Fuel cycle performance of intermediate spectrum reactors with U/Th feed and continuous recycling of U/TRU and Th/U3

Nicholas Brown, Michael Todosow

Research output: Chapter in Book/Report/Conference proceedingConference contribution

1 Citation (Scopus)

Abstract

This paper documents fuel cycle analysis of an intermediate spectrum critical reactor with natural uranium and thorium as feed materials and continuous recycling of uranium with transuranics and thorium with uranium (mainly 233U). The objective of the effort was to determine the impacts of both intermediate spectrum and U/Th feed versus the reference fast spectrum and U-only feed case. In this context the intermediate energy regime is considered to be between 1 eV and 0.1 MeV. The potential benefits of introducing thorium into the natural resource feed include extending the availability of uranium resources as well as potential operational/safety benefits, particularly related to the void coefficient in some reactor designs. Two systems were analyzed at a near-equilibrium condition, a high void boiling water reactor with 54% of fissions occurring in the intermediate energy regime and a D20 cooled pressurized water reactor with 65% of fissions occurring in the intermediate energy regime. The systems analyzed in this study were determined to be self-sustaining at equilibrium when accounting for loss rates in fabrication and separations, and exhibit similar resource utilization when compared to a fast system. Differences in performance versus a fast system are driven to some extent by the fact that eta for 233U and 239Pu at intermediate energies is never as high as for 239Pu at fast energies.

Original languageEnglish (US)
Title of host publication5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015
Subtitle of host publicationAdvances in Nuclear Fuel Management V
PublisherAmerican Nuclear Society
Pages1-18
Number of pages18
ISBN (Electronic)9781510808034
StatePublished - 2015
Event5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015 - Hilton Head, United States
Duration: Mar 29 2015Apr 1 2015

Other

Other5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015
CountryUnited States
CityHilton Head
Period3/29/154/1/15

Fingerprint

Uranium
Thorium
Recycling
Boiling water reactors
Pressurized water reactors
Natural resources
Availability
Fabrication

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering
  • Fuel Technology
  • Energy Engineering and Power Technology

Cite this

Brown, N., & Todosow, M. (2015). Fuel cycle performance of intermediate spectrum reactors with U/Th feed and continuous recycling of U/TRU and Th/U3. In 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V (pp. 1-18). American Nuclear Society.
Brown, Nicholas ; Todosow, Michael. / Fuel cycle performance of intermediate spectrum reactors with U/Th feed and continuous recycling of U/TRU and Th/U3. 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V. American Nuclear Society, 2015. pp. 1-18
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Brown, N & Todosow, M 2015, Fuel cycle performance of intermediate spectrum reactors with U/Th feed and continuous recycling of U/TRU and Th/U3. in 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V. American Nuclear Society, pp. 1-18, 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015, Hilton Head, United States, 3/29/15.

Fuel cycle performance of intermediate spectrum reactors with U/Th feed and continuous recycling of U/TRU and Th/U3. / Brown, Nicholas; Todosow, Michael.

5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V. American Nuclear Society, 2015. p. 1-18.

Research output: Chapter in Book/Report/Conference proceedingConference contribution

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Brown N, Todosow M. Fuel cycle performance of intermediate spectrum reactors with U/Th feed and continuous recycling of U/TRU and Th/U3. In 5th Topical Meeting on Advances in Nuclear Fuel Management, ANFM 2015: Advances in Nuclear Fuel Management V. American Nuclear Society. 2015. p. 1-18