Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Physics studies for sodium cooled ATW blanket

Abstract

Because the choice of blanket technologies is among the most important technical decisions faced in the Accelerator Transmutation of Waste (ATW) program, extensive system studies have been pursued on blanket design. A wide range of potential transmuter configurations and fuel cycle scenarios have been investigated using sodium, lead-bismuth eutectic (LBE), and gas as coolant. The primary objective has been to define the characteristics of a system that effectively consumes transuranics (TRU) separated from LWR spent fuel and minimizes TRU losses to the waste stream. For the liquid-metal cooled design studies, a fission-power level of 840 MWt was targeted, the same level previously adopted for the PRISM Advanced Liquid Metal Reactor (ALMR). The blanket is fueled with a non-uranium metallic dispersion fuel; pyrochemical techniques are used for recycle of residual TRU in this fuel after irradiation. Parametric studies were performed to optimize the sizing of the sodium cooled transmuter blanket, to mitigate the power peaking problems near the source region, and to assess startup core performance; results are summarized in this paper. Performance evaluations indicate that an average discharge burnup of 275 MWd/kg (29.5 atom%) is achieved with a 3.5 to 4 year fuel residence time. Reactivity loss over the half-year cycle is 4.9%Δk. The sodium coolant allows a compact core design with the volume reduced by ~1/3 compared to LBE cooled ATW blanket designs.

view the full text of this article (16 pages, format: PDF, size= 254kB)

Reference:

Proceedings of a Committee Meeting (TCM) on “Core Physics and Engineering Aspects of Emerging Nuclear Energy Systems for Energy Generation and Transmutation” held in Argonne, Illinois, U.S.A., 28 November - 1 December 2000

International Atomic Energy Agency, Vienna (Austria)

IAEA-TECDOC--1356, pp:94-109