Xiaoxing Liu、Koji Morita、Hidemasa Yamano2020-08-04OpenAlex
Abstract Investigation of the eutectic reaction in a core disruptive accident of sodium cooled reactor is of importance since reactor criticality will be affected by the change in reactivity after eutectic reaction. In our previous study, a two-dimensional fast reactor safety analysis code, SIMMER-III, was extended to…
Nuclear reactor physics and engineeringNuclear Materials and PropertiesThermodynamic and Structural Properties of Metals and Alloys
Sei Hirano、Daisuke Hirasawa、Yoshihisa Kiyotoki 等 6 位作者2020-08-04OpenAlex
Abstract Background: When terminal stage of Severe Accident (SA) with no coolant injection at a nuclear power plant, the equipment that has cooled and solidified through water injection to a molten core that has ex-vessel and fallen outside of the pressure vessel will then be required to operate autonomously by heat d…
Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear and radioactivity studies
Jacob P. Gorton、Nicholas R. Brown2020-08-04OpenAlex
Abstract A control rod withdrawal (CRW) is a possible reactivity initiated accident (RIA) in modular high-temperature gas-cooled reactors (mHTGRs). The purpose of this study is to perform a sensitivity analysis of a CRW event in an mHTGR model using the systems code RELAP5-3D with point kinetics feedback to demonstrat…
Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Engineering Thermal-Hydraulics
Yasunori Yamamoto、Masayoshi Mori、Kosuke Ono 等 4 位作者2020-08-04OpenAlex
Abstract Isolation Condenser (IC) is one of the passive core cooling systems with natural circulation flow, which is effective for safety measures against station black out. Once core uncover occurs, hydrogen generated in the core affects operating condition of ICs. To use ICs as an important safety measure not only f…
Nuclear Materials and PropertiesCombustion and Detonation ProcessesNuclear Engineering Thermal-Hydraulics
Yong Mann Song、Jong Yeob Jung、Sunil Nijhawan2020-08-04OpenAlex
Abstract CANDU PHWR spent fuel pools (SFPs), smaller than a tennis court, contain up to 38,000 or more (49,000 in Wolsong)fuel bundles in geometries not replicated in any other power reactor. Therefore, the phenomenological issues, accident progression pathways and effectiveness of mitigative actions are somewhat diff…
Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear and radioactivity studies
Takeshi Aoki、Hiroyuki Satō、Hirofumi Ohashi2020-08-04OpenAlex
Abstract In the thermal hydraulic design of the prismatic-type of the high temperature gas cooled reactor (HTGR), unintended flows such as gap flows between columns, cross flows between column layers and gap flows between permanent reflectors should be analyzed to minimizing the unintended flows. The flow distribution…
Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Engineering Thermal-Hydraulics
Mohamed S. El‐Genk、Timothy M. Schriener2020-08-04OpenAlex
Abstract The walk-away safe, SLIMM and VSLLIM small and micro reactor designs have recently been developed at the University of New Mexico’s Institute for Space and Nuclear Power studies. These passive operation reactors concepts could generate 10–100 MWth and 1.0–10 MWth without refueling for 6.3–68 full power years…
Nuclear reactor physics and engineeringGraphite, nuclear technology, radiation studiesNuclear and radioactivity studies
Yue Zou、Brian Derreberry2020-08-04OpenAlex
Abstract Thermal cycling induced fatigue is widely recognized as one of the major contributors to the damage of nuclear plant piping systems, especially at locations where turbulent mixing of flows with different temperature occurs. Thermal fatigue caused by swirl penetration interaction with normally stagnant water l…
Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Engineering Thermal-Hydraulics
Zhichun Xu、Yapei Zhang、G.H. Su 等 5 位作者2020-08-04OpenAlex
Abstract In a postulated severe accident situation in Light Water Reactors (LWRs), if the core fuel cannot be effectively cooled, the reactor core material will be heated and form a molten corium in the lower head. When the lower plenum of the reactor vessel fails, the molten corium may flow into the cavity under the…
Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear and radioactivity studies
Junxiu Xu、Ming Ding、Changqi Yan 等 4 位作者2020-08-04OpenAlex
Abstract The Passive Residual Heat Removal System (PRHRS) is very important for the safety of the heating reactor after shutdown. PRHRS is a natural circulation system driven by density difference, therefore, the heat transfer performance of the Passive Residual Heat Removal Heat Exchanger (PRHR HX) has a great impact…
Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Engineering Thermal-Hydraulics
M. Kropík、Ján Rataj、Ladislav Reisner 等 4 位作者2020-08-04OpenAlex
Abstract The VR-1 training reactor with 500W maximum power operates at the Czech Technical University in Prague. Its control system was approaching obsolescence. It was therefore decided to upgrade the control system using up-to-date hardware and software using a new industrial PC with Windows 10 and the RTX real time…
Nuclear reactor physics and engineeringRadiation Effects in ElectronicsGraphite, nuclear technology, radiation studies
Ning Wang、Renze Wang、Yang Yapeng 等 7 位作者2020-08-04OpenAlex
Abstract Fukushima accident shows again that the probability of reactor accident exists even though it is extremely small. In case of emergency in nuclear power plant, emergency condition of the reactor plays an important role in decision making. During emergency response, especially early stage of severe accident wit…
Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear Engineering Thermal-Hydraulics
Kazuo Tominaga、Sohei Fukui、Motoi Tanaka 等 5 位作者2020-08-04OpenAlex
Abstract All of the boiling water reactors in Japan were required to install filtered containment venting system (FCVS) for restart after the accident of Fukushima Daiichi Nuclear Power Plant. FCVS is composed of alkaline water and a metal fiber filter (MFF). Alkaline water has the function of reducing aerosol and ino…
Covalent Organic Framework Applications
Eunhyun Ryu、Han Gyu Joo、Seungyul Yoo 等 4 位作者2020-08-04OpenAlex
Abstract Among the various parts in a pressurized heavy-water reactor (PHWR), pressure tubes are of tremendous importance. This is because they withstand extreme both pressure and temperature differences that exist between the Primary Heat Transport System (PHTS) and the moderator. The pressure tubes also contribute t…
Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear and radioactivity studies
Guanlin Shi、Conglong Jia、Shanfang Huang 等 5 位作者2020-08-04OpenAlex
Abstract With the increase interest in nuclear data sensitivity and uncertainty analysis, Many researches have developed new methods that can be used to perform sensitivity analysis for different response functions. In previous researches, several methods have been developed in the continuous-energy Reactor Monte Carl…
Nuclear reactor physics and engineeringProbabilistic and Robust Engineering DesignNuclear Materials and Properties
Liang Chen、Hua Pang、Ximing Xie 等 5 位作者2020-08-04OpenAlex
Abstract The transient stratification of the corium in the lower plenum and its impact on the heat flux distribution on the outside of reactor vessel is analyzed in this work. A method for predicting the kinetic corium pool structure is proposed, which takes into account both thermo-chemical equilibrium and density ev…
Fusion materials and technologiesNuclear reactor physics and engineeringNuclear Materials and Properties
Feryantama Putra2020-08-04OpenAlex
Abstract The subcritical fission system could be used to transmute actinide elements from spent fuel into thermal power. Since the subcritical system needs an external neutron source, the D-T Fusion reactor was introduced as a fast neutron source to drive the chain reaction. Fusion driven system based on Spherical tok…
Fusion materials and technologiesNuclear reactor physics and engineeringNuclear Materials and Properties
Li Rongpeng、Yumin Li、Sui Chunguang 等 4 位作者2020-08-04OpenAlex
Abstract With the change of anti-terrorism situation, civil unmanned aerial vehicles carrying small equivalent of explosives may cause damage to the reinforced concrete wall or roof of nuclear facilities at close range. Existing research has mostly focused on the overall damage caused by large equivalent explosives at…
High-Velocity Impact and Material BehaviorStructural Response to Dynamic LoadsTransportation Safety and Impact Analysis
Feng Li、Takeshi Mihara、Yutaka Udagawa 等 4 位作者2020-08-04OpenAlex
Abstract Fuel cladding may be subjected to biaxial tensile stress in axial and hoop directions during pellet-cladding mechanical interaction (PCMI) of a reactivity-initiated accident (RIA). Incipient crack in the hydride rim assisted by the scattered hydrides in the metal phase may lead to failure of the cladding at s…
Nuclear Materials and PropertiesPowder Metallurgy Techniques and MaterialsNuclear and radioactivity studies
Meng Dongyuan、Shutang Sun、Hongchao Sun 等 4 位作者2020-08-04OpenAlex
Abstract In this paper, a simplified typical radioactive material transport container model is used to change the thickness of the container insulation layer and the thickness of the heat sink respectively. The finite element method is used to simulate the heat transfer, and a quantitative optimization of the heat tra…
Graphite, nuclear technology, radiation studiesNuclear and radioactivity studies