• Nuclear Engineering and Technology
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• 제53권6호
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• pp.1869-1877
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• 2021

This paper presents the neutron dose rate analysis of the new CONSTOR® RBMK-1500/M2 storage cask intended for the spent nuclear fuel storage at Ignalina Nuclear Power Plant in Lithuania. These casks are designed to be stored in a new "closed" type interim storage facility, with the capacity to store up to 202 CONSTOR® RBMK-1500/M2 casks. In 2016 y, the "hot trials" of this new facility were conducted and 10 CONSTOR® RBMK-1500/M2 casks loaded with the spent nuclear fuel were transported to the dedicated storage places in this facility. During "hot trials", the dose rate measurements of the CONSTOR® RBMK-1500/M2 casks were performed as the dose rate is one of the critical parameter to control and it must be below design (and safety) criteria. Therefore, having the actual data of the spent nuclear fuel characteristics, the neutron dose rate modeling of the CONSTOR® RBMK-1500/M2 cask loaded with this particular fuel was also performed. Neutron dose rate modeling was performed using MCNP 5 computer code with very detailed geometrical representation of the cask and the fuel. The obtained modeling results were compared with the measurement results and it was revealed, that modeling results are generally in good agreement with the measurements.

• Nuclear Engineering and Technology
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• 제53권8호
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• pp.2445-2453
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• 2021

Since the nuclear data forms a vital component in reactor physics computations, the nuclear community needs processing codes as tools for translating the Evaluated Nuclear Data Files (ENDF) to simulate nuclear-related problems such as an ACE format that is used for MCNP. Errors, inaccuracies or discrepancies in library processing may lead to a calculation that disagrees with the experimentally measured benchmark. This paper provides an overview of the processing and preparation of ENDF/B-VIII.0 incident neutron data with NECP-Atlas and NJOY codes for implementation in the MCNP code. The resulting libraries are statistically inter-compared and tested by conducting benchmark calculations, as the mutualcomparison is a source of strong feedback for further improvements in processing procedures. The database of the benchmark experiments is based on a selection taken from the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP handbook) and those proposed by Russell D. Mosteller. In general, there is quite good agreement between the NECP-Atlas1.2 and NJOY21^(1.0.0.json) results with no substantial differences, if the correct input parameters are used.

• Nuclear Engineering and Technology
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• 제6권4호
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• pp.253-259
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• 1974

펄스된 이온화상자(PIC)의 출력 신호전압이 전자밀도가 $10^{13}$-$10^{17}$ m$^{-3}$인 플라즈마들에 대해 측정되었다. 이 PIC 기술치 한 응용으로서 이체 재결합 상수들이 PIC의 출력신호전압으로 측정된 전자밀도들로부터 구해졌다. 압력의 함수로서의 이 값들은 이론적인 예측과 잘 부합하며, 수치는 300$^{\circ}$K에 있는 1-10기압의 $^3$He 플라즈마에 대해 5$\times$$10^{-14}$ -3$\times$$10^{-13}$ ㎥/sec의 범위에 있다.

• Nuclear Engineering and Technology
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• 제55권12호
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• pp.4395-4407
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• 2023

Bubble columns are widely encountered in several industries, especially in the field of nuclear safety. The Eulerian-Eulerian and the Eulerian-Lagrangian methods are commonly used to investigate bubble columns. Eulerian approaches require additional tasks such as strict volume conservation at the interface and a predefined well-structured grid. In contrast, the Lagrangian approach can be easily implemented. Hence, we introduce a fully Lagrangian approach for the simulation of bubble columns using the discrete bubble model (DBM) and moving particle semi-implicit (MPS) methods. Additionally, we propose a rigorous method to estimate the volume fraction accurately, and verified it through experimental data and analytical results. The MPS method was compared with the experimental data of Dambreak. The DBM was verified by analyzing the terminal velocity of a single bubble for each bubble size. It agreed with the analytical results for each of the four drag correlations. Additionally, the improved method for calculating the volume fraction showed agreement with the Ergun equation for the pressure drop in a packed bed. The implemented MPS-DBM was used to simulate the bubble column, and the results were compared with the experimental results. We demonstrated that the MPS-DBM was in quantitative agreement with the experimental data.

• 핵의학기술
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• 제26권1호
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• pp.33-37
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• 2022

¹⁸F-FBB 판독은 회백질과 백질의 신호강도를 육안으로 비교하여 이루어진다. 정량화된 영상분석을 판독과 비교하여 영상분석의 유용성을 평가하고자 한다. 환자는 판독결과를 기준으로 음성과 양성을 100명씩 나누었고 FBB 300 MBq 주입하고 90분 뒤 20분간 촬영했다. 장비는 Discovery 600 (GE Healthcare, MI, USA)을 사용하였다. 제조사에서 제공하는 아밀로이드 판독 기준을 근거하여 4개의 관심영역을 설정하였다. 영상분석은 각 SUVmean을 소뇌로 나누어 SUVr를 산출하고 전체 영역에서의 평균 SUVr로 진행하였다. 통계분석은 ROC Curve를 통한 Cutoff 도출과 독립표본 t-test의 그룹간 차이, 그리고 Kappa test를 통한 판독결과와 일치도를 분석하였다. 전체 영역에서의 평균 SUVr의 Cutoff는 1.23으로 나왔다. Cutoff를 사용한 판독결과와 일치도는 음성에서 95/100 (95 %), 양성에서 92/100 (92 %)로 나왔다. t-test 결과 그룹 간에 통계적으로 유의한 차이가 있었고(P < 0.05) Kappa 통계 결과 0.867로 높은 일치도를 나타냈다(P < 0.05). 영상분석의 결과가 통계적으로 유의하며 판독결과에도 높은 일치도를 보여 주었다. 추가적으로 FBB 영상분석은 아밀로이드가 축적된 부위를 3D 매핑하여 볼 수 있고 위치추정이 가능하며 정량분석 결과를 세분화하여 볼 수 있다. 정량화된 FBB 영상분석을 보조지표로 활용한다면 판독에 도움이 될 것으로 사료된다.

• 산업진흥연구
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• 제5권3호
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• pp.123-134
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• 2020

본 연구는 탈냉전이후 역대 한국정부의 북핵전략내용들을 규명하고, 동일시기 한반도에 영향을 준 미국의 B. 클린턴과 G.W.부시 행정부의 대북핵정책과 북한의 핵전략 및 전술이 한국정부의 북핵전략에 어떠한 인과론적 결과를 파생하였는지 상호연계·분석하여 향후의 대응방안을 제시하는데 있다. 탈냉전직후인 1991년 12월 13일 남북한이 공동 합의한 '남북기본합의서'는 한국이 남북관계를 주도해 가는 토대를 마련해 주었고, 북핵해결의 기점이라 하는 '한반도비핵화선언'은 냉전종식에 대한 미국의 '해외전술핵무기폐기선언'과 직결되는 일련의 조치로, 냉전해체후 국제질서 재편과정의 파생물이자 북한의 교묘한 핵전략에 말려든 오판의 산물이었다. 이후 김영삼의 문민정부-->김대중정부의 햇볕정책-->노무현정부의 평화·번영정책--> 이명박 정부의 상생·공영정책과 비핵·개방·3000 전략은 남북관계발전을 정부정책의 제일기조로 삼고 제시한 정책적 모토이고 추진과정에서 방법상의 차이가 있었다. 그러나 북핵문제대응에 대한 공통적 측면은 북핵문제해결을 위한 주도적이고 적극적인 대응책 마련과 실행의 노력보다는 국제기구나 다자적국제체제 및 미국역할에대한 기대심리가 지대했음을 인지할 수 있었다. 본 연구에서는 이의 미흡한 점을 보강하기 위한 결론적 제안으로 일치단결된 국민의식으로 북핵폐기를 위한 단호한 대전략(大戰略)수립과, 북핵문제해결을 위한 다자협의체제와 국제레짐의 공조(共助)를 통한 보다 쇄신되고 강력한 미래의 역할주문과 한국의 역대정부에서 이룩한 남북한 5대합의문의 재보강을 통한 확대된 억지책(extended deterrence)강구를 제언하였다.

• Nuclear Engineering and Technology
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• 제45권4호
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• pp.427-438
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• 2013

In this paper we discuss spent fuel management options in the Republic of Korea (ROK) from two interrelated perspectives: Centralized dry cask storage and spent fuel pyroprocessing and burning in sodium fast reactors (SFRs). We argue that the ROK will run out of space for at-reactors spent fuel storage by about the year 2030 and will thus need to transition centralized dry cask storage. Pyroprocessing plant capacity, even if approved and successfully licensed and constructed by that time, will not suffice to handle all the spent fuel discharged annually. Hence centralized dry cask storage will be required even if the pyroprocessing option is successfully developed by 2030. Pyroprocessing is but an enabling technology on the path leading to fissile material recycling and burning in future SFRs. In this regard we discuss two SFR options under development in the U.S.: the Super Prism and the Travelling Wave Reactor (TWR). We note that the U.S. is further along in reactor development than the ROK. The ROK though has acquired more experience, recently in investigating fuel recycling options for SFRs. We thus call for two complementary joint R&D project to be conducted by U.S. and ROK scientists. One leading to the development of a demonstration centralized away-fromreactors spent fuel storage facility. The other involve further R&D on a combined SFR-fuel cycle complex based on the reactor and fuel cycle options discussed in the paper.

• Nuclear Engineering and Technology
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• 제52권12호
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• pp.2910-2917
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• 2020

Digital light processing three-dimensional (3D) printing technique is a powerful tool to rapidly manufacture plastic scintillators of almost any shape or geometric features. In our previous study, the main properties of light output and transmission were analyzed. However, a more detailed study of the other properties is required to develop 3D printed plastic scintillators with expectable and reproducible properties. The 3D printed plastic scintillator displayed an average decay time constants of 15.6 ns, intrinsic energy resolution of 13.2%, and intrinsic detection efficiency of 6.81% for 477 keV Compton electrons from the ¹³⁷Cs γ-ray source. The 3D printed plastic scintillator showed a similar decay time and intrinsic detection efficiency as that of a commercial plastic scintillator BC408. Furthermore, the presented estimates for the properties showed good agreement with the analyzed data.

• Nuclear Engineering and Technology
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• 제38권3호
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• pp.251-258
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• 2006

This study presents an idea of using analogy concept to the heat transfer studies regarding the HTGR development. Theoretical backgrounds regarding the idea were reviewed. In order to investigate the predictability of a mass transfer system for heat transfer system phenomenology, an electroplating system coupled with a limiting current technique was adopted. Test facilities for laminar forced convection and natural convections under laminar and turbulent conditions were constructed, for which heat transfer correlations are known. The test results showed a close agreement between mass transfer and heat transfer systems, which is an encouraging indication of the validity of the analogy theory and the experimental methodology adopted. This paper shows the potential of the experimental method that validates the little-understood heat transfer phenomena, even in complex geometries such as HTGR.

• Nuclear Engineering and Technology
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• 제29권4호
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• pp.291-298
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• 1997

In advanced nuclear reactors, the passive containment cooling has been suggested to enhance the safety. The passive cooling has two mechanisms, air natural convection and oater cooling with evaporation. To confirm the coolability of PCCS, many works have been performed experimentally and numerically. In this study, the water cooling test was performed to obtain the evaporative heat transfer coefficients in a scaled don segment type PCCS facility which have same configuration with AP600 prototype containment. Air-steam mixture temperature and velocity, relative humidity and well heat flux are measured. The local steam mass flow rates through the vertical plate part of the facility are calculated from the measured data to obtain evaporative heat transfer coefficients. The measured evaporative heat transfer coefficients are compared with an analytical model which use a mass transfer coefficients. From the comparison, the predicted coefficients show good agreement with experimental data however, some discrepancies exist when the effect of wave motion is not considered. Finally, a new correlation on evaporative heat transfer coefficients are developed using the experimental values.