HTGR Reactor Physics and Fuel Cycle Studies

The high-temperature gas-cooled reactor (HTGR) appears as a good candidate for the next generation of nuclear power plants. In the HTGR_n project of the European Union Fifth Framework Program, analyses have been performed on a number of conceptual HTGR designs, derived from reference pebble-bed and hexagonal block-type HTGR types. It is shown that several HTGR concepts are quite promising as systems for the incineration of plutonium and possibly minor actinides. These studies were mainly concerned with the investigation and intercomparison of the plutonium and actinide burning capabilities of a number of HTGR concepts and associated fuel cycles, with emphasis on the use of civil plutonium from spent LWR uranium fuel (first generation Pu) and from spent LWR MOX fuel (second generation Pu).

KUIJPER J.C.;  RAEPSET X;  DE HAAS J.B.M.;  VON LENSA Werner;  OHLIG U.;  RUETTEN H.J.;  BROCKMANN H.;  DAMIAN F.;  DOLCI F.;  BERNNAT W.;  OPPE J.;  KLOOSTERMAN Jan Leen;  CERULLO Nicola;  LOMONACO G.;  NEGRINI A.;  MAGILL Joseph;  SEILER R.; 

2006-05-31

ELSEVIER SCIENCE BV

JRC33598

https://publications.jrc.ec.europa.eu/repository/handle/JRC33598,   

10.1016/j.nucengdes.2005.10.021,