Fuel Cycle Analysis of Novel Assembly Design for Thorium-Uranium-Ceramic–Fueled Thermal, High-Conversion Reactor-Reference-Cited by-同舟云学术

Fuel Cycle Analysis of Novel Assembly Design for Thorium-Uranium-Ceramic–Fueled Thermal, High-Conversion Reactor

Published:2019-06-14 Issue:1 Volume:206 Page:48-72
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Kaffezakis N.¹^ORCID,Kotlyar D.¹

Affiliation:

1. Georgia Institute of Technology, Department of Nuclear and Radiological Engineering, Atlanta, Georgia

Funder

U.S. Nuclear Regulatory Commission

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2019.1616475

Reference27 articles.

1. F. SOKOLOV, K. FUKUDA, and H. P. NAWADA, “Thorium Fuel Cycle—Potential Benefits and Challenges,” IAEA-TECDOC-1450, International Atomic Energy Agency (2005).

2. Th/U-233 multi-recycle in PWRs.

3. “Nuclear Power Reactors in the World,” IAEA-RDS-2/37, 2017 ed., International Atomic Energy Agency (2016).

4. J. R. SMITH, S. D. REEDER, and R. G. FLUHARTY, “Measurement of the Absolute eta for U-233, U-235, and Pu-239 Using Monochromatic Neutrons,” IDO-17083, U. S. Atomic Energy Commission (1966).

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