Triso
National Institutes of Health
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The study simulated the design basis accidents (DBAs) sequences of the HTR-10GT core with THERMIX. When a DBA happens, the…
In the High Temperature Gas-Cooled Reactor (HTGR) the TRISO particle fuel serves as the primary fission product containment…
A neutronic feasibility study is performed to evaluate the utilization of fully ceramic microencapsulated (FCM) fuel in the…
When the chord length sampling (CLS) method is used to analyze radiation transport in a finite region consisting of a stochastic…
The PUMA project is a Specific Targeted Research Project of the European Union EURATOM 6th Framework Program. Complementary with…
The success of gas reactors depends upon the safety and quality of the coated particle fuel. The understanding and evaluation of…
Abstract. In anticipation of future licensing applications for gas-cooled reactors, the United States Nuclear Regulatory…
Abstract A new type of nuclear reactor is presented that consists of a graphite-walled tube partly filled with TRISO-coated fuel…
The fuel particle system for the steam cycle cogeneration HTGR being developed in the US consists of 20% enriched UC/sub 0/./sub…