS; REACTOR SIMULATORS; RISK ASSESSMENT; SIMULATION; THERMAL HYDRAULICS; THERMAL STRESSES
- Descriptors DEC
- ANALOG SYSTEMS; ENERGY TRANSFER; FLUID MECHANICS; FUNCTIONAL MODELS; HEATING; HYDRAULICS; KINETICS; MECHANICS; REACTOR COMPONENTS; REACTORS; SIMULATORS; STRESSES; TESTING; THERMODYNAMIC CYCLES
Optional Information
- Copyright
- Copyright (c) 2010 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.