The Advanced Recycling Reactor (ARR) design study sponsored by DOE of USA has been conducted [1]. This paper presents the pre-conceptual design of the ARR that is a loop-typed sodium cooled reactor with MOX fuel. The International Nuclear Recycling Alliance (INRA) takes advantage of international experience and agreed to use Japan Sodium-cooled Fast Reactor (JSFR) [2] as reference for Funding Opportunity Announcement (FOA) studies [1]. Since the scale-up factor of two is acceptable increase from manufacturing and licensing points of view, INRA proposes 3 evolutions of the ARR; ARR1, a 500 MWe demonstration plant, online in 2025; ARR2, a 1,000 MWe commercial plant, online in 2035; ARR3, a 1,500 MWe full-scale commercial plant, online in 2050. Japan has conducted R&Ds for the JSFR incorporating thirteen technology enhancements expected to improve safety, enhance economics, and increase reactor reliability. The ARR design is based on such the technology enhancements that it can benefit from this development effort and the ARR3 can become cost competitive with the similar sized LWRs. Major features of key technology enhancements are the following: Decay heat can be removed by natural circulation to improve safety. The primary cooling system consists of two-loop system and the integrated IHX/Pump to improve economics. The steam generator with the straight double-walled tube is used to improve reliability. The reactor core of the ARR1 is 70 cm high. The conversion ratio of fissile is set up less than 0.6 and the amount of burned TRU is 45–51 kg/TWeh. The ARR1 consists of a reactor building (including reactor auxiliary facilities and electrical / control systems), a turbine building, and a reprocessing building. The dimensions of the overall reactor building will be 46.1 m (W) × 72.8 m (L) × 70.3 m (H), and the volume of the building will be approximately 180,000 m3.
Skip Nav Destination
17th International Conference on Nuclear Engineering
July 12–16, 2009
Brussels, Belgium
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4351-2
PROCEEDINGS PAPER
Advanced Recycling Reactor Design Study
Makoto Mito,
Makoto Mito
Mitsubishi FBR Systems, Inc., Tokyo, Japan
Search for other works by this author on:
Shigeru Kunishima,
Shigeru Kunishima
Mitsubishi Heavy Industries, Ltd., Tokyo, Japan
Search for other works by this author on:
Kazumi Ikeda,
Kazumi Ikeda
Mitsubishi FBR Systems, Inc., Tokyo, Japan
Search for other works by this author on:
Horoyuki Sato
Horoyuki Sato
Mitsubishi Heavy Industries, Ltd., Tokyo, Japan
Search for other works by this author on:
Makoto Mito
Mitsubishi FBR Systems, Inc., Tokyo, Japan
Shigeru Kunishima
Mitsubishi Heavy Industries, Ltd., Tokyo, Japan
Kim O. Stein
AREVA NP, Inc., Lynchburg, VA
Kazumi Ikeda
Mitsubishi FBR Systems, Inc., Tokyo, Japan
Horoyuki Sato
Mitsubishi Heavy Industries, Ltd., Tokyo, Japan
Paper No:
ICONE17-75698, pp. 909-918; 10 pages
Published Online:
February 25, 2010
Citation
Mito, M, Kunishima, S, Stein, KO, Ikeda, K, & Sato, H. "Advanced Recycling Reactor Design Study." Proceedings of the 17th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems. Brussels, Belgium. July 12–16, 2009. pp. 909-918. ASME. https://doi.org/10.1115/ICONE17-75698
Download citation file:
10
Views
Related Proceedings Papers
Related Articles
Rotor Profiles Synthesis for Lobe Pumps With Given Flow Rate Functions
J. Mech. Des (March,2005)
Variability and Component Criticality in Component Reuse and Remanufacturing Systems
J. Comput. Inf. Sci. Eng (December,2010)
High-Stiffness, Lock-and-Key Heat-Reversible Locator-Snap Systems for the Design for Disassembly
J. Mech. Des (April,2009)
Related Chapters
New Generation Reactors
Energy and Power Generation Handbook: Established and Emerging Technologies
Evaluation of Leachability of Radium Contaminated Soil
Waste Testing and Quality Assurance: Third Volume
Machinery Recycling Experiment and Study on the Degradation Characteristics for Waste Thermosetting Plastics
International Conference on Computer Technology and Development, 3rd (ICCTD 2011)