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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
> Journal Vol & Issue
Nuclear Engineering and Technology
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Journal DOI :
Korean Nuclear Society
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Volume & Issues
Volume 41, Issue 10 - Dec 2009
Volume 41, Issue 9 - Nov 2009
Volume 41, Issue 8 - Oct 2009
Volume 41, Issue 7 - Sep 2009
Volume 41, Issue 6 - Aug 2009
Volume 41, Issue 5 - Jun 2009
Volume 41, Issue 4 - May 2009
Volume 41, Issue 3 - Apr 2009
Volume 41, Issue 2 - Mar 2009
Volume 41, Issue 1 - Feb 2009
Selecting the target year
SOME OUTSTANDING PROBLEMS IN NEUTRON TRANSPORT COMPUTATION
Cho, Nam-Zin ; Chang, Jong-Hwa ;
Nuclear Engineering and Technology, volume 41, issue 4, 2009, Pages 381~390
DOI : 10.5516/NET.2009.41.4.381
This article provides selects of outstanding problems in computational neutron transport, with some suggested approaches thereto, as follows: i) ray effect in discrete ordinates method, ii) diffusion synthetic acceleration in strongly heterogeneous problems, iii) method of characteristics extension to three-dimensional geometry, iv) fission source and
convergence in Monte Carlo, v) depletion in Monte Carlo, vi) nuclear data evaluation, and vii) uncertainty estimation, including covariance data.
SAFETY ASSESSMENT OF KOREAN NUCLEAR FACILITIES: CURRENT STATUS AND FUTURE
Baek, Won-Pil ; Yang, Joon-Eon ; Ha, Jae-Joo ;
Nuclear Engineering and Technology, volume 41, issue 4, 2009, Pages 391~402
DOI : 10.5516/NET.2009.41.4.391
This paper introduces the development of safety assessment technology in Korea, focusing on the activities of the Korea Atomic Energy Research Institute in the areas of system thermal hydraulics, severe accidents and probabilistic safety assessment. In the 1970s and 1980s, safety analysis codes and methodologies were introduced from the United States, France, Canada and other developed countries along with technology related to the construction and operation of nuclear power plants. The main focus was on understanding and utilizing computer codes that were sourced from abroad up to the early 1990s, when efforts to develop domestic safety analysis codes and methodologies became active. Remarkable achievements have been made over the last 15 years in the development and application of safety analysis technologies. In addition, significant experimental work has been performed to verify the safety characteristics of reactors and fuels as well as to support the development and validation of analysis methods.
NUCLEAR REGULATORY RESEARCH IN KOREA: ACHIEVEMENTS AND FUTURE DIRECTION
Ryu, Yong-Ho ;
Nuclear Engineering and Technology, volume 41, issue 4, 2009, Pages 403~412
DOI : 10.5516/NET.2009.41.4.403
For efficient and effective nuclear regulation, regulatory organizations must establish consistent and rigorous regulatory positions on safety matters. These positions should be based on high technical expertise and relevant ordinances, standards, and guidelines reflecting policy changes governing nuclear regulations. The Korea Institute of Nuclear Safety, a regulatory expert organization in Korea, has developed regulatory requirements, guidelines and analytical tools that provide regulatory technical bases for ensuring nuclear safety. The nuclear regulatory research also contributes to regulatory decision making by providing resolution for current and future safety issues. In this article, we introduce nuclear regulatory research and its main achievements in the past 10 years. Also, suggested here are future directions of nuclear regulatory research.
PERSPECTIVES OF NUCLEAR HEAT AND HYDROGEN
Lee, Won-Jae ; Kim, Yong-Wan ; Chang, Jong-Hwa ;
Nuclear Engineering and Technology, volume 41, issue 4, 2009, Pages 413~426
DOI : 10.5516/NET.2009.41.4.413
Nuclear energy plays an important role in world energy production by supplying 6% of the world's current total electricity production. However, 86% of the energy consumed worldwide to produce industrial process heat, to generate electricity and to power the transportation sector still originates in fossil fuels. To cope with dwindling fossil fuels and climate change, it is clear that a clean alternative energy that can replace fossil fuels in these sectors is urgently required. Clean hydrogen energy is one such alternative. Clean hydrogen can play an important role not only in synthetic fuel production but also through powering fuel cells in the anticipated hydrogen economy. With the introduction of the high temperature gas-cooled reactor (HTGR) that can produce nuclear heat up to
without greenhouse gas emissions, nuclear power is poised to broaden its mission beyond electricity generation to the provision of nuclear process heat and the massive production of hydrogen. In this paper, the features and potential of the HTGR as the energy source of the future are addressed. Perspectives on nuclear heat and hydrogen applications using the HTGR are discussed.
ADVANCED SFR DESIGN CONCEPTS AND R&D ACTIVITIES
Hahn, Do-Hee ; Chang, Jin-Wook ; Kim, Young-In ; Kim, Yeong-Il ; Lee, Chan-Bock ; Kim, Seong-O ; Lee, Jae-Han ; Ha, Kwi-Seok ; Kim, Byung-Ho ; Lee, Yong-Bum ;
Nuclear Engineering and Technology, volume 41, issue 4, 2009, Pages 427~446
DOI : 10.5516/NET.2009.41.4.427
In order to meet the increasing demand for electricity, Korea has to rely on nuclear energy due to its poor natural resources. In order for nuclear energy to be expanded in its utilization, issues with uranium supply and waste management issues have to be addressed. Fast reactor system is one of the most promising options for electricity generation with its efficient utilization of uranium resources and reduction of radioactive waste, thus contributing to sustainable development. The Korea Atomic Energy Research Institute (KAERI) has been performing R&Ds on Sodium-cooled Fast Reactors (SFRs) under the national nuclear R&D program. Based on the experiences gained from the development of KALIMER conceptual designs of a pool-type U-TRU-10%Zr metal fuel loaded reactor, KAERI is currently developing Advanced SFR design concepts that can better meet the Generation IV technology goals. This also includes developing, Advanced SFR technologies necessary for its commercialization and basic key technologies, aiming at the conceptual design of an Advanced SFR by 2011. KAERI is making R&D efforts to develop advanced design concepts including a passive decay heat removal system and a supercritical
Brayton cycle energy conversion system, as well as developing design methodologies, computational tools, and sodium technology. The long-term Advanced SFR development plan will be carried out toward the construction of an Advanced SFR demonstration plant by 2028.
TECHNICAL REVIEW ON THE LOCALIZED DIGITAL INSTRUMENTATION AND CONTROL SYSTEMS
Kwon, Kee-Choon ; Lee, Myeong-Soo ;
Nuclear Engineering and Technology, volume 41, issue 4, 2009, Pages 447~454
DOI : 10.5516/NET.2009.41.4.447
This paper is a technical review of the research and development results of the Korea Nuclear Instrumentation and Control System (KNICS) project and Nu-Tech 2012 program. In these projects man-machine interface system architecture, two digital platforms, and several control and protection systems were developed. One platform is a Programmable Logic Controller (PLC) for a digital safety system and another platform is a Distributed Control System (DCS) for a non-safety control system. With the safety-grade platform PLC, a reactor protection system, an engineered safety feature-component control system, and reactor core protection system were developed. A power control system was developed based on the DCS. A logic alarm cause tracking system was developed as a man-machine interface for APR1400. Also, Integrated Performance Validation Facility (IPVF) was developed for the evaluation of the function and performance of developed I&C systems. The safety-grade platform PLC and the digital safety system obtained approval for the topical report from the Korean regulatory body in February of 2009. A utility and vendor company will determine the suitability of the KNICS and Nu- Tech 2012 products to apply them to the planned nuclear power plants.
CURRENT STATUS OF NUCLEAR FUSION ENERGY RESEARCH IN KOREA
Kwon, My-Eun ; Bae, Young-Soon ; Cho, Seung-Yon ; Choe, Won-Ho ; Hong, Bong-Geun ; Hwang, Yong-Seok ; Kim, Jin-Yong ; Kim, Kee-Man ; Kim, Yaung-Soo ; Kwak, Jong-Gu ; Lee, Hyeon-Gon ; Lee, San-Gil ; Na, Yong-Su ; Oh, Byung-Hoon ; Oh, Yeong-Kook ; Park, Ji-Yeon ; Yang, Hyung-Lyeol ; Yu, In-Keun ;
Nuclear Engineering and Technology, volume 41, issue 4, 2009, Pages 455~476
DOI : 10.5516/NET.2009.41.4.455
The history of nuclear fusion research in Korea is rather short compared to that of advanced countries. However, since the mid-1990s, at which time the construction of KSTAR was about to commence, fusion research in Korea has been actively carried out in a wide range of areas, from basic plasma physics to fusion reactor design. The flourishing of fusion research partly owes to the fact that industrial technologies in Korea including those related to the nuclear field have been fully matured, with their quality being highly ranked in the world. Successive pivotal programs such as KSTAR and ITER have provided diverse opportunities to address new scientific and technological problems in fusion as well as to draw young researchers into related fields. The frame of the Korean nuclear fusion program is now changing from a small laboratory scale to a large national agenda. Coordinated strategies from different views and a holistic approach are necessary in order to achieve optimal efficiency and effectiveness. Upon this background, the present paper reflects upon the road taken to arrive at this point and looks ahead at the coming future in nuclear fusion research activities in Korea.
WOLSONG LOW- AND INTERMEDIATE-LEVEL RADIOACTIVE WASTE DISPOSAL CENTER: PROGRESS AND CHALLENGES
Park, Jin-Beak ; Jung, Hae-Ryong ; Lee, Eun-Young ; Kim, Chang-Lak ; Kim, Geon-Young ; Kim, Kyung-Su ; Koh, Yong-Kwon ; Park, Kyung-Woo ; Cheong, Jae-Hak ; Jeong, Chan-Woo ; Choi, Jong-Soo ; Kim, Kyung-Deok ;
Nuclear Engineering and Technology, volume 41, issue 4, 2009, Pages 477~492
DOI : 10.5516/NET.2009.41.4.477
In this paper, we discuss the experiences during the preparation of the Wolsong Low- and Intermediate-Level Radioactive Waste Disposal Center. These experiences have importance as a first implementation for the national LILW disposal facility in the Republic of Korea. As for the progress, it relates to the area of selected disposal site, the disposal site characteristics, waste characteristics of the disposal facility, safety assessment, and licensing process. During these experiences, we also discuss the necessity for new organization and change for a radioactive waste management system. Further effort for the safe management of radioactive waste needs to be pursued.
PROGRESS IN NUCLEAR FUEL TECHNOLOGY IN KOREA
Song, Kun-Woo ; Jeon, Kyeong-Lak ; Jang, Young-Ki ; Park, Joo-Hwan ; Koo, Yang-Hyun ;
Nuclear Engineering and Technology, volume 41, issue 4, 2009, Pages 493~520
DOI : 10.5516/NET.2009.41.4.493
During the last four decades, 16 Pressurized Water Reactors (PWR) and 4 Pressurized Heavy Water Reactors (PHWR) have been constructed and operated in Korea, and nuclear fuel technology has been developed to a self-reliant state. At first, the PWR fuel design and manufacturing technology was acquired through international cooperation with a foreign partner. Then, the PWR fuel R&D by Korea Atomic Energy Research Institute (KAERI) has improved fuel technology to a self-reliant state in terms of fuel elements, which includes a new cladding material, a large-grained
pellet, a high performance spacer grid, a fuel rod performance code, and fuel assembly test facility. The MOX fuel performance analysis code was developed and validated using the in-reactor test data. MOX fuel test rods were fabricated and their irradiation test was completed by an international program. At the same time, the PWR fuel development by Korea Nuclear Fuel (KNF) has produced new fuel assemblies such as PLUS7 and ACE7. During this process, the design and test technology of fuel assemblies was developed to a self-reliant state. The PHWR fuel manufacturing technology was developed and manufacturing facility was set up by KAERI, independently from the foreign technology. Then, the advanced PHWR fuel, CANFLEX(CANDU Flexible Fuelling), was developed, and an irradiation test was completed in a PHWR. The development of the CANFLEX fuel included a new design of fuel rods and bundles.. The nuclear fuel technology in Korea has been steadily developed in many national R&D programs, and this advanced fuel technology is expected to contribute to a worldwide nuclear renaissance that can create solutions to global warming.
OPPORTUNITIES AND CHALLENGES OF NEUTRON SCIENCE AND TECHNOLOGY IN KOREA
Lee, Kye-Hong ; Park, J.M. Sung-Il ; Kim, Hark-Rho ; Jun, Byung-Jin ; Kim, Young-Jin ; Ha, Jae-Joo ; Kim, Mahn-Won ; Choi, Sung-Min ;
Nuclear Engineering and Technology, volume 41, issue 4, 2009, Pages 521~530
DOI : 10.5516/NET.2009.41.4.521
Neutron science and technology, the utilization of neutron beams for a wide variety of scientific and engineering research ranging from materials and life science to industrial applications, has been one of the key elements of modem science and technology. Currently, the neutron science and technology in Korea is in rapid growth with the operation of the 30 MW High-flux Advanced Neutron Application Reactor (HANARO) at the Korea Atomic Energy Research Institute, which is one of the most powerful nuclear research reactors in the world. Furthermore, a state of the art HANARO cold neutron research facility, which will open a new era for the neutron science and technology in Korea, is expected to become available in 2010. In this paper, the progress of neutron science and technology in Korea is reviewed and its unprecedented new opportunities and challenges in coming years are presented.
CURRENT RESEARCH ON ACCELERATOR-BASED BORON NEUTRON CAPTURE THERAPY IN KOREA
Kim, Jong-Kyung ; Kim, Kyung-O ;
Nuclear Engineering and Technology, volume 41, issue 4, 2009, Pages 531~544
DOI : 10.5516/NET.2009.41.4.531
This paper is intended to provide key issues and current research outcomes on accelerator-based Boron Neutron Capture Therapy (BNCT). Accelerator-based neutron sources are efficient to provide epithermal neutron beams for BNCT; hence, much research, worldwide, has focused on the development of components crucial for its realization: neutron-producing targets and cooling equipment, beam-shaping assemblies, and treatment planning systems. Proton beams of 2.5 MeV incident on lithium target results in high yield of neutrons at relatively low energies. Cooling equipment based on submerged jet impingement and micro-channels provide for viable heat removal options. Insofar as beam-shaping assemblies are concerned, moderators containing fluorine or magnesium have the best performance in terms of neutron accumulation in the epithermal energy range during the slowing-down from the high energies. NCT_Plan and SERA systems, which are popular dose distribution analysis tools for BNCT, contain all the required features (i.e., image reconstruction, dose calculations, etc.). However, detailed studies of these systems remain to be done for accurate dose evaluation. Advanced research centered on accelerator-based BNCT is active in Korea as evidenced by the latest research at Hanyang University. There, a new target system and a beam-shaping assembly have been constructed. The performance of these components has been evaluated through comparisons of experimental measurements with simulations. In addition, a new patient-specific treatment planning system, BTPS, has been developed to calculate the deposited dose and radiation flux in human tissue. It is based on MCNPX, and it facilitates BNCT efficient planning based via a user-friendly Graphical User Interface (GUI).
CURRENT STATUS AND PROSPECT FOR PERIODIC SAFETY REVIEW OF AGING NUCLEAR POWER PLANTS IN KOREA
Jin, Tae-Eun ; Roh, Heui-Young ; Kim, Tae-Ryong ; Park, Young-Sheop ;
Nuclear Engineering and Technology, volume 41, issue 4, 2009, Pages 545~548
DOI : 10.5516/NET.2009.41.4.545
Korean utility has utilized a Periodic Safety Review (PSR) that assesses the cumulative effects of plant aging, modifications, operating experience, technical developments, and site characteristics since 2000. In particular, the assessment and management of plant aging is one of the major areas in PSR. It includes identification of critical Systems, Structures, and Components (SSCs) for aging, assessment of aging effects, and implementation of aging management programs. Since the PSR system was introduced based on the atomic energy acts and related laws, PSRs of eight sets for 12 Nuclear Power Plants (NPPs) that have been operating more than 10 years have been completed. PSRs of two sets for 4 NPPs are currently being carried out. The utility has confirmed that domestic NPPs have been operated safely through these PSRs and have implemented the follow-up corrective activities to increase the nuclear safety. In this paper, the status of PSR implementation is discussed and improvement programs to conduct PSR follow-up corrective activities efficiently for NPPs are suggested based on experiences with aging assessments.
CONTRIBUTION OF NUCLEAR POWER TO THE NATIONAL ECONOMIC DEVELOPMENT IN KOREA
Lee, Man-Ki ; Nam, Kee-Yung ; Jeong, Ki-Ho ; Min, Byung-Joo ; Jung, Young-Eek ;
Nuclear Engineering and Technology, volume 41, issue 4, 2009, Pages 549~560
DOI : 10.5516/NET.2009.41.4.549
Over the last three decades, nuclear technology development has played a vital role in the socio-economic development of the Republic of Korea. This study, being the first of its kind, focuses on quantifying the actual economic contribution of nuclear technologies to economic development by evaluating the net benefit of the nuclear power with respect to the country's Gross Domestic Product (GDP). An input-output analysis was employed as a methodological approach to analyze inter-industrial economic activities by calculating the industrial value added as a means of the economic contribution during the period of 1980 to 2005. The industrial value added of nuclear technologies was estimated from the construction and operation of nuclear power (backward-linked industrial value added) and from the industrial activities attributed to the electricity generated by the nuclear power (forward-linked industrial value added). It was found that the total net contribution of nuclear technologies as a percentage share of GDP amounted to 2.38% in 2005.