Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 28

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

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

Pshenichnikov, A.; Kurata, Masaki; Nagae, Yuji

Proceedings of International Topical Workshop on Fukushima Decommissioning Research (FDR2022) (Internet), 4 Pages, 2022/10

The CLADS-MADE-04 is the next test in the series aiming at understanding of the melt propagation behaviour in the lower core region. In this contribution, recent results of the post-test analysis including microstructure of metallic debris investigated by Electron Probe Micro Analyzer (EPMA) are discussed. During the test, melting of the control blade happened with sudden wave of strong heat release relatively slowly (several cm/min) spread from the hottest area downwards along the degrading control blade and channel box consuming the walls made of Zircaloy-4. A significant damage happened with the sample supporting plate as well. The investigation of microstructure of such metallic debris would allow understanding of a mechanism of enhanced local core degradation. The nature of strong heat release and possibility of spreading to the surrounding materials is to be confirmed after thorough phase identification by EPMA. The difference between Fe-B eutectic debris and Zr-Fe eutectic debris will be outlined. It is especially important for understanding of the lower core plate melt-through and a possibility of a Zr-Fe molten material progression into the lower plenum.

Journal Articles

Ten years of Fukushima Dai-ichi post-accident research on the degradation phenomenology of the BWR core components

Pshenichnikov, A.; Shibata, Hiroki; Yamashita, Takuya; Nagae, Yuji; Kurata, Masaki

Journal of Nuclear Science and Technology, 59(3), p.267 - 291, 2022/03

 Times Cited Count:1 Percentile:32.89(Nuclear Science & Technology)

Journal Articles

Raman investigation of the CLADS-MADE-02 test debris to confirm the mechanism of the volatile and non-volatile boron compounds formation

Pshenichnikov, A.; Nagae, Yuji; Kurata, Masaki

Proceedings of TopFuel 2021 (Internet), 12 Pages, 2021/10

Journal Articles

A BWR control blade degradation observed in situ during a CLADS-MADE-02 test under Fukushima Dai-Ichi Unit 3 postulated conditions

Pshenichnikov, A.; Kurata, Masaki; Nagae, Yuji

Journal of Nuclear Science and Technology, 58(9), p.1025 - 1037, 2021/09

 Times Cited Count:2 Percentile:47.54(Nuclear Science & Technology)

Journal Articles

Features of a BWR neutron absorber melt relocation in an oxidative environment during the CLADS-MADE-02 test

Pshenichnikov, A.; Nagae, Yuji; Kurata, Masaki

Proceedings of 28th International Conference on Nuclear Engineering (ICONE 28) (Internet), 7 Pages, 2021/08

Journal Articles

Comparison of the observed Fukushima Dai-ichi Unit 2 debris with simulated debris from the CLADS-MADE-01 control blade degradation test

Pshenichnikov, A.; Nagae, Yuji; Kurata, Masaki

Journal of Nuclear Science and Technology, 58(4), p.416 - 425, 2021/04

 Times Cited Count:9 Percentile:82.73(Nuclear Science & Technology)

Journal Articles

On the degradation progression of a BWR control blade under high-temperature steam-starved conditions

Pshenichnikov, A.; Nagae, Yuji; Kurata, Masaki

Mechanical Engineering Journal (Internet), 7(3), p.19-00503_1 - 19-00503_10, 2020/06

Journal Articles

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.; Kurata, Masaki; Bottomley, D.; Sato, Ikken; Nagae, Yuji; Yamazaki, Saishun

Journal of Nuclear Science and Technology, 57(4), p.370 - 379, 2020/04

 Times Cited Count:10 Percentile:66.42(Nuclear Science & Technology)

Journal Articles

Raman characterization of the simulated control blade debris to understand the boric compounds transformations during severe accidents

Pshenichnikov, A.; Nagae, Yuji; Kurata, Masaki

Mechanical Engineering Journal (Internet), 7(2), p.19-00477_1 - 19-00477_8, 2020/04

Journal Articles

Characterization of the Fukushima Dai-ichi Unit 2 sediments / debris based on the on-site video investigations in comparison to the debris obtained after integral CLADS-MADE-01 test

Pshenichnikov, A.; Kurata, Masaki; Nagae, Yuji

Dai-24-Kai Doryoku, Enerugi Gijutsu Shimpojiumu Koen Rombunshu (USB Flash Drive), 4 Pages, 2019/06

Journal Articles

Features of a control blade degradation observed ${it in situ}$ during severe accidents in boiling water reactors

Pshenichnikov, A.; Yamazaki, Saishun; Bottomley, D.; Nagae, Yuji; Kurata, Masaki

Journal of Nuclear Science and Technology, 56(5), p.440 - 453, 2019/05

 Times Cited Count:13 Percentile:85.03(Nuclear Science & Technology)

Journal Articles

Heterogeneity of BWR control blade degradation under steam-starved conditions

Pshenichnikov, A.; Yamazaki, Saishun; Nagae, Yuji; Kurata, Masaki

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 8 Pages, 2019/05

Journal Articles

The Behaviour of materials in case of solidified absorber melt - oxidized BWR channel box interaction revealed after CLADS-MADE-01 test

Pshenichnikov, A.; Kurata, Masaki; Nagae, Yuji; Yamazaki, Saishun

Proceedings of International Topical Workshop on Fukushima Decommissioning Research (FDR 2019) (Internet), 4 Pages, 2019/05

Journal Articles

High temperature oxidation test of simulated BWR fuel bundle in steam-starved conditions

Yamazaki, Saishun; Pshenichnikov, A.; Pham, V. H.; Nagae, Yuji; Kurata, Masaki; Tokushima, Kazuyuki*; Aomi, Masaki*; Sakamoto, Kan*

Proceedings of Annual Topical Meeting on Reactor Fuel Performance (TopFuel 2018) (Internet), 8 Pages, 2018/10

It is predictively evaluated that degradation of fuel assembly proceeded in a certain steam-starved condition at the early stage of a SA at 1F unit 2 (BWR). As for PWR fuel assembly, effective steam flow rate was properly indicated by normalizing to a unit of g-H$$_{2}$$O/sec/rod which is used as an important parameter for evaluating fuel degradation progression. Due to the inhomogeneous configuration of BWR fuel assembly, the difference of Zry oxidation and hydrogen uptake between the inside and outside of the channel box cannot be properly evaluated by this normalization. Instead of g-H$$_{2}$$O/sec/rod, proper evaluation unit for BWR configuration is necessary. To accumulate Zry oxidation and hydrogen uptake data for steam-starved conditions, high temperature oxidation tests were performed using a simulated BWR fuel bundle sample. The use of equivalent diameter of the cross section of BWR fuel assembly was proposed for normalization of effective steam flow rate.

Oral presentation

Specifications of CLADS test facilities for fuel degradation simulation

Pshenichnikov, A.; Yamazaki, Saishun; Nagae, Yuji; Kurata, Masaki

no journal, , 

Oral presentation

CLADS test facilities on BWR core material degradation

Nagae, Yuji; Shibata, Hiroki; Pshenichnikov, A.; Yamazaki, Saishun; Kurata, Masaki

no journal, , 

Oral presentation

Focusing the test strategy of CLADS-MADE-01 and first results of the BWR control blade degradation test

Pshenichnikov, A.; Yamazaki, Saishun; Nagae, Yuji; Kurata, Masaki

no journal, , 

Oral presentation

Consideration for modeling of Zry oxidation and hydrogen uptake in steam-starved conditions

Yamazaki, Saishun; Pshenichnikov, A.; Pham, V. H.; Nagae, Yuji; Kurata, Masaki

no journal, , 

no abstracts in English

Oral presentation

Advanced multi-scale modeling and experimental tests on fuel degradation in severe accident conditions, 1-4; Development of modeling for oxidation and hydrogen uptake of Zircaloy

Yamazaki, Saishun; Pshenichnikov, A.; Nagae, Yuji; Kurata, Masaki; Sakamoto, Kan*; Tokushima, Kazuyuki*; Aomi, Masaki*

no journal, , 

no abstracts in English

Oral presentation

Status and first results of the BWR control blade degradation test under steam-starved conditions

Pshenichnikov, A.; Yamazaki, Saishun; Nagae, Yuji; Kurata, Masaki

no journal, , 

28 (Records 1-20 displayed on this page)