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Profil bibliographique

Koji Fujimura

Informations fournies par OpenAlex. Research Africa ne déduit ni nationalité, ni poste, ni coordonnées personnelles.

116Publications signalées
1681Citations signalées
1Affiliations récentes

Les institutions déclarées

Les domaines associés

Nuclear reactor physics and engineeringNuclear Materials and PropertiesNuclear and radioactivity studiesAdvanced Chemical Sensor TechnologiesGraphite, nuclear technology, radiation studies

Les publications récentes

Accès ouvert 2025 article OpenAlex

A Safety Enhanced Core Concept for Metal-Fuel Sodium-Cooled Fast Reactors

Sho Fuchita, Koji Fujimura, Kazuhiro Fujimata, Hirotaka NAKAHARA et autres

A safety enhanced metal fuel core has been developed that prevents fuel pin failure and coolant boiling during unprotected loss of flow (ULOF), unprotected transient over power (UTOP) and unprotected loss of heat sink (ULOHS) without relying on radial expansion reactivity.Specifically, we …

jp (code pays fourni par la source)

0 citations Progress in Nuclear Science and Technology
Accès ouvert 2025 article OpenAlex

MA Transmutation Core Concept for a Metal-Fueled Sodium-Cooled Fast Reactor

Koji Fujimura, Junichi Miwa, Takeshi Mitsuyasu, Sho Fuchita et autres

We have developed a conceptual framework for a minor actinide (MA) transmutation core for a metal-fueled sodium-cooled fast reactor (FR) that is suitable for a scenario in which light water reactors (LWRs) and FRs coexist.First, a target value was established for the …

jp (code pays fourni par la source)

1 citation Progress in Nuclear Science and Technology
Accès ouvert 2025 article OpenAlex

Core concept of innovative small SFR with metal fuel for deployment in Japan

Sho Fuchita, Koji Fujimura, Daisuke Watanabe, Hirotaka NAKAHARA et autres

We are developing a metal-fueled sodium-cooled fast reactor (SFR) to solve social issues regarding nuclear power for the future.Fast reactors are effective for efficient use of uranium (U) resources and reducing the volume and radiotoxicity of high-level radioactive wastes (HLWs).In particular, the …

jp (code pays fourni par la source)

0 citations Progress in Nuclear Science and Technology
2024 article OpenAlex

Enhancing the Thermoelectric Performance of Si-Based Clathrates via Carrier Optimization Considering Finite Temperature Effects

Masato Ohnishi, Takahiro Yamamoto, Koji Fujimura, Hiroshi Shimizu et autres

Clathrate compounds are promising thermoelectric materials that embody the phonon-glass electron-crystal concept. Among the various types of clathrate compounds, those based on silicon are particularly favored for practical applications owing to their low cost. In this study, we synthesize type-I clathrate compounds …

jp (code pays fourni par la source)

12 citations Chemistry of Materials
Accès ouvert 2023 article OpenAlex

Polydimethylsiloxane-coated macroporous silica adsorbent in thermal desorption gas chromatography

Ikuo Ueta, Mizuki Hayashibe, Katsunori Sumiya, Yuki Ariizumi et autres

Polydimethylsiloxane (PDMS)-coated macroporous silica (MPSi) particles were developed for the extraction of volatile organic compounds (VOCs) from air samples in thermal desorption-gas chromatographic analysis. The gas sample was collected by a gas sampling pump at 100 mL/min. Different amounts of PDMS coating …

jp (code pays fourni par la source)

7 citations Journal of Chromatography Open
2023 article OpenAlex

A safety enhanced sodium-cooled MOX fueled fast reactor core concept

Koji Fujimura, Sho Fuchita, Kazuhiro Fujimata, Satoshi Takeda et autres

We have developed a 750MWe sodium-cooled MOX fueled fast reactor core with enhanced safety against typical ATWS. Design goals were set as follows: 1) negative void reactivity for the loss of flow (ULOF); and 2) burnup reactivity less than 1 $ for …

jp (code pays fourni par la source)

6 citations Journal of Nuclear Science and Technology
2020 conference-paper OpenAlex

Development of Safety-Enhanced Fast Reactor by Using Minor Actinide Bearing Internal Blanket

Sho Fuchita, Satoshi Takeda, Koji Fujimura, Toshikazu Takeda et autres

Abstract For a 750MWe sodium-cooled fast reactor core using MOX fuel, safety-enhancement measures have been studied to reduce the risk of core damage under unprotected loss of flow (ULOF) and unprotected transient overpower (UTOP) accidents. As passive measures the followings are considered: …

jp (code pays fourni par la source)

3 citations

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