Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Thorium utilization in PWRs: status of work in the cooperative Brazilian/German program

Peehs, M.; Schlosser, G. (Kraftwerk Union A.G., Erlangen (Germany, F.R.)); Pinheiro, R.B. (Empresas Nucleares Brasileiras SA, Belo Horizonte); Maly, V. (Kernforschungsanlage Juelich G.m.b.H. (Germany, F.R.)); Hrovat, M. (Nuklear-Chemie und -Metallurgie G.m.b.H. (NUKEM), Hanau (Germany, F.R.))

Abstract

The major results of the program ''Th-Utilization in PWR's'' are presented and discussed: The investigations show that the standard KWU-PWR can accommodate (Th,U)O2 and (Th,Pu)O2 fuel without changes in the fuel element design, in 3 and 4-batch operation scheme, without penalties in the reactor performance. An advanced fuel fabrication scheme using direct pelletizing methods out of ex-gel microspheres has been developed on laboratory scale. The (Th,U)O2 test fuel produced satisfies PWR-specification and is currently undergoing irradiation testing. Thermal and mechanical design of fuel pins with thoria-based fuel is validated by the current instrumented single rod irradiation test. Cold laboratory investigations indicate that the (Th,U)O2 PWR-fuel can be reprocessed using presently known technology, including the chop-leach technique and modified THOREX extraction process.

view the full text of this article (17 pages, format: PDF, size= 719kB)

key words: fuel pins; performance testing; planning; pwr type reactors; reactor cores; recycling; research programs; specifications; thorium cycle; thorium
Reference:
Proceedings of a technical committee meeting on utilization of thorium-based nuclear fuel: current status and perspectives held in Vienna, 2-4 December 1985
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--412, pp:28-44