서지주요정보
발전소 출력감발하에서 핵분열 생성기체의 장출 거동에 대한 연구 = A study on the behavior of fission gas release under power ramping
서명 / 저자 발전소 출력감발하에서 핵분열 생성기체의 장출 거동에 대한 연구 = A study on the behavior of fission gas release under power ramping / 한진규.
저자명 한진규 ; Han, Jin-Kyu
발행사항 [서울 : 한국과학기술원, 1989].
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소장정보

등록번호

4105947

소장위치/청구기호

학술문화관(문화관) 보존서고

MNE 8928

SMS전송

도서상태

이용가능

대출가능

반납예정일

초록정보

The SPEAR-BETA's fission gas release model was modefied by use of effective thermal conductivity and axial fission gas mixing between fuel-clad gap and plenum. With use of this modified code fission gas release was analyzed under a reactor operating condition with rapid power ramping. Effective fuel thermal conductivity for which the effect of fuel cracking is taken into account was devised in calculation of fuel temperature distribution and inner gas pressure under rapid power ramping. Mixing and dilution effect due to fission gas flow and diffusion was also taken into account in computing the gap condition. The axial fission gas flow model was solved by the Crank-Nicholson method, and the finite difference method was used to realize fast running time. The present modified fission gas release code was validated by comparing its predicted results with experimental results from the Studsvik ramping tests and calculated results with use of unmodified SPEAR-BETA code and with use of FEMAXI-IV code. Predicted results with use of the modified code showed better agreement with experimental results from the Studsvik tests than latters' calculated results. It was found that the fuel centerline temperature resulting from use of the modified heat conduction model was higher by 200°C than that resulting from use of the unmodified heat conduction model. The fraction of fission gas release predicted by using the modified code that took into account the axial gas flow was larger by nearly 6 % than that calculated by use of the unmodified code. Effects on fission gas release of gap width, fuel grain size, terminal power level and power ramp rate also were evaluated with use of the modified code.

서지기타정보

서지기타정보
청구기호 {MNE 8928
형태사항 [iv], 57 p. : 삽도 ; 26 cm
언어 한국어
일반주기 저자명의 영문표기 : Jin-Kyu Han
지도교수의 한글표기 : 윤용구
지도교수의 영문표기 : Young-Ku Yoon
학위논문 학위논문(석사) - 한국과학기술원 : 핵공학과,
서지주기 참고문헌 : p. 36-38
주제 Fission products.
Gas leakage.
출력. --과학기술용어시소러스
핵분열 생성물. --과학기술용어시소러스
기체. --과학기술용어시소러스
방사능 방출. --과학기술용어시소러스
Fission gases.
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