Journal ArticleDOI
Evaluation of JSFR Key Technologies
Yoshitaka Chikazawa,Kazumi Aoto,Hiroki Hayafune,Shoji Kotake,Yushi Ohno,Takaya Ito,Mikio Toda +6 more
Reads0
Chats0
TLDR
In this paper, the authors evaluated the key technologies for Japan Sodium-cooled Fast Reactor (JSFR) and found that the ten technologies -high-burnup core, safety enhancement, compact reactor vessel, two-loop cooling system using...Abstract:
Key technologies for Japan Sodium-cooled Fast Reactor (JSFR) have been evaluated. The ten technologies - high-burnup core, safety enhancement, compact reactor vessel, two-loop cooling system using ...read more
Citations
More filters
Journal ArticleDOI
Ferritic-martensitic steels for fission and fusion applications
TL;DR: In this article, the challenges associated with the use of high chromium Ferritic/Martenstic (FM) steels in advanced fission reactors are addressed, including fabrication, joining and codification issues.
Journal ArticleDOI
Thermal transient test and strength evaluation of a tubesheet structure made of Mod.9Cr–1Mo steel. Part II: Creep-fatigue strength evaluation
Masanori Ando,Shinnichi Hasebe,Sumio Kobayashi,Naoto Kasahara,Akira Toyoshi,Takahiro Ohmae,Yasuhiro Enuma +6 more
TL;DR: In this paper, the strength of a tubesheet test model simulating a semispherical tubesheet structure subjected to cyclic thermal transients was evaluated using the finite element analysis (FEA).
Journal ArticleDOI
Thermal transient test and strength evaluation of a tubesheet structure made of Mod.9Cr–1Mo steel. Part I: Test model design and experimental results
Masanori Ando,Shinnichi Hasebe,Sumio Kobayashi,Naoto Kasahara,Akira Toyoshi,Takahiro Ohmae,Yasuhiro Enuma +6 more
TL;DR: In this article, a cyclic thermal loading test was performed using a tubesheet model test structure made of Mod.9Cr-1Mo steel, which was subjected to 1873 cycles of severe thermal transient loads using a large-scale sodium loop, in which sodium heated to 600 and 250°C was flowed repeatedly with periods for each transient of 2 and 1h, respectively.
Journal ArticleDOI
Severe External Hazard on Hypothetical JSFR in 2010
TL;DR: In this paper, severe external hazards on the Japan Sodium-cooled Fast Reactor (JSFR) have been analyzed and evaluated, and safety components are confirmed to maintain their functions even against...
Journal ArticleDOI
JSFR key technology evaluation on fuel handling system
TL;DR: A simplified fuel handling system design for the demonstration Japan sodium-cooled fast reactor (JSFR) has been proposed in this article, where a full-scale FHM mockup has been fabricated and tested in the air accumulating performance and seismic tolerance data.
References
More filters
Journal ArticleDOI
Development of 9Cr-ODS Martensitic Steel Claddings for Fuel Pins by means of Ferrite to Austenite Phase Transformation
TL;DR: In this article, Fe-0.12C-9Cr-2W ODS martensitic steel claddings were developed by cold-rolling under the softened ferrite phase induced by slow cooling from austenite phase to break up substantially elongated grains produced by cold rolling at the final heat treatment.
Journal ArticleDOI
Characterization of high temperature creep properties in recrystallized 12Cr-ODS ferritic steel claddings
Shigeharu Ukai,Takanari Okuda,Masayuki Fujiwara,Toshimi Kobayashi,S Mizuta,Hideharu Nakashima +5 more
TL;DR: In this article, the high temperature strengthening mechanism of previously manufactured 12Cr-ODS ferritic steel claddings was clarified, and the grain boundary sliding associated with grain morphology was considered to be controlled by the near Σ11, Σ and Σ19 coincidence boundaries with a (110) common axis.
Journal ArticleDOI
Experimental Study on Gas Entrainment at Free Surface in Reactor Vessel of a Compact Sodium-Cooled Fast Reactor
TL;DR: In this paper, the authors investigate the occurrence of gas entrainment under certain conditions and the mechanism of the gas entrainedment in an innovative sodium-cooled fast-reactor.