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Science and Technology of Nuclear Installations
Volume 2013, Article ID 185640, 1 page

Advanced Reactor Concepts and Fuel Cycle Technologies

1General Atomics, 3550 General Atomics Court, San Diego, CA 92121-1122, USA
2Canadian Nuclear Safety Commission, 280 Slater Street, Ottawa, ON, Canada K1P 5S9

Received 7 April 2013; Accepted 7 April 2013

Copyright © 2013 Hangbok Choi and Wei Shen. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.

Nuclear power is an abundant source with zero CO2 output, and expanded fission power is an attractive option especially in growing countries. Various reactor concepts are being studied to comply with requirements of future nuclear fuel cycle such as safety, sustainability, cost-effectiveness, and proliferation risk reduction. These generation IV reactor concepts include both thermal and fast reactors and are being developed in conjunction with advanced reprocessing technology. In addition, beyond-generation IV type reactors are being developed, which mitigate the concern on the nuclear waste issue by adopting very high-burnup fuel and long-life core. Considering movement towards future nuclear cycle, we have collected papers which cover the topical areas of new activities in advanced reactors and fuel cycle technologies and published these in this special issue on advanced reactor concepts and fuel cycle technologies.

This special issue contains 10 research articles, including seven papers on advanced reactor concepts. The advanced reactor concept covers sodium-cooled fast reactor (SFR), gas-cooled fast reactor (GFR), supercritical water reactor (SCWR), and pressurized water reactor (PWR). The research topics include an advanced Korean SFR system design and analysis, improvement of Japanese SFR core performance by moderators in the blanket region, use of moderating materials to compensate the drawback of minor actinide containing transmutation fuel in European fast reactors, a multiphysics modeling technique for in situ breeding and burning reactors, an ultralong fuel cycle compact GFR system design and analysis, a simulation strategy for the evaluation of neutronic properties of a Canadian SCWR fuel channel, and a thorium-plutonium fuel cycle for operating cycle extension of a PWR. The special issue also includes research results on the modeling forced-flow chemical vapor infiltration for fabrication of SiC-SiC composite materials, development of inactive demonstration facility for a proliferation-resistant pyroprocessing technology, and the economic analysis of a closed fuel cycle.

Hangbok Choi
Wei Shen