Published 1997 | Version v1
Miscellaneous Open

Thorium fuel cycle study for PWR applications

  • 1. Kyung Hee Univ., Seoul (Korea, Republic of)

Description

A nuclear design feasibility of thorium fueled high converting PWR was investigated. Two kinds of fuel design option were tested for the comparison with conventional UO2 fuel. The first one was an application of MHTGR pyro-carbon coated particle fuels. The other design was an application of MOX fuels as a ThO2-PuO2 ceramic pellet. In the case of carbon-coated particle fuels, there was no benefit in nuclear design aspect because enrichment of U-235 was required over 5 w/o in order to match with the K-infinite of Ulchin-3/4 fuels. However, the use of thorium based plutonium fuels in PWR gave favorable aspects in nuclear design such as flatter K-infinite curve, lower M. T. C. and lower F. T. C. than that of UO2 fuel. (author). 6 refs., 3 tabs., 6 figs

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Part of:
Proceedings of the second seminar on the new fuel technology toward the 21st century, November 25-26, 1997, Korea Atomic Energy Research Institute, Taejon, Korea

Additional details

Publishing Information

Publisher
KAERI.
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the second seminar on the new fuel technology toward the 21st century, November 25-26, 1997, Korea Atomic Energy Research Institute, Taejon, Korea
Imprint Pagination
198 p.
Journal Page Range
p. 69-77.
Report number
INIS-KR--0004

Conference

Title
2. Seminar on the new fuel technology toward the 21st century.
Dates
25-26 Nov 1997.
Place
Taejon (Korea, Republic of).

Optional Information