Search Results - "Hidemasa YAMANO"

Raman spectroscopy of eutectic melting between boride granule and stainless steel for sodium-cooled fast reactors by Fukai, Hirofumi, Furuya, Masahiro, Yamano, Hidemasa

“…To understand the eutectic reaction mechanism and the relocation behavior of the core debris is indispensable for the safety assessment of core disruptive…”
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Viscosity Measurements of Molten Metal Using an Improved Oscillating Crucible Method by Sato, Rika, Nishi, Tsuyoshi, Ohta, Hiromichi, Yamano, Hidemasa

“…We developed a simple viscosity measurement method to directly evaluate the period and logarithmic decrement of oscillation. The viscosity of a molten metal is…”
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Development of probabilistic risk assessment methodology against strong wind for sodium-cooled fast reactors by NISHINO, Hiroyuki, YAMANO, Hidemasa, KURISAKA, Kenichi

“…For nuclear power plants, probabilistic risk assessment (PRA) should be performed not only against earthquake and tsunami, which are critical events especially…”
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Structural analysis of a reactor vessel in a sodium-cooled fast reactor under extremely high temperature conditions by YAMANO, Hidemasa, FUTAGAMI, Satoshi, ANDO, Masanori

“…To enhance resilience of next-generation nuclear structures, it is necessary to develop design methodology that mitigates impacts of failure caused by…”
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Kinetic study on eutectic reaction between boron carbide and stainless steel by differential thermal analysis by KIKUCHI, Shin, NAKAMURA, Kinya, YAMANO, Hidemasa

“…In a postulated severe accidental condition of sodium-cooled fast reactor (SFR), the eutectic reaction between boron carbide (B4C) as control rod element and…”
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Thermophysical properties of austenitic stainless steel containing boron carbide in a solid state by TAKAI, Toshihide, FURUKAWA, Tomohiro, YAMANO, Hidemasa

“…In a core disruptive accident scenario, boron carbide, which is used as a control rod material, may melt below the melting temperature of stainless steel owing…”
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Raman spectroscopy of eutectic melting between boride granule and stainless steel for sodium-cooled fast reactors by Hirofumi Fukai, Masahiro Furuya, Hidemasa Yamano

“…To understand the eutectic reaction mechanism and the relocation behavior of the core debris is indispensable for the safety assessment of core disruptive…”
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Hazard curve evaluation method development for a forest fire as an external hazard on nuclear power plants by Okano, Yasushi, Yamano, Hidemasa

“…A method to obtain a hazard curve of a forest fire was developed. The method has four steps: a logic tree formulation, a response surface evaluation, a Monte…”
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Development of probabilistic risk assessment methodology against extreme snow for sodium-cooled fast reactor by Yamano, Hidemasa, Nishino, Hiroyuki, Kurisaka, Kenichi

“…•Snow PRA methodology was developed.•Snow hazard category was defined as the combination of daily snowfall depth (speed) and snowfall duration.•Failure…”
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Editorial: Experimental and numerical studies on liquid metal cooled fast reactors by Cheng, Songbai, Zhou, Wenzhong, Gu, Long, Chen, Hongli, Yun, Di, Morita, Koji, Yamano, Hidemasa, Revankar, Shripad T.

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Post-test material analysis of eutectic melting reaction of boron carbide and stainless steel by Hidemasa YAMANO, Toshihide TAKAI, Tomohiro FURUKAWA

“…It is necessary to simulate a eutectic melting reaction and relocation behavior of boron carbide (B4C) as a control rod material and stainless steel (SS)…”
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Development of a probabilistic risk assessment methodology against a combination hazard of strong wind and rainfall for sodium-cooled fast reactors by YAMANO, Hidemasa, NISHINO, Hiroyuki, KURISAKA, Kenichi

“…This paper describes the development of a probabilistic risk assessment (PRA) methodology against a combination hazard of strong wind and rainfall. In this…”
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Development of probabilistic risk assessment methodology of decay heat removal function against combination hazard of low temperature and snow for sodium-cooled fast reactors by NISHINO, Hiroyuki, YAMANO, Hidemasa, KURISAKA, Kenichi

“…A probabilistic risk assessment (PRA) should be performed not only for earthquake and tsunami which are major natural events in Japan but also for other…”
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Sensitivity study on forest fire breakout and propagation conditions for forest fire hazard curve evaluations by OKANO, Yasushi, YAMANO, Hidemasa

“…As a part of external hazard probabilistic risk assessment methodology development, a sensitivity study on forest fire hazard curves was performed on condition…”
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Development of the evaluation methodology for the material relocation behavior in the core disruptive accident of sodium-cooled fast reactors by Tobita, Yoshiharu, Kamiyama, Kenji, Tagami, Hirotaka, Matsuba, Ken-ichi, Suzuki, Tohru, Isozaki, Mikio, Yamano, Hidemasa, Morita, Koji, Guo, LianCheng, Zhang, Bin

“…The in-vessel retention (IVR) of core disruptive accident (CDA) is of prime importance in enhancing safety characteristics of sodium-cooled fast reactors…”
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Matched refractive-index PIV visualization of complex flow structure in a three-dimentionally connected dual elbow by Yuki, Kazuhisa, Hasegawa, Shunsuke, Sato, Tsukasa, Hashizume, Hidetoshi, Aizawa, Kosuke, Yamano, Hidemasa

“…► A flow separation is formed near the inner wall of the 1st elbow. ► The 2nd elbow has significant impact on vortex shedding from behind the separation…”
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Numerical simulations of forest fire propagation and smoke transport as an external hazard assessment methodology development for a nuclear power plant by OKANO, Yasushi, YAMANO, Hidemasa

“…A new method has been developed to assess potential challenges by forest fire smoke on a cooling function of a decay heat removal system (DHRS) of a…”
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Development of technical basis in the initiating and transition phases of unprotected events for Level-2 PSA methodology in sodium-cooled fast reactors by Yamano, Hidemasa, Sato, Ikken, Tobita, Yoshiharu

“…► Phenomenological event trees in the initiating/transition phases of unprotected events in SFRs. ► Technical database to quantify the probability of event…”
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Core and safety design for France–Japan common concept on sodium-cooled fast reactor by Takano, Kazuya, Ohki, Shigeo, Ozawa, Takayuki, Yamano, Hidemasa, Kubo, Shigenobu, Ogura, Masashi, Yamada, Yumi, Koyama, Kazuya, Kurita, Koichi, Costes, Laurent, Venard, Christophe, Carluec, Bernard, Perrin, Benoit, Verrier, Denis

“…France (CEA and FRAMATOME) and Japan (JAEA, MFBR, and MHI) teams have carried out collaborative works to have common technical views regarding a sodium-cooled…”
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Experimental analyses by SIMMER-III on duct-wall failure and fuel discharge/relocation behavior by YAMANO, Hidemasa, TOBITA, Yoshiharu

“…This paper describes experimental analyses using SIMMER-III and -IV, which are respectively two- and three-dimensional multi-component multi-phase Eulerian…”
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