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Application of CR-39 plastic nuclear track detectors for quality assurance of MOX fuel pellet

https://repo.qst.go.jp/records/71495
https://repo.qst.go.jp/records/71495
1bea8c34-413a-4b79-bfa8-b76a2b77d8ff
Item type 会議発表用資料 / Presentation(1)
公開日 2014-09-22
タイトル
タイトル Application of CR-39 plastic nuclear track detectors for quality assurance of MOX fuel pellet
言語
言語 eng
資源タイプ
資源タイプ識別子 http://purl.org/coar/resource_type/c_c94f
資源タイプ conference object
アクセス権
アクセス権 metadata only access
アクセス権URI http://purl.org/coar/access_right/c_14cb
著者 Kodaira, Satoshi

× Kodaira, Satoshi

WEKO 703013

Kodaira, Satoshi

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Kurano, Mieko

× Kurano, Mieko

WEKO 703014

Kurano, Mieko

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Hosogane, Tatsuya

× Hosogane, Tatsuya

WEKO 703015

Hosogane, Tatsuya

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Ishikawa, Fumitaka

× Ishikawa, Fumitaka

WEKO 703016

Ishikawa, Fumitaka

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Kageyama, Tomio

× Kageyama, Tomio

WEKO 703017

Kageyama, Tomio

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Sato, Mitsuhiro

× Sato, Mitsuhiro

WEKO 703018

Sato, Mitsuhiro

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Yasuda, Nakahiro

× Yasuda, Nakahiro

WEKO 703019

Yasuda, Nakahiro

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小平 聡

× 小平 聡

WEKO 703020

en 小平 聡

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蔵野 美恵子

× 蔵野 美恵子

WEKO 703021

en 蔵野 美恵子

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安田 仲宏

× 安田 仲宏

WEKO 703022

en 安田 仲宏

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抄録
内容記述タイプ Abstract
内容記述 The plutonium-thermal use is expected as one of the approach for reuse of spent uranium fuel in nuclear power generation. On the other hand, many kinds of nuclides including Pu with extremely long half-lives are generated in the used fuels, which would be problems for storage and control of radioactive waste. The MOX (Mixed Oxide) consisting of plutonium dioxide enriched with 4-9% Pu and uranium oxide from spent uranium fuel would allow to reduce half-lives of radioactive waste significantly through the nuclear fission. The MOX pellet is produced through sintering process after the mixing of Pu oxide and U oxide powders. The quality of MOX pellet depends on the homogeneous dispersion of Pu. The region of highly concentrated Pu is sometimes observed as “Pu spot” in the pellet, which has the potential of anomalous combustion localized at that region. The detection of Pu spot and evaluation of its size and concentration are one of the important quality assurance of MOX pellet for the safety use in the nuclear power plant. We have applied CR-39 plastic nuclear track detectors for the measurement of Pu spot inside MOX pellet. CR-39 can image a cross-section of MOX pellet by recording α-particle tracks from Pu in the pellet, like autoradiography. The Pu spot is visibly imaged as a “black spot” due to the dense α tracks compared to homogeneously dispersed region. Conventionally, the Pu spot measurement has been carried out with manual scanning, which takes much longer times and huge amount of human work. We have developed the automatic detection and measurement system of Pu spot recorded on CR-39 by the image processing with filtering and clustering algorithms. The detection efficiency with CR-39 is achieved to be almost 100% compared with conventional manual scanning result. It provides more information about the number, size and position of Pu spot. This system will be a powerful tool of screening test for the quality assurance of MOX pellet.
会議概要(会議名, 開催地, 会期, 主催者等)
内容記述タイプ Other
内容記述 The 26th International Conference on Nuclear Tracks in Solids
発表年月日
日付 2014-09-18
日付タイプ Issued
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