Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference7 articles.
1. Analytical calculation of the average Dancoff factor for a fuel kernel in a pebble bed high-temperature reactor;Bende;Nucl. Sci. Eng.,1999
2. Briesmeister J.F., 1997. MCNP™—A General Monte Carlo n-Particle Transport Code. Los Alamos National Laboratory, Version 4B, LA-12625.
3. The Monte Carlo method application in computation studies of fuel compositions with the HTGR coated particles of water-cooled reactors;Goltsev;Ann. Nucl. Energy,1997
4. International Atomic Energy Agency, 2001. Evaluation of High Temperature Gas Cooled Reactor Performance. Interim draft of First CRP-5 TECDOC.
5. Prediction calculations and experiments for the first criticality of the 10 MW High Temperature Gas-cooled Reactor-Test Module;Jing;Nucl. Eng. Des.,2002
Cited by
43 articles.
订阅此论文施引文献
订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献