Development of Advanced Fuel Handling Machine for JSFR

Katoh, Atsushi; Chikazawa, Yoshitaka; Obata, Hiroyuki; Kotake, Shoji

doi:10.1080/18811248.2010.9720962

Cited by 10 publications

(4 citation statements)

References 3 publications

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“…A full-scale mockup of the pantograph FHM has been manufactured to evaluate basic feasibility [11]. Major requirements on the FHM are as follows:…”

Section: Flexible Arm Type Pantograph Fhmmentioning

confidence: 99%

“…As a result of the fabrication tests, fin machining had no technical issues, and the high velocity oxygen Figure 5. Stress with design base seismic conditions [11]. fuel thermal process was selected because it was found to be more suitable for coating on the rather complicated shaped surface such as fin than the detonation process.…”

Section: Sodium Pot With Two Core Component Positionsmentioning

confidence: 99%

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JSFR key technology evaluation on fuel handling system

Chikazawa¹,

Katoh²,

Obata³

et al. 2014

Journal of Nuclear Science and Technology

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A simplified fuel handling system design for the demonstration Japan sodium-cooled fast reactor (JSFR) has been proposed. Fast Reactor Cycle Technology Development project phase I results of key technology evaluations on a pantograph fuel handling machine (FHM), a fuel transfer pot with two core component positions, dry spent fuel cleaning and minor actinide-bearing fresh fuel shipping cask are summarized. A full-scale FHM mockup has been fabricated and tested in the air accumulating performance and seismic tolerance data. A mockup fuel transfer pot with fins and chromium carbide coating has been fabricated and tested with sodium accumulating heat transfer performance data. Several sodium cleaning tests using a dummy subassembly has been conducted accumulating cleaning performance data. For fresh fuel shipping cask, a design tool for evaluation of heat transfer capability has been developed and a helium gas cask shows cooling capability of minor actinide-bearing fresh fuel. Those experimental and analytical efforts have shown that key technologies to develop simplified fuel handling system are matured enough to proceed large-scale sodium experiments and conceptual design study for the demonstration JSFR.

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“…A full-scale mockup of the pantograph FHM has been manufactured to evaluate basic feasibility [11]. Major requirements on the FHM are as follows:…”

Section: Flexible Arm Type Pantograph Fhmmentioning

confidence: 99%

Section: Sodium Pot With Two Core Component Positionsmentioning

confidence: 99%

JSFR key technology evaluation on fuel handling system

Chikazawa¹,

Katoh²,

Obata³

et al. 2014

Journal of Nuclear Science and Technology

Self Cite

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“…A full-scale mockup of the pantograph FHM has been manufactured to evaluate basic feasibility (Katoh, A., 2009(Katoh, A., , 2010a(Katoh, A., , 2010b. Major requirements on the FHM are as follows:…”

Section: Randd Status Of Key Technologies 31 Pantograph Fhmmentioning

confidence: 99%

Icone19-43727 Conceptual Design Study for the Demonstration Reactor of JSFR : (6) Fuel Handling System Design

Chikazawa¹,

Katoh²,

Obata³

et al. 2011

ICONE

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“…Thus, there is no need to move the UIS from the core top and a single rotation plug system is adopted. This fuel handling system using the UIS slit contributes to reduce the reactor vessel diameter [5]. Figure 2 shows the schematic view of the UIS design of JSFR and the geometry of the fuel subassembly outlet and the sampling nozzle.…”

Section: Introductionmentioning

confidence: 99%

Water experiment and numerical simulation on failed fuel detection and location system of Japan sodium-cooled fast reactor (JSFR)

Aizawa

Ohshima

Kamide

et al. 2012

Journal of Nuclear Science and Technology

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A conceptual design study of Japan sodium-cooled fast reactor (JSFR) is in progress as the ''Fast Reactor Cycle Technology Development (FaCT)'' project in Japan. A selector-valve type failed fuel detection and location (FFDL) system is applied to the JSFR design that has an upper internal structure (UIS) with a slit above the core and several sampling nozzles for the FFDL are set in the UIS around the slit to detect the fission product (FP) from the subassemblies below the slit. Therefore, mixing process in the UIS of complicated geometry should be known and appropriate arrangement of the sampling nozzles in the UIS is needed. A water experiment using a 1/5-scale model was carried out to investigate the mixing process in the UIS and concentration distribution of FP simulant. Experimental results showed that the sampling nozzles set in the UIS detected the FP simulant concentration within the criteria of FFDL signal detection, even in case of failed subassemblies under the UIS slit. In addition, identification of the failed fuel subassembly under the UIS slit was achieved by means of comparing concentration profiles in the UIS. Therefore, the suitable sampling nozzle arrangement was obtained for JSFR. A numerical simulation using a CFD code was carried out and the simulation method was validated based on the experimental data of the FP simulant concentrations. The simulation results showed that the simulation predicts the FP concentration distributions.

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Development of Advanced Fuel Handling Machine for JSFR

Cited by 10 publications

References 3 publications

JSFR key technology evaluation on fuel handling system

JSFR key technology evaluation on fuel handling system

Icone19-43727 Conceptual Design Study for the Demonstration Reactor of JSFR : (6) Fuel Handling System Design

Water experiment and numerical simulation on failed fuel detection and location system of Japan sodium-cooled fast reactor (JSFR)

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