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학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2013.1
- 수록면
- 573 - 580 (8page)
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초록· 키워드
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The combined effects of reactivity coefficients, along with other core nuclear characteristics, determine reactor core behavior in normal operation and accident conditions. The Power Coefficient of Reactivity (PCR) is an aggregate indicator representing the change in reactor core reactivity per unit change in reactor power. It is an integral quantity which captures the contributions of the fuel temperature, coolant void, and coolant temperature reactivity feedbacks. All nuclear reactor designs provide a balance between their inherent nuclear characteristics and the engineered reactivity control features, to ensure that changes in reactivity under all operating conditions are maintained within a safe range. The CANDU® reactor design takes advantage of its inherent nuclear characteristics, namely a small magnitude of reactivity coefficients, minimal excess reactivity, and very long prompt neutron lifetime, to mitigate the demand on the engineered systems for controlling reactivity and responding to accidents. In particular, CANDU reactors have always taken advantage of the small value of the PCR associated with their design characteristics, such that the overall design and safety characteristics of the reactor are not sensitive to the value of the PCR. For other reactor design concepts a PCR which is both large and negative is an important aspect in the design of their engineered systems for controlling reactivity. It will be demonstrated that during Loss of Regulation Control (LORC) and Large Break Loss of Coolant Accident (LBLOCA) events, the impact of variations in power coefficient, including a hypothesized larger than estimated PCR, has no safety-significance for CANDU reactor design. Since the CANDU 6 PCR is small, variations in the range of values for PCR on the performance or safety of the reactor are not significant.
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참고문헌 (13)
참고문헌 신청
AECB / 1973 / Reactor Licensing and Safety Requirements
B. Hanna / 2004 / CATHENA MOD-3.5d Abstract
CNSC / / Mythbuster ? Myth: CANDU reactors are dangerous due to their power coefficient of reactivity
CNSC / 2008 / Design of New Nuclear Power Plants
D. Rouben / 2009 / Large Loss of Coolant in the Primary Circuit with Safety Systems Available
B. Hanna / 2004 / CATHENA MOD-3.5d Abstract
CNSC / / Mythbuster ? Myth: CANDU reactors are dangerous due to their power coefficient of reactivity
CNSC / 2008 / Design of New Nuclear Power Plants
D. Rouben / 2009 / Large Loss of Coolant in the Primary Circuit with Safety Systems Available
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