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Journal Articles

Preliminary study of the criticality monitoring method based on the simulation for the activity ratio of short half-life noble-gas fission products from fuel debris

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

Journal of Nuclear Science and Technology, 8 Pages, 2024/00

 Times Cited Count:0 Percentile:0.18(Nuclear Science & Technology)

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

 Times Cited Count:1 Percentile:31.61(Chemistry, Physical)

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:1 Percentile:16.35(Nuclear Science & Technology)

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

JAEA Reports

Thermal-hydraulic tests with out-of-pile test facility simulating natural convection capsule

Inaba, Yoshitomo; Sakamoto, Taichi; Yamaura, Takayuki

JAEA-Technology 2009-080, 22 Pages, 2010/02

JAEA-Technology-2009-080.pdf:7.06MB

The power transient tests for the fuels of light water reactors are to be carried out in the Japan Materials Testing Reactor (JMTR) using capsule-type test facilities, and the integrity of the fuels is to be investigated by the tests. Prior to the irradiation tests of the fuels, the out-of-pile test facility, which had an electric heater pin instead of a test fuel pin, was designed and fabricated to simulate the capsules used in the power transient tests. Using this facility, necessary tests for the planning of the test methods were carried out. In the present report, the outline of the out-of-pile test facility, the test plan and the tests simulating natural convection capsule were described. As a result of the tests, it was found that the power of the heater pin with a diameter of 9.5 mm can achieve to 600 W/cm without transition from nucleate boiling to film boiling under BWR and PWR coolant pressure conditions.

Journal Articles

Conceptual plan of radiopharmaceutical production process in JMTR

Iimura, Koichi; Sakamoto, Taichi; Kanno, Masaru; Hori, Naohiko

FAPIG, (178), p.14 - 18, 2009/02

At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA) advances the plan of refurbishing Japan Materials Testing Reactor (JMTR) to start the operation in fiscal 2011. As part of effective use for JMTR, JAEA is planning to product $$^{99}$$Mo, which is a parent nuclide of $$^{rm 99m}$$Tc. $$^{rm 99m}$$Tc is most commonly used as a radiopharmaceutical in the field of nuclear medicine. Currently the supplying of $$^{99}$$Mo is only depend on imports from foreign countries, so JAEA is aiming at domestic production of a part of $$^{99}$$Mo in cooperation with the industrial circles. In this article, JAEA introduced the Conceptual Plan about the choice and fabric of the irradiation facilities for $$^{99}$$Mo production, and commercializing equipment after irradiation for $$^{99}$$Mo production.

JAEA Reports

Conceptual study of silicon semiconductor production facility in JMTR

Hosokawa, Jinsaku; Kanno, Masaru; Sakamoto, Taichi

JAEA-Technology 2008-038, 24 Pages, 2008/06

JAEA-Technology-2008-038.pdf:2.95MB

At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA) advances the plan of refurbishing Japan Materials Testing Reactor (JMTR) to start the operation in fiscal 2011. Silicon Semiconductor is used in every Country and every industrial field. Nowadays, the demand of large diameter Silicon Semiconductors are increasing. At JMTR in JAEA Oarai, the production of Silicon Semiconductors utilizing NTD (Neutron Transmutation Doping) Method is investigated. Particularly, this report describes the installation of Silicon Semiconductors producing facility on JMTR. This Report described the Conceptual Study for Silicon Semiconductor Irradiation Facility in JMTR.

JAEA Reports

Conceptual study of $$^{99}$$Mo production facility in JMTR

Iimura, Koichi; Hosokawa, Jinsaku; Kanno, Masaru; Kitajima, Toshio; Nakagawa, Tetsuya; Sakamoto, Taichi; Hori, Naohiko; Kawamura, Hiroshi

JAEA-Technology 2008-035, 47 Pages, 2008/06

JAEA-Technology-2008-035.pdf:7.91MB

At Oarai Research and Development Center, Japan Atomic Energy Agency (JAEA) advances the plan of refurbishing Japan Materials Testing Reactor (JMTR) to start the operation in fiscal 2011. As part of effective use for JMTR, JAEA is planning to product $$^{99}$$Mo, which is a parent nuclide of $$^{rm 99m}$$Tc. $$^{rm 99m}$$Tc is most commonly used as a radiopharmaceutical in the field of nuclear medicine. Currently the supplying of $$^{99}$$Mo is only depend on imports from foreign countries, so JAEA is aiming at domestic production of a part of $$^{99}$$Mo in cooperation with the industrial circles. In this article, JAEA described the process, the choice and fabric of the irradiation facilities for $$^{99}$$Mo production, the technical study of commercializing equipment after irradiation, and the cost study for $$^{99}$$Mo production.

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

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, , 

Oral presentation

Application of bubble detector to fuel debris detection

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

no journal, , 

no abstracts in English

Oral presentation

Correlation between the canisters criticality and activity ratio of short-half-life noble-gas fission products under various fuel debris material compositions

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

no journal, , 

Oral presentation

Characterization of neutrons emitted from fuel debris

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

no journal, , 

no abstracts in English

Oral presentation

Practical gamma ray measurement of short half-life noble gas ($$^{135}$$Xe, $$^{88}$$Kr) emitted by fuel debris for criticality estimation

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

no journal, , 

20 (Records 1-20 displayed on this page)
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