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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2018.1
- 수록면
- 1,277 - 1,288 (12page)
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초록· 키워드
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In this work, the reactor kinetics capability is used to compute the design safety parameters in a PWR dueto complete loss of coolant flow during protected and unprotected accidents. A thermal-hydraulic codecoupled with a point reactor kinetic model are used for these calculations; where kinetics parametershave been developed from the neutronic SRAC code to provide inputs to RELAP5-3D code to calculateparameters related to safety and guarantee that they meet the regulatory requirements. In RELAP5-3Dthe reactivity feedback is computed by both separable and tabular models. The results show theimportance of the reactivity feedback on calculating the power which is the key parameter that controlsthe clad and fuel temperatures to maintain them below their melting point and therefore prevent coremelt. In addition, extending modeling capability from separable to tabular model has nonremarkableinfluence on calculated safety parameters
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참고문헌 (15)
참고문헌 신청
C. Housiadas / 2000 / Simulation of loss-of-flow transients in research reactors / Ann. Nucl. Energy 27:1683~1693
B.N. Hamid / 2015 / Modeling an unprotected loss-of-flow accident in research reactors using the eureka-2/Rr code / J. Phys. Sci 26(2):73~87
I. Iliuk / 2016 / Thermal-hydraulic analysis under partial loss of flow accident hypothesis of a plate-type fuel surrounded by two water channels using RELAP5 code / Adv. Mech. Eng 8(1):1~8
B. Jia / 2017 / Research of Complete Loss of Flow Accident for Hualong One Based on Trace Code / Springer Singapore
M.Q. Huda / 2003 / Analysis of the DNB Ratio and the Loss-offlow Accident (LOFA) of the 3 MW TRIGA MARK 11 Research Reactor
B.N. Hamid / 2015 / Modeling an unprotected loss-of-flow accident in research reactors using the eureka-2/Rr code / J. Phys. Sci 26(2):73~87
I. Iliuk / 2016 / Thermal-hydraulic analysis under partial loss of flow accident hypothesis of a plate-type fuel surrounded by two water channels using RELAP5 code / Adv. Mech. Eng 8(1):1~8
B. Jia / 2017 / Research of Complete Loss of Flow Accident for Hualong One Based on Trace Code / Springer Singapore
M.Q. Huda / 2003 / Analysis of the DNB Ratio and the Loss-offlow Accident (LOFA) of the 3 MW TRIGA MARK 11 Research Reactor
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