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지원사업
학술연구/단체지원/교육 등 연구자 활동을 지속하도록 DBpia가 지원하고 있어요.
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논문 기본 정보
- 자료유형
- 학술저널
- 저자정보
- 발행연도
- 2013.12
- 수록면
- 53 - 60 (8page)
이용수
초록· 키워드
오류제보하기
The boron transport model has been implemented into the CUPID code to simulate the boron transport phenomena of the PWR. The boron concentration conservation was confirmed through a simulation of a conceptual boron transport problem in which water with a constant inlet boron concentration injected into an inlet of the 2-dimensional vertical flow tube. The step wise boron transport problem showed that the numerical diffusion of the boron concentration can be reduced by the second order convection scheme. In order to assess the adaptability of the developed boron transport model to the realistic situation, the ROCOM test was simulated by using the CUPID implemented with the boron transportation.
목차
1. 서론
2. 붕소 수송 모델
3. 검증 계산 및 응용 계산
4. 결론
References
참고문헌 (10)
참고문헌 신청
1. [학술지(정기간행물)] - 정재준 / 2010 / DEVELOPMENT AND PRELIMINARY ASSESSMENT OF A THREE-DIMENSIONAL THERMAL HYDRAULICS CODE, CUPID / Nuclear Engineering and Technology 42 (3) : 279 ~ 296
3. [학술지(정기간행물)] - Han Young Yoon / 2012 / Multi-Scale Thermal-Hydraulic Analysis of PWRs using the CUPID Code / Nuclear Engineering and Technology 44 (8) : 831 ~ 846
4. [학술지(정기간행물)] - Yun, B.J. / 2006 / Investigation of the Downcomer Boiling Phenomena during the Reflood Phase of a Postualted Large-break LOCA in the APR1400 / Nuclear Technology 156 : 56 ~ 68
5. [학술대회논문] - Lee, J.R. / 2012 / Coupled Simulation of the Reactor Core using CUPID/MASTER / ICAPP ‘12 Chicago
6. [학술지(정기간행물)] - Park, I.K. / 2013 / An Implicit Code Coupling of 1-D System Code and 3-D In-house CFD Code for Multi-scaled Simulations of Nuclear Reactor Transients / Annals of Nuclear Energy 59 : 80 ~ 91
3. [학술지(정기간행물)] - Han Young Yoon / 2012 / Multi-Scale Thermal-Hydraulic Analysis of PWRs using the CUPID Code / Nuclear Engineering and Technology 44 (8) : 831 ~ 846
4. [학술지(정기간행물)] - Yun, B.J. / 2006 / Investigation of the Downcomer Boiling Phenomena during the Reflood Phase of a Postualted Large-break LOCA in the APR1400 / Nuclear Technology 156 : 56 ~ 68
5. [학술대회논문] - Lee, J.R. / 2012 / Coupled Simulation of the Reactor Core using CUPID/MASTER / ICAPP ‘12 Chicago
6. [학술지(정기간행물)] - Park, I.K. / 2013 / An Implicit Code Coupling of 1-D System Code and 3-D In-house CFD Code for Multi-scaled Simulations of Nuclear Reactor Transients / Annals of Nuclear Energy 59 : 80 ~ 91
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UCI(KEPA) : I410-ECN-0101-2015-420-001067880