Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: On some issues of thorium fuel cycle study

Abstract

In conceptual aspect, various reactor systems have been under study. They include PWRs fueled with Pu-Th and 233U-Th, molten salt reactors, fast reactors with mixed Pu-233U -Th 238U fuel cycle. Burning of plutonium in thorium matrix makes it possible to convert plutonium into 233U. In the long term, ecological hazard of 233U thorium fuel cycle may appear to be lower, compared to uranium-plutonium one. 233U plus 238U blend may be good fuel for thermal reactors. Considerable efforts have been concentrated on studies of initial steps for mastering thorium cycle. In this connection, investigated were issues such as 233U accumulation in thorium in various neutron spectra, methods for obtaining 233U with 232U levels acceptable for its simpler handling. A series of such experiments was carried out with different reactors. These experiments have confirmed the probability o initial accumulation of 233U in fast reactors in the form allowing a simpler subsequent handling. This is important for experimental works on mastering the technologies of 233Th fuel cycle. The program includes also the development and tests of technologies for radiochemical separation of 233U from thorium, technological studies with samples of thorium and 233U. Experiments with critical assemblies and nuclear constant measurements are also a part of the programme for thorium and 233U studies.

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Reference:

Proceedings of three IAEA meetings held in Vienna in 1997, 1998 and 1999

International Atomic Energy Agency, Vienna (Austria)

IAEA-TECDOC--1319, pp:316-320