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Title: Self-Sustaining Thorium Boiling Water Reactors

The primary objectives of this project are to: Perform a pre-conceptual design of a core for an alternative to the Hitachi proposed fuel-self- sustaining RBWR-AC, to be referred to as a RBWR-Th. The use of thorium fuel is expected to assure negative void coefficient of reactivity (versus positive of the RBWR-AC) and improve reactor safety; Perform a pre-conceptual design of an alternative core to the Hitachi proposed LWR TRU transmuting RBWR-TB2, to be referred to as the RBWR-TR. In addition to improved safety, use of thorium for the fertile fuel is expected to improve the TRU transmutation effectiveness; Compare the RBWR-Th and RBWR-TR performance against that of the Hitachi RBWR core designs and sodium cooled fast reactor counterparts - the ARR and ABR; and, Perform a viability assessment of the thorium-based RBWR design concepts to be identified along with their associated fuel cycle, a technology gap analysis, and a technology development roadmap. A description of the work performed and of the results obtained is provided in this Overview Report and, in more detail, in the Attachments. The major findings of the study are summarized.
Authors:
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  1. Univ. of California, Berkeley, CA (United States)
  2. Univ. of Michigan, Ann Arbor, MI (United States)
  3. Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
  4. Brookhaven National Lab. (BNL), Upton, NY (United States)
Publication Date:
OSTI Identifier:
1183773
Report Number(s):
DOE/NEUP--11-3023
11-3023; TRN: US1500407
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
Univ. of California, Berkeley, CA (United States); Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States); Univ. of Michigan, Ann Arbor, MI (United States); Brookhaven National Lab. (BNL), Upton, NY (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE). Nuclear Energy University Programs (NEUP)
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; REACTOR SAFETY; VOID COEFFICIENT; THORIUM; SODIUM COOLED REACTORS; DESIGN; REACTOR CORES; TRANSURANIUM ELEMENTS; NUCLEAR FUELS; COMPARATIVE EVALUATIONS; FUEL CYCLE; COMMERCIALIZATION; PERFORMANCE; TRANSMUTATION; BWR TYPE REACTORS