• Nuclear Engineering and Technology
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• 제54권4호
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• pp.1482-1494
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• 2022

Power conversion cycles (Subcritical Steam, Supercritical Steam, Open Air Brayton, Recuperated Air Brayton, Combined Cycle, Closed Brayton Supercritical CO₂ (sCO₂), and Stirling) are evaluated for land-based nuclear microreactors based on technical maturity, system efficiency, size, cost and maintainability, safety implications, and siting considerations. Based upon these criteria, Air Brayton systems were selected for further evaluation. A brief history of the development and applications of Brayton power systems is given, followed by a description of how these thermal-to-electrical energy conversion systems might be integrated with a nuclear microreactor. Modeling is performed for optimized cycles operating at 3 MW(e) with turbine inlet temperatures of 500 ℃, 650 ℃ and 850 ℃, corresponding to: a) sodium fast, b) molten salt or heat pipe, and c) helium or sodium thermal reactors, coupled with three types of Brayton power conversion units (PCUs): 1) simple open-cycle gas turbine, 2) recuperated open-cycle gas turbine, and 3) recuperated and intercooled open-cycle gas turbine. Aeroderivative turboshaft engines employing the simple Brayton cycle and two industrial gas turbine engines employing recuperated air Brayton cycles are also analyzed. These engines offer mature technology that can facilitate near-term deployment with a modest improvement in efficiency.

• Nuclear Engineering and Technology
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• 제55권6호
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• pp.2172-2194
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• 2023

A variational nodal method (VNM) with unstructured-mesh is presented for solving steady-state and dynamic neutron diffusion equations. Orthogonal polynomials are employed for spatial discretization, and the stiffness confinement method (SCM) is implemented for temporal discretization. Coordinate transformation relations are derived to map unstructured triangular nodes to a standard node. Methods for constructing triangular prism space trial functions and identifying unique nodes are elaborated. Additionally, the partitioned matrix (PM) and generalized partitioned matrix (GPM) methods are proposed to accelerate the within-group and power iterations. Neutron diffusion problems with different fuel assembly geometries validate the method. With less than 5 pcm eigenvalue (k_eff) error and 1% relative power error, the accuracy is comparable to reference methods. In addition, a test case based on the kilowatt heat pipe reactor, KRUSTY, is created, simulated, and evaluated to illustrate the method's precision and geometrical flexibility. The Dodds problem with a step transient perturbation proves that the SCM allows for sufficiently accurate power predictions even with a large time-step of approximately 0.1 s. In addition, combining the PM and GPM results in a speedup ratio of 2-3.

• 한국건축시공학회:학술대회논문집
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• 한국건축시공학회 2021년도 가을 학술논문 발표대회
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• pp.242-243
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• 2021

The concrete inside the steel tube of CFT columns enables them to have great strength and ductility. CFT columns are also excellent in fire-resistance because explosive heat upon a fire can be contained in the tube by the concrete debris. However, the studies to evaluate the residual strength of CFT columns after a fire have not been conducted enough. The studies to evaluate the residual strength of CFT columns after a fire are indispensable because it is the barometer of the damage of composite columns caused by a fire and the degree of repair and reinforcement work for the columns after a fire. Accordingly, the purpose of this study is to evaluate the deterioration of load capacity and structural behavior of square CFT columns with the same shapes and boundary conditions before and after a fire. The study also evaluates the influential factors of the CFT columns reinforced to secure the residual strength after a fire.

• Nuclear Engineering and Technology
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• 제55권7호
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• pp.2604-2612
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• 2023

Spent nuclear fuel and long-lived radioactive waste must be carefully handled before disposing them off to a geological repository. After the pre-storage period in water pools, spent nuclear fuel is stored in casks, which are widely used for interim storage. Interim storage in casks is very important part in the whole cycle of nuclear energy generation. This paper presents the results of the numerical study that was performed to evaluate the thermal behavior of a metal-concrete CONSTOR RBMK-1500 cask loaded with spent nuclear fuel and placed in an open type interim storage facility which is under fire conditions (steady-state, fire, post-fire). The modelling was performed using the ANSYS Fluent code. Also, a local sensitivity analysis of thermal parameters on temperature variation was performed. The analysis demonstrated that the maximum increase in the fuel load temperatures is about 10 ℃ and 8 ℃ for 30 min 800 ℃ and 60 min 600 ℃ fires respectively. Therefore, during the fire and the post-fire periods, the fuel load temperatures did not exceed the 300 ℃ limiting temperature set for an RBMK SNF cladding for long-term storage. This ensures that fire accident does not cause overheating of fuel rods in a cask.

• Nuclear Engineering and Technology
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• 제55권12호
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• pp.4685-4694
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• 2023

The ability to calculate the material density sensitivity coefficients of power with respect to the material density has broad application prospects for accelerating Monte Carlo-Thermal Hydraulics iterations. The second-order material density sensitivity coefficients for the general Monte Carlo score have been derived based on the differential operator sampling method in this paper, and the calculation of the sensitivity coefficients of cell power scores with respect to the material density has been realized in continuous-energy Monte Carlo code RMC. Based on the power-density sensitivity coefficients, the sensitivity coefficients of power scores to some other physical quantities, such as power-boron concentration coefficients and power-temperature coefficients considering only the thermal expansion, were subsequently calculated. The effectiveness of the proposed method is demonstrated in the power-density coefficients problems of the pressurized water reactor (PWR) moderator and the heat pipe reactor (HPR) reflectors. The calculations were carried out using RMC and the ENDF/B-VII.1 neutron nuclear data. It is shown that the calculated sensitivity coefficients can be used to predict the power scores accurately over a wide range of boron concentration of the PWR moderator and a wide range of temperature of HPR reflectors.

• Nuclear Engineering and Technology
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• 제56권1호
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• pp.1-8
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• 2024

In this study, the influence of thermal aging on structural integrity is investigated for Gr. 91 steel. A commercial grade Gr. 91 steel is used for the virgin material, and service-exposed Gr. 91 steel is sampled from a steam pipe of a super critical plant. Time versus creep strain curves are obtained through creep tests with various stress levels at 600 ℃ for the virgin and service-exposed Gr. 91 steels, respectively. Based on the creep test results, the improved Omega model is characterized for describing the total creep strain curve for both Gr. 91 steels. The proposed parameters for creep deformation model are used for predicting the steady-state creep strain rate, creep rupture curve, and stress relaxation. Creep-fatigue damage is evaluated for the intermediate heat exchanger (IHX) in a large-scale sodium test facility of STELLA-2 by using creep deformation model with proposed creep parameters and creep rupture curve for both Gr. 91 steels. Based on the comparison results of creep fatigue damage for the virgin and service-exposed Gr. 91 steels, the thermal aging effect has been shown to be significant.

• 한국재난정보학회 논문집
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• 제10권4호
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• pp.583-597
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• 2014

난방기기에 의한 화재는 다양한 난방기기의 종류처럼 그 원인도 다양하고. 매년 계속되는 전통재래시장에서의 난방기기에 의한 화재사고가 빈번히 발생하여 인명 및 재산상의 손실을 초래하고 있다. 일반주택이나 아파트 등 대부분의 주거시설은 난방용 보일러가 보급되어 난방기기로 인한 화재가 그리 많지 않으나 식당, 시장의 점포와 사무실, 체육관, 공장, 작업장 등에서는 여전히 석유난로, 전기난로 등 난방기기를 사용 하고 있어 화재의 위험성에 노출되어 있다. 또한 난방용 기기의 발생건수를 살펴보면 가정용보일러, 목탄난로, 석유난로, 가스난로/스토브, 전기스토브/히터 순으로 발생한 것으로 분석되었으며, 인명피해 별 건수는 가스난로/스토브, 석유난로 /곤로, 전기히터/스토브, 연탄/석탄난로 순으로 분석되었다. 또한 가스 및 석유관련 난방용기기가 발생빈도(frequency)는 낮지만 화재강도(intensity)가 높은 것으로 분석 되었다. 따라서 본 연구의 목적은 다중이용시설인 전통재래시장에서 아직도 많이 사용되고 있고, 실제 화재발생사례가 많은 석유난로와 전기스토브에 의한 발화 위험성 즉 최소발화온도, 탄화 정도와 그에 따른 열유속을 정상상태와 비정상상태 하에서의 가연물의 접촉 및 전도로 인한 화재 발생 가능성을 재연하여 검토해 봄으로서 보다 과학적인 화재조사 및 감식 접근방법을 강구하고자 하였다. 재연실험 결과 실험체 2종(석유난로/전기스토브) 모두 양호한 축열 조건이 만들어지지 않는 한 발화위험성은 극히 적은 것으로 나타났지만 탄화의 상태는 각 부위별로 진행되는 것으로 분석되었다. 결국 화재로의 전이는 축열에 의한 발화이므로 최소한 화재장소의 축열 온도조건이 $500^{\circ}C$ 이상일 때 발화되는 것으로 분석되었다. 특히 전기스토브의 발열체인 석영관인 경우 가장 짧은 시간 내(10sec)에 $600^{\circ}C$ 이상의 온도로 급 가열 되어 이때의 열유속은 6.26kW/m2으로 나타나 이는 보온된 PVC케이블이 손상과 함께 인체에는 2도 화상을 입히는 결과를 나타내는 것으로 분석 되었다. 아울러 온도 조건 이외에 거리변화에 따른 열량의 감소분을 나타내는 형태계수(Geometric View Factor)와 화재하중(Fire Load)에 따른 온도 변화도 고려되어야 할 중요한 변수임 알았다. 따라서 이에 관한 세심한 화재조사 및 감식의 매뉴얼이 있어야 할 것으로 사료되며 이러한 실험에 의한 과학적이고 합리적인 노력들이 향후 화재조사 및 감식에 대한 매뉴얼 작성과 이론적 토대를 세우는데 기여하기를 기대한다.

• 한국태양에너지학회 논문집
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• 제37권1호
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• pp.47-57
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• 2017

Solar energy is one of the important renewable energy resources. It can be used for air heating, hot water supply, heat source of desiccant cooling system and so on. And many researches for enhancing efficiency have been conducted because of these various uses of solar thermal energy. This study was performed to investigate the air heating performance of hybrid solar air-water heater that can heat air and liquid respectively or simultaneously and finding method for improving thermal performance of this collector. This collector has both liquid pipe and air channel different with the traditional solar water and air heater. Fins were installed in the air channel for enhancing the air heating performance of collector. Also air inlet & outlet temperature, ambient temperature and solar collector's inner part temperature were confirmed with different air velocity on similar solar irradiance. As a result, temperature of heated air was shown about $43^{\circ}C$ to $60^{\circ}C$ on the $30^{\circ}C$ of ambient temperature and thermal efficiency of solar collector was shown 28% to 73% with respect to air velocity. Also, possibility of improvement of thermal performance of this collector could be ascertained from the heat transfer coefficient calculated from this experiment. Thus, it is considered that the research for finding optimal structure of hybrid solar air-water heater for enhancing thermal performance might be needed to conduct as further study based on the method for improving air heating performance confirmed in this study.

• Nuclear Engineering and Technology
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• 제52권7호
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• pp.1396-1408
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• 2020

Filtered containment venting system (FCVS) is one of the severe accident mitigation systems designed to release containment pressurization to maintain its integrity. The thermal-hydraulic behaviors in FCVSs are important since they affect the operation characteristics of the FCVS. In this study, a representative FCVS was modeled by RELAP5/Mod3.3 code, and the Station BlackOut (SBO) was chosen as an accident scenario. The thermal-hydraulic behaviors of an FCVS during long-term operation with two venting strategies (open-and-close strategy, open-and-non-close strategy) and the sensitivity analysis of important parameters were investigated. The results show that the FCVS can operate up to 250 h with a periodic open-and-close strategy during an SBO. Under the combined effects of steam condensation and water evaporation, the solution inventory in the FCVS increases during the venting phase and decreases during the intermission phase, showing a periodic pattern. Under this condition, the appropriate initial water level is 3-4 m; however, it should be adjusted according to the environment temperature. The FCVS can accommodate a decay heat power of 150-260 kW and may need to feed water for a higher decay heat power or drain water for a lower decay heat power during the late phase. The FCVS can function within an opening pressure range from 450 kPa to 500 kPa and a closing pressure range between 250 kPa and 350 kPa. When the open-and-non-close strategy is adopted, the solution inventory increases quickly in the early venting phase due to steam condensation and then decreases gradually due to the evaporation of water; drying-up may occur in the late venting phase. Decreasing the venting pipe diameter and increasing the initial water level can mitigate the evaporation of the scrubbing solution. These results are expected to provide useful references for the design and engineering application of FCVSs.

• 한국산학기술학회논문지
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• 제20권3호
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• pp.476-482
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• 2019

본 기후변화협약, 온실가스배출규제와 같은 규제적 규약들은 고효율 에너지 기자재 개발과 에너지의 효율적 이용을 촉진하는 촉매로 작용하고 있다. 에너지소비가 큰 분야 중 전열기기가 효율이 좋지 못한 편이다. 전기보일러는 히터에 물을 접촉시켜 순환시키는 방식을 주로 사용하고 있다. 기존 전기보일러를 활용할 경우 물의 미네랄이 고온의 히터와 접촉하여 탄화되어 흡착되는 과정에서 히터의 부식을 촉진시키고 히터의 효율을 저하시킨다. 이러한 이유로 에너지 효율이 높고, 전도나 대류가열보다 피가열물을 균일하게 가열시킬 수 있는 유도가열방식을 보일러에 적용시킨 전기유도보일러가 각광을 받고 있는데, 이 방식은 물이 담겨 있는 보일러 관로를 유도가열방식으로 가열하여 직접가열시 발생하는 문제를 해결시킬 수 있는 대안으로 인정받고 있다. 비교적 오랜 기간 유도가열에 대한 연구가 이루어졌음에도 불구하고 유도가열을 이용한 전열기술에 대한 연구결과는 그리 많지 않은 실정이다. 따라서 본 논문에서는 전기유도보일러의 발열효율을 개선하기 위하여 매개변수연구방법을 통하여 권선의 단면적, 권선의 수 및 권선의 겹수에 의한 영향을 유한요소법을 이용하여 해석하고 발열의 요소가 되고 있는 동손과 철손을 분석하여 발열을 극대화시킬 수 있는 권선설계방법으로 총손실이 최대가 되는 설계점을 찾는 방법을 제시하였다.