プシェニチニコフアントン (Anton Pshenichnikov) - マイポータル

基本情報

所属: 国立研究開発法人日本原子力研究開発機構福島廃炉安全工学研究所　廃炉環境国際共同研究センター　デブリ・廃棄物マネジメントグループ研究副主幹

連絡先: pshenichnikov.antonjaea.go.jp
J-GLOBAL ID: 202101018085309692
researchmap会員ID: R000021747

外部リンク: https://clads.jaea.go.jp/jp/rd/debris_02.html

研究分野

論文

INSIGHT ON CS AND B AEROSOLS BEHAVIOUR REVEALED DURING THE CLADS-MADE-05 SIMULATED BWR BUNDLE DEGRADATION TEST

Anton Pshenichnikov, Bella Zubekhina, Hiroshi Ohgi, Hai Pham

Proceedings of FDR2024 International Topical Workshop on Fukushima Decommissioning Research (FDR2024-1039) 2024年10月
Interaction of CsOH with structural steel 316L and simulated products of the steel-cladding reaction under assumed conditions relevant for the accident at the Fukushima Dai-Ichi Unit 2 and 3

Anton Pshenichnikov, Bella Zubekhina

Journal of Nuclear Materials 597 155136-155136 2024年8月査読有り
The key role of sample analysis in Fukushima Dai-Ichi decommissioning, debris management, and accident progression investigation

Bella Zubekhina, Anton Pshenichnikov, Yuji Nagae, Masaki Kurata

Frontiers in Nuclear Engineering 2(1324221) 2023年12月5日査読有り招待有り
AN INVESTIGATION OF THE MICROSTRUCTURE AND PHASE COMPOSITION OF THE ZR BEARING METALLIC DEBRIS IN A BYPASS CHANNEL OF A BWR FUEL AFTER THE EXOTHERMIC REACTION IN THE CLADS-MADE-04 TEST

Anton Pshenichnikov, Masaki Kurata, Yuji Nagae

Proceedings of FDR2022 International Topical Workshop on Fukushima Decommissioning Research (FDR2022-1047) 2022年10月
Ten years of Fukushima Dai-Ichi post-accident research on the degradation phenomenology of the BWR core components

Anton Pshenichnikov, Hiroki Shibata, Takuya Yamashita, Yuji Nagae, Masaki Kurata

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 59(3) 267-291 2022年3月
A BWR control blade degradation observed in situ during a CLADS-MADE-02 test under Fukushima Dai-Ichi Unit 3 postulated conditions

Anton Pshenichnikov, Masaki Kurata, Yuji Nagae

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY 58(9) 1025-1037 2021年9月
Comparison of the observed Fukushima Dai-ichi Unit 2 debris with simulated debris from the CLADS-MADE-01 control blade degradation test

Pshenichnikov A., 永江勇二, 倉田正輝

Journal of Nuclear Science and Technology 58(4) 416-425 2021年4月査読有り
FEATURES OF A BWR NEUTRON ABSORBER MELT RELOCATION IN AN OXIDATIVE ENVIRONMENT DURING THE CLADS-MADE-02 TEST

Anton Pshenichnikov, Yuji Nagae, Masaki Kurata

PROCEEDINGS OF 2021 28TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING (ICONE28), VOL 3 2021年
On the degradation progression of a BWR control blade under high-temperature steam-starved conditions

Pshenichnikov A., 永江勇二, 倉田正輝

Mechanical Engineering Journal (Internet) 7(3) 19-00503\_1-19-00503\_10 2020年6月査読有り
Raman characterization of the simulated control blade debris to understand the boric compounds transformations during severe accidents

Pshenichnikov A., 永江勇二, 倉田正輝

Mechanical Engineering Journal (Internet) 7(2) 19-00477\_1-19-00477\_8 2020年4月査読有り
New research programme of JAEA/CLADS to reduce the knowledge gaps revealed after an accident at Fukushima-1; Introduction of boiling water reactor mock-up assembly degradation test programme

Pshenichnikov A., 倉田正輝, Bottomley D., 佐藤一憲, 永江勇二, 山崎宰春

Journal of Nuclear Science and Technology 57(4) 370-379 2020年4月査読有り
Heterogeneity of BWR control blade degradation under steam-starved conditions

Pshenichnikov A., 山崎宰春, 永江勇二, 倉田正輝

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet) 8 2019年5月査読有り
Features of a control blade degradation observed {\it in situ} during severe accidents in boiling water reactors

Pshenichnikov A., 山崎宰春, Bottomley D., 永江勇二, 倉田正輝

Journal of Nuclear Science and Technology 56(5) 440-453 2019年5月査読有り
模擬BWR燃料集合体試験体を用いた水蒸気枯渇条件での高温酸化試験

山崎宰春, Pshenichnikov A., Pham V. H., 永江勇二, 倉田正輝, 徳島二之*, 青見雅樹*, 坂本寛*

Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet) 8 2018年10月査読有り

MISC

福島第一原子力発電所2号機ペデスタル部デブリに係るビデオ画像分析

Pshenichnikov A., 倉田正輝, 永江勇二

第24回動力・エネルギー技術シンポジウム講演論文集(USB Flash Drive) 4 2019年6月
The Behaviour of materials in case of solidified absorber melt - oxidized BWR channel box interaction revealed after CLADS-MADE-01 test

Pshenichnikov A., 倉田正輝, 永江勇二, 山崎宰春

Proceedings of International Topical Workshop on Fukushima Decommissioning Research (FDR 2019) (Internet) 4 2019年5月

講演・口頭発表等

Status and first results of the CLADS-MADE-02 BWR control blade degradation test under steam-rich conditions related to 1F Unit 3 accident

Pshenichnikov A., 山崎宰春, 永江勇二, 倉田正輝

25th International QUENCH Workshop
The Characterization of the CLADS-MADE-01 and -02 BWR control blade degradation test debris by Raman spectroscopy

Pshenichnikov A., 永江勇二, 倉田正輝

25th International QUENCH Workshop
The Mechanism of B$_{4}$C granules decomposition during 1F control blade degradation test revealed by Raman spectroscopy

Pshenichnikov A., 永江勇二, 倉田正輝

日本原子力学会関東・甲越支部第18回若手研究者・技術者発表討論会
Boron behaviour issue during control blade degradation at the beginning phase of postulated scenario for 1F Unit 2 accident reproduced in the CLADS MADE 01 test

Pshenichnikov A., 倉田正輝, 永江勇二, 山崎宰春

Fukushima Research Conference on Materials Science for Severe Accident and Fukushima Daiichi Decommissioning Workshop 2019
Analysis of the video data from Fukushima Dai-ichi Unit 2 pedestal debris inspection in comparison to the CLADS-MADE-01 debris

Pshenichnikov A., 倉田正輝, 永江勇二, 山崎宰春

Fukushima Research Conference on Materials Science for Severe Accident and Fukushima Daiichi Decommissioning Workshop 2019
福島第一原子力発電所2号機堆積物調査とCLADS制御棒ブレード破損試験堆積物の特徴比較評価

Pshenichnikov A.

3rd CEA-Waseda Joint Workshop on Severe Accident and Safety of Nuclear Reactors
Status and first results of the BWR control blade degradation test under steam-starved conditions

Pshenichnikov A., 山崎宰春, 永江勇二, 倉田正輝

24th International QUENCH Workshop
シビアアクシデント時の燃料破損・溶融過程解析手法の高度化,1-4; ジルカロイ酸化/水素化モデルの整備

山崎宰春, Pshenichnikov A., 永江勇二, 倉田正輝, 坂本寛*, 徳島二之*, 青見雅樹*

日本原子力学会2018年秋の大会
水蒸気枯渇条件でのジルカロイの酸化水素吸収モデルに関する考察

山崎宰春, Pshenichnikov A., Pham V. H., 永江勇二, 倉田正輝

2nd TITECH-CRIEPI-JAEA Joint Workshop
Focusing the test strategy of CLADS-MADE-01 and first results of the BWR control blade degradation test

Pshenichnikov A., 山崎宰春, 永江勇二, 倉田正輝

2nd TITECH-CRIEPI-JAEA Joint Workshop
廃炉国際共同研究センターにおけるBWR溶融挙動に係る試験装置

永江勇二, 柴田裕樹, Pshenichnikov A., 山崎宰春, 倉田正輝

23rd QUENCH Workshop 2017
Specifications of CLADS test facilities for fuel degradation simulation

Pshenichnikov A., 山崎宰春, 永江勇二, 倉田正輝

TITECH-CRIEPI-JAEA Joint Workshop

プシェニチニコフアントン

基本情報

研究分野

論文

MISC

講演・口頭発表等

メニュー

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