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NEA Document
A Code to Code Benchmark for High-Temperature Gas-Cooled Reactor Fuel Element Depletion
NEA/NSC/R(2019)1

The high-temperature gas-cooled reactor (HTGR) is a Generation IV reactor concept that uses a graphitemoderated gas-cooled nuclear reactor with a once-through uranium fuel cycle. This design permits ...

English Nuclear fuel Fuel studies Generation IV reactors Reactor physics Multiphysics Reactor physics Cogeneration NSC Gas-cooled reactors Benchmark …
Published date: 18 January 2019
Publications and Reports
Basic Studies in the Field of High-temperature Engineering

In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) and the need for improved knowledge of materials for nuclear applications that resist high temperatures, the NEA or...

English Generation IV reactors Nuclear science Gas-cooled reactors Multiphysics Proceedings Reactor physics …
Published date: 1 January 2000
Publications and Reports
Basic Studies in the Field of High-temperature Engineering

In response to increasing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, th...

English Generation IV reactors Nuclear science Gas-cooled reactors Multiphysics Proceedings Reactor physics …
Published date: 29 May 2002
Publications and Reports
Basic Studies in the Field of High-temperature Engineering

In response to growing interest in high-temperature, gas-cooled reactors (HTGRs) in many countries and the need for improved materials for nuclear applications in high-temperature environments, the N...

English Generation IV reactors Nuclear science Gas-cooled reactors Multiphysics Proceedings Reactor physics …
Published date: 1 June 2004