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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2005.1
- 수록면
- 139 - 150 (12page)
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A robust control design procedure for a nuclear reactor has been developed and experimentally validated on the Penn State TRIGA research reactor. The utilization of the robust controller as a component of an autonomous control system is also demonstrated. Two methods of specifying a low order (fourth-order) nominal-plant model for a robust control design were evaluated: 1) by approximation based on the “physics” of the process and 2) by an optimal Hankel approximation of a higher order plant model. The uncertainty between the nominal plant models and the higher order plant model is supplied as a specification to the -synthesis robust control design procedure. Two methods of quantifying uncertainty were evaluated: 1) a combination of additive and multiplicative uncertainty and 2) multiplicative uncertainty alone. The conclusions are that the optimal Hankel approximation and a combination of additive and multiplicative uncertainty are the best approach to design robust control for this application. The results from nonlinear simulation testing and the physical experiments are consistent and thus help to confirm the correctness of the robust control design procedures and conclusions.
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참고문헌 (21)
참고문헌 신청
/ / An IncrementalApproach to Control Modernization of Existing and FutureNuclear Reactors and Power Plants : 167 ~ 183
/ / ？ IEEE Transactions on NuclearScience : 2298 ~ 2309
/ / ？AnAutomatic Tuning Method of a Fuzzy Logic Controller forNuclear Reactors ？ IEEE Transactions on Nuclear Science : 1253 ~ 1262
/ / ？Robust Fault-Accommodating Control of Nuclear Reactors and PowerPlants : 137 ~ 148
/ 1991 / ？SafetyIssues Involved in Using the PSBR for Control AlgorithmTesting ？ Proceedings of AI 91 Frontiers in InnovativeComputing for the Nuclear Industry
/ / ？ IEEE Transactions on NuclearScience : 2298 ~ 2309
/ / ？AnAutomatic Tuning Method of a Fuzzy Logic Controller forNuclear Reactors ？ IEEE Transactions on Nuclear Science : 1253 ~ 1262
/ / ？Robust Fault-Accommodating Control of Nuclear Reactors and PowerPlants : 137 ~ 148
/ 1991 / ？SafetyIssues Involved in Using the PSBR for Control AlgorithmTesting ？ Proceedings of AI 91 Frontiers in InnovativeComputing for the Nuclear Industry
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