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Bayesian statistical model for cladding high-temperature burst under loss-of-coolant accident conditions J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-29 Yudai Tasaki, Takafumi Narukawa, Yutaka Udagawa
This study developed a probabilistic determination model with respect to cladding high-temperature burst conditions based on the Bayesian statistical method to reasonably evaluate fuel behaviors un...
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Experimental investigations on flow-induced vibration characteristics of fuel rod with an independent channel for Small Lead-based Reactor J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-27 Guowei Yang, Yong Zhang, Yong Song, Tiandi Fan, Jianwei Chen, Yunqing Bai
The technology of nuclear reactors is evolving rapidly, driven by the pursuit of more powerful and efficient systems. The Small Lead-based Reactor (SLR) represents an advanced nuclear reactor desig...
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Molecular dynamics simulation study of the effect of Ce4+ incorporation at Zr site on the threshold displacement energy in Y4Zr3O12 material J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-26 Mohammed Ado, Qingyu Wang, Shehu Adam Ibrahim, Simon Ochieng Adede, Yushou Song, Ibrahim Alfasatleh
This study utilizes classical molecular dynamics (MD) simulations to examine the structure and the impact of cerium (Ce4+) incorporation, serving as a surrogate for plutonium (Pu), at the zirconium...
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Rare earth elements and radioactive elements in black sands from the Konkan and Malabar coasts of India J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-23 V. K. Shukla, Abhishek Kr. Rai, S. Dubey, R. Kumar, P. K. Shahi, N. Rai, A.K. Rai
The objective of the present work is to demonstrate the ability of the Laser-induced breakdown spectroscopy (LIBS) technique for quick detection and quantification of rare earth elements (REEs) and...
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Heat of transport for hydrogen and hydrides in Zircaloy J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-22 G.A. McRae, C.E. Coleman
Hydrogen diffuses in zirconium alloys in response to gradients in hydrogen concentration, temperature, and stress. This essay discusses the results of several evaluations of the coefficient describ...
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The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-19 Kodai Wadayama, Retsu Kojo, Tamon Niisoe
In a nuclear emergency, consequence assessment based on the plant conditions using a simple method is important for a prompt response. Response Technical Manual (RTM-96) is a manual calculation met...
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The Effect of Alpha Irradiation on the Performance of Glass Matrix in Simulated Radioactive Contaminated Soil by Microwave Treatment J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-19 Jiaqin Wei, Wenhong Han, Guilin Wei, Xiaoyan Shu, Beilong Yuan, Jiahong Wang, Xirui Lu
Understanding the irradiation stability of radioactive waste matrices is beneficial to the long-term waste treatment. In this work, different contents of Nd2O3 were mixed with soil to simulated nuc...
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A study on the fracture pattern change of high-burnup fuel cladding failed by pellet-cladding mechanical interaction failure under reactivity-initiated accident conditions J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-15 Feng Li, Takeshi Mihara, Yutaka Udagawa
In a part of the historical reactivity-initiated accident (RIA) simulated tests on high-burnup fuels performed at the Nuclear Safety Research Reactor, the fuel failure caused by pellet-cladding mec...
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Design of moderator and collimator based on compact D-T neutron source for neutron imaging J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-12 Hao Chen, Shuang Qiao, Chenyi Zhao, Tian Zhang, Xiangyu Yao
The Compact thermal neutron imaging systems have become an important development trend. Compact thermal neutron imaging systems can use neutron tubes as neutron sources because of their low cost, s...
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Activation level of the concrete building and pressure vessel in JAEA-Tokai tandem accelerator J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-12 Go Yoshida, Hiroshi Matsumura, Hajime Nakamura, Taichi Miura, Akihiro Toyoda, Kazuyoshi Masumoto, Takayuki Nakabayashi, Makoto Matsuda
The activation level of the JAEA-Tokai tandem accelerator facility was investigated experimentally in advance of the future decommissioning. JAEA-Tokai tandem accelerator facility has a higher term...
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High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of nickel-base alloy 82 weld metal J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-09 Yoichi Wada, Hikari Murotani, Kazushige Ishida, Mayu Sasaki, Makoto Nagase, Ryosuke Shimizu, Shinobu Okido
The electrochemical corrosion potential (ECP) data of nickel-base alloy 82 weld metal (Alloy 82) in both O2 and H2O2 environments were measured. Although Alloy 82 is used at various welds in boilin...
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Numerical Study of Turbulent Heat Transfer of Annular Fuel Assembly in a Sodium-cooled Fast Reactor by a SST k-ω-kθ-εθ Model J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-05 Yuefeng Guo, Xingkang Su, Guan Wang, Xianwen Li, Long Gu
The annular fuel has two cooling surfaces inside and outside, which can fully take away the heat of the fuel assemblies, and have strong advantages in safety and economy. It is urgent to conduct re...
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EXPERIENCES from the CUTTING of METALLIC BLOCKS from SIMULANT FUKUSHIMA DAIICHI FUEL DEBRIS J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-05 C. Journeau, D. Molina, E. Brackx, R. Berlemont, Y. Tsubota
CEA has manufactured a series of Fukushima Daiichi fuel debris simulants, either with depleted uranium oxide or with hafnium oxide as a surrogate of UO2. In ex-vessel compositions resulting from an...
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Preliminary study of the criticality monitoring method based on the simulation for the activity ratio of short half-life noble-gas fission products from fuel debris J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-05 Eka Sapta Riyana, Keisuke Okumura, Masahiro Sakamoto, Taichi Matsumura, Kenichi Terashima, Ikuo Kanno
We investigated the possibility of estimating the effective neutron multiplication factor (keff) of the fuel debris inside the canister and primary containment vessel (PCV) of Unit 2 of the Fukushi...
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Calculations and analysis of n+52Cr reactions below 20 MeV J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-05 Wenye Wang, Jimin Wang, Yinlu Han, Tao Xi, Jin Yongli, Xu Ruirui, Yue Zhang
Chromium is one of the important structural materials in the process of nuclear reaction, and the precise nuclear data of n + 52Cr reaction is very important. On the basis of the spherical optical ...
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Double-differential cross sections for charged particle emissions from α particle impinging on Al at 230 MeV/u J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-05 Toshimasa Furuta, Yusuke Uozumi, Yuji Yamaguchi, Yosuke Iwamoto, Yusuke Koba, Elena Velicheva, Vladimir Kalinnikov, Zviadi Tsamalaidze, Petr Evtoukhovitch
Charged particle production from α particle fragmentation reactions was investigated experimentally by measurement of 230-MeV/u α particles bombarding an aluminum target. Double differential cross ...
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Measurement of the neutron capture cross section of 185Re in the keV energy region J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-05 Tatsuya Katabuchi, Yaoki Sato, Karin Takebe, Masayuki Igashira, Seigo Umezawa, Ryo Fujioka, Tatsuhiro Saito, Nobuyuki Iwamoto
Despite various applications of Rhenium in nuclear science and engineering, there have been limited measurements of the neutron capture cross section of 185Re in the keV energy region, with existin...
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Experimental study of photoneutron spectra from tantalum, tungsten, and bismuth targets for 16.6 MeV polarized photons J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-05 Nguyen Thi Hong Thuong, Toshiya Sanami, Hirohito Yamazaki, Toshiro Itoga, Yoichi Kirihara, Kenta Sugihara, Tran Kim Tuyet, Mohd Faiz Bin Mohd Zin, Shuji Miyamoto, Satoshi Hashimoto, Yoshihiro Asano
The double differential cross-sections (DDXs) of photoneutron production via the photonuclear reaction on tantalum, tungsten, and bismuth for 16.6 MeV linearly polarized photon beam were measured u...
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Status of the 226Ra nuclear data library and its impact on the production amount of 225Ac via the 226Ra (n,2n) reaction J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-05 Yuto Sasaki, Nobuyuki Iwamoto, Naoyuki Takaki, Shigetaka Maeda
225Ac is a promising alpha emitter for targeted alpha therapy. However, the current capability of 225Ac supply is limited to approximately 63 GBq/y, primarily relying on the natural source of 229Th...
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Shielding design of NanoTerasu for gas bremsstrahlung and photonuclear reaction J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-05 Hiroki Matsuda, Masayuki Hagiwara, Akihiro Takeuchi, Toshiro Itoga, Hiroyuki Konishi
To exclude an experimental hall from a radiation-controlled area at the state-of-the-art 3 GeV synchrotron radiation facility, NanoTerasu, Japan, the shielding design of optical hatches for gas bre...
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Comparison and evaluation of resolved resonance region covariance representations J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-05 Hunter Belanger, Amanda Lewis, Devin Barry
The covariance matrices for the evaluated resolved resonance region parameters are typically processed into a grouped covariance representation for use in uncertainty propagation studies. An altern...
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Whole core analysis of BEAVRS benchmark for hot zero power condition using MVP3 with JENDL-5 J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-05 Motomu Suzuki, Yasunobu Nagaya
With the release of the latest Japanese evaluated nuclear data library JENDL-5, the prediction accuracy of JENDL-5 for neutronics parameters of the BEAVRS benchmark for the hot zero power condition...
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Measurements of keV-Neutron capture cross sections and capture gamma-ray spectra of 74,76,78,80,82Se J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-05 So Kamada, Masayuki Igashira, Tatsuya Katabuchi, Motoharu Mizumoto
The neutron capture cross sections and capture γ-ray spectra of 74,76,78,80,82Se were measured in a region from 15 to 100 keV and around 550 keV. A neutron time-of-flight method was used with a ns-...
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Characterization of a HPGe detector response for activation cross section measurements: regression method versus Monte Carlo method J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-02-05 Valentina Semkova, Naohiko Otuka, Arjan J. M. Plompen
The full energy peak efficiencies and covariances of a high purity germanium (HPGe) detector studied by the regression method and Monte Carlo method were compared. The impact of the obtained result...
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Measurement of neutron spectra for various thicknesses of concrete and steel shielding at 24-GeV/c proton beam facility using Bonner sphere spectrometer J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-25 Tetsuro Matsumoto, Akihiko Masuda, Eunji Lee, Toshiya Sanami, Takahiro Oyama, Tsuyoshi Kajimoto, Noriaki Nakao, Hiroshi Yashima, Seiji Nagaguro, Yoshitomo Uwamino, Seiya Manabe, Nobuhiro Shigyo, Hideki Harano, Robert Froeschl, Elpida Iliopoulou, Angelo Infantino, Stefan Roesler, Markus Brugger
Neutron energy spectra down to thermal energy were measured using a Bonner sphere spectrometer (BSS) for various thicknesses of concrete and steel shielding at the CERN/CHARM facility, where high-e...
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Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33 J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-25 Tatsuhiko Sato, Yosuke Iwamoto, Shintaro Hashimoto, Tatsuhiko Ogawa, Takuya Furuta, Shin-Ichiro Abe, Takeshi Kai, Yusuke Matsuya, Norihiro Matsuda, Yuho Hirata, Takuya Sekikawa, Lan Yao, Pi-En Tsai, Hunter N. Ratliff, Hiroshi Iwase, Yasuhito Sakaki, Kenta Sugihara, Nobuhiro Shigyo, Lembit Sihver, Koji Niita
The Particle and Heavy Ion Transport code System (PHITS) is a general-purpose Monte Carlo radiation transport code that can simulate the behavior of most particle species with energies up to 1 TeV ...
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EXFOR-Editor package for entering, processing and representing nuclear reaction data in the EXFOR format J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-25 G.N. Pikulina, S.M. Taova
EXFOR-Editor package for entering, editing and saving experimental nuclear reaction data in the EXFOR format has been developed at the Center of Nuclear Physics Data (CNPD) of the Russian Federal N...
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Preface to a special issue of journal of nuclear science and Technology on “Nuclear Data and Code Systems as a Basis of Nuclear Technology” J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-25 Satoshi Chiba, Hideo Harada, Naohiko Otuka, Go Chiba, Masayuki Hagiwara
Published in Journal of Nuclear Science and Technology (Vol. 61, No. 1, 2024)
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Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-27 Elvan Sahin, Brian Lattimer, Mohammad Amer Allaf, Juliana Pacheco Duarte
Due to the complexity of spill fire, predicting heat release rate (HRR) is a challenging aspect, therefore, identifying key contributors to uncertainty is essential to develop reliable models for f...
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Interaction of europium with calcium silicate hydrate under conditions saturated with groundwater J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-22 Taiji Chida, Kengo Suto, Tsugumi Seki, Yuichi Niibori
The barrier effect of calcium silicate hydrate (C – S – H), which is secondarily formed around a repository owing to the utilization of cementitious materials, was explored. Eu was employed as a ch...
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Reactor antineutrinos and novel application to real-time remote monitoring of nuclear reactors J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-25 Chikako Ishizuka, Karen Sasaki, Naoki Yamano, Tadashi Yoshida, Satoshi Chiba
We have constructed a computational scheme to obtain energy spectra of reactor antineutrinos, including the inverse β-decay process through which they were to be detected. The antineutrino spectra ...
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Effects of correlations in uncertainties of total cross section and elastic angular distribution for a deep penetration of 14-MeV neutrons in Cu J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-25 Naoki Yamano, Satoshi Chiba, Tsunenori Inakura, Chikako Ishizuka
Uncertainty in neutron reaction rates after penetrating a thick copper benchmark assembly was estimated based on two different kinds of Total Monte Carlo methods under random sampling methodology. ...
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Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-25 Kazuki Fujio, Shin Okumura, Chikako Ishizuka, Satoshi Chiba, Tatsuya Katabuchi
We have developed a novel theoretical method to obtain independent fission product yields and prompt neutron observables by connecting mass and total kinetic energy (TKE) distributions calculated b...
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Experimental and computational verifications of the dose calculation accuracy of PHITS for high-energy photon beam therapy J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-25 Naoya Kuga, Takuro Shiiba, Tatsuhiko Sato, Shintaro Hashimoto, Yasuyoshi Kuroiwa
This study aimed to assess the accuracy of the particle and heavy-ion transport code system (PHITS) for its application of clinical dosimetry in high-energy photon beam therapy. Percentage depth do...
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EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242 J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-25 Riko Okuyama, Naohiko Otuka, Go Chiba, Osamu Iwamoto
The 242Pu neutron-induced fission cross section was evaluated from 100 keV to 200 MeV. The experimental 242Pu and 235U fission cross sections and their ratios in the EXFOR library were reviewed and...
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Development of nuclear de-excitation model EBITEM Ver.2 J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-25 T. Ogawa, S. Hashimoto, T. Sato
The gamma de-excitation model of the general-purpose radiation transport code Particle and Heavy Ion Transport code System, called the Evaluated Nuclear Structure Data File (ENSDF)-Based Isomeric T...
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A simulation research on thermal-pressure coupling loading of a 1:3.2 containment Model J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-22 Xuze Zhao, Di Yao, Jingwei Gao, Jianyu Tan, Xiaowen Hao
Due to the important role of nuclear power plant containment in the prevention of nuclear leaks, it is of great necessity to study the containment model’s loading mechanism and gas distribution. Mo...
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Numerical analysis of flow-induced deflection of curved nuclear reactor fuel plates under high velocity flows J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-22 Junwen Zheng, Xiaoxin Wang, Li Shi, Wenli Guo, Qin Zhou
Plate-type fuel elements, widely used in high flux reactor (HFR), may experience collapse or vibration under high coolant flow rates. The study examined the behaviors of curved fuel plates under va...
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The effect of boron carbide doping content on the mechanical properties of polyethylene J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-16 X. Q. Pan, Y. Wu, S. Zhang
Boron carbide doped polyethylene (known as boron-containing polyethylene) is a commonly used neutron shielding material. The effect of doping on the mechanical properties of polyethylene is one of ...
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The relationship between human error and occupational stress of commissioning workers in nuclear power plants: the mediating effects of anxiety J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-02 Yuan Kuang, Shuicheng Tian, Guangli Li, Dejun Zhao, Tao Qing
The commissioning of a nuclear power plant (NPP) is a high-intensity job with severe consequences in the event of accidents. Commissioning workers are exposed to both mentally and physically demand...
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Human reliability analysis of shared equipment in multi-unit site J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-02 Wanxin Feng, Jinkai Wang, Zhixin Xu, Ming Wang, Li Wen, Yu Yu, Zecong Li
Currently, there is no mature method for calculating the probability of human failure that occurs in multi-unit. In this study, the single-unit HRA is expanded and improved, and we have compiled a ...
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Analytical studies on effects of wind on dispersion of hydrogen leaked in a Partially Open Space J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-04 Atsuhiko Terada, Ryuji Nagaishi
In order to elucidate ventilation and exhaust of hydrogen (H2) leaked in a partially open space (room) practically, the effects of outer wind (forced external flow) on them were studied analyticall...
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Development of a radiation tolerant laser-induced breakdown spectroscopy system using a single crystal micro-chip laser for remote elemental analysis J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-02 Koji Tamura, Ryuzo Nakanishi, Hironori Ohba, Takahiro Karino, Takuya Shibata, Takunori Taira, Ikuo Wakaida
For the development of the remote elemental analysis method in a radiation environment based on the laser-induced breakdown spectroscopy (LIBS), the radiation effects on the laser oscillation prope...
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Mean-field dependence of fragment-production cross sections in heavy-ion induced reactions calculated by antisymmetrized molecular dynamics J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2024-01-03 Yuta Mukobara, Toshiya Sanami, Akira Ono, Tsunenori Inakura, Tatsuya Katabuchi, Satoshi Chiba, Chikako Ishizuka
Dependence of the fragment production cross-sections in heavy-ion induced reactions on employed mean-field models was investigated based on antisymmetrized molecular dynamics. For this purpose, fiv...
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A review on failure behavior and life prediction of circulation pumps in lead-bismuth eutectic cooled reactors J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-28 Fan Wang, Fei Xiao, Ma Wensheng, Tianzhou Wang, Tao Wang
In advanced nuclear power systems, structure materials have compatibility problems with lead-bismuth eutectic coolants such as liquid metal corrosion, and the corrosion failure behavior of the circ...
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Investigation of random beam trips in a linear accelerator at the Japan proton accelerator research complex for the development of an accelerator-driven nuclear transmutation system J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-20 Hayanori Takei
In a proton linear accelerator (linac), the proton beam is sometimes unexpectedly interrupted because of the electrical discharge caused by radio frequency, device/equipment failure, and other fact...
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Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-20 Xing-Kang Su, Jin-Biao Zhang, Jing Qiu, Qi-Jian Chen, Yue-Feng Guo, Xian-Wen Li, Long Gu
The supercritical carbon dioxide Brayton cycle system is being considered for application in the power conversion system of advanced liquid metal fast reactors. One important research topic is the ...
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Technical research on rapid source term calculation and prediction technology of nuclear accidents based on Bayesian network J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-17 Mingliang Xie, Yuqing Chen, Lei Yu, Wei Wei, Boyu Chen, Zhengquan Xie, Xueyan Hou
How to evaluate and predict potential source terms quickly and effectively is very important for emergency response. In this paper, the traditional forward analysis calculation based on determinist...
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The effect of a cyclic bending load on the bending resistance of ballooned, ruptured, and oxidized Zircaloy-4 cladding J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-17 Feng Li, Takafumi Narukawa, Yutaka Udagawa
The seismic resistance of fuel cladding during the long-term core cooling after loss-of-coolant accidents (LOCAs) was investigated by performing cyclic four-point bending tests (4PBTs) of up to 100...
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Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-14 Takumi Abe, Kenji Nishihara
Direct disposal concepts of mixed oxide spent fuel (MOXSF) consumed in light water reactors were investigated via heat transfer calculation. The temperature of the buffer material surrounding the w...
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Monte Carlo burnup analysis of measured nuclide inventories on high-burnup PWR-UO2 and BWR-MOX fuels in the RUBUS program J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-06 Toru Yamamoto
To validate the nuclear data in JENDL-4.0 and obtain information to improve their accuracy, the analysis of the measured nuclide inventories of the high-burnup PWR UO2 and BWR MOX fuels in the REBU...
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Power profile analysis of criticality accidents involving fissile solution boiling with considering evaporation J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-05 Tomoaki Watanabe, Yuichi Yamane
The total fission energy released in a criticality accident involving fissile solution boiling tends to be high because the relatively high fission power continues during boiling. Simulating fissio...
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Proposal of uncertainty analysis methodology for L1PRA using Markov state-transition Model J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-04 Masanobu Haruhara, Hitoshi Muta, Yasuki Ohtori, Shohei Yamagishi, Shota Terayama
In recent years, digital devices have been increasingly introduced into various control systems in nuclear power plants, and digital devices are even used in reactor protection systems (RPS). These...
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Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-04 Guopeng Liang, Yunlong Wang, Guan Guan, Chaoguang Jin, Ming Chen
Floating nuclear power platform (FNPP), unlike onshore nuclear power plants, is subjected to periodic rolling loads at sea. These loads will have a more obvious impact on the flow characteristics a...
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A study on the establishment of database for local government disaster response and decision support system in the nuclear accidents J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-04 Eunghyeon Kim, Minho Cha, Younwon Park, Minsang Ryu, Sooyeun Park, Kyeongil Ahn, Wonjo Kim, Haeyeol Gong
Radiological disasters have been recognized as a prominent societal catastrophe worldwide since the Fukushima nuclear accident in 2011. In order to cope with such disasters, efforts have been made ...
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Request for 35Cl(n,p) reaction cross-section measurements and re-evaluations from the standpoint of molten chloride salt fast reactor design J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-04 Yoshihisa Tahara, Haruka Hirano, Satoshi Chiba, Hiroyasu Mochizuki, Tatsuya Katabuchi
A molten chloride salt fast reactor with inherent safety features is being studied in order to utilize spent fuel discharged from light-water reactors effectively and to reduce environmental burden...
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The development of petri net-based continuous Markov chain Monte Carlo methodology applying to dynamic probability risk assessment for multi-state resilience systems with repairable multi-component interdependency under longtermly thereat J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-01 Chun-Yen Li, Akira Watanabe, Akihiro Uchibori, Yasushi Okano
For all the nuclear reactor systems, quantitative assessment of the accident management (AM) effects against long-term external hazards became one of the essential issues after the lesson learned f...
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Thinning behavior of solid boron carbide immersed in molten stainless steel for core disruptive accident of sodium-cooled fast reactor J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-12-01 Yuki Emura, Toshihide Takai, Shin Kikuchi, Kenji Kamiyama, Hidemasa Yamano, Hiroki Yokoyama, Kan Sakamoto
Boron carbide (B4C)–stainless steel (SS) eutectic reaction behavior is one of the most important issues in the core disruptive accidents (CDAs) of sodium-cooled fast reactors (SFRs). In this study,...
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Evaluation of radiation dose caused by bremsstrahlung photons generated by high-energy beta rays using the PHITS and GEANT4 simulation codes J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-11-22 Yoshiaki Shikaze
High-energy beta-ray sources generate bremsstrahlung photons in the building materials, generated by the radioactive nuclides inside the nuclear reactor buildings emitted by the Fukushima Daiichi n...
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A new separation method of hydrogen isotope by dynamically created nonequilibrium state J. Nucl. Sci. Technol. (IF 1.2) Pub Date : 2023-11-21 Takashi Yabe, Takayoshi Norimatsu, Kohei Yamanoi, Feng Xiao
Composition of deuterium (heavy) water in light water was drastically reduced to one-half by one stage of a newly invented device that can create a nonequilibrium vapor state driven by a dynamic sy...