34
Views
2
CrossRef citations to date
0
Altmetric
Regular Technical Paper

R&D in Support of ASTRID and JSFR: Cross-Analysis and Identification of Possible Areas of Cooperation

, , , &
Pages 170-186 | Published online: 10 Aug 2017

REFERENCES

  • K. Aizawa, “R&D for Fast Reactor Fuel Cycle Technologies in JNC,” Proc. GLOBAL 2001, Paris, France, 2001.
  • Y. Chikazawa, S. Kotake, and S. Sawada, “Comparison of Pool/Loop Configurations in the JAEA Feasibility Study 1999-2006,” Proc. Int. Conf. Fast Reactors and Related Fuel Cycles: Challenges and Opportunities, Kyoto, Japan, 2009, International Atomic Energy Agency (2009).
  • S. Kotake et al., “Feasibility Study on Commercialized Fast Reactor Cycle Systems, Current Status of the FR System Design,” Proc. Global 2005, Tsukuba, Japan, October 9–13, 2005.
  • Y. Sagayama, “Launch of Fast Reactor Cycle Technology Development Project in Japan,” Proc. Global 2007, Boise, Idaho, September 9–13, 2007, American Nuclear Society (2007).
  • H. Niwa, “Current Status and Perspective of Advanced Loop Type Fast Reactor in Fast Reactor Cycle Technology Development Project,” Proc. Global 2007, Boise, Idaho, September 9–13, 2007, American Nuclear Society (2007).
  • T. Sakai et al., “Conceptual Design Study Toward the Demonstration Reactor of JSFR,” Proc. ICAPP ’10, San Diego, California, June 13–17, 2010, American Nuclear Society (2010).
  • K. Aoto et al., “Japan JSFR Design Study and R&D Progress in the FaCT Project,” Proc. Int. Conf. Fast Reactors and Related Fuel Cycles: Challenges and Opportunities, Kyoto, Japan, 2009, International Atomic Energy Agency (2009).
  • Y. Chikazawa et al., “Conceptual Design for a Large-Scale Japan Sodium-Cooled Fast Reactor (1) Feasibility of Key Technologies,” Proc. ICAPP 2011, Nice, France, May 2–5, 2011.
  • Basic Safety Principles for Nuclear Power Plant 75-INSAG-3 Rev. 1,” INSAG-12, International Nuclear Safety Advisory Group Report, International Atomic Energy Agency (1999).
  • S. Kubo et al., “Status of Conceptual Safety Design Study of Japanese Sodium-Cooled Fast Reactor,” Proc. Global 2005, Tsukuba, Japan, October 9–13, 2005.
  • S. Kotake et al., “Safety Design Features for JSFR— Passive Safety and CDA Mitigation,” Proc. Annual Mtg. Nuclear Technology, Dresden, Germany, 2009.
  • N. Nishiyama, “Japan JSFR Design Study and R&D Progress in the FaCT Project,” Proc. Int. Conf. Fast Reactors and Related Fuel Cycles: Challenges and Opportunities, Kyoto, Japan, 2009, International Atomic Energy Agency (2009).
  • JSME S NA1:2002, “Codes for Nuclear Power Generation Facilities—Rules on Fitness-for-Service for Nuclear Power Plants,” Japan Society of Mechanical Engineers, Tokyo, Japan.
  • ASME Boiler and Pressure Vessel Code, Sec. XI, “Rules for In-Service Inspection of Nuclear Power Plant Components,” American Society of Mechanical Engineers, New Yorks.
  • S. Beils et al., “Safety Approach and R&D Program for Future French Sodium-Cooled Fast Reactors,” J. Nucl. Sci. Technol., 48, 4, 1 (2011).
  • G. François et al., “Sodium Fast Reactor Concepts,” Proc. ICAPP ’08, Anaheim, California, June 8–12, 2008, American Nuclear Society (2008).
  • J. Rouault, J.-P. Serpantié, and D. Verwaerde, “French R&D Program on SFR and the ASTRID Prototype,” Proc. Int. Conf. Fast Reactors and Related Fuel Cycles: Challenges and Opportunities, Kyoto, Japan, 2009, International Atomic Energy Agency (2009).
  • E. Breui, A. Villedieu, and M. Saez, “Assessment of Pool Type Sodium Fast Reactor Design Options,” Proc. ICAPP2011, Nice, France, May 2–5, 2011.
  • F. Baqué et al., “Challenges and R&D Program for Improving Inspection of Sodium Cooled Fast Reactors and Systems,” Proc. Int. Conf. Fast Reactors and Related Fuel Cycles: Challenges and Opportunities, Kyoto, Japan, 2009, International Atomic Energy Agency (2009).
  • J. Sibilo et al., “Generation IV Nuclear Reactors: Strategy and Challenges of R&D Program for Improving Inspection and Repair of Sodium Cooled Systems,” Proc. ICAPP ’10, San Diego, California, June 13–17, 2010, American Nuclear Society (2010).
  • P. Le COZ, J-P. Serpantie, and J-F. Sauvage, “Sodium-Cooled Fast Reactors: The ASTRID Plant Project,” Proc. ICAPP2011, Nice, France, May 2–5, 2011.
  • G. Mignot et al., “Preliminary Analysis to Guide the Choice of the Power Capacity of the Future French Sodium Fast Reactor Prototype,” Proc. ICAPP ’10, San Diego, California, June 13–17, 2010, American Nuclear Society (2010).
  • B. Giraud et al., “Innovative Steam Generator Concepts for Sodium Fast Reactors,” Proc. ICAPP ’08, Anaheim, California, June 8–12, 2008, American Nuclear Society (2008).
  • M. Saez et al., “The Use of Gas Based Energy Conversion Cycles for Sodium Fast Reactors,” Proc. ICAPP ’08, Anaheim, California, June 8–12, 2008, American Nuclear Society (2008).
  • M. Chassignet et al., “Challenges and Innovative Technologies on Fuel Handling Systems for Future Sodium Cooled Fast Reactors,” Proc. Int. Conf. Fast Reactors and Related Fuel Cycles: Challenges and Opportunities, Kyoto, Japan, 2009, International Atomic Energy Agency (2009).
  • J. L. Seran et al., “Behaviour Under Neutron Irradiation of the 15/15 Ti andEM10 Steels Used as Standard Materials of the PHENIX Fuel Subassembly,” presented at 15th Int. Symp. Effects of Radiation on Materials, Nashville, Tennessee, 1990s.
  • J. S. Benjamin, “Dispersion Strengthened Superalloys by Mechanical Alloying,” Metallurgical Trans.,” 1, 2943 (Oct. 1970).
  • Ph. DUBUISSON et al., “Behavior of an Oxide Dispersion Strengthened Ferritic Steel Irradiated in Phénix,” Effects of Radiation on Materials, 18th International Symposium, ASTM STP 1325, R. K. Nanstad et al., Eds., American Society for Testing and Materials, West Conshohocken, Pennsylvania (1999).
  • S. Beils et al., “Safety Objectives of SEPIA Systems for Sodium-Cooled Fast Reactor,” Proc. ICAPP ’10, San Diego, California, June 13–17, 2010, American Nuclear Society (2010).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.