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VERIFICATION AND VALIDATION OF BACK-END CYCLE SOURCE TERM CALCULATION OF THE NODAL CODE RAST-K [PDF]
EPJ Web of Conferences, 2021 Verification and validation (V&V) results of source term calculation capability implemented in the nodal diffusion code RAST-K are presented in this paper.
Jang Jaerim +4 more
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NMB4.0: development of integrated nuclear fuel cycle simulator from the front to back-end
EPJ Nuclear Sciences & Technologies, 2021 Nuclear Material Balance code version 4.0 (NMB4.0) has been developed through collaborative R&D between TokyoTech&JAEA. Conventional nuclear fuel cycle simulation codes mainly analyze actinides and are specialized for front-end mass balance analysis ...
Okamura Tomohiro +6 more
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IEEE Journal of the Electron Devices Society, 2021 From our other works, we have developed urea biosensor based on graphene oxide/nickel oxide sensing film modified either by Au nanoparticles or ${\gamma }$ -Fe2O3 nanoparticles.
Yu-Hsun Nien +8 more
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IOb-Cache: A High-Performance Configurable Open-Source Cache
Algorithms, 2021 Open-source processors are increasingly being adopted by the industry, which requires all sorts of open-source implementations of peripherals and other system-on-chip modules.
João V. Roque +3 more
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Nuclear Engineering and Technology, 2021 This paper presents the verification and validation (V&V) of a calculation module for isotope inventory prediction to control the back-end cycle of spent nuclear fuel (SNF).
Jaerim Jang +5 more
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Energies, 2021 This paper presents the results of various benefit–cost ratio (BCR) analyses of back-end nuclear fuel cycle alternatives. Korea is currently considering two alternatives for the disposal of spent nuclear fuel: direct disposal and pyroprocessing.
Sungki Kim, Jin-Seop Kim, Dong-Keun Cho
doaj +1 more source
Validation of spent nuclear fuel decay heat calculation by a two-step method
Nuclear Engineering and Technology, 2021 In this paper, we validate the decay heat calculation capability via a two-step method to analyze spent nuclear fuel (SNF) discharged from pressurized water reactors (PWRs).
Jaerim Jang +5 more
doaj +1 more source
Uncertainty quantification in decay heat calculation of spent nuclear fuel by STREAM/RAST-K
Nuclear Engineering and Technology, 2021 This paper addresses the uncertainty quantification and sensitivity analysis of a depleted light-water fuel assembly of the Turkey Point-3 benchmark. The uncertainty of the fuel assembly decay heat and isotopic densities is quantified with respect to ...
Jaerim Jang +5 more
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Integration of the Back-end of the Nuclear Fuel Cycle: An Overview [PDF]
MRS Advances, 2020 AbstractRecent efforts have been made toward the integration of the back-end of the nuclear fuel cycle in the United States. The back-end integration seeks to address several management challenges: 1) current storage practices are not optimized for transport and disposal; 2) the impact of interim storage on the disposal strategy needs to be evaluated ...
Diaz-Maurin, François, Ewing, Rodney C.
openaire +2 more sources
Energies, 2021 The Korean government is currently evaluating two alternatives, direct disposal and pyroprocessing, for the disposal of spent nuclear fuel. This paper presents the ranking results of comparing and evaluating direct disposal and pyro-SFR fuel cycle ...
Sungki Kim, Jin-Seop Kim, Dong-Keun Cho
doaj +1 more source