Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident

Sato, Ikken; Tobita, Yoshiharu; Konishi, Kensuke; Kamiyama, Kenji; Toyooka, Jun-ichi; Nakai, Ryodai; Kubo, S.; Kotake, Shoji; Koyama, Kazuya; Vassiliev, Yuri S.; Vurim, Alexander; Zuev, V. A.; Kolodeshnikov, Alexander A.

doi:10.3327/jnst.48.556

Cited by 4 publications

(2 citation statements)

References 4 publications

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“…Self-levelling also helps to reduce the effective neutron multiplication factor by allowing more neutron leakage, thus decreasing the chances of recriticality. In the upcoming Japanese reactor JSFR, a multi tray core catcher is planned and the self-levelling mechanism is relied upon for even distribution of the debris [1]. They perceive self-levelling mechanism as the mechanism by which the debris depth will be automatically regulated to the level below which sodium boiling will not happen.…”

Section: Introductionmentioning

confidence: 99%

Experimental analysis of heaping and self-levelling phenomena in core debris using lead spheres

Sudha

Murthy

Kumaresan

et al. 2015

Experimental Thermal and Fluid Science

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Section: Introductionmentioning

confidence: 99%

Experimental analysis of heaping and self-levelling phenomena in core debris using lead spheres

Sudha

Murthy

Kumaresan

et al. 2015

Experimental Thermal and Fluid Science

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“…One of the future generation Sodium-cooled Fast Reactors (SFR) design strategies is to achieve In-Vessel Retention (IVR) for Core Disruptive Accident (CDA) (Suzuki et al, 2014;Sato et al, 2011). In CDA, molten fuel is discharged from the core region and becomes solidified particle debris with fuel-coolant interaction.…”

Section: Introductionmentioning

confidence: 99%

Study on high-speed calculation of debris bed coolability for sodium-cooled fast reactors

Matsuo¹,

Sasa²,

Abe

et al. 2020

Mechanical Engineering Journal

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Many sensitivity calculations are necessary to evaluate the effect of the uncertainties of Core Disruptive Accident (CDA) scenarios on debris bed coolability for Sodium-cooled Fast Reactors (SFR). This paper describes a calculation model and a technique for high-speed calculations of debris bed coolability. Firstly, the detailed coolability calculation model taking into account phase change and vapor-liquid advection for a boiling zone in the debris bed is derived as a single equation. The vapor-liquid advection is based on the momentum equation including inertial, viscous, capillary and gravitational effects. In addition, the streamlined calculation which ignores inertial and gravitational effects for the boiling zone is proposed. Secondly, both the detailed and streamlined calculation models are validated through the analysis of the Sandia ACRR-D10 in-pile experiments. Then, the effects of the ignoring on debris bed coolability are evaluated through sensitivity calculations. Thirdly, the speed-up technique for the streamlined calculation model is proposed which solves the boiling zone by the combination of transient and steady state calculations and allows using coarse mesh size and time step. Owing to the technique, the calculation time becomes about 1/50. The application of the speed-up technique to the streamlined calculation model is confirmed under typical SFR conditions. Finally, it is demonstrated that the streamlined calculation model and the speed-up technique enable us to perform many sensitivity calculations in a realistic time. The model and technique developed in this study is practical to evaluate the effect of the uncertainties of CDA scenarios on debris bed coolability for SFR.

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A Study on Mechanism of Early Failure of Inner Duct Wall within Fuel Subassembly with High Heat Flux from Molten Core Materials based on Analysis of an EAGLE Experiment Simulating Core Disruptive Accidents in an LMFBR

Toyooka

Endô

Tobita

et al. 2013

Nihon Genshiryoku Gakkai wabun rombunshi

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In the design of a Japanese sodium-cooled fast reactor (JSFR), a design measure (fuel subassembly with an inner duct structure; FAIDUS) is considered to prevent severe recriticality events even in the case of core disruptive accidents by molten fuel ejection out of the core region through the duct equipped within the fuel subassembly. Conˆrming the principle eŠectiveness of such a design measure is important. In this study, the systematic heat transfer behavior in the ID1 test, which was conducted in the impulse graphite reactor (IGR) in Republic of Kazakhstan, was evaluated by applying a heat conduction code TAC2D and a reactor safety analysis code SIMMER III focusing on the clariˆcation of heat transfer from a hightemperature mixture of molten fuel and steel to the duct. As a result, the duct failure caused by high heat ‰ux from the mixture was identiˆed as one of an important mechanisms of early duct failure in FAIDUS. It was also suggested from this study that the high heat ‰ux from the mixture is caused by the direct contact of molten steel in the absence of fuel crust on the duct wall. Based on theseˆndings, it is judged that the mechanism of early duct failure with high heat ‰ux obtained in the ID1 test satisˆes the required condition for FAIDUS, i.e., the inner duct of FAIDUS should fail at an early phase of core disruptive accident in advance of wrapper tube failure so that the produced molten fuel can escape from the core region, which supports the feasibility of the FAIDUS concept.

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Safety Strategy of JSFR Eliminating Severe Recriticality Events and Establishing In-Vessel Retention in the Core Disruptive Accident

Cited by 4 publications

References 4 publications

Experimental analysis of heaping and self-levelling phenomena in core debris using lead spheres

Experimental analysis of heaping and self-levelling phenomena in core debris using lead spheres

Study on high-speed calculation of debris bed coolability for sodium-cooled fast reactors

A Study on Mechanism of Early Failure of Inner Duct Wall within Fuel Subassembly with High Heat Flux from Molten Core Materials based on Analysis of an EAGLE Experiment Simulating Core Disruptive Accidents in an LMFBR

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