Yoshinori Taniguchi - My portal

Profile Information

Affiliation: Japan Atomic Energy Agency

J-GLOBAL ID: 202101001841541685
researchmap Member ID: R000017336

Papers

High-temperature rupture failure of high-burnup LWR-MOX fuel under a reactivity-initiated accident condition

Taniguchi Yoshinori, Mihara Takeshi, Kakiuchi Kazuo, Udagawa Yutaka

Annals of Nuclear Energy, 195 110144\_1-110144\_11, Jan, 2024 Peer-reviewed
Behavior of high-burnup BWR UO$_{2}$ fuel with additives under reactivity-initiated accident conditions

Mihara Takeshi, Kakiuchi Kazuo, Taniguchi Yoshinori, Udagawa Yutaka

Journal of Nuclear Science and Technology, 60(5) 512-525, May, 2023 Peer-reviewed
Radiochemical analysis of the drain water sampled at the exhaust stack shared by Units 1 and 2 of the Fukushima Daiichi Nuclear Power Station

Shimada Asako, Taniguchi Yoshinori, Kakiuchi Kazuo, Ohira Saki, Iida Yoshihisa, Sugiyama Tomoyuki, Amaya Masaki, Maruyama Yu

Scientific Reports (Internet), 12(1) 2086\_1-2086\_11, Feb, 2022 Peer-reviewed
Simulation of the effect of radially oriented hydride precipitates on failure limit of high-burnup BWR fuel cladding under PCMI loading

Taniguchi Yoshinori, Mihara Takeshi, Udagawa Yutaka

Proceedings of TopFuel 2021 (Internet), 10, Oct, 2021 Peer-reviewed
Follow-up experimental study on causes of the low-enthalpy failure observed in the reactivity-initiated-accident-simulated test on LWR additive fuels

Mihara Takeshi, Kakiuchi Kazuo, Taniguchi Yoshinori, Udagawa Yutaka

Proceedings of TopFuel 2021 (Internet), 10, Oct, 2021 Peer-reviewed
The Effect of base irradiation on failure behaviors of UO$_{2}$ and chromia-alumina additive fuels under simulated reactivity-initiated accidents; A Comparative analysis with FEMAXI-8

Udagawa Yutaka, Mihara Takeshi, Taniguchi Yoshinori, Kakiuchi Kazuo, Amaya Masaki

Annals of Nuclear Energy, 139 107268\_1-107268\_9, May, 2020 Peer-reviewed
Analytical study of SPERT-CDC test 859 using fuel performance codes FEMAXI-8 and RANNS

Taniguchi Yoshinori, Udagawa Yutaka, Amaya Masaki

Annals of Nuclear Energy, 139 107188\_1-107188\_7, May, 2020 Peer-reviewed
Behavior of high-burnup LWR-MOX fuel under a reactivity-initiated accident condition

Taniguchi Yoshinori, Udagawa Yutaka, Mihara Takeshi, Amaya Masaki, Kakiuchi Kazuo

Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), 551-558, Sep, 2019 Peer-reviewed
Behavior of LWR fuels with additives under reactivity-initiated accident conditions

Mihara Takeshi, Udagawa Yutaka, Amaya Masaki, Taniguchi Yoshinori, Kakiuchi Kazuo

Proceedings of International Nuclear Fuel Cycle Conference / Light Water Reactor Fuel Performance Conference (Global/Top Fuel 2019) (USB Flash Drive), 544-550, Sep, 2019 Peer-reviewed
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, Oct, 2018 Peer-reviewed
Behavior of high-burnup advanced LWR fuels under design-basis accident conditions

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

Proceedings of 2017 Water Reactor Fuel Performance Meeting (WRFPM 2017) (USB Flash Drive), 10, Sep, 2017 Peer-reviewed
Analyses of SPERT-CDC test 859 by FEMAXI-7 and RANNS codes

Taniguchi Yoshinori, Udagawa Yutaka, Amaya Masaki

Proceedings of Annual Topical Meeting on LWR Fuels with Enhanced Safety and Performance (TopFuel 2016) (USB Flash Drive), 229-238, Sep, 2016 Peer-reviewed
Behavior of high-burnup advanced LWR fuels under accident conditions

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

Proceedings of Annual Topical Meeting on LWR Fuels with Enhanced Safety and Performance (TopFuel 2016) (USB Flash Drive), 53-62, Sep, 2016 Peer-reviewed

Misc.

Fuel Safety Research Meeting 2018

Taniguchi Yoshinori, Kakiuchi Kazuo, Amaya Masaki

Kaku Nenryo, (54-1) 16-19, Mar, 2019

Presentations

Development of analytical model on high temperature oxidation behavior of Cr-coated accident tolerant fuel cladding

Taniguchi Yoshinori, Udagawa Yutaka

事故耐性燃料開発に関するワークショップ
Development of fuel performance code RANNS for analysis of accident conditions; High temperature oxidation behavior of Cr-coated accident tolerant fuel cladding

Taniguchi Yoshinori, Udagawa Yutaka

日本原子力学会2023年秋の大会
Study on the failure behavior of high-burnup fuels under reactivity initiated accident conditions (Analyses of the failure mode change observed on a PWR-MOX fuel and its occurrence condition)

Taniguchi Yoshinori, Mihara Takeshi, Kakiuchi Kazuo, Hakamatsuka Shun, Yoshida Takuya, Udagawa Yutaka

日本原子力学会2022年秋の大会
High temperature rupture failure of M5 sheathed MOX fuel rod under high temperature and high pressure RIA transient

Taniguchi Yoshinori

Fuel Safety Research Meeting 2021 (FSRM 2021)
Overview of research activities of the Fuel Safety Research Group

Narukawa Takafumi, Mihara Takeshi, Taniguchi Yoshinori, Kakiuchi Kazuo, Tasaki Yudai, Udagawa Yutaka

令和3年度原子力規制庁技術基盤グループ-原子力機構安全研究・防災支援部門合同研究成果報告会
Analysis of water collected at a drain sump of common stack for units 1 and 2 of Fukushima Daiichi NPS

Shimada Asako, Taniguchi Yoshinori, Ohira Saki, Iida Yoshihisa

日本原子力学会2021年秋の大会
RIA-simulated experiments on high-burnup BWR fuel and PWR-MOX fuel; Follow-up study on causes of the recently observed low-enthalpy failure and failure mode change

Mihara Takeshi, Taniguchi Yoshinori, Akiyama Yoshiya, Muramatsu Yasuyuki, Usami Koji, Yoshida Takuya, Udagawa Yutaka

日本原子力学会2021年秋の大会
The Behavior of high-burnup MOX fuel (CN-1 test rod) under RIA condition

Taniguchi Yoshinori

Fuel Safety Research Meeting 2019 (FSRM 2019)
Behavior of high-burnup advanced fuels under reactivity-initiated accident (RIA) and loss-of-coolant accident (LOCA), 4; Behavior of high-burnup MOX fuel under reactivity-initiated accident (RIA)

Taniguchi Yoshinori, Udagawa Yutaka, Muramatsu Yasuyuki, Hiruta Kenta, Amaya Masaki

日本原子力学会2019年春の年会
Behavior of high burnup MOX fuel with M5 cladding under RIA conditions

Taniguchi Yoshinori

Fuel Safety Research Meeting 2018 (FSRM 2018)
Analytical study of the cladding corrosion effect on the failure limit of SPERT-CDC Test 756 by using FEMAXI-7 and RANNS Codes

Taniguchi Yoshinori

Fuel Safety Research Meeting 2017 (FSRM 2017)
Analytical study of the cladding corrosion effect on the failure limit of SPERT-CDC Test 859 by using FEMAXI-7 and RANNS Codes

Taniguchi Yoshinori

Fuel Safety Research Meeting 2016 (FSRM 2016)
An Analysis of SPERT-CDC test 859 using a fuel performance code RANNS

Taniguchi Yoshinori, Udagawa Yutaka, Amaya Masaki

日本原子力学会2016年春の年会