• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.16 no.1
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• pp.56-64
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• 2020

The safety related heat exchangers have been evaluated for their performance during the operation of the nuclear power plant. The evaluation program for the safety related heat exchanger was developed in 2010 and used by KHNP based on EPRI TR-10739 algorithms. The spend fuel pool heat exchanger is one of the safety related heat exchanger in the nuclear power plant and also evaluated for their performance. Recently the performance evaluation for the spend fuel pool heat exchanger was not available because of the decreased heat in the spend fuel pool due to the long term overhaul. This paper analyzes the main cause of evaluation failure in the evaluation process and suggests the criteria for the heat exchanger performance evaluation during the long term overhaul.

• Nuclear Engineering and Technology
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• v.35 no.6
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• pp.581-595
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• 2003

Transport lattice codes require the resonance integral tables for the resonant nuclides where the resonance integral is a function of the background cross section and can be prepared through a special program solving the slowing down equation. In case the cross section libraries do not include the resonance integral table for the resonant nuclides, the computational prediction produces a large error. We devised a new method using a Monte Carlo calculation for the effective resonance cross sections to solve this problem provisionally. We extended this method to obtain the resonance integral table for general purpose. The MCNP code is used for the effective resonance integrals and the LIBERTE code for the effective background cross sections. We modified the HELIOS library with the effective cross sections and the resonance integral tables obtained by the newly developed Monte Carlo method, and performed sample calculations using HELIOS and LIBERTE. The results showed that this method is very effective for the resonance treatment.

• Nuclear Engineering and Technology
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• v.31 no.6
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• pp.66-82
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• 1999

The national long-term R&D program, updated in 1997, requires Korea Atomic Energy Research Institute(KAERI) to complete by the year 2006 the basic design of Korea Advanced Liquid Metal Reactor(KALIMER), along with supporting R&D work, with the capability of resolving the issue of spent fuel storage as well as with significantly enhanced safety. KALIMER is a 150 MWe pool-type sodium cooled prototype reactor that uses metallic fuel. The conceptual design is currently under way to establish a self-consistent design meeting a set of major safety design requirements for accident prevention. Some of the current emphasis includes those for inherent and passive means of negative reactivity insertion and decay heat removal, high shutdown reliability, prevention of and protection from sodium chemical reaction, and high seismic margin, among others. All of these requirements affect the reactor design significantly and involve extensive supporting R&D programs. This paper summarizes some of the results of conceptual engineering and design analyses performed for the safety of HAMMER in the area of inherent safety, passive decay heat removal, sodium water reaction, and seismic isolation.

• Proceedings of the Computational Structural Engineering Institute Conference
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• 2004.10a
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• pp.312-319
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• 2004

This paper is mai y focused to develop new concrete material model such as ultimate failure surface in compression-compression region, hardening rule and cracking criteria which are basically used in the nonlinear finite element analysis of nuclear prestressed concrete containment building. From the Kepri's experimental results, failure surface of the concrete based on the elasto-plastic material model is modified and new cracking criteria is proposed. Nonlinear FE analysis program using a new material model is implemented to analysis plane concrete. Finally, numerical simulation to compare the performance of the new material model with experimental results is employed. The numerical results by the proposed model in this study agree very well with the experimental data.

• Proceedings of the KIEE Conference
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• 2001.05a
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• pp.10-13
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• 2001

이 연구에서는 2010년도 154kV, 34skV 및 765kV 송전 계통을 대상으로 전력 조류 계산 및 과도 안정도 해석 프로그램을 개발하여 새로 건설되는 대용량 원전 전력계통의 안전성을 평가하였다. 개발된 프로그램은 실계통 전체 송전망 및 전국 발전기 모선을 대상으로 전력 조류계산, 3상 단락 고장계산, 과도안정도 계산을 위하여 통합된 형태의 MS-Windows 기반 프로그램 패키지로 개발되었다. 프로그램의 효용성 검증을 위한 사례연구로 2010년의 송전계통에 대한 전력 조류를 계산하여 과도안정도를 해석한 결과 대용량 원전 전력계통은 극단적인 경우를 제외하고는 과도적으로 안정함을 확인하였다.

• Proceedings of the KIEE Conference
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• 2000.11a
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• pp.26-28
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• 2000

국내 원전 소외 전력 계통과 실계통 대상과도 안정도 해석은 대형 해석프로그램인 PSS/E 등에 의존하여 해석해왔으나, 규제 관점에서 보수적인 과도 안정도를 해석할 수 있는 간이 프로그램을 개발하여, 규제 요건 적합성 여부를 확인할 수 있게 하였다. 본 프로그램은 원전 전력계통에 적용되는 품질요건을 적용하지 않는 제어기에 대하여 신뢰를 두지 않았으며, 송전망 보호 계통-보호계전기 및 차단기-에 의존하여 3상 평형 단락 고장 조건 과도 안정도를 해석한 결과, 과도적인 안정도 판별에 적합함을 확인하였다. 가혹한 송전망 조건 아래 원전 발전기의 고장제거 지연시간에 대한 민감도 분석을 통하여 취약한 원전 부지 및 원전 발전기를 확인할 수 있다.

• Journal of Mechanical Science and Technology
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• v.17 no.9
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• pp.1297-1315
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• 2003

This study deals with the free vibration of two identical circular plates coupled with a bounded or unbounded fluid. An analytical method based on the finite Fourier-Bessel series expansion and Rayleigh-Ritz method is suggested. The proposed method is verified by the finite element analysis using commercial program with a good accuracy The case of bounded or unbounded fluid is studied for the effect on the vibration characteristics of two circular plates. Also, the effect of gap between the plates on the fluid-coupled natural frequencies is investigated.

• Proceedings of the Korean Operations and Management Science Society Conference
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• 1996.04a
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• pp.217-220
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• 1996

This study presents a R&D performance monitoring system (RDMS) that is applicable for managing nuclear program in KAERI. The prime goal of RDMS is to furnish project manager with reliable and accurate information on status of progress, performance and resource allocation, and attain traceability and visibility of project implementation for effective project management. In this study, the work breakdown structure (WBS) as the governing factor for integration of scope, schedule, resource data was derived, and the above parameters were loaded personal computer. A RDMS is comprised of about 12,000 R&D activities of the 16 goverment-led projects. The Primavera software was used to monitor the progress, evaluate the performance and analyze the resource distribution to activities.

• Proceedings of the KSPS conference
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• 2005.04a
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• pp.3-7
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• 2005

This research is for finding prototypes and characteristics of intonation found in ${\ulcorner}$-a/e, $t{\int}ijo$<${\lrcorner}$ and ${\ulcorner}$p/simnida${\lrcorner}$ among modern Korean predicate statements by constructing spoken corpus based on the current radio broadcast. So the result of the study is as follows. : (1) The construction of the balanced spoken corpus and the standard for boundary determination of rhythm are needed for the intonation model of speech synthesis. (2) Korean intonation units have the splited word tone which includes the nuclear tone and the pre-nuclear tone makes unclear tone more detailed. (3) I made man and woman intonation models individually through t-test of SPSS. (4) The standard intonation model is devided '-ajo'type and '-nida'type

• Transactions of the Korean Society of Mechanical Engineers A
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• v.33 no.11
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• pp.1239-1243
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• 2009

To evaluate the structural integrity of the nuclear seismic category penetration cooling water pump under the seismic service conditions the seismic analysis was performed in accordance with IEEE-STD-344 code. The finite element computer program, ANSYS, Version 10.0, is used to perform both a mode frequency analysis and an equivalent static seismic analysis of the pump assembly. The mode frequency analysis results show the fundamental natural frequency is greater than 33 Hz and does not exist in seismic range, thus justifying the use of the static analysis. The stresses resulted from various loadings and their combinations are within the allowable limits specified in the above mentioned IEEE code. The results of the seismic evaluation fully satisfied the structural acceptance criteria of the IEEE code. Accordingly the structural integrity on the pump assembly was proved.