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Journal Articles

Microstructural evolution of intermetallic phase precipitates in Cr-coated zirconium alloy cladding in high-temperature steam oxidation up to 1400$$^{circ}$$C

Mohamad, A. B.; Nemoto, Yoshiyuki; Furumoto, Kenichiro*; Okada, Yuji*; Sato, Daiki*

Corrosion Science, 224, p.111540_1 - 111540_15, 2023/11

 Times Cited Count:0 Percentile:0(Materials Science, Multidisciplinary)

Journal Articles

Particle-based simulation of jet impingement behaviors

Takatsuka, Daichi*; Morita, Koji*; Liu, W.*; Zhang, T.*; Nakamura, Takeshi*; Kamiyama, Kenji

Proceedings of 12th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS12) (Internet), 10 Pages, 2022/10

Journal Articles

Particle-based simulation of heat transfer behavior in EAGLE ID1 in-pile test

Morita, Koji*; Ogawa, Ryusei*; Tokioka, Hiromi*; Liu, X.*; Liu, W.*; Kamiyama, Kenji

Proceedings of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12) (USB Flash Drive), 11 Pages, 2018/10

The EAGLE in-pile ID1 test has been performed by Japan Atomic Energy Agency to demonstrate early fuel discharge from a fuel subassembly with an inner duct structure, which is named FAIDUS. It was deduced that early duct wall failure observed in the test was initiated by high heat flux from the molten pool of fuel and steel mixture. The posttest analyses suggest that molten pool-to-duct wall heat transfer might be enhanced effectively by the molten steel with large thermal conductivity in the pool without the presence of fuel crust on the duct wall. In this study, mechanisms of heat transfer from the molten pool to the duct wall was analyzed using a fully Lagrangian approach based on the finite volume particle method for multi-component, multi-phase flows. A series of pin disruption, molten pool formation and duct wall failure behaviors was simulated to investigate mixing and separation behavior of molten steel and fuel in the pool, and their effect on molten pool-to-duct wall heat transfer. The present 2D particle-based simulations demonstrated that large thermal load beyond 10 MW/m$$^{2}$$ on the duct wall was caused by effective heat transfer due to direct contact of liquid fuel with nuclear heat to the duct wall.

Journal Articles

Behaviors of high-burnup LWR fuels with improved materials under design-basis accident conditions

Amaya, Masaki; Udagawa, Yutaka; Narukawa, Takafumi; Mihara, Takeshi; Taniguchi, Yoshinori

Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 10 Pages, 2018/10

Journal Articles

Neutron resonance analysis for nuclear safeguards and security applications

Paradela, C.*; Heyse, J.*; Kopecky, S.*; Schillebeeckx, P.*; Harada, Hideo; Kitatani, Fumito; Koizumi, Mitsuo; Tsuchiya, Harufumi

EPJ Web of Conferences, 146, p.09002_1 - 09002_4, 2017/09

 Times Cited Count:10 Percentile:97.68(Nuclear Science & Technology)

Journal Articles

Experimental discussion on fragmentation mechanism of molten oxide discharged into a sodium pool

Matsuba, Kenichi; Kamiyama, Kenji; Toyooka, Junichi; Tobita, Yoshiharu; Zuev, V. A.*; Kolodeshnikov, A. A.*; Vasilyev, Y. S.*

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 6 Pages, 2015/05

To develop a method for evaluating the distance for fragmentation of molten core material discharged into sodium, the particle size distribution of alumina debris obtained in the FR tests was analyzed. The mass median diameters of solidified alumina particles were around 0.4 mm, which are comparable to particle sizes predicted by hydrodynamic instability theories such as Kelvin-Helmholtz instability. However, even though hydrodynamic instability theories predict that particle size decreases with an increase of Weber number, such the dependence of particle size on We was not observed in the FR tests. It can be interpreted that the tendency of measured mass median diameters (i.e., non-dependence on Weber number) suggests that before hydrodynamic instabilities sufficiently grow to induce fragmentation, thermal phenomena such as local coolant vaporization and resultant vapor expansion accelerate fragmentation.

Journal Articles

Development of remote surveillance squads for nuclear facility accidents

Kobayashi, Tadayoshi; Miyajima, Kazutoshi; Yanagihara, Satoshi

Keisoku Jido Seigyo Gakkai Dai-3-Kai Shisutemu Integureshon Bumon Koenkai (SI2002) Koen Rombunshu, 2, p.105 - 106, 2002/00

no abstracts in English

JAEA Reports

Research program (VEGA) on the fission product release from irradiated fuel

Nakamura, Takehiko; Hidaka, Akihide; Hashimoto, Kazuichiro; Harada, Yuhei; Nishino, Yasuharu; Kanazawa, Hiroyuki; Uetsuka, Hiroshi; Sugimoto, Jun

JAERI-Tech 99-036, 34 Pages, 1999/03

JAERI-Tech-99-036.pdf:1.55MB

no abstracts in English

JAEA Reports

HEINPUT computer code for estimating the late somatic effects and genetic effects induced by radiation exposure in nuclear reactor accidents

Togawa, Orihiko; Homma, Toshimitsu; Masumura, Tomomi*

JAERI-Data/Code 99-002, 59 Pages, 1999/01

JAERI-Data-Code-99-002.pdf:2.55MB

no abstracts in English

Journal Articles

Social acceptability and scientific prospect of fusion energy, 7; Safety

Seki, Yasushi

Purazuma, Kaku Yugo Gakkai-Shi, 74(8), p.795 - 801, 1998/08

no abstracts in English

Journal Articles

Experimental study on criticality accidents using the TRACY

Nakajima, Ken; ; ; ; *; Sakuraba, Koichi; Ono, Akio

PHYSOR 96: Int. Conf. on the Physics of Reactors, 4, p.L83 - L92, 1996/00

no abstracts in English

Journal Articles

A Model to predict the ultimate failure of coated fuel particles during core heatup events

Ogawa, Toru; Minato, Kazuo; Fukuda, Kosaku; ; ; Sekino, Hajime; ; Ito, Tadaharu; ;

Nuclear Technology, 96, p.314 - 322, 1991/12

 Times Cited Count:12 Percentile:76.62(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Observation of FBR-type fuel rod melting in void under power transients

Sobajima, Makoto; Katanishi, Shoji;

SMiRT 11 Transactions,Vol. C, p.191 - 194, 1991/08

no abstracts in English

Journal Articles

Safety characteristics of the High Temperature Engineering Test Reactor

Shindo, Masami; *; Kunitomi, Kazuhiko; ; Sawa, Kazuhiro

Nucl. Eng. Des., 132, p.39 - 45, 1991/00

 Times Cited Count:5 Percentile:53.87(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Review of Current Topics on Power Cooling Mismatch Experiment

; ; ; ; ;

JAERI-M 6927, 79 Pages, 1977/02

JAERI-M-6927.pdf:2.85MB

no abstracts in English

Oral presentation

Fuel safety research at JAEA

Amaya, Masaki

no journal, , 

no abstracts in English

Oral presentation

Particle-based simulation on heat transfer behavior between molten pool and duct wall in EAGLE ID1 and ID2 in-pile tests

Zhang, T.*; Morita, Koji*; Liu, X.*; Liu, W.*; Kamiyama, Kenji

no journal, , 

Oral presentation

Oral presentation

Transition of the Zr(Cr, Fe)$$_{2}$$ intermetallic phase up to the eutectic temperature

Mohamad, A. B.; Nemoto, Yoshiyuki; Furumoto, Kenichiro*; Okada, Yuji*; Sato, Daiki*

no journal, , 

22 (Records 1-20 displayed on this page)