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Journal Articles

Analytical tool development for coarse break-up of a molten jet in a deep water pool

Moriyama, Kiyofumi; Nakamura, Hideo; Maruyama, Yu*

Nuclear Engineering and Design, 236(19-21), p.2010 - 2025, 2006/10

 Times Cited Count:21 Percentile:82.37(Nuclear Science & Technology)

A computer code JASMINE-pre was developed for the prediction of premixing conditions of fuel-coolant interactions and the debris bed formation behavior relevant to severe accidents of light water reactors. JASMINE-pre consists of three melt component models: melt jet, melt particles and melt pool, coupled with a two-phase flow model derived from the ACE-3D code developed at JAERI. Simulations of the FARO corium quenching experiments with a saturated water pool and with a subcooled water pool were performed with JASMINE-pre and ${tt pmjet}$. JASMINE-pre reproduced the pressurization and fragmentation behaviors observed in the experiments with a reasonable accuracy. The results by pmjet showed qualitatively the same trend with JASMINE-pre in the fragmentation behavior.

JAEA Reports

Coarse break-up of a stream of oxide and steel melt in a water pool (Contract research)

Moriyama, Kiyofumi; Maruyama, Yu; Usami, Tsutomu*; Nakamura, Hideo

JAERI-Research 2005-017, 173 Pages, 2005/08

JAERI-Research-2005-017.pdf:11.17MB

A series of experiments on the break-up of high temperature oxide and steel melt jets in a water pool was conducted. The objective was to obtain data for the jet break-up length and size distribution of the droplets produced by the jet break-up, and information on the influence of material properties. Also, we tried to obtain additional information giving a clue to the mechanism governing the melt jet break-up, such as flow intensity of the steam column surrounding the melt jet, and its relation with the droplet size. In the experiments, zirconia-alumina mixture and stainless steel melt jets with diameter $$sim$$17mm and velocity $$sim$$7.8m/s at the water surface were dropped into a deep (2.1m) or shallow (0.6m) water pool with various subcool. From the results of the present experiments and also by referring other experimental data from literature, we obtained empirical correlation equations for the jet break-up length, the fraction of jet broken-up in a shallow pool where the jet was not completely broken-up, and the droplet size.

JAEA Reports

Study on steam explosions with molten silicon

Moriyama, Kiyofumi; Maruyama, Yu*; Nakamura, Hideo

JAERI-Research 2002-021, 36 Pages, 2002/11

JAERI-Research-2002-021.pdf:6.0MB

Silicon is a material which is easily oxidized like zirconium which is one of the LWR core materials. Also, its steam explosion behavior is a concern in semi-conductor industries where its melt is handled. In this study, steam explosion behavior of silicon melt and contribution of oxidation reaction in a steam explosion were investigated. Two cases of experiments were performed by dropping silicon melt into a water pool and both produced spontaneous steam explosions. Energy conversion ratio was 4--9% which was similar or slightly larger compared with previous experiments with thermite melt. Fragmentation of the melt was finer than previous experiments and the mass median diameter of the debris was 65--85$$mu$$m. An oxide layer of about 5$$mu$$m thick was fond on the debris surface indicating possibility of oxidation of several % of the melt.

Journal Articles

Visualization and measurement of subcooled water jet injection into high-temperature melt by using high-frame-rate neutron radiography

Shibamoto, Yasuteru; Kukita, Yutaka*; Nakamura, Hideo

Nuclear Technology, 139(3), p.205 - 220, 2002/09

 Times Cited Count:25 Percentile:83.26(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Current status of study on fuel-coolant interactions (FCIs) relevant to LWR severe accidents

Moriyama, Kiyofumi; Nakamura, Hideo; Hirano, Masashi

Nihon Kikai Gakkai Dai-8-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu, p.209 - 214, 2002/06

Through a review of experimental works on steam explosions and consideration on the uncertainty in the methodology for plant scale analysis of each stage of the phenomena, it was identified that the molten jet breakup process in premixing has an important uncertainty caused by lack of experimental knowledge. Based on this perspective, an experimental work are under planning at Japan Atomic Energy Research Institute (JAERI), in which the premixing stage of steam explosions in a deep water pool is modeled by high temperature oxide melts. Melt material and scale of the experiment were examined in terms of the simulation capability of the jet breakup mechanism in a plant scale phenomena. Materials and geometrical scale considered adequate were found.

Journal Articles

Development of fuel-coolant interaction analysis code

Moriyama, Kiyofumi; Maruyama, Yu; Nakamura, Hideo; Hashimoto, Kazuichiro; Kamo, Hideki*; Onuki, Akira; Akimoto, Hajime

Dai-7-Kai Doryoku Enerugi Gijutsu Shimpojiumu Koen Rombunshu (00-11), p.451 - 456, 2000/11

no abstracts in English

JAEA Reports

An Evaluation study of measures for prevention of Re-criticality in sodium-cooled large FBR with MOX fuel

JNC TN9400 2000-038, 98 Pages, 2000/04

JNC-TN9400-2000-038.pdf:7.49MB

As an effort in the feasibility study on commercialized Fast Breeder Reactor cycle systems, an evaluation of the measures to prevent the energetic re-criticality in sodium-cooled large MOX core, which is one of the candidates for the commercialized reactor, has been performed. The core disruptive accident analysis of Demonstration FBR showed that the fuel compaction of the molten fuel by radial motion in a large molten core pool had a potential to drive the severe super-prompt re-criticality phenomena in ULOF sequence. ln order to prevent occurrence of the energetic re-criticality, a subassembly with an inner duct and the removal of a part of LAB are suggested based on CMR (Controlled Material Relocation) concept. The objective of this study is the comparison of the effectiveness of CMR among these measures by the analysis using SIMMER-III. The molten fuel in the subassembly with inner duct flows out faster than that from other measures. The subassembly with inner duct will work effectively in preventing energetic re-criticality. Though the molten fuel in the subassembly without a part of LAB flows out a little slower, it is still one of the promising measures. However, the UAB should be also removed from the same pin to prevent the fuel re-entries into the core region due to the pressurization by FCl below the core, unless it disturbs the core performance. The effect of the axial fuel length of the center pin to CMR behavior is small, compared to the effect of the existence of UAB.

Journal Articles

Visualization and measurment of subcooled water jet injection into molten alloy

Shibamoto, Yasuteru; Kukita, Yutaka*; Nakamura, Hideo; Park, H. S.*; Anoda, Yoshinari

Proceedings of 8th International Conference on Nuclear Engineering (ICONE-8) (CD-ROM), p.12 - 0, 2000/00

no abstracts in English

JAEA Reports

Fundamental experiments on accumulation behavior of molten fuel in a pressure vessel lower head

Shibamoto, Yasuteru; Nakamura, Hideo; Anoda, Yoshinari; Kukita, Yutaka*

JAERI-Tech 99-042, 41 Pages, 1999/05

JAERI-Tech-99-042.pdf:3.36MB

no abstracts in English

JAEA Reports

ALPHA visual data collection STX005-025; Melt drop steam explosion experiments

Moriyama, Kiyofumi; ; Maruyama, Yu; Kudo, Tamotsu; Sugimoto, Jun

JAERI-Data/Code 99-017, 34 Pages, 1999/03

JAERI-Data-Code-99-017.pdf:7.96MB

no abstracts in English

JAEA Reports

The Premixing and propagation phases of fuel-coolant interactions; A Review of recent experimental studies and code developments

A.R.Antariksawan*; Moriyama, Kiyofumi; H.Park*; Maruyama, Yu; Y.Yang*; Sugimoto, Jun

JAERI-Review 98-012, 66 Pages, 1998/09

JAERI-Review-98-012.pdf:3.36MB

no abstracts in English

JAEA Reports

Assessment of loads and performance of a containment in a hypothetical accident (ALPHA); Facility design report

; Maruyama, Yu; Kudo, Tamotsu; Moriyama, Kiyofumi; Ito, Hideo; ; ; Sugimoto, Jun

JAERI-Tech 98-019, 105 Pages, 1998/06

JAERI-Tech-98-019.pdf:4.03MB

no abstracts in English

Journal Articles

The Effect of system constraint on coolant injection mode of energetic fuel-coolant interactions

Park, H.; Yamano, Norihiro; Maruyama, Yu; Moriyama, Kiyofumi; Yang, Y.; Sugimoto, Jun

Dai-35-Kai Nihon Dennetsu Shimpojiumu Koen Rombunshu, 3, p.803 - 804, 1998/00

no abstracts in English

Journal Articles

Study on subcooled water injection into molten material

Park, H.; ; Moriyama, Kiyofumi; Maruyama, Yu; Y.Yang*; Sugimoto, Jun

Proc. of 11th Int. Heat Transfer Conf. (Heat Transfer 1998), 6, p.69 - 74, 1998/00

no abstracts in English

Journal Articles

Effect of water jet dynamics in the coolant injection mode of fuel-coolant interactions

H.S.Park*; ; Maruyama, Yu; Moriyama, Kiyofumi; Y.Yang*; Sugimoto, Jun

Proc. of 1998 ASME/JSME Joint Pressure Vessels and Piping Conf., 362, p.49 - 56, 1998/00

no abstracts in English

Journal Articles

Study on energetic fuel-coolant interaction in the coolant injection mode of contact

H.Park*; ; Maruyama, Yu; Moriyama, Kiyofumi; Y.Yang*; Sugimoto, Jun

Proc. of 6th Int. Conf. on Nucl. Eng. (ICONE-6) (CD-ROM), 12 Pages, 1998/00

no abstracts in English

Journal Articles

Interaction between high speed water jet and quiescent high temperature melt pool

H.Park*; ; Maruyama, Yu; Moriyama, Kiyofumi; Y.Yang*; Sugimoto, Jun

Proceedings of 1st Korea-Japan Symp. on Nuclear Thermal Hydraulics and Safety (NTHAS 98), 8 Pages, 1998/00

no abstracts in English

Journal Articles

Current trends of thermal-hydraulic research on severe accident

Nariai, Hideki*; Sugiyama, Kenichiro*; Kataoka, Isao*; Mishima, Kaichiro*; *; Monde, Masanori*; Sugimoto, Jun; ; Hidaka, Akihide; *; et al.

Nihon Genshiryoku Gakkai-Shi, 39(9), p.739 - 752, 1997/00

 Times Cited Count:1 Percentile:13.16(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Visualization study of molten metal-water interaction by using neutron radiography

Mishima, Kaichiro*; Hibiki, Takashi*; *; *; Moriyama, Kiyofumi; Sugimoto, Jun

Proc. of Int. Seminar on Vapor Explosions and Explosive Eruptions, p.101 - 109, 1997/00

no abstracts in English

31 (Records 1-20 displayed on this page)