Results 121 to 130 of about 3,602,304 (354)

Study on the effect of high temperature on the pore structure and closed-pore gas release behavior of nuclear-grade graphite IG110

Nuclear Engineering and Technology
As one of the fourth-generation nuclear energy systems, the Very High Temperature Gas cooled Reactors (VHTRs) face significant challenges related to material corrosion and radionuclide generation caused by impurity gases in the helium coolant.
Penghui Xiao, Huang Zhang, Bin Du, Huaqiang Yin, Xuedong He, Tao Ma   +5 more
doaj   +1 more source

Experimental and Numerical Study on Pressure Distribution of 90° Elbow for Flow Measurement

Science and Technology of Nuclear Installations, 2014
Numerical simulation is performed to investigate the pressure distribution of helium gas under high pressure and high temperature for 10 MW High Temperature Gas-Cooled Reactor (HTGR-10).
Beibei Feng, Shiming Wang, Shengqiang Li, Xingtuan Yang, Shengyao Jiang   +4 more
doaj   +1 more source

Uncertainty analysis of large risk assessment models with applications to the railway safety and standards board safety risk model

, 2009
Probabilistic risk analysis aims to assess the safety risk of a system so that actions can then be taken to improve safety. Uncertainty however always exists in modelling. For more informed decision making, uncertainty in the outputs of the model must be
Cheng, Doasheng, Cheng, Daosheng
core   +1 more source

Study on the performance of membrane reactor using steam methane reforming for hydrogen production heated by HTGR

Nuclear Engineering and Technology
Using High-Temperature Gas-cooled Reactor (HTGR) for hydrogen production through steam methane reforming (SMR) offers advantages such as high hydrogen yield, methane savings, relatively low cost, and ease of scale-up.
Chengye Wu, Baozhi Wu, Huang Zhang, Huaqiang Yin   +3 more
doaj   +1 more source

THORIA EHANCEMENT OF NUCLEAR REACTOR SAFETY

, 2013
The recent nuclear accident in Fukushima demonstrates that a nuclear mishap should be viewed using interdisciplinary tools. For example, the urania fuel melts not only because of enhanced neutron flux but also because its thermal conductivity degrades ...
B. Szpunar, J. Szpunar
semanticscholar   +1 more source

Accident Analysis in Research Reactors

The first Research Reactor reaches its criticality on 2nd December 1942. Nowadays, more than 300 research reactors are currently in operation. Over the past fifty years, research reactors have progressed through a variety of tasks.
Adorni, Martina
core  

Report to the President for year ended June 30, 2015, Nuclear Reactor Laboratory

, 2015
This report contains the following sections: Reactor Administration; Educational Impact; Facilities and Resources; Reactor Operations; Reactor Engineering; Reactor Research Facilities and Services; Reactor Research, Development, and Utilization ...
Moncton, David E.
core  

Report to the President for year ended June 30, 2009, Nuclear Reactor Laboratory

, 2009
This report includes the following sections: Facilities and Resources; Reactor Administration; Reactor Operations; Reactor Research Facilities and Services; Reactor Research, Development, and Utilization; Reactor Engineering; Research Programs; New ...
Moncton, David E.
core  

Reactor operation safety information document

, 1990
The report contains a reactor facility description which includes K, P, and L reactor sites, structures, operating systems, engineered safety systems, support systems, and process and effluent monitoring systems; an accident analysis section which ...

core   +1 more source

Report to the President for year ended June 30, 2004, Nuclear Reactor Laboratory

, 2004
This report contains the following sections: MIT Research Reactor; Reactor Administration and Organization; Organizational Diversity; Safety and Security; Relicensing and Redesign; Major Reactor Services; Research ...
Moncton, David E.
core