Comparison of US/FRG accident condition fuel failure and release models | Zendy

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Comparison of US/FRG accident condition fuel failure and release models

Author(s) -

John Bolin,

T. Dunn

Publication year - 1989

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/453988

Subject(s) - work (physics) , nuclear engineering , nuclear fission product , engineering , environmental science , fission products , forensic engineering , waste management , mechanical engineering

Although there are many differences between the High-Temperature Gas Cooled Reactor (HTGR) concepts being developed in the US and the High Temperature Reactor (HTR) concepts in the Federal Republic of Germany (FRG), the coated fuel particles are very similar. Significant benefits are achievable through cooperative research and exchange of information and data on the fuel performance and radionuclide retention in the coated fuel particles. This draft report describes cooperative work on HTGR safety research as agreed to in the "USA/FRG Umbrella Agreement for Cooperation in GCR Development: Safety Research Subprogram Plan," specifically, this work was conducted under Project Work Statement (PWS) S-6 titled "Fission Product Retention in Fuel," 9 refs., 12 figs., 4 tabs

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