Refine your search:     
Report No.
 - 
Search Results: Records 1-11 displayed on this page of 11
  • 1

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

Accuracy of measuring rebar strain in concrete using a diffractometer for residual stress analysis

Yasue, Ayumu*; Kawakami, Mayu*; Kobayashi, Kensuke*; Kim, J.; Miyazu, Yuji*; Nishio, Yuhei*; Mukai, Tomohisa*; Morooka, Satoshi; Kanematsu, Manabu*

Quantum Beam Science (Internet), 7(2), p.15_1 - 15_14, 2023/05

Journal Articles

Influence of shape of deformed rebar on bond performance of reinforced concrete

Kobayashi, Kensuke*; Yasue, Ayumu*; Morooka, Satoshi; Kanematsu, Manabu*

Konkurito Kogaku Nenji Rombunshu (DVD-ROM), 44(1), p.208 - 213, 2022/07

no abstracts in English

Journal Articles

Evaluation of bond performance of reinforced concrete using hot-dip galvanized rebar by neutron diffraction

Kobayashi, Kensuke*; Suzuki, Hiroshi; Nishio, Yuhei*; Kanematsu, Manabu*

Nihon Kenchiku Gakkai Kozokei Rombunshu, 86(785), p.1026 - 1035, 2021/07

no abstracts in English

Journal Articles

Study on loss-of-cooling and loss-of-coolant accidents in spent fuel pool, 4; Investigation of fuel loading effects in BWR spent fuel rack

Tojo, Masayuki*; Kanazawa, Toru*; Nakashima, Kazuo*; Iwamoto, Tatsuya*; Kobayashi, Kensuke*; Goto, Daisuke*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 13 Pages, 2019/05

In this study, fuel loading effects in BWR spent fuel rack accidents are widely investigated using three-dimensional analysis methods from both nuclear and thermal hydraulics viewpoints, including: (a) Decay heat of spent fuel after discharge, (b) The maximum temperature of spent fuel cladding in the spent fuel rack depending on heat transfer phenomena, and (c) Criticality of the spent fuel rack after collapsing of the fuel due to a severe accidents in the BWR spent fuel pool (SFP).

Oral presentation

Study on improvement of safety for accident conditions in spent fuel pool, 3; Evaluation of decay heat and cladding temperature during accident

Kobayashi, Kensuke*; Goto, Daisuke*; Tojo, Masayuki*; Ikehara, Tadashi*; Kaji, Yoshiyuki; Nemoto, Yoshiyuki

no journal, , 

We evaluate fuel temperature based on the steady state heat transfer analysis with considering accurate fuel history and storage conditions.

Oral presentation

Study on improvement of safety for accident conditions in spent fuel pool, 9; Temperature evaluations of BWR fuels by three dimensional steady-state heat transfer analyses

Goto, Daisuke*; Tojo, Masayuki*; Kobayashi, Kensuke*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki

no journal, , 

Steady-state heat transfer analysis method for the BWR spent fuel rack system was adopted to evaluate the cladding temperature in spent fuel pool accident condition. The cladding temperature seems to depend on spent fuel distribution, and the evaluation results were compared with the results obtained by using the MAAP. Ideas for the deployment of the fuels to prevent temperature elevation during the spent fuel pool water level decrease will be discussed.

Oral presentation

Study on improvement of safety for accident conditions in spent fuel pool, 10; Effects on criticality due to the differences of water level between in and out of channel box of BWR fuel

Kobayashi, Kensuke*; Tojo, Masayuki*; Goto, Daisuke*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki

no journal, , 

It is suggested that effective multiplication factor would increase if there is a water level difference between in and out of channel box of BWR fuel. Monte Carlo criticality analysis was conducted in consideration of the water density and the water level in and out of the channel box which were indicated in the evaluation using void fraction correlation obtained in previous works simulating several irradiation conditions of BWR fuels.

Oral presentation

Study on improvement of safety for accident conditions in spent fuel pool, 23; CFD analysis for the loss of coolant accident in SFP with Zircalloy-2 cladding oxidation model

Tojo, Masayuki*; Kanazawa, Toru*; Kobayashi, Kensuke*; Goto, Daisuke*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki

no journal, , 

Computational fluid dynamics (CFD) analysis for the loss of coolant accident in spent fuel pool (SFP) with Zircalloy-2 cladding was conducted. In the higher region of spent fuel rack internal, oxygen content in the atmosphere was decreased because of oxigen consumption during the oxidation reaction of cladding material. This oxygen depression is thought to surpress the oxidation of claddings.

Oral presentation

Study on improvement of safety for accident conditions in spent fuel pool, 24; Create a data base of BWR fuel temperature in SFP based on the steady-state heat transfer analyses

Goto, Daisuke*; Kobayashi, Kensuke*; Tojo, Masayuki*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki

no journal, , 

Influence of base temperature of the spent fuel pool (SFP), rack dimension, structure, and decay heat distribution, for the maximum temperature of cladding in spent fuel rack during the SFP loss of coolant accident was evaluated in this study, by using the previously developed 3 dimensional steady-state heat transfer analysis method.

Oral presentation

Study on improvement of safety for accident conditions in spent fuel pool, 25; Experiment and analysis of the water level mismatch between in and out of CB of BWR fuel under Loss of Cooling System

Kobayashi, Kensuke*; Goto, Daisuke*; Tojo, Masayuki*; Nemoto, Yoshiyuki; Kaji, Yoshiyuki

no journal, , 

Experiment and analysis simulating the water level mismatch between inside and outside of chanel box of BWR fuel under loss of cooling system were conducted for validation of the equation for void fraction correlation.

Oral presentation

The Effect on bond performance of concrete strength by the neutron diffraction

Kobayashi, Kensuke*; Ooka, Tokunao*; Kanematsu, Manabu*; Suzuki, Hiroshi; Tateyama, Soichi*; Nagai, Tomoya*; Nishio, Yuhei*; Hirata, Yoshikazu*; Yoshioka, Masahiro*

no journal, , 

no abstracts in English

11 (Records 1-11 displayed on this page)
  • 1