The Experts below are selected from a list of 297 Experts worldwide ranked by ideXlab platform
Jamshid Kamali - One of the best experts on this subject based on the ideXlab platform.
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effectiveness of the neutron shield nanocomposites for a dual purpose cask of bushehr s water water energetic reactor vver 1000 nuclear power plant Spent Fuels
Nuclear Engineering and Technology, 2017Co-Authors: Mahdi Rezaeian, Jamshid Kamali, Seyed Javad Ahmadi, Mohammad Amin KianiAbstract:Abstract In order to perform dry interim storage and transportation of the Spent-fuel assemblies of the Bushehr Nuclear Power Plant, dual-purpose casks can be utilized. The effectiveness of different neutron-shield materials for the dual-purpose cask was analyzed through a set of calculations carried out using the Monte Carlo N-Particle (MCNP) code. The dose rate for the dual-purpose cask utilizing the recently developed materials of epoxy/clay/B 4 C and epoxy/clay/B 4 C/carbon fiber was less than the allowable radiation level of 2 mSv/h at any point and 0.1 mSv/h at 2 m from the external surface of the cask. By utilization of epoxy/clay/B 4 C instead of an ethylene glycol/water mixture, the dose rates on the side surface of the cask due to neutron sources and consequent secondary gamma rays will be reduced by 17.5% and 10%, respectively. The overall dose rate in this case will be reduced by 11%.
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Effectiveness of the neutron-shield nanocomposites for a dual-purpose cask of Bushehr's Water–Water Energetic Reactor (VVER) 1000 nuclear-power-plant Spent Fuels
Nuclear Engineering and Technology, 2017Co-Authors: Rezaeian, Jamshid Kamali, Seyed Javad Ahmadi, Mohammad Amin KianiAbstract:Abstract In order to perform dry interim storage and transportation of the Spent-fuel assemblies of the Bushehr Nuclear Power Plant, dual-purpose casks can be utilized. The effectiveness of different neutron-shield materials for the dual-purpose cask was analyzed through a set of calculations carried out using the Monte Carlo N-Particle (MCNP) code. The dose rate for the dual-purpose cask utilizing the recently developed materials of epoxy/clay/B 4 C and epoxy/clay/B 4 C/carbon fiber was less than the allowable radiation level of 2 mSv/h at any point and 0.1 mSv/h at 2 m from the external surface of the cask. By utilization of epoxy/clay/B 4 C instead of an ethylene glycol/water mixture, the dose rates on the side surface of the cask due to neutron sources and consequent secondary gamma rays will be reduced by 17.5% and 10%, respectively. The overall dose rate in this case will be reduced by 11%.
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Basket criticality design of a dual purpose cask for VVER 1000 Spent fuel assemblies
Kerntechnik, 2016Co-Authors: Mahdi Rezaeian, Jamshid KamaliAbstract:Abstract Dual purpose cask technology is one of the most prominent options for interim storage of Spent Fuels following their removal from reactors. Criticality safety of the Spent fuel assemblies are ensured by design of the basket within these casks. In this study, a set of criticality design calculations of a dual purpose cask for 12 VVER 1000 Spent fuel assemblies of Bushehr nuclear power plant were carried out. The basket material of borated stainless steel with 0.5 to 2.5 wt% of boron and Boral (Al-B4C) with 1.5 to 40 wt% of boron carbide, were investigated and the minimum required receptacle pitch of the basket was determined. Using the calculated receptacle pitch of the basket, the minimum required diameter of the cavity could be established.
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radioactive source specification of bushehr s vver 1000 Spent Fuels
Science and Technology of Nuclear Installations, 2016Co-Authors: Mahdi Rezaeian, Jamshid KamaliAbstract:Due to high radioactivity and significant content of medium- and long-lived radionuclides, different operations with Spent nuclear Fuels (e.g., handling, transportation, and storage) shall be accompanied by suitable radiation protections. On the other hand, determination of radioactive source specification is the initial step for any radiation protection design. In this study, radioactive source specification of the Spent Fuels of Bushehr nuclear power plant, which is a VVER-1000 type pressurized water reactor, was determined. For the depletion and decay calculations, ORIGEN code was utilized. The results are presented for burnups of 30 to 49 GWd/MTHM and different cooling times up to 100 years. According to these results, total activity of a Spent fuel assembly with initial enrichment of 3.92%, burnup of 49 GWd/MTHM, and cooling time of 3 years is 1.92 × 1016 Bq. The results can be utilized specifically in transportation/storage cask design for Spent fuel management of Bushehr nuclear power plant.
Heuijoo Choi - One of the best experts on this subject based on the ideXlab platform.
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Characteristics of the Spent Fuel Generated in Korea
ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management Volume 1, 2020Co-Authors: Donghak Kook, Jongwon Choi, Heuijoo ChoiAbstract:Nuclear power has satisfied the national electric power demand for three decades, and there are only two reactor types in Korea. The nuclear fuel species, however, have a large variety of fuel types, dimensions, initial enrichment, and fuel supply vendors. A Spent fuel accumulation problem has arisen like any other country that uses nuclear power. The Spent fuel wet storage capacity in the reactor pool is getting close to its limit, and so hence, short & long-term solutions are being actively proposed. First the general status for the nuclear industries and Spent Fuels will be introduced, then Spent fuel characteristics will follow, and last the future anticipation of Spent fuel management will close this article.Copyright © 2009 by ASME
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An Analysis on the Borehole Spacing for Deep Borehole Disposal of HLW
2020Co-Authors: Heuijoo ChoiAbstract:A mined deep geological disposal system is considered as the safest method to isolate the Spent Fuels or high-level radioactive waste from the human environment with the best available technology at present time. However, if these high-level radioactive wastes can be disposed of in deeper and more stable rock formation than mined deep geological disposal depth, it has several advantages. Therefore, as an alternative disposal concept, i.e., deep borehole disposal technology is under consideration in number of countries in terms of its outstanding safety and cost effectiveness. In this paper, the general concept and key technologies for deep borehole disposal of Spent Fuels or HLW, as an alternative method to the mined deep geological disposal method, were reviewed. After then an analysis on the distance between boreholes for the disposal of HLW was carried out. Based on the results, a disposal area was calculated approximately and compared with that of mined deep geological disposal.
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development of geological disposal systems for Spent Fuels and high level radioactive wastes in korea
Nuclear Engineering and Technology, 2013Co-Authors: Heuijoo Choi, Jongwon ChoiAbstract:Two different kinds of nuclear power plants produce a substantial amount of Spent fuel annually in Korea. According to the current projection, it is expected that around 60,000 MtU of Spent fuel will be produced from 36 PWR and APR reactors and 4 CANDU reactors by the end of 2089. In 2006, KAERI proposed a conceptual design of a geological disposal system (called KRS, Korean Reference disposal System for Spent fuel) for PWR and CANDU Spent fuel, as a product of a 4-year research project from 2003 to 2006. The major result of the research was that it was feasible to construct a direct disposal system for 20,000 MtU of PWR Spent Fuels and 16,000 MtU of CANDU Spent fuel in the Korean peninsula. Recently, KAERI and MEST launched a project to develop an advanced fuel cycle based on the pyroprocessing of PWR Spent fuel to reduce the amount of HLW and reuse the valuable fissile material in PWR Spent fuel. Thus, KAERI has developed a geological disposal system for high-level waste from the pyroprocessing of PWR Spent fuel since 2007. However, since no decision was made for the CANDU Spent fuel, KAERI improved the disposal density of KRS by introducing several improved concepts for the disposal canister. In this paper, the geological disposal systems developed so far are briefly outlined. The amount and characteristics of Spent fuel and HLW, 4 kinds of disposal canisters, the characteristics of a buffer with domestic Ca-bentonite, and the results of a thermal design of deposition holes and disposal tunnels are described. The different disposal systems are compared in terms of their disposal density.
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preliminary conceptual design of a geological disposal system for high level wastes from the pyroprocessing of pwr Spent Fuels
Nuclear Engineering and Design, 2011Co-Authors: Heuijoo ChoiAbstract:Abstract The inventories of Spent Fuels are linearly dependent on the production of electricity generated by nuclear energy. Pyroprocessing of PWR Spent Fuels is one of promising technologies which can reduce the volume of Spent Fuels remarkably. The properties of high-level wastes from the pyroprocessing are totally different from those of Spent Fuels. A geological disposal system is proposed for the high-level wastes from pyroprocessing of Spent Fuels. The amount and characteristics of high-level wastes are analyzed based on the material balance of pyroprocessing. Around 665 kg of monazite ceramic wastes are expected from the pyroprocessing of 10 MtU of PWR Spent Fuels. Decay heat from monazite ceramic wastes is calculated using the ORIGEN-ARP program. Disposal modules consisting of storage cans, overpacks, and a deposition hole or a disposal tunnel are proposed. Four kinds of deposition methods are proposed. Thermal design is carried out with ABAQUS program and geological data obtained from the KAERI Underground Research Tunnel. Through the thermal analysis, the spacing between the disposal modules is determined for the peak temperature in buffer not to exceed 100 °C. Thermal analysis shows that the optimum spacing between the vertical deposition holes with 4 overpacks is 8 m when the disposal tunnel spacing is 40 m and optimum spacing of 2 m for horizontal disposal tunnel with 25 m tunnel spacing. Also, the spacing reduces to 6 m for vertical deposition when the double-layered buffer is used, which reduces the disposal area to one-sixty fifth (1/65th) compared with the direct disposal of Spent Fuels. Finally, the effect of cooling time on the disposal area is illustrated.
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current status of Spent Fuels and the development of computer programs for the pwr Spent fuel management in korea
Progress in Nuclear Energy, 2011Co-Authors: Heuijoo Choi, Donghak Kook, Jongwon ChoiAbstract:Nuclear power has supplied the national electric power demand for three decades in the Republic of Korea, which has resulted in the accumulation of a large amount of Spent Fuels. The government has a policy on the temporary storage of these at nuclear power plants at present. In order to establish a proper policy for Spent fuel management in the near future, the characteristics and amount of Spent Fuels should be figured out properly. In this paper, the current status of Spent Fuels in the Republic of Korea is outlined focusing on the major characteristics of Spent Fuels such as initial enrichment and discharge burnup. According to the current trend, the average burnup of PWR Spent Fuels will reach 55 GWd/MtU by the middle of 2010s. Three different kinds of computer programs were developed to supply crucial data regarding Spent Fuels. The first one was developed to project the amount of Spent Fuels in the future based on three different projection models. The projection was verified with real Spent fuel data. The second Database program was prepared for the analysis of statistics regarding PWR Spent Fuels. Each PWR Spent fuel assembly was specified with 18 items of data such as fuel type, initial enrichment, and discharge burnup. The usefulness of the Database program was illustrated through an analysis of the geological disposal density and cooling time of PWR Spent Fuels. Disposal area could be reduced by 50% through a proper analysis of the cooling time of PWR Spent Fuels. Finally, A-SOURCE program was developed to easily calculate source-terms such as decay heat and radionuclide concentration after the pyro-processing of PWR Spent fuel assemblies. Linked to the Database program, the A-SOURCE program selected PWR Spent fuel assemblies and could calculate the source-terms for any combination of them. An illustration of the usage of the program was demonstrated.
Mahdi Rezaeian - One of the best experts on this subject based on the ideXlab platform.
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effectiveness of the neutron shield nanocomposites for a dual purpose cask of bushehr s water water energetic reactor vver 1000 nuclear power plant Spent Fuels
Nuclear Engineering and Technology, 2017Co-Authors: Mahdi Rezaeian, Jamshid Kamali, Seyed Javad Ahmadi, Mohammad Amin KianiAbstract:Abstract In order to perform dry interim storage and transportation of the Spent-fuel assemblies of the Bushehr Nuclear Power Plant, dual-purpose casks can be utilized. The effectiveness of different neutron-shield materials for the dual-purpose cask was analyzed through a set of calculations carried out using the Monte Carlo N-Particle (MCNP) code. The dose rate for the dual-purpose cask utilizing the recently developed materials of epoxy/clay/B 4 C and epoxy/clay/B 4 C/carbon fiber was less than the allowable radiation level of 2 mSv/h at any point and 0.1 mSv/h at 2 m from the external surface of the cask. By utilization of epoxy/clay/B 4 C instead of an ethylene glycol/water mixture, the dose rates on the side surface of the cask due to neutron sources and consequent secondary gamma rays will be reduced by 17.5% and 10%, respectively. The overall dose rate in this case will be reduced by 11%.
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Basket criticality design of a dual purpose cask for VVER 1000 Spent fuel assemblies
Kerntechnik, 2016Co-Authors: Mahdi Rezaeian, Jamshid KamaliAbstract:Abstract Dual purpose cask technology is one of the most prominent options for interim storage of Spent Fuels following their removal from reactors. Criticality safety of the Spent fuel assemblies are ensured by design of the basket within these casks. In this study, a set of criticality design calculations of a dual purpose cask for 12 VVER 1000 Spent fuel assemblies of Bushehr nuclear power plant were carried out. The basket material of borated stainless steel with 0.5 to 2.5 wt% of boron and Boral (Al-B4C) with 1.5 to 40 wt% of boron carbide, were investigated and the minimum required receptacle pitch of the basket was determined. Using the calculated receptacle pitch of the basket, the minimum required diameter of the cavity could be established.
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radioactive source specification of bushehr s vver 1000 Spent Fuels
Science and Technology of Nuclear Installations, 2016Co-Authors: Mahdi Rezaeian, Jamshid KamaliAbstract:Due to high radioactivity and significant content of medium- and long-lived radionuclides, different operations with Spent nuclear Fuels (e.g., handling, transportation, and storage) shall be accompanied by suitable radiation protections. On the other hand, determination of radioactive source specification is the initial step for any radiation protection design. In this study, radioactive source specification of the Spent Fuels of Bushehr nuclear power plant, which is a VVER-1000 type pressurized water reactor, was determined. For the depletion and decay calculations, ORIGEN code was utilized. The results are presented for burnups of 30 to 49 GWd/MTHM and different cooling times up to 100 years. According to these results, total activity of a Spent fuel assembly with initial enrichment of 3.92%, burnup of 49 GWd/MTHM, and cooling time of 3 years is 1.92 × 1016 Bq. The results can be utilized specifically in transportation/storage cask design for Spent fuel management of Bushehr nuclear power plant.
Jongwon Choi - One of the best experts on this subject based on the ideXlab platform.
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Characteristics of the Spent Fuel Generated in Korea
ASME 2009 12th International Conference on Environmental Remediation and Radioactive Waste Management Volume 1, 2020Co-Authors: Donghak Kook, Jongwon Choi, Heuijoo ChoiAbstract:Nuclear power has satisfied the national electric power demand for three decades, and there are only two reactor types in Korea. The nuclear fuel species, however, have a large variety of fuel types, dimensions, initial enrichment, and fuel supply vendors. A Spent fuel accumulation problem has arisen like any other country that uses nuclear power. The Spent fuel wet storage capacity in the reactor pool is getting close to its limit, and so hence, short & long-term solutions are being actively proposed. First the general status for the nuclear industries and Spent Fuels will be introduced, then Spent fuel characteristics will follow, and last the future anticipation of Spent fuel management will close this article.Copyright © 2009 by ASME
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development of geological disposal systems for Spent Fuels and high level radioactive wastes in korea
Nuclear Engineering and Technology, 2013Co-Authors: Heuijoo Choi, Jongwon ChoiAbstract:Two different kinds of nuclear power plants produce a substantial amount of Spent fuel annually in Korea. According to the current projection, it is expected that around 60,000 MtU of Spent fuel will be produced from 36 PWR and APR reactors and 4 CANDU reactors by the end of 2089. In 2006, KAERI proposed a conceptual design of a geological disposal system (called KRS, Korean Reference disposal System for Spent fuel) for PWR and CANDU Spent fuel, as a product of a 4-year research project from 2003 to 2006. The major result of the research was that it was feasible to construct a direct disposal system for 20,000 MtU of PWR Spent Fuels and 16,000 MtU of CANDU Spent fuel in the Korean peninsula. Recently, KAERI and MEST launched a project to develop an advanced fuel cycle based on the pyroprocessing of PWR Spent fuel to reduce the amount of HLW and reuse the valuable fissile material in PWR Spent fuel. Thus, KAERI has developed a geological disposal system for high-level waste from the pyroprocessing of PWR Spent fuel since 2007. However, since no decision was made for the CANDU Spent fuel, KAERI improved the disposal density of KRS by introducing several improved concepts for the disposal canister. In this paper, the geological disposal systems developed so far are briefly outlined. The amount and characteristics of Spent fuel and HLW, 4 kinds of disposal canisters, the characteristics of a buffer with domestic Ca-bentonite, and the results of a thermal design of deposition holes and disposal tunnels are described. The different disposal systems are compared in terms of their disposal density.
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current status of Spent Fuels and the development of computer programs for the pwr Spent fuel management in korea
Progress in Nuclear Energy, 2011Co-Authors: Heuijoo Choi, Donghak Kook, Jongwon ChoiAbstract:Nuclear power has supplied the national electric power demand for three decades in the Republic of Korea, which has resulted in the accumulation of a large amount of Spent Fuels. The government has a policy on the temporary storage of these at nuclear power plants at present. In order to establish a proper policy for Spent fuel management in the near future, the characteristics and amount of Spent Fuels should be figured out properly. In this paper, the current status of Spent Fuels in the Republic of Korea is outlined focusing on the major characteristics of Spent Fuels such as initial enrichment and discharge burnup. According to the current trend, the average burnup of PWR Spent Fuels will reach 55 GWd/MtU by the middle of 2010s. Three different kinds of computer programs were developed to supply crucial data regarding Spent Fuels. The first one was developed to project the amount of Spent Fuels in the future based on three different projection models. The projection was verified with real Spent fuel data. The second Database program was prepared for the analysis of statistics regarding PWR Spent Fuels. Each PWR Spent fuel assembly was specified with 18 items of data such as fuel type, initial enrichment, and discharge burnup. The usefulness of the Database program was illustrated through an analysis of the geological disposal density and cooling time of PWR Spent Fuels. Disposal area could be reduced by 50% through a proper analysis of the cooling time of PWR Spent Fuels. Finally, A-SOURCE program was developed to easily calculate source-terms such as decay heat and radionuclide concentration after the pyro-processing of PWR Spent fuel assemblies. Linked to the Database program, the A-SOURCE program selected PWR Spent fuel assemblies and could calculate the source-terms for any combination of them. An illustration of the usage of the program was demonstrated.
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development of a computer program for the analysis logistics of pwr Spent Fuels
Journal of the Nuclear Fuel Cycle and Waste Technology, 2008Co-Authors: Heuijoo Choi, Jongwon ChoiAbstract:It is expected that the temporary storage facilities at the nuclear power plants will be full of the Spent Fuels within 10 years. Provided that a centralized interim storage facility is constructed along the coast of the Korean peninsula to solve this problem, a substantial amount of Spent Fuels should be transported by sea or by land every year. In this paper we developed a computer program for the analysis of transportation logistics of the Spent Fuels from 4 different nuclear power plant sites to the hypothetical centralized interim storage facility and the final repository. Mass balance equations were used to analyze the logistics between the nuclear power plants and the interim storage facility. To this end a computer program, CASK, was developed by using the VISUAL BASIC language. The annual transportation rates of Spent Fuels from the four nuclear power plant sites were determined by using the CASK program. The parameter study with the program illustrated the easiness of logistics analysis. The program could be used for the cost analysis of the Spent fuel transportation as well.
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concept of a korean reference disposal system for Spent Fuels
Journal of Nuclear Science and Technology, 2007Co-Authors: Heuijoo Choi, Jongwon ChoiAbstract:A deep geologic disposal system for the Spent Fuels from nuclear power plants has been developed since this program was launched in 1997 in Korea. In this paper, the concept of a Korean reference high-level waste (HLW) vertical disposal system (KRS-V1) is described. Though no site for the underground repository has yet been specified in Korea, a generic site with a granitic rock is considered for a reference Spent fuel repository design. The depth of the repository is assumed to be 500 m. The repository consists of a disposal area, a controlled area, and an uncontrolled area. The disposal area consists of disposal tunnels, panel tunnels, and a central tunnel. In the controlled area and the uncontrolled area, there are technical rooms and tunnels and/or shafts to connect them to the ground level, respectively. The repository will be excavated, operated, and backfilled in several phases including an underground research laboratory (URL) phase. The result of this concept development will be used for an evalu...
Mohammad Amin Kiani - One of the best experts on this subject based on the ideXlab platform.
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Effectiveness of the neutron-shield nanocomposites for a dual-purpose cask of Bushehr's Water–Water Energetic Reactor (VVER) 1000 nuclear-power-plant Spent Fuels
Nuclear Engineering and Technology, 2017Co-Authors: Rezaeian, Jamshid Kamali, Seyed Javad Ahmadi, Mohammad Amin KianiAbstract:Abstract In order to perform dry interim storage and transportation of the Spent-fuel assemblies of the Bushehr Nuclear Power Plant, dual-purpose casks can be utilized. The effectiveness of different neutron-shield materials for the dual-purpose cask was analyzed through a set of calculations carried out using the Monte Carlo N-Particle (MCNP) code. The dose rate for the dual-purpose cask utilizing the recently developed materials of epoxy/clay/B 4 C and epoxy/clay/B 4 C/carbon fiber was less than the allowable radiation level of 2 mSv/h at any point and 0.1 mSv/h at 2 m from the external surface of the cask. By utilization of epoxy/clay/B 4 C instead of an ethylene glycol/water mixture, the dose rates on the side surface of the cask due to neutron sources and consequent secondary gamma rays will be reduced by 17.5% and 10%, respectively. The overall dose rate in this case will be reduced by 11%.
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effectiveness of the neutron shield nanocomposites for a dual purpose cask of bushehr s water water energetic reactor vver 1000 nuclear power plant Spent Fuels
Nuclear Engineering and Technology, 2017Co-Authors: Mahdi Rezaeian, Jamshid Kamali, Seyed Javad Ahmadi, Mohammad Amin KianiAbstract:Abstract In order to perform dry interim storage and transportation of the Spent-fuel assemblies of the Bushehr Nuclear Power Plant, dual-purpose casks can be utilized. The effectiveness of different neutron-shield materials for the dual-purpose cask was analyzed through a set of calculations carried out using the Monte Carlo N-Particle (MCNP) code. The dose rate for the dual-purpose cask utilizing the recently developed materials of epoxy/clay/B 4 C and epoxy/clay/B 4 C/carbon fiber was less than the allowable radiation level of 2 mSv/h at any point and 0.1 mSv/h at 2 m from the external surface of the cask. By utilization of epoxy/clay/B 4 C instead of an ethylene glycol/water mixture, the dose rates on the side surface of the cask due to neutron sources and consequent secondary gamma rays will be reduced by 17.5% and 10%, respectively. The overall dose rate in this case will be reduced by 11%.
