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Journal Articles

Improvement of JASMINE code for ex-vessel molten core coolability in BWR

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

Annals of Nuclear Energy, 178, p.109348_1 - 109348_13, 2022/12

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

The Japan Atomic Energy Agency extended the applicability of their fuel-coolant interaction analysis code JASMINE to simulate the relevant phenomena of molten core in a severe accident. In order to evaluate the total coolability, it is necessary to know the mass fraction of particle, agglomerated and cake debris and the final geometry at the cavity bottom. An agglomeration model that considers the fusion of hot particles on the cavity floor was implemented in the JASMINE code. Another improvement is introduction of the melt spreading model based on the shallow water equation with consideration of crust formation at the melt surface. For optimization of adjusting parameters, we referred data from the agglomeration experiment DEFOR-A and the under-water spreading experiment PULiMS conducted by KTH in Sweden. The JASMINE analyses reproduced the most of the experimental results well with the common parameter set, suggesting that the primary phenomena are appropriately modelled.

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

Accident management measures on steam explosion and debris coolability for light water reactors

Maruyama, Yu; Yamano, N.; Kudo, Tamotsu; Hidaka, Akihide; Sugimoto, Jun

NEA/CSNI/R(95)3, 0, p.223 - 240, 1995/07

no abstracts in English

Journal Articles

Phenomenological studies on melt-coolant interactions in the ALPHA program

Yamano, Norihiro; Maruyama, Yu; Kudo, Tamotsu; Hidaka, Akihide; Sugimoto, Jun

Nuclear Engineering and Design, 155(1-2), p.369 - 389, 1995/04

 Times Cited Count:47 Percentile:96.3(Nuclear Science & Technology)

no abstracts in English

Oral presentation

Technical issues for safety improvement, 4; Integrity of containment

Oikawa, Hirohide*; Arai, Kenji*; Fujii, Tadashi*; Umezawa, Shigemitsu*; Nishi, Yoshihisa*; Nakamura, Hideo

no journal, , 

no abstracts in English

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