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Journal Articles

Characterization of bremsstrahlung and $$gamma$$-rays of fuel debris

Matsumura, Taichi; Okumura, Keisuke; Fujita, Manabu*; Sakamoto, Masahiro; Terashima, Kenichi; Riyana, E. S.

Radiation Physics and Chemistry, 199, p.110298_1 - 110298_8, 2022/10

Journal Articles

Depletion calculation of subcritical system with consideration of spontaneous fission reaction

Riyana, E. S.; Okumura, Keisuke; Sakamoto, Masahiro; Matsumura, Taichi; Terashima, Kenichi

Journal of Nuclear Science and Technology, 59(4), p.424 - 430, 2022/04

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

Journal Articles

A Prediction method for the dose rate of fuel debris depending on the constituent elements

Terashima, Kenichi; Okumura, Keisuke

Journal of Advanced Simulation in Science and Engineering (Internet), 8(1), p.73 - 86, 2021/03

Journal Articles

Gamma detector response simulation inside the pedestal of Fukushima Daiichi Nuclear Power Station

Riyana, E. S.; Okumura, Keisuke; Terashima, Kenichi; Matsumura, Taichi; Sakamoto, Masahiro

Mechanical Engineering Journal (Internet), 7(3), p.19-00543_1 - 19-00543_8, 2020/06

Journal Articles

Calculation of gamma and neutron emission characteristics emitted from fuel debris of Fukushima Daiichi Nuclear Power Station

Riyana, E. S.; Okumura, Keisuke; Terashima, Kenichi

Journal of Nuclear Science and Technology, 56(9-10), p.922 - 931, 2019/09

 Times Cited Count:3 Percentile:46.76(Nuclear Science & Technology)

Journal Articles

Calculation of gamma and neutron emission characteristics emitted from fuel debris as a basis for determination of suitable detector system

Riyana, E. S.; Okumura, Keisuke; Terashima, Kenichi

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 4 Pages, 2019/05

Journal Articles

Electronic nematicity above the structural and superconducting transition in BaFe$$_2$$(As$$_{1-x}$$P$$_x$$)$$_2$$

Kasahara, Shigeru*; Shi, H. J.*; Hashimoto, Kenichiro*; Tonegawa, Sho*; Mizukami, Yuta*; Shibauchi, Takasada*; Sugimoto, Kunihisa*; Fukuda, Tatsuo; Terashima, Takahito*; Nevidomskyy, A. H.*; et al.

Nature, 486(7403), p.382 - 385, 2012/06

 Times Cited Count:353 Percentile:99.39(Multidisciplinary Sciences)

Oral presentation

Issues of non-destructive assay technology aiming at nuclear material accountancy of fuel debris in canister

Okumura, Keisuke; Terashima, Kenichi; Nagatani, Taketeru; Komeda, Masao; Shiba, Tomooki; Nauchi, Yasushi*; Takada, Akira*; Kosuge, Yoshihiro*

no journal, , 

no abstracts in English

Oral presentation

Development of a dose rate prediction method for various sampled fuel debris

Okumura, Keisuke; Terashima, Kenichi

no journal, , 

The dose rate of fuel debris retrieved from the Fukushima Daiichi Nuclear Power Plant is necessary for radiation shielding, exposure management of workers and so on. However, it depends on many parameters of fuel debris such as size, radiation source nuclides, elemental composition, density, porosity, burnup, and evaluation time. Therefore, we have developed a dose rate prediction formula applicable to various fuel debris by combining theoretical models and a large amount of photon transport calculations with PHITS code.

Oral presentation

Prediction of the dose rate of various fuel debris to be sampled from Fukushima Daiichi Nuclear Power Station

Terashima, Kenichi; Okumura, Keisuke

no journal, , 

The dose rate around the surface of retrieved fuel debris is important information for radiation shielding, handling, transport, analysis and storage of the fuel debris. Therefore, we have developed a dose rate prediction method applicable to various fuel debris to be sampled from the Fukushima Daiichi Nuclear Power Station in the near future. Using the method, we predicted the dose rate of the fuel debris to be sampled in 2021 and clarified the sensitivities to the contributing parameters.

Oral presentation

Development of nuclear fuel material evaluation method using integral dosimeter; Basic data acquisition of babble detector

Terashima, Kenichi; Kaburagi, Masaaki; Sakamoto, Masahiro; Matsumura, Taichi; Fujita, Manabu*; Okumura, Keisuke

no journal, , 

Bubble detector (BD) is neutron integral dosimeter with advantages of insensitivity to gamma ray, no power supply, visual confirmation and controllability of irradiation time according to neutron flux. Therefore, application of detection and nondestructive measurement for fuel debris is expected at Fukushima Daiichi Nuclear Power Station. Then, basic data of babble detector obtained by neutron irradiation experiment for applicability evaluation of BD.

Oral presentation

Development of a decay heat estimation method for various fuel debris

Sakamoto, Masahiro; Terashima, Kenichi; Matsumura, Taichi; Fujita, Manabu*; Okumura, Keisuke

no journal, , 

It is important to estimate the decay heat of the fuel debris at the Fukushima Daiichi Nuclear Power Station in examining the cooling method and evaluating the heat removal of the debris transport and storage containers for debris retrieval. However, fuel debris is not easy to estimate the decay heat because the composition of nuclides is not clear like the spent fuel whose combustion history is clear. Therefore, we developed a method to easily calculate the decay heat of debris considering parameters such as debris weight, burnup, nuclide release rate, and elapsed time etc.

Oral presentation

Development of theoretical scaling factor method for $$^{135}$$Cs caused by the Fukushima Daiichi NPP accident

Terashima, Kenichi; Sakamoto, Masahiro; Matsumura, Taichi; Okumura, Keisuke; Fujita, Manabu*

no journal, , 

no abstracts in English

Oral presentation

Strontium-90 measurement in trace amount of hard tissues for distribution analysis

Koarai, Kazuma; Matsueda, Makoto; Aoki, Jo; Yanagisawa, Kayo*; Fujiwara, Kenso; Terashima, Motoki; Kino, Yasushi*; Oka, Toshitaka; Okutsu, Kenichi*; Yamashita, Takuma*; et al.

no journal, , 

We demonstrated a method of $$^{90}$$Sr measurement in small pieces of hard tissues with radioactivity measurement or ICP-MS measurement. Interference elements of the measurements were removed by chemical separation. We could determine $$^{90}$$Sr in 0.1 g of hard tissues by radioactivity measurement method and ICP-MS method. Limit of detection of the ICP-MS method was lower than that of the radioactivity measurement. The ICP-MS method is adequate method for distribution analysis of $$^{90}$$Sr in the hard tissues.

Oral presentation

Depletion calculation of subcritical system with consideration of spontaneous fission reaction

Riyana, E. S.; Okumura, Keisuke; Sakamoto, Masahiro; Matsumura, Taichi; Terashima, Kenichi

no journal, , 

Oral presentation

Neutron irradiation test of bubble detector for fuel debris detections

Terashima, Kenichi; Matsumura, Taichi; Kaburagi, Masaaki; Sakamoto, Masahiro; Riyana, E. S.; Okumura, Keisuke

no journal, , 

no abstracts in English

Oral presentation

Characterization of beta-rays and bremsstrahlung X-rays of fuel debris

Matsumura, Taichi; Fujita, Manabu*; Terashima, Kenichi; Sakamoto, Masahiro; Okumura, Keisuke

no journal, , 

no abstracts in English

Oral presentation

The Possible use of short half-life noble gas fission products for measurement of criticality and identification of plutonium in fuel debris canister

Riyana, E. S.; Okumura, Keisuke; Sakamoto, Masahiro; Matsumura, Taichi; Terashima, Kenichi

no journal, , 

18 (Records 1-18 displayed on this page)
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