Results 1 to 10 of about 1,705,201 (196)

VALIDATION OF SRAC CODE SYSTEM FOR NEUTRONIC PARAMETERS CALCULATION OF THE PWR MOX/UO2 CORE BENCHMARK

Urania, 2021
VALIDATION OF SRAC CODE SYSTEM FOR NEUTRONIC PARAMETERS CALCULATION OF THE PWR MOX/UO2 CORE BENCHMARK. Determination of neutronic parameter value is an important part in determining reactor safety, so accurate calculation results can be obtained.
Wahid Luthfi, Surian Pinem
doaj   +1 more source

Study of Gas Amplification Impact on Plateau Curve Characteristics in Boron-Coated Proportional Counters

Energies
The characteristics of the plateau curve, specifically its length and slope, in boron-coated proportional counters are key performance indicators that impact the detector’s overall performance.
Yaolong Liu, Zhi Chen, Youjun Huang, Tingfang Luo, Hongliang Zhu, Wenchao Wu   +5 more
doaj   +1 more source

Phase Distribution for Subcooled Flow Boiling in an Inclined Circular Tube

International Journal of Photoenergy, 2018
An experimental investigation of phase distribution for subcooled flow boiling in an inclined circular tube (i.d. 24 mm) was conducted in this paper.
Wei Bao, JianJun Xu, TianZhou Xie, BingDe Chen, YanPing Huang, DianChuan Xing   +5 more
doaj   +1 more source

Investigation of Turbulence and Turbulent Prandtl Number Models for He-Xe Thermal Hydraulics in Quasi-Triangular Channel

Energies
Compact nuclear reactor systems usually use helium–xenon (He-Xe) mixtures as coolants. Tight-lattice rod-bundled channels, serving as primary core configurations in compact nuclear reactor designs, exhibit quasi-triangular cross-sections where fluid ...
Yue Xie, Wei Zeng, Zonglan Wei, Junlong Li, Rui Li   +4 more
doaj   +1 more source

Accuracy Improvement of Neutron Nuclear Data on Minor Actinides

EPJ Web of Conferences, 2015
Improvement of accuracy of neutron nuclear data for minor actinides (MAs) and long-lived fission products (LLFPs) is required for developing innovative nuclear system transmuting these nuclei.
Harada Hideo, Iwamoto Osamu, Iwamoto Nobuyuki, Kimura Atsushi, Terada Kazushi, Nakao Taro, Nakamura Shoji, Mizuyama Kazuhito, Igashira Masayuki, Katabuchi Tatsuya, Sano Tadafumi, Takahashi Yoshiyuki, Takamiya Koichi, Pyeon Cheol Ho, Fukutani Satoshi, Fujii Toshiyuki, Hori Jun-ichi, Yagi Takahiro, Yashima Hiroshi   +18 more
doaj   +1 more source

A Multi-Variable Coupled Control Strategy Based on a Deep Deterministic Policy Gradient Reinforcement Learning Algorithm for a Small Pressurized Water Reactor

Energies
The reactor system has multivariate, nonlinear, and strongly coupled dynamic characteristics, which puts high demands on the robustness, real-time demand, and accuracy of the control strategy.
Jie Chen, Kai Xiao, Ke Huang, Zhen Yang, Qing Chu, Guanfu Jiang   +5 more
doaj   +1 more source

Impact of silicon on neutronic performance and microstructural evolution of FeCrAl alloys for ATF cladding

EPJ Nuclear Sciences & Technologies
FeCrAl alloys are promising candidate for accident tolerant fuel (ATF) cladding in light water-cooled nuclear reactors (LWRs) due to their excellent high-temperature oxidation resistance and mechanical strength.
Ngarayana I. Wayan, Mulyana Dany, Andryansyah, Saragi Elfrida, Sony Tjahyani Damianus Toersiwi, Citra Amelia Almira, Farihin Parikin, Djuliana Safiya   +7 more
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Research and development for accuracy improvement of neutron nuclear data on minor actinides

EPJ Web of Conferences, 2017
To improve accuracy of neutron nuclear data on minor actinides, a Japanese nuclear data project entitled “Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides (AIMAC)” has been implemented.
Harada Hideo, Iwamoto Osamu, Iwamoto Nobuyuki, Kimura Atsushi, Terada Kazushi, Nakao Taro, Nakamura Shoji, Mizuyama Kazuhito, Igashira Masayuki, Katabuchi Tatsuya, Sano Tadafumi, Shibahara Yuji, Takahashi Yoshiyuki, Takamiya Koichi, Pyeon Cheol Ho, Fukutani Satoshi, Fujii Tosiyuki, Hori Jun-ichi, Yashima Hiroshi   +18 more
doaj   +1 more source

Analysis of the physical properties of a boron meter based on He-3 neutron detector

Alexandria Engineering Journal
Boron meter is commonly used for real-time monitoring of boron concentration in the primary circuit water of pressurized water reactors to ensure the safe operation of the reactor.
Qi-Dong Dai, Guo-En Fu, Can-Hui Wang, Xun-Cheng Zong, Hong-Bo Wang, Can Cui   +5 more
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Physical analysis of PRC reactor based on zero power physical experiments

Ain Shams Engineering Journal
The Pulsed Reactor of China (PRC) can provide a stable neutron field for neutron science applications, with a steady-state rated power of 1 MW. This study aims to provide a comprehensive physical analysis of the PRC reactor through an integrated approach
Qi-Dong Dai, Jiang Niu, Ming-Chang Wu, Yi-Fan Zhang, Li-Yuan Huang, Na Zhang, Tian-Xiong Wang, Lin-Feng Yang, Yong-Mu Yang, Wen-Cong Wang   +9 more
doaj   +1 more source