• 대한수학회지
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• 제51권1호
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• pp.163-187
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• 2014

We present a multi-stage Roe-type numerical scheme for a model of two-phase flows arisen from the modeling of deflagration-to-detonation transition in granular materials. The first stage in the construction of the scheme computes the volume fraction at every time step. The second stage deals with the nonconservative terms in the governing equations which produces states on both side of the contact wave at each node. In the third stage, a Roe matrix for the two-phase is used to apply on the states obtained from the second stage. This scheme is shown to capture stationary waves and preserves the positivity of the volume fractions. Finally, we present numerical tests which all indicate that the proposed scheme can give very good approximations to the exact solution.

• 대한기계학회논문집B
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• 제34권11호
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• pp.957-964
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• 2010

본 연구에서는 친환경 연소로서 순산소 연소의 내제한 문제점에 대하여 논의하고 있다. 그 중 DDT의 발전에 의해 발생되는 강한 압력 충격파에 의한 구조물의 손상에 대한 내용을 다루고 있다. 이를 위하여 DDT에 대해 인식시키기 위하여 기본적인 개념과 더불어 이를 발전시키는 요인들에 대해서 논의해 보았다. 그리고 순산소 연소의 DDT 발생에 의한 압력파 생성과 더불어 이에 따른 구조물 손상을 설명하기 위하여 순산소 연소를 사용하는 친환경 용융로(미분탄과 순산소 연소를 사용한 용융로) 내부의 풍구 손상을 AUTODYN hydrocode를 이용하여 모델링하였다. 이를 통하여 순산소 연소에 내제된 위험성에 대하여 살펴보았다.

• Nuclear Engineering and Technology
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• 제41권5호
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• pp.617-648
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• 2009

Under the government supported long-term nuclear R&D program, the severe accident research program at KAERI is directed to investigate unresolved severe accident issues such as core debris coolability, steam explosions, and hydrogen combustion both experimentally and numerically. Extensive studies have been performed to evaluate the in-vessel retention of core debris through external reactor vessel cooling concept for APR1400 as a severe accident management strategy. Additionally, an improvement of the insulator design outside the vessel was investigated. To address steam explosions, a series of experiments using a prototypic material was performed in the TROI facility. Major parameters such as material composition and void fraction as well as the relevant physics affecting the energetics of steam explosions were investigated. For hydrogen control in Korean nuclear power plants, evaluation of the hydrogen concentration and the possibility of deflagration-to-detonation transition occurrence in the containment using three-dimensional analysis code, GASFLOW, were performed. Finally, the integrated severe accident analysis code, MIDAS, has been developed for domestication based on MELCOR. The data transfer scheme using pointers was restructured with the modules and the derived-type direct variables using FORTRAN90. New models were implemented to extend the capability of MIDAS.

• 한국항공우주학회지
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• 제48권2호
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• pp.135-146
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• 2020

경계면을 정의하는 기존의 레벨-셋 기법은 대개 수학적인 수식을 이용한다. 그러나 3차원 데카르트 좌표계에서 복잡한 경계면을 수식으로 설정하는 방식은 거의 불가능하다. 이러한 이유로 우리는 보편적으로 사용되는 스테레오리쏘그래피(STL) 형식을 매개 변수화하여 3D 캐드 형상의 내부와 외부를 구분하는 레벨-셋 경계면 설정 알고리즘을 개발하였다. 본 논문은 반응막대 실험 모사를 통해 기존의 경계면 설정 방식과 새로운 경계면 설정 방식 결과와 비교하여 이 알고리즘이 적용된 하이드로 다이내믹 솔버의 타당성을 확보하였다. 이를 통해 가연성 기체로 채워진 다양한 형상 안에서 충격파와 상호작용이 연소 폭발 천이 현상에 미치는 영향을 수치적으로 해석하였다. 또한, 실제 크기의 공장 설비에서 화염이 퍼져나가는 과정과 데토네이션 발생이 설비에 미치는 피해를 수치적으로 예측하는 시뮬레이션을 진행하였다.

• 한국전산유체공학회지
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• 제10권3호
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• pp.9-18
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• 2005

During a hypothetical severe accident in a nuclear power plant (NPP), hydrogen is generated by the active reaction of fuel-cladding and steam in the reactor pressure vessel and released with steam into the containment. In order to mitigate hydrogen hazards possibly occurred in the NPP containment, hydrogen mitigation system (HMS) is usually adopted. The design of the next generation NPP (APR1400) designed in Korea specifies 26 passive autocatalytic recombiners and 10 igniters installed in the containment for the hydrogen mitigation. in this study, the analysis of the hydrogen and steam behavior during a total lose of feed water (TLOFW) accident in the APR1400 containment has been conducted by using the CFD code GASFLOW. During the accident, a huge amount of hot water, steam, and hydrogen is released in the in-containment refueling water storage tank (IRWST). The current design of the APR1400 includes flap-type dampers at the IRWST vents which are operated depending on the pressure difference between inside and outside of the IRWST. it was found that the flaps strongly affects the flow structure of the steam and hydrogen in the containment. The possibilities of a flame acceleration and transition from deflagration to detonation (DDT) were evaluated by using Sigma-Lambda criteria. Numerical results indicate the DDT possibility could be heavily reduced in the IRWST compartment when the flaps are installed.