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Journal Articles

Experiments of melt jet-breakup for agglomerated debris formation using a metallic melt

Iwasawa, Yuzuru; Sugiyama, Tomoyuki; Abe, Yutaka*

Nuclear Engineering and Design, 386, p.111575_1 - 111575_17, 2022/01

Journal Articles

Melt impingement on a flat spreading surface under wet condition

Sahboun, N. F.; Matsumoto, Toshinori; Iwasawa, Yuzuru; Sugiyama, Tomoyuki

Proceedings of Asian Symposium on Risk Assessment and Management 2021 (ASRAM 2021) (Internet), 15 Pages, 2021/10

Journal Articles

Development of evaluation framework for ex-vessel core coolability

Matsumoto, Toshinori; Iwasawa, Yuzuru; Sugiyama, Tomoyuki

Proceedings of Reactor core and Containment Cooling Systems, Long-term management and reliability (RCCS 2021) (Internet), 8 Pages, 2021/10

A methodological framework is being developed in JAEA for evaluating debris coolability at ex-vessel during the severe accident (SA) of BWR under the wet cavity strategy. The probability of ex-vessel debris coolability under the wet cavity strategy is analyzed to demonstrate the evaluation approach. Probabilistic distribution of the melt conditions ejected from the RPV was obtained as the result of the iterative analyses with MELCOR code. Five uncertainty parameters relating with the core degradation and transfer process were chosen. Parameter sets were generated by Latin hypercube sampling (LHS). JASMINE code plays the physical model to predict the mass fraction of agglomerated debris and melt pool spreading on the floor. Fifty-nine input parameter set for JASMINE code were generated by LHS again using the probabilistic distribution of melt condition determined from the results of MELCOR analyses. The depth of the water pool was set as 0.5, 1.0 and 2.0 m. The accumulated debris height was compared with the criterion to judge the debris coolability. As the result, the success probability of debris cooling was obtained through the sequence of calculations.

Journal Articles

The Analysis for Ex-Vessel debris coolability of BWR

Matsumoto, Toshinori; Iwasawa, Yuzuru; Ajima, Kohei*; Sugiyama, Tomoyuki

Proceedings of Asian Symposium on Risk Assessment and Management 2020 (ASRAM 2020) (Internet), 10 Pages, 2020/11

The probability of ex-vessel debris coolability under the wet cavity strategy is analyzed. The first step is the uncertainty analyses by severe accident analysis code MELCOR to obtain the melt condition. Five uncertain parameters which are relating with the core degradation and transfer process were chosen. Input parameter sets were generated by LHS. The analyses were conducted and the conditions of the melt were obtained. The second step is the analyses for the behavior of melt under the water by JASMINE code. The probabilistic distribution of parameters are determined from the results of MELCOR analyses. Fifty-nine parameter sets were generated by LHS. The depth of water pool is set to be 0.5, 1.0 and 2.0 m. Debris height were compared with the criterion to judge the debris coolability. As the result, the success probability of debris cooling was obtained through the sequence of calculations. The technical difficulties of this evaluation method are also discussed.

Journal Articles

Development of a multiphase particle method for melt-jet breakup behavior of molten core in severe accident

Wang, Z.; Iwasawa, Yuzuru; Sugiyama, Tomoyuki

Proceedings of 2020 International Conference on Nuclear Engineering (ICONE 2020) (Internet), 12 Pages, 2020/08

Journal Articles

Formation of agglomerated debris in jet-breakup experiment using metallic melts

Iwasawa, Yuzuru; Sugiyama, Tomoyuki; Maruyama, Yu; Kaneko, Akiko*; Abe, Yutaka*

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 6 Pages, 2019/05

Journal Articles

Numerical study on influence of Ohnesorge number and Reynolds number on the jet breakup behavior using the lattice Boltzmann method

Iwasawa, Yuzuru*; Abe, Yutaka*; Kaneko, Akiko*; Kanagawa, Tetsuya*; Saito, Shimpei*; Matsuo, Eiji*; Ebihara, Kenichi; Sakaba, Hiroshi*; Koyama, Kazuya*; Nariai, Hideki*

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05

For the safety design in which heat is properly removed from the molten fuel after the core disruptive accident in a sodium-cooled fast reactor, the estimation of the breakup behavior of molten fuel discharged into the coolant like a jet is desired. In order to investigate the influence of viscocity on the jet behavior, we simulated a jet discharged into a coolant using the three-dimensional lattice Boltzmann model for two-phase fluid, and examined the influence of Ohnesorge number and Reynolds number on the jet behavior. As a result, we made clear that it is necessary to consider viscosity of the coolant as well as that of the jet for the estimation of jet behavior.

Journal Articles

Numerical simulation of jet breakup behavior by the lattice Boltzmann method

Matsuo, Eiji*; Abe, Yutaka*; Iwasawa, Yuzuru*; Ebihara, Kenichi; Koyama, Kazuya*

Nihon Kikai Gakkai Rombunshu (Internet), 81(822), p.14-00409_1 - 14-00409_20, 2015/02

In order to understand the jet breakup behavior of the molten core material into coolant during a core disruptive accident (CDA) for a sodium-cooled fast reactor (SFR), we simulated the jet breakup due to the hydrodynamic interaction using the lattice Boltzmann method (LBM). The applicability of the LBM to the jet breakup simulation was validated by comparison with our experimental data. In addition, the influence of several dimensionless numbers such as Weber number and Froude number was examined using the LBM. As a result, we validated applicability of the LBM to the jet breakup simulation, and found that the jet breakup length is independent of Froude number and in good agreement with the Epstein's correlation when the jet interface becomes unstable.

Journal Articles

Evaluation of jet breakup behavior by the lattice Boltzmann HCZ model, 1; Evaluation of jet breakup length

Matsuo, Eiji*; Abe, Yutaka*; Iwasawa, Yuzuru*; Ebihara, Kenichi; Kaneko, Akiko*; Sakaba, Hiroshi*; Koyama, Kazuya*

Dai-18-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.75 - 76, 2013/06

When supposing a core distractive accident (CDA) in a sodium-cooled fast reactor (SFR), it is necessary to understand the breakup behavior of the molten core material jet into coolant. Thus, the jet breakup was simulated by the lattice Boltzmann (LB) HCZ model. First, the applicability to jet breakup of the LBHCZ model was verified by comparing the simulation result to our experimental data. Next, from sensitive analyses by the simulation, it was found that the jet breakup length is in good agreement with Epstein's correlation when hydrodynamic fragmentation is a dominant phenomenon of the jet breakup.

Journal Articles

Evaluation of jet breakup behavior by the lattice Boltzmann HCZ model, 2; Effect of ambient fluid field on jet breakup

Iwasawa, Yuzuru*; Abe, Yutaka*; Matsuo, Eiji*; Ebihara, Kenichi; Kaneko, Akiko*; Sakaba, Hiroshi*; Koyama, Kazuya*

Dai-18-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.77 - 78, 2013/06

When supposing a core distractive accident (CDA) in a sodium-cooled fast reactor (SFR), it is necessary to understand the breakup behavior of the molten core material jet into coolant. In order to examine the effect of ambient fluid around the jet, the surface and fragmentation behavior was investigated using the lattice Boltzmann (LB) HCZ model. As a result, it was confirmed that the mechanism of the jet breakup behavior is one proposed by Epstein when hydrodynamic fragmentation is the dominant phenomenon for the jet break up.

Journal Articles

Influence of fragmentation on jet breakup behaviour

Iwasawa, Yuzuru*; Abe, Yutaka*; Kaneko, Akiko*; Kuroda, Taihei*; Matsuo, Eiji*; Ebihara, Kenichi; Sakaba, Hiroshi*; Koyama, Kazuya*; Ito, Kazuhiro*; Nariai, Hideki*

Proceedings of 15th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-15) (USB Flash Drive), 12 Pages, 2013/05

In the safety design of a Fast Breeder Reactor(FBR), when it is supposed that a Core Disruptive Accident(CDA) occurs, it is strongly required that molten core materials are completely solidified and are cooled down by sodium coolant in a reactor vessel. In this study, we injected molten alloy and transparent fluid, which are a simulant of the molten core material, into water, which is a simulant of the coolant. In this study, we injected molten alloy and transparent fluid, which simulate the molten core material, into water, which simulates the coolant. In the experiment, we observed the jet breakup behavior of them using a high speed video camera, and compared the observe images with the previous theories. In addition, we simulated numerically the qualitative behavior of the liquid jet using a two-phase fluid model of the lattice Boltzmann method.

Oral presentation

Study on quench behavior at core disruptive accident for fast breeder reactor, 23; Simulation of breakup behavior of liquid jet by lattice Boltzmann method

Iwasawa, Yuzuru*; Abe, Yutaka*; Kaneko, Akiko*; Saito, Shimpei*; Matsuo, Eiji*; Ebihara, Kenichi; Sakaba, Hiroshi*; Koyama, Kazuya*; Nariai, Hideki*

no journal, , 

Since there is a possibility that molten core is spouted out into coolant in the case of the core disruptive accident of a fast breeder reactor, it is important to predict the jet breakup length, which is the distance that the jet reaches, for proper cooling. The previous report discusses the adaptability of the simulation by the lattice Boltzmann model to the experiment of liquid jet by comparing to the experiment with air entrainment which is not considered in the model. In this presentation, we discussed the mechanism of jet breakup by comparing the simulation to the experiment without air entrainment. As a result, the model reproduced the jet behavior without air entrainment well, and the dimensionless number regarding the jet breakup length was almost same with that of the experiment. In addition, according to the flow velocity distribution obtained from the simulation, it was confirmed that vortexes at the leading-edge of the jet promote the jet breakup.

Oral presentation

Study on quench behavior at core disruptive accident for fast breeder reactor, 27; Numerical study on effect of viscosity on jet breakup behavior in liquid-liquid system using the lattice Boltzmann method

Iwasawa, Yuzuru*; Abe, Yutaka*; Kaneko, Akiko*; Kanagawa, Tetsuya*; Saito, Shimpei*; Matsuo, Eiji*; Ebihara, Kenichi; Sakaba, Hiroshi*; Koyama, Kazuya*; Nariai, Hideki*

no journal, , 

no abstracts in English

Oral presentation

Evaluation of molten core coolability in containment vessel using JASMINE code

Iwasawa, Yuzuru; Matsumoto, Toshinori; Kawabe, Ryuhei; Ajima, Kohei; Sugiyama, Tomoyuki; Maruyama, Yu

no journal, , 

For assessment the molten core coolability during severe accident in LWRs, we improved the models in the JASMINE code regarding to agglomeration of melt particles and melt spreading in containment vessel based on the DEFOR-A and the PULiMS experiments conducted by KTH. The improved models generally show good agreement with these experimental results.

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