Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor
Joint Authors
van Rooijen, W. F. G.
Yamaguchi, Katsuhisa
Arita, Yuji
Mochizuki, Hiroyasu
Takeda, Toshikazu
Uno, Masayoshi
Source
Science and Technology of Nuclear Installations
Issue
Vol. 2012, Issue 2012 (31 Dec. 2012), pp.1-13, 13 p.
Publisher
Hindawi Publishing Corporation
Publication Date
2012-04-24
Country of Publication
Egypt
No. of Pages
13
Main Subjects
Engineering Sciences and Information Technology
Abstract EN
This paper discusses the objectives and results of a multiyear R&D project to improve the modeling accuracy for the detailed calculation of the Japanese Sodium-cooled Fast Reactor (JSFR), although the preliminary design of JSFR is prepared using conventional methods.
For detailed design calculations, new methods are required because the JSFR has special features, which cannot be accurately modeled with existing codes.
An example is the presence of an inner duct in the fuel assemblies.
Therefore, we have developed new calculational and experimental methods in three areas: (1) for neutronics, we discuss the development of methods and codes to model advanced FBR fuel subassemblies, (2) for fuel materials, modeling and measurement of the thermal conductivity of annular fuel is discussed, and (3) for thermal hydraulics, we describe advances in modeling and calculational models for the intermediate heat exchanger and the calculational treatment of thermal stratification in the hot plenum of an FBR under low flow conditions.
The new methods are discussed and the verification tests are described.
In the validation test, measured data from the prototype FBR Monju is partly used.
American Psychological Association (APA)
Takeda, Toshikazu& van Rooijen, W. F. G.& Yamaguchi, Katsuhisa& Uno, Masayoshi& Arita, Yuji& Mochizuki, Hiroyasu. 2012. Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor. Science and Technology of Nuclear Installations،Vol. 2012, no. 2012, pp.1-13.
https://search.emarefa.net/detail/BIM-465058
Modern Language Association (MLA)
Takeda, Toshikazu…[et al.]. Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor. Science and Technology of Nuclear Installations No. 2012 (2012), pp.1-13.
https://search.emarefa.net/detail/BIM-465058
American Medical Association (AMA)
Takeda, Toshikazu& van Rooijen, W. F. G.& Yamaguchi, Katsuhisa& Uno, Masayoshi& Arita, Yuji& Mochizuki, Hiroyasu. Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor. Science and Technology of Nuclear Installations. 2012. Vol. 2012, no. 2012, pp.1-13.
https://search.emarefa.net/detail/BIM-465058
Data Type
Journal Articles
Language
English
Notes
Includes bibliographical references
Record ID
BIM-465058