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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2017.6
- 수록면
- 700 - 709 (10page)
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초록· 키워드
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This work looks at the effect of changes in kinetic parameters on simultaneous reactivityinsertions and beam tube flooding in a typical material testing reactor-type researchreactor with low enriched high density (U3Si2-Al) fuel. Using a modified PARET code,various ramp reactivity insertions (from $0.1/0.5 s to $1.3/0.5 s) plus beam tube flooding($0.5/0.25 s) accidents under uncontrolled conditions were analyzed to find their effects onpeak power, net reactivity, and temperature. Then, the effects of changes in kinetic parametersincluding the Doppler coefficient, prompt neutron lifetime, and delayed neutronfractions on simultaneous reactivity insertion and beam tube flooding accidents wereanalyzed. Results show that the power peak values are significantly sensitive to theDoppler coefficient of the system in coupled accidents. The material testing reactor-typesystem under such a coupled accident is not very sensitive to changes in the promptneutron life time; the core under such a coupled transient is not very sensitive to changesin the effective delayed neutron fraction.
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참고문헌 (29)
참고문헌 신청
R. K. Cardell / 1967 / Reactivity accident test results and analysis for the SPERT IIIE Core
D. E. Cullen / 1986 / Applications in Nuclear Data and Reactor Physics / Word Scientific
C. F. Obenchain / 1969 / PARETdA Program for the Analysis of Reactor Transients
W. L. Woodruff / 1982 / The PARET Code and the Analysis of the SPERT-I Transients
C. Housiadas / 2000 / Simulation of loss of flow transients in research reactors / Ann. Nucl. Energy 27:1683~1693
D. E. Cullen / 1986 / Applications in Nuclear Data and Reactor Physics / Word Scientific
C. F. Obenchain / 1969 / PARETdA Program for the Analysis of Reactor Transients
W. L. Woodruff / 1982 / The PARET Code and the Analysis of the SPERT-I Transients
C. Housiadas / 2000 / Simulation of loss of flow transients in research reactors / Ann. Nucl. Energy 27:1683~1693
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