Investigation on Slit Jet through Upper Internal Structure (UIS) in Highly Compact Vessel of Sodium-Cooled Fast Reactor

Kamide, Hideki; Aizawa, Kosuke; Ohshima, Jun; Nakayama, Oukatsu; Kasahara, Naoto

doi:10.3327/jnst.47.810

Cited by 3 publications

(4 citation statements)

References 1 publication

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“…Numerical simulation of velocity field using the similar method and mesh scheme was also carried out. Comparison of velocity distributions between experiments and analyses showed good agreements [8]. Thus, it is believed that this numerical analysis also provided well predicted velocity profiles in this 1/5-rectangular test model.…”

Section: Validation Of Concentration Analysissupporting

confidence: 64%

“…Furthermore, following findings were obtained from the 1/10-scale water experiment [8]. The 1/10-scale water experiment which modeled the whole reactor upper plenum of JSFR showed that the flow field around the UIS slit was mainly determined by the jet through the slit.…”

Section: Applicability Of Partial Modelmentioning

confidence: 67%

“…obtained by a 1/10-scale water experiment of JSFR reactor upper plenum [8]. Applied numerical options in this study were the same as in the simulation above and listed in Table 1.…”

Section: Numerical Simulation Methodsmentioning

confidence: 99%

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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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Section: Validation Of Concentration Analysissupporting

confidence: 64%

Section: Applicability Of Partial Modelmentioning

confidence: 67%

See 1 more Smart Citation

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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“…In the UIS region, there are no settle down effects, and thus, the flow distribution in the liquid region can be anticipated, because the flow from subassembly outlets could directly go through the UIS slit with much higher flow velocity than those of other ones. 6) From the viewpoint of the detection of failure fuel located under the slit by the sampling of gas from the fuel, the UIS slit is also desired to be narrow. 7) The FHM arm and gripper mechanism are supposed to be slim to keep the UIS slit narrow.…”

Section: Design Requirementsmentioning

confidence: 99%

Development of Advanced Fuel Handling Machine for JSFR

Katoh

Chikazawa

Obata

et al. 2010

Journal of Nuclear Science and Technology

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The Japan Sodium-cooled Fast Reactor (JSFR) has adopted an in-vessel fuel handling system that consists of a single rotating plug, an upper inner structure (UIS) with a vertically penetrating slit, and a fuel handling machine (FHM) with a pantograph arm enhancing a compact reactor vessel design. Since the reactor vessel design depends on the in-vessel fuel handling system, the feasibility of the JSFR compact reactor vessel design is directly related to the feasibility of the new FHM. In this study, we have fabricated a full-scale mock-up of the JSFR FHM and performed tests in air. From the tests, the FHM mock-up shows sufficient performance in terms of positioning accuracy, motion speed, and stiffness to ensure durability for practical use in commercial plants. Structural analyses have been conducted to validate and improve the seismic analysis model and the positioning control of the FHM. The numerical results are in good agreement with the vibration and positioning tests, showing that there is a sufficient possibility that the model has enough performance to conduct seismic analysis and improve positioning accuracy.

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Development of Failed Fuel Detection and Location System in Sodium-Cooled Large Reactors (Sampling Method of Failed Fuels under the Slit)

et al. 2011

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A conceptual design study of Japan Sodium-cooled Fast Reactor (JSFR) is in progress as an issue of the "Fast Reactor Cycle Technology Development (FaCT)" project in Japan. JSFR adopts a selector-valve mechanism for a failed fuel detection and location (FFDL) system. The Selector-Valve FFDL system identifies failed fuel subassemblies by sampling sodium from each fuel subassembly outlet and detecting fission product. One of the JSFR design features is employing an upper internal structure (UIS) with a radial slit, in which an arm of fuel handling machine can move and access the fuel assemblies under the UIS. Thus, JSFR cannot place sampling nozzles right above the fuel subassemblies located under the slit. In this study, appropriate sampling method for indentifying under-slit failed fuel subassemblies has been developed by water experiments.

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Investigation on Slit Jet through Upper Internal Structure (UIS) in Highly Compact Vessel of Sodium-Cooled Fast Reactor

Cited by 3 publications

References 1 publication

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

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

Development of Advanced Fuel Handling Machine for JSFR

Development of Failed Fuel Detection and Location System in Sodium-Cooled Large Reactors (Sampling Method of Failed Fuels under the Slit)

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