• Nuclear Engineering and Technology
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• 제48권1호
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• pp.43-54
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• 2016

In the present paper, development of the three-dimensional (3D) computational code based on Galerkin finite element method (GFEM) for solving the multigroup forward/adjoint diffusion equation in both rectangular and hexagonal geometries is reported. Linear approximation of shape functions in the GFEM with unstructured tetrahedron elements is used in the calculation. Both criticality and fixed source calculations may be performed using the developed GFEM-3D computational code. An acceptable level of accuracy at a low computational cost is the main advantage of applying the unstructured tetrahedron elements. The unstructured tetrahedron elements generated with Gambit software are used in the GFEM-3D computational code through a developed interface. The forward/adjoint multiplication factor, forward/adjoint flux distribution, and power distribution in the reactor core are calculated using the power iteration method. Criticality calculations are benchmarked against the valid solution of the neutron diffusion equation for International Atomic Energy Agency (IAEA)-3D and Water-Water Energetic Reactor (VVER)-1000 reactor cores. In addition, validation of the calculations against the $P_1$ approximation of the transport theory is investigated in relation to the liquid metal fast breeder reactor benchmark problem. The neutron fixed source calculations are benchmarked through a comparison with the results obtained from similar computational codes. Finally, an analysis of the sensitivity of calculations to the number of elements is performed.

• Journal of Advanced Marine Engineering and Technology
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• 제38권4호
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• pp.456-462
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• 2014

본 논문에서는 시설물의 효율적인 유지보수를 지원하기 위하여 시설물을 구성하는 부품의 고장 영향 및 교체 주기 알람 기능을 제공하는 시설물 관리 시스템의 개발에 관한 내용을 다룬다. 이를 위해 시설물의 BOM을 활용하여 시설물을 구성하는 각 부품에 가중치를 부여하여 부품별 중요도를 계산하고 부품 간의 관계를 구조화하였다. 또한 BOM에 FMECA 기법을 도입하여 시설물을 구성하는 각 부품별 고장 원인 및 영향 등을 도출하였으며, 시설물에서의 위험 우선순위를 구하기 위한 심각도, 발생도, 검출도에 관한 기준을 정의하였다. 이러한 내용을 반영하여 웹 기반 시설물 관리 시스템을 개발하였으며 이를 통해 제안하는 방법의 유용성을 실험하였다. 개발한 시스템은 향후 시설물의 관리뿐만 아니라 선박 및 해양플랜트의 유지보수 등 여러 분야에 적용될 수 있을 것으로 기대된다.

• Nuclear Engineering and Technology
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• 제20권1호
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• pp.27-34
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• 1988

1990년 중반에는 우리나라 모든 원자력 발전소의 사용 후 핵연료 저장조의 용량부족이 예견된다. 따라서 조밀화 집합체로 저장하는 MDR 방법을 가장 저장용량이 적은 9, 10호기 원전의 저장용량을 확장시키는데 적용하고자 하였다. 이러한 방법을 채택할 때 9,10원전의 사용후 핵연료 저장조의 안전성을 확인하기 위해 격자 간격과 저장통 두께를 변화시키면서 중성자 증배계수를 AMPX-KENO IV코드로 계산하였다. 그리고 이 전산체제를 검증하기 위해 1981년 B & W에서 실시한 임계실험에 대하여 검증계산을 수행하였다. 또한 가상사고로써 malposition사고도 모사하였다. 그 결과, 원전 9, 10호기의 핵연료 조밀화 저장법은 안전하며, 설비 및 냉각공간을 고려하여 9/3 노심분을 27/3 노심분의 저장 용량으로 확장할 수 있을 것이다.

• Nuclear Engineering and Technology
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• 제49권1호
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• pp.1-5
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• 2017

The heavy water zero power reactor (HWZPR), which is a critical assembly with a maximum power of 100 W, can be used in different lattice pitches. The last change of core configuration was from a lattice pitch of 18-20 cm. Based on regulations, prior to the first operation of the reactor, a new core was simulated with MCNP (Monte Carlo N-Particle)-4C and WIMS (Winfrith Improved Multigroup Scheme)-CITATON codes. To investigate the criticality of this core, the effective multiplication factor ($K_{eff}$) versus heavy water level, and the critical water level were calculated. Then, for safety considerations, the reactivity worth of $D_2O$, the reactivity worth of safety and control rods, and temperature reactivity coefficients for the fuel and the moderator, were calculated. The results show that the relevant criteria in the safety analysis report were satisfied in the new core. Therefore, with the permission of the reactor safety committee, the first criticality operation was conducted, and important physical parameters were measured experimentally. The results were compared with the corresponding values in the original core.

• Nuclear Engineering and Technology
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• 제50권1호
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• pp.18-24
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• 2018

This study proposes a new method of analyzing the burnup credit in boiling water reactor spent fuel assemblies against various operating parameters. The operating parameters under investigation include fuel temperature, axial burnup profile, axial moderator density profile, and control blade usage. In particular, the effects of variations in one and two operating parameters on the curve of effective multiplication factor ($k_{eff}$) versus burnup (B) are, respectively, the so-called single and compound effects. All the calculations were performed using SCALE 6.1 together with the Evaluated Nuclear Data Files, part B (ENDF/B)-VII238-neutron energy group data library. Furthermore, two geometrical models were established based on the General Electric (GE)14 $10{\times}10$ boiling water reactor fuel assembly and the Generic Burnup-Credit (GBC)-68 storage cask. The results revealed that the curves of $k_{eff}$ versus B, due to single and compound effects, can be approximated using a first degree polynomial of B. However, the reactivity deviation (or changes of $k_{eff}$, ${\Delta}k$) in some compound effects was not a summation of the all ${\Delta}k$ resulting from the two associated single effects. This phenomenon is undesirable because it may to some extent affect the precise assessment of burnup credit. In this study, a general formula was thus proposed to express the curves of $k_{eff}$ versus B for both single and compound effects.

• Nuclear Engineering and Technology
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• 제24권3호
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• pp.319-328
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• 1992

일차원 구에서 유한요소법의 Galerkin formulation이 일차형태의 단일 에너지 중성자 수송방정식의 적분법에 적용되었다. 구분적으로 1차 혹은 2차인 Lagrange 다항식들이 선형대수 방정식들의 집합을 만들기 위해 적분법에 있는 각의존 중성자속(angular flux)에 대하여 활용되었다. 수치해석이 균질구에서의 임계문제와 비균질구에서의 scalar flux 분포에 대해서 행해졌다. 공간과 각에 대하여 연속적인 유한요소를 사용한 균질구에서의 임계문제에 대한 유한요소법의 결과들은 이론적인 해들자 비교되었다. 비균질 문제에서는 각자 공간에 대하여 불연속 유한요소를 사용하여 구한 scalar flux 분포는 ANISN code에 의한 계산결과와 잘 일치하였다.

• 시스템엔지니어링학술지
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• 제12권1호
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• pp.105-112
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• 2016

An aircraft must be designed to minimize system failure rate for obtaining the aircraft safety, because the aircraft system failure causes a fatal accident. The safety of the aircraft system can be predicted by analyzing availability, reliability, and maintainability of the system. In this study, the reliability and the maintainability of the hydraulic system are analysed except the availability, and therefore the reliability and the maintainability analysis process and the results are presented for a helicopter hydraulic system. For prediction of the system reliability, the failure rate model presented in MIL-HDBK-217F is used, and MTBF is calculated by using the Part Stress Analysis Prediction and quality/temperature/environmental factors described in NPRD-95 and MIL-HDBK-338B. The maintainability is predicted by FMECA(Failure Mode, Effect & Criticality Analysis) based on MIL-STD-1629A.

• Nuclear Engineering and Technology
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• 제55권11호
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• pp.4228-4237
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• 2023

The Improved Deterministic Truncation of Monte Carlo (iDTMC) is a powerful acceleration and variance reduction scheme in the Monte Carlo analysis. The concept of the iDTMC method and correlated sampling-based real variance estimation are briefly introduced. Moreover, the application of the iterative scheme to the correlated sampling is discussed. The iDTMC method is utilized in a 3-dimensional small modular reactor (SMR) model problem. The real variances of burnup-dependent criticality and power distribution are evaluated and compared with the ones obtained from 30 independent iDTMC calculations. The impact of the inactive cycles on the correlated sampling is also evaluated to investigate the consistency of the correlated sample scheme. In addition, numerical performances and sensitivity analysis on the real variance estimation are performed in view of the figure of merit of the iDTMC method. The numerical results show that the correlated sampling accurately estimates the real variances with high computational efficiencies.

• Nuclear Engineering and Technology
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• 제53권5호
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• pp.1464-1478
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• 2021

Selective Production of Exotic Species is an innovative plant for advanced nuclear physic studies. A radioactive beam, generated by using an UCx target-ion source system, is ionized, selected and accelerated for experimental objects. Very high vacuum conditions and appropriate safety systems to storage exhaust gases are required to avoid radiological risk for operators and people. In this paper, Failure Mode, Effects, and Criticality Analysis of a preliminary design of high activity gas recovery system is performed by using a modified Fuzzy Risk Priority Number to rank the most critical components in terms of failures and human errors. Comparisons between fuzzy approach and classic application allow to show that Fuzzy Risk Priority Number is able to enhance the focus of risk assessments and to improve the safety of complex and innovative systems such as those under consideration.

• 한국안전학회지
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• 제39권2호
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• pp.75-86
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• 2024

Hydrogen has been selected as one of the key technologies for reducing CO₂ emissions to achieve carbon neutrality by 2050. However, hydrogen safety issues should be fully guaranteed before the commercial and widespread utilization of hydrogen. Here, a bow-tie risk assessment is conducted for the hydrogen fuel supply system in a gas turbine power plant, which can be a mass consumption application of hydrogen. The bow-tie program is utilized for a qualitative risk assessment, allowing the analysis of the causes and consequences according to the stages of accidents. This study proposed an advanced bow-tie method, which includes the barrier criticality matrix and visualized maps of quantitative risk reduction. It is based on evaluating the importance of numerous barriers for the extent of their impact. In addition, it emphasizes the prioritization and concentrated management of high-importance barriers. The radar chart of a bow tie allows the visual comparison of risk levels before/after the application of barriers (safety measures). The risk reduction methods are semi-quantitatively analyzed utilizing the criticality matrix and radar chart, and risk factors from multiple aspects are derived. For establishing a secure hydrogen fuel storage system, the improvements suggested by the bow-tie risk assessment results, such as 'Ergonomic equipment design to prevent human error' and 'Emergency shutdown system,' will enhance the safety level. It attempts to contribute to the development and enhancement of an efficient safety management system by suggesting a method of calculating the importance of barriers based on the bow-tie risk assessment.