Results 31 to 40 of about 9,780,048 (313)

Considering for the blanket structure scheme of HCCB DEMO

Theoretical and Applied Mechanics Letters, 2019
: For the solid blanket concept of helium cooled ceramic breeder (HCCB) demonstration fusion power plant (DEMO), a feasible blanket structure with configuration 2×X is proposed as considering relatively low temperature limit of neutron multiplier ...
Zhou Zhao, Zaixin Li, Xiaoyu Wang, Xueren Wang, Kaiming Feng   +4 more
doaj   +1 more source

Evaluated displacement and gas production cross-sections for materials irradiated with intermediate energy nucleons

EPJ Web of Conferences, 2017
Atomic displacement and gas production cross-sections were obtained for a number of materials to calculate radiation damage and gas production rate in nuclear- and fusion reactors, and neutron spallation sources.
Konobeyev Alexander Yu., Fischer Ulrich, Pereslavtsev Pavel E., Simakov Stanislav P., Akça Sibel   +4 more
doaj   +1 more source

A review of the application of artificial intelligence to nuclear reactors: Where we are and what's next

Heliyon, 2023
As a form of clean energy, nuclear energy has unique advantages compared to other energy sources in the present era, where low-carbon policies are being widely advocated. The exponential growth of artificial intelligence (AI) technology in recent decades
Qingyu Huang, Shinian Peng, Jian Deng, Hui Zeng, Zhuo Zhang, Yu Liu, Peng Yuan   +6 more
doaj   +1 more source

PointMTL: Multi-Transform Learning for Effective 3D Point Cloud Representations

IEEE Access, 2021
Effectively learning and extracting the feature representations of 3D point clouds is an important yet challenging task. Most of existing works achieve reasonable performance in 3D vision tasks by modeling the relationships among points appropriately ...
Yifan Jian, Yuwei Yang, Zhi Chen, Xianguo Qing, Yang Zhao, Liang He, Xuekun Chen, Wei Luo   +7 more
doaj   +1 more source

A Modified Multiobjective Self-Adaptive Differential Evolution Algorithm and Its Application on Optimization Design of the Nuclear Power System

Science and Technology of Nuclear Installations, 2019
A modified multiobjective self-adaptive differential evolution algorithm (MMOSADE) is presented in this paper to improve the accuracy of multiobjective optimization design in the nuclear power system.
Yunjia Yang, Shinian Peng, Li Zhu, Dan Zhang, Zhifang Qiu, Hongsheng Yuan, Lin Xian   +6 more
doaj   +1 more source

Time discretization sensitivity analysis for a rod ejection transient scenario in a generic SMR concept using Serpent/SUBCHANFLOW [PDF]

EPJ Web of Conferences
This paper analyses a control rod ejection transient scenario in a generic SMR concept using the multi-physics coupling tool which includes the Monte Carlo Serpent code (developed at VTT, Finland) and the subchannel thermal-hydraulic code SUBCHANFLOW ...
Huaccho Gianfranco, Sánchez-Espinoza Victor Hugo, Mercatali Luigi   +2 more
doaj   +1 more source

Microstructural Evolution and Vacancy Defect Formation in Mn–Mo–Ni RPV Steel Under Low Cycle Fatigue: Insights From EBSD and PALS

Advanced Engineering Materials, EarlyView.
Low‐cycle fatigue damage in Mn–Mo–Ni reactor pressure vessel steel is examined using a combined electron backscatter diffraction and positron annihilation lifetime spectroscopy approach. The study correlates texture evolution, dislocation substructure development, and vacancy‐type defect formation across uniform, necked, and fracture regions, providing
Apu Sarkar, Dhanadeep Dutta, G. Bharat Reddy   +2 more
wiley   +1 more source

Sensitivity and uncertainty analysis for the tritium breeding ratio of a DEMO fusion reactor with a helium cooled pebble bed blanket

EPJ Web of Conferences, 2017
An uncertainty analysis was performed for the tritium breeding ratio (TBR) of a fusion power plant of the European DEMO type using the MCSEN patch to the MCNP Monte Carlo code.
Nunnenmann Elena, Fischer Ulrich, Stieglitz Robert   +2 more
doaj   +1 more source

Experimental study on aerosol behavior in water pool scrubbing under severe accident conditions

International Journal of Advanced Nuclear Reactor Design and Technology, 2020
In severe accident of nuclear power plant, large quantities of steam and radioactive aerosol may release to the containment. Meanwhile, hydrogen may be generated by zirconium-steam reaction and released to the containment and mixed with steam and air to ...
Youyou Xu, Jian Deng, Zhiqiang Zou, Guangming Jiang, Xiaoli Wu   +4 more
doaj   +1 more source

Reactor User Interface Technology Development Roadmaps for a High Temperature Gas-Cooled Reactor Outlet Temperature of 750 degrees C [PDF]

, 2010
This report evaluates the technology readiness of the interface components that are required to transfer high-temperature heat from a High Temperature Gas-Cooled Reactor (HTGR) to selected industrial applications.
Mckirdy, Ian, null Ian Mckirdy
core   +1 more source