• Nuclear Engineering and Technology
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• 제55권9호
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• pp.3409-3416
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• 2023

Licensing the next-generation of nuclear reactor designs requires extensive use of Modeling and Simulation (M&S) to investigate system response to many operational conditions, identify possible accidental scenarios and predict their evolution to undesirable consequences that are to be prevented or mitigated via the deployment of adequate safety barriers. Deep Learning (DL) and Artificial Intelligence (AI) can support M&S computationally by providing surrogates of the complex multi-physics high-fidelity models used for design. However, DL and AI are, generally, low-fidelity 'black-box' models that do not assure any structure based on physical laws and constraints, and may, thus, lack interpretability and accuracy of the results. This poses limitations on their credibility and doubts about their adoption for the safety assessment and licensing of novel reactor designs. In this regard, Physics Informed Neural Networks (PINNs) are receiving growing attention for their ability to integrate fundamental physics laws and domain knowledge in the neural networks, thus assuring credible generalization capabilities and credible predictions. This paper presents the use of PINNs as surrogate models for accidental scenarios simulation in Nuclear Power Plants (NPPs). A case study of a Loss of Heat Sink (LOHS) accidental scenario in a Nuclear Battery (NB), a unique class of transportable, plug-and-play microreactors, is considered. A PINN is developed and compared with a Deep Neural Network (DNN). The results show the advantages of PINNs in providing accurate solutions, avoiding overfitting, underfitting and intrinsically ensuring physics-consistent results.

• Korean Chemical Engineering Research
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• 제54권4호
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• pp.582-585
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• 2016

ALOHA, PHAST 등의 사고영향평가 프로그램들을 활용하여 전기 전자 등의 산업 분야에서 많이 쓰이며 인체에 유독한 HF 가 누출되는 사고의 발생 시 대피해야 하는 초기 이격거리에 대한 연구를 수행하였다. 다양한 공정조건과 상태로 저장되어 있는 HF의 사고시나리오를 간단하게 정의하기는 어렵지만 화학물질안전원의 지침대로 10분 내 총 저장량 누출을 최악의 시나리오, 결속된 배관의 일부 파열을 대안의 시나리오로 하여 비상상황을 가정하였다. 그로부터 사고모델링의 시작인 누출속도 산정을 한 후 보수적으로 확산모델링을 적용하여 밤과 낮의 대표적인 기상상태에 따라 일반적인 대피거리로 권고되는 ERPG-2 농도가 도달하는 끝점거리를 구하여 현장에서 신속하게 쓸 수 있는 간단한 그래프와 같은 형태로 제시하였다. 이는 유사시를 대비한 사전적인 성격의 그래프로 화학물질 누출사고 시 신속한 비상대응계획을 수립하는 데 도움이 될 것이다.

• International Journal of Naval Architecture and Ocean Engineering
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• 제12권1호
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• pp.241-257
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• 2020

The rapid proliferation of oil/gas drilling and wind turbine installations with jack-up rig-formed structures increases structural safety requirements, due to the greater risks of operational collisions during use of these structures. Therefore, current industrial practices and regulations have tended to increase the required accidental collision design loads (impact energies) for jack-up rigs. However, the existing simplified design approach tends to be limited to the design and prediction of local members due to the difficulty in applying the increased uniform impact energy to a brace member without regard for the member's position. It is therefore necessary to define accidental load estimation in terms of a reasonable collision scenario and its application to the structural response analysis. We found by a collision probabilistic approach that the kinetic energy ranged from a minimum of 9 MJ to a maximum 1049 MJ. Only 6% of these values are less than the 35 MJ recommendation of DNV-GL (2013). This study assumed and applied a representative design load of 196.2 MN for an impact load of 20,000 tons. Based on this design load, the detailed design of a leg structure was numerically verified via an FE analysis comprising three categories: linear analysis, buckling analysis and progressive collapse analysis. Based on the numerical results from this analysis, it was possible to predict the collapse mode and position of each member in relation to the collision load. This study provided a collision strength assessment between attendant vessels and a jack-up rig based on probabilistic collision scenarios and nonlinear structural analysis. The numerical results of this study also afforded reasonable evaluation criteria and specific evaluation procedures.

• 한국대기환경학회지
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• 제15권5호
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• pp.687-696
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• 1999

Characteristics of four publicly-available accidental release models, ALOHA, SLAB, HGSYSTEM, and DEGADIS, are compared. These models are world-widely used and recently recommended by the Chemical Dispersion and Consequence Assessment(CDCA) Working Group of the United States as models applicable to generally broad safety-basis documentation applicatons. Four release scenarios are assumed by referring to the usage and storage conditions of toxic substances in the field as well as the USEPA model guideline(1993). Sensitivity of impact radius by varying meteorological conditions is tested in typical and worst-case meteorological conditions. The results show that ALOHA generally gives conservative estimates and the results from HGSYSTEM are sensitive to variations in meteorological conditions.

• 한국대기환경학회지
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• 제15권2호
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• pp.151-158
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• 1999

Offsite consequences resulting form worst-case scenarios involving release of toxic substances in the Yochon area were estimated using the ALOHA(Areal Locations of Hazardous Atmospheres) model. Eight toxic substances, including NH3, were considered; five were toxic gases and three were toxic liquids at ambient temperature. For toxic gases, the entire quantity was assumed to be released at a constant rate during a 10-minute period. For toxic liquids, the entire quantity stored in the tank was assumed to be spilled and spread and spread instantaneously to form a pool with a depth of 1cm, and then evaporated over some period of time. Except for phosgene and toluene 2,4-diisocyanate, for which concentration levels corresponding to human health effects are very low, average distances of the area at risk of adverse health effects for a 1- tom release were predicted to be $2.3{\pm}1.1 km$ for the worst-case meteorological conditions and $0.93{\pm}0.69km$ under typical meteorological conditions of the Yochon are. Because a large number of people were predicted to be affected in the current analysis, refined analyses considering both realistic accident scenarios and topographic effects were warranted.

• Nuclear Engineering and Technology
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• 제53권6호
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• pp.1858-1868
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• 2021

Resisting an accidental impact of large commercial aircrafts is an important aspect of advanced nuclear power plant (NPP) design. Especially after the 9·11 event, some regulations were enacted, which required the design of NPPs should consider the accidental impact of large commercial aircrafts. Normal working of equipment is important for stopping reactor under an impact when an NPP is in operation. However, there is a lack of reliable analysis and research on the impact test of nuclear prototype equipment. Therefore, in order to study the response of the equipment under high acceleration impact, a centrifugal pump is selected as the research object to perform the impact test. A horizontal half-sinusoidal pulse wave was applied to the working pump. The test results show that the horizontal response of the motor and flange is greater compared to other parts, as well as the vertical response of the coupling. The stress response of the pump body support and motor support is high, hence these parts should be considered in the design of the pump. Finally, combined with the damage and stress evaluation results of the pump under different amplitudes, the ultimate impact acceleration that the pump can withstand is given.

• Journal of Radiation Protection and Research
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• 제41권4호
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• pp.368-372
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• 2016

Background: Methodologies for a series of radiological consequence assessments show a distinctive difference according to the design principles of the original nuclear suppliers and their technical standards to be imposed. This is due to the uncertainties of the accidental source term, radionuclide behavior in the environment, and subsequent radiological dose. Both types of PWR and PHWR are operated in Korea. However, technical standards for evaluating atmospheric dispersion have been enacted based on the U.S. NRC's positions regardless of the reactor types. For this reason, it might cause a controversy between the licensor and licensee of a nuclear power plant. Materials and Methods: It was modelled under the framework of the NRC Regulatory Guide 1.145 for light-water reactors, reflecting the features of heavy-water reactors as specified in the Canadian National Standard and the modelling features in MACCS2, such as atmospheric diffusion coefficient, ground deposition, surface roughness, radioactive plume depletion, and exposure from ground deposition. Results and Discussion: An integrated accident consequence assessment code, ACCESS (Accident Consequence Assessment Code for Evaluating Site Suitability), was developed by taking into account the unique regulatory positions for reactor types under the framework of the current Korean technical standards. Field tracer experiments and hand calculations have been carried out for validation and verification of the models. Conclusion: The modelling approaches of ACCESS and its features are introduced, and its applicative results for a hypothetical accidental scenario are comprehensively discussed. In an applicative study, the predicted results by the light-water reactor assessment model were higher than those by other models in terms of total doses.

• 한국가스학회지
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• 제10권1호
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• pp.26-31
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• 2006

LPG충전시설에 설치된 각종 안전장치의 유효성을 평가하기 위해 하역작업 중 탱크로리의 비등액체팽창증기폭발(BLEVE, Boiling Liquid Expanding Vapor Explosion) 시나리오에 대해 빈도분석을 수행하였으며, 분석방법으로는 정량적인 분석법인 결함수목분석(Fault Tree Analysis)법을 사용하였다. 안전장치의 유효성은 안전장치의 부착여부와 용량변화에 따른 빈도변화를 관찰함으로써 간접적으로 평가하였다. 이 분석을 통해 허용 가능한 위험수준을 만족하기 위해 필수적인 안전장치와 설치 우선순위를 도출할 수 있었다.

• Nuclear Engineering and Technology
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• 제54권12호
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• pp.4422-4430
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• 2022

Studying the effects of gamma radiation on the instrumentation and control (I&C) system of a nuclear power plant is critical to the successful and reliable operation of the plant. In the accidental scenario, the adverse environment of ionizing radiation affects the performance of the I&C system and it leads to inaccurate and incomprehensible results. This paper reports the effects of gamma radiation on the AT89C51RD2, a commercial-off-the-shelf 8-bit high-performance flash microcontroller. The microcontroller, selected for the device under test for this study is used in the remote terminal unit for a nuclear power plant. The custom circuits were made to test the microcontroller under different gamma doses using a ⁶⁰Co gamma source in both ex-situ and in-situ modes. The device was exposed to a maximum dose of 1.5 kGy. Under this hostile environment, the performance of the microcontroller was studied in terms of device current and voltage changes. It was observed that the microcontroller device can operate up to a total absorbed dose of approximately 0.6 kGy without any failure or degradation in its performance.

• 한국가스학회지
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• 제22권1호
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• pp.18-25
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• 2018

산업의 발전에 따라 화학물질 중 독성물질의 종류와 사용량도 함께 증가하였고 이에 따라 산업현장에서의 사고 발생 가능성과 사고 영향성도 높아질 것으로 예측된다. 특히 독성물질의 누출은 인명 및 인근 지역의 환경에 치명적인 피해를 주기 때문에 누출사고 시 대피 및 안전거리 계산은 매우 중요하다. 이에 본 연구에서는 액체성상의 독성물질의 경우 알고리즘을 새롭게 제시하였으며, 벤젠 및 아크릴로나이트릴을 선정하여 영향범위에 대하여 알아보고자 한다. 시나리오는 화학물질 안전원의 지침대로 최악의 시나리오 분석 시 10분간 전량 방출할 경우와, 즉시 방출하여 독성 액체가 방류벽을 범람할 경우로 하였으며 대안의 시나리오는 저장용기의 연결된 배관의 부분 파열로 인하여 누출공이 생긴 경우로 하였다. 각각의 시나리오에서 방류벽의 유무를 중심으로 연구를 진행하였으며 그로부터 기상 및 지형조건에 따라 ALOHA(Areal Locations of Hazardous Atmospheres) 프로그램을 사용하여 ERPG-2(Emergency Response Planning Guideline) 농도의 끝점 도달거리를 알아보았다. 그 결과 데이터를 통하여 그래프 및 회귀식으로 나타내었고, 이러한 자료는 피해범위를 예측함으로써 비상상황 발생 시 비상대책 자료로 활용될 수 있기를 기대한다.