Science and Technology of Nuclear Installations

Advanced Reactor Concepts and Fuel Cycle Technologies


Publishing date
01 Feb 2013
Status
Published
Submission deadline
23 Nov 2012

Lead Editor
Guest Editors

1General Atomics, 3550 General Atomics Court, San Diego, CA 92121-1122, USA

2Physics and Fuel Division (PFD), Directorate of Assessment and Analysis, Canadian Nuclear Safety Commission, 280 Slater Street, Ottawa, Ontario, Canada K1P 5S9


Advanced Reactor Concepts and Fuel Cycle Technologies

Description

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 decided to gather a collection of papers which cover the topical areas of new activities in advanced reactors and fuel cycle technologies and to publish these in this special issue.

We invite investigators to contribute original research as well as review articles. The main topic of this special issue is the advanced reactor and associated fuel cycle technologies that fulfill future nuclear fuel cycle requirements. Potential topics include, but are not limited to:

  • Nonconventional reactor concepts including fast/thermal reactors, generation IV reactors, and beyond-generation IV type reactors
  • Advanced fuel cycle technologies including open/closed fuel cycle, uranium/thorium fuels, and recovered fuels
  • Accident-tolerant and/or radiation-resistant fuel and materials for advanced reactor safety
  • Issues associated with advanced reactor fuel cycle

Before submission authors should carefully read over the journal's Author Guidelines, which are located at http://www.hindawi.com/journals/stni/guidelines/. Prospective authors should submit an electronic copy of their complete manuscript through the journal Manuscript Tracking System at http://mts.hindawi.com/ according to the following timetable:


Articles

  • Special Issue
  • - Volume 2013
  • - Article ID 185640
  • - Editorial

Advanced Reactor Concepts and Fuel Cycle Technologies

Hangbok Choi | Wei Shen
  • Special Issue
  • - Volume 2013
  • - Article ID 290362
  • - Review Article

Design Concept of Advanced Sodium-Cooled Fast Reactor and Related R&D in Korea

Yeong-il Kim | Yong Bum Lee | ... | Chiwoong Choi
  • Special Issue
  • - Volume 2013
  • - Article ID 127676
  • - Research Article

Modeling Forced Flow Chemical Vapor Infiltration Fabrication of SiC-SiC Composites for Advanced Nuclear Reactors

Christian P. Deck | H. E. Khalifa | ... | C. A. Back
  • Special Issue
  • - Volume 2013
  • - Article ID 618707
  • - Research Article

A Compact Gas-Cooled Fast Reactor with an Ultra-Long Fuel Cycle

Hangbok Choi | Robert W. Schleicher | Puja Gupta
  • Special Issue
  • - Volume 2013
  • - Article ID 154706
  • - Research Article

Multiphysics Model Development and the Core Analysis for In Situ Breeding and Burning Reactor

Shengyi Si
  • Special Issue
  • - Volume 2013
  • - Article ID 172518
  • - Research Article

Moderating Material to Compensate the Drawback of High Minor Actinide Containing Transmutation Fuel on the Feedback Effects in SFR Cores

Bruno Merk
  • Special Issue
  • - Volume 2013
  • - Article ID 343492
  • - Research Article

Current Status of Pyroprocessing Development at KAERI

Hansoo Lee | Geun-IL Park | ... | IL-Je Cho
  • Special Issue
  • - Volume 2013
  • - Article ID 879634
  • - Research Article

Improvement of Core Performance by Introduction of Moderators in a Blanket Region of Fast Reactors

Toshio Wakabayashi
  • Special Issue
  • - Volume 2013
  • - Article ID 352757
  • - Research Article

Simulation Strategy for the Evaluation of Neutronic Properties of a Canadian SCWR Fuel Channel

G. Harrisson | G. Marleau
  • Special Issue
  • - Volume 2013
  • - Article ID 867561
  • - Research Article

Study of Thorium-Plutonium Fuel for Possible Operating Cycle Extension in PWRs

Klara Insulander Björk | Cheuk Wah Lau | ... | Urban Sandberg
Science and Technology of Nuclear Installations
 Journal metrics
Acceptance rate33%
Submission to final decision62 days
Acceptance to publication40 days
CiteScore0.810
Impact Factor1.082
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