JPH03231196A - Radioisotope container - Google Patents
Radioisotope containerInfo
- Publication number
- JPH03231196A JPH03231196A JP2525890A JP2525890A JPH03231196A JP H03231196 A JPH03231196 A JP H03231196A JP 2525890 A JP2525890 A JP 2525890A JP 2525890 A JP2525890 A JP 2525890A JP H03231196 A JPH03231196 A JP H03231196A
- Authority
- JP
- Japan
- Prior art keywords
- container
- main body
- detector
- insertion part
- radiation
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 238000003780 insertion Methods 0.000 claims abstract description 15
- 230000037431 insertion Effects 0.000 claims abstract description 15
- 230000005855 radiation Effects 0.000 claims abstract description 14
- 239000012857 radioactive material Substances 0.000 claims abstract description 9
- 239000000941 radioactive substance Substances 0.000 claims description 6
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 abstract description 12
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 abstract description 12
- 238000005259 measurement Methods 0.000 abstract description 9
- 238000009434 installation Methods 0.000 abstract 1
- 238000000034 method Methods 0.000 abstract 1
- 239000003758 nuclear fuel Substances 0.000 description 8
- 238000010586 diagram Methods 0.000 description 4
- 238000012545 processing Methods 0.000 description 4
- 238000012958 reprocessing Methods 0.000 description 4
- 230000007423 decrease Effects 0.000 description 3
- 239000000446 fuel Substances 0.000 description 3
- 239000000463 material Substances 0.000 description 3
- 239000006096 absorbing agent Substances 0.000 description 2
- 238000001514 detection method Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 230000001066 destructive effect Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000005251 gamma ray Effects 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000002915 spent fuel radioactive waste Substances 0.000 description 1
- 230000002269 spontaneous effect Effects 0.000 description 1
Landscapes
- Measurement Of Radiation (AREA)
Abstract
Description
【発明の詳細な説明】
[発明の目的]
(産業上の利用分野)
本発明はたとえば原子力発電所、核燃料加工工場、また
は燃料再処理施設などで使用される放射性物質を貯蔵す
るための放射性物質保管容器に関する。[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to radioactive materials for storing radioactive materials used in, for example, nuclear power plants, nuclear fuel processing plants, or fuel reprocessing facilities. Regarding storage containers.
(従来の技術)
原子力発電所の核燃料に加工するための核燃料加工工場
または原子力発電所で使用された使用済燃料を再処理す
る再処理工場では放射性物質である核燃料を専用の保管
容器に貯蔵している。(Conventional technology) Nuclear fuel processing plants for processing into nuclear fuel for nuclear power plants or reprocessing plants for reprocessing spent fuel used in nuclear power plants store nuclear fuel, which is radioactive material, in special storage containers. ing.
これらの保管容器に収容されている内容物の放射性同位
体の同定を非破壊で行うには放射性物質から出る放射線
を測定する必要がある。In order to non-destructively identify the radioactive isotopes in the contents contained in these storage containers, it is necessary to measure the radiation emitted from the radioactive materials.
第5図は核燃料加工工場内において、原子力発電所で使
用する燃料ペレットに加工する前の二酸化ウラン粉末を
入れる収容する保管容器と、この保管容器を放射線測定
する場合を示している。同図では、断面をあられす容器
本体1に二酸化ウラン2を収容したのち、蓋3により密
封したものである。二酸化ウランはU−238が自発核
分裂を起こすために常に中性子を発生している。この中
性子を検出するために中性子検出器4を備えており、こ
の中性子検出器4は測定回路5に接続されている。FIG. 5 shows a storage container containing uranium dioxide powder before being processed into fuel pellets to be used in a nuclear power plant in a nuclear fuel processing plant, and a case in which this storage container is subjected to radiation measurements. In the figure, uranium dioxide 2 is contained in a container body 1 whose cross section is rough, and then the container body 1 is sealed with a lid 3. Uranium dioxide constantly generates neutrons because U-238 undergoes spontaneous nuclear fission. A neutron detector 4 is provided to detect these neutrons, and this neutron detector 4 is connected to a measurement circuit 5.
(発明が解決しようとする課題)
しかしながら、このような形状をした放射性物質容器で
は以下のような課題があった。(Problems to be Solved by the Invention) However, the radioactive substance container having such a shape has the following problems.
第6図は第5図において測定回路5でカウントする中性
子のカウント数を縦軸に、容器本体1の径を横軸にとっ
てグラフ化したものである。なお、横軸の幅は第5図に
示した容器本体1の径と同寸法にしである。第6図から
明らかなように測定回路5ての中性子のカウント数は容
器本体1の表面では大きいか中心部に向かって徐々に低
下する。FIG. 6 is a graph showing the number of neutrons counted by the measuring circuit 5 in FIG. 5 on the vertical axis and the diameter of the container body 1 on the horizontal axis. Note that the width of the horizontal axis is the same as the diameter of the container body 1 shown in FIG. As is clear from FIG. 6, the number of neutron counts in the measuring circuit 5 is large on the surface of the container body 1, and gradually decreases toward the center.
これは中心方向に沿うにしたかって中性子検出器4との
間に存在する中性子吸収体となる二酸化ウラン2の量か
多くなるためである。このような場合、中性子のカウン
ト数から二酸化ウランの総量を求めると中性子の検出効
率か低いため精度に課題かあった。This is because the amount of uranium dioxide 2 serving as a neutron absorber existing between the neutron detector 4 and the neutron detector 4 increases along the center direction. In such cases, calculating the total amount of uranium dioxide from the number of neutron counts poses a problem with accuracy because the neutron detection efficiency is low.
本発明は上記課題を解決するためになされたもので、放
射線計測の測定精度を向上させることができる放射性物
質保管容器を提供することにある。The present invention has been made to solve the above problems, and an object of the present invention is to provide a radioactive substance storage container that can improve the measurement accuracy of radiation measurement.
[発明の構成]
(課題を解決するための手段)
本発明は密封構造の容器本体と、この容器本体にその中
心方向に沿って設けられ該容器本体内に収容された放射
性物質の放射線を検出するための放射線検出器を挿入す
る挿入部とからなることを特徴とする。[Structure of the Invention] (Means for Solving the Problems) The present invention includes a container body having a sealed structure, and a device provided along the center direction of the container body to detect radiation of a radioactive substance contained in the container body. and an insertion section into which a radiation detector is inserted.
(作 用)
本発明においては、容器本体内に収容されている放射性
物質の測定に際して挿入部に放射線検出器を挿入するこ
とによって非破壊で精度よく測定することかできる。(Function) In the present invention, by inserting a radiation detector into the insertion portion when measuring the radioactive substance contained in the container main body, the measurement can be performed non-destructively and with high precision.
(実施例)
本発明に係る放射性物質保管容器の第1の実施例を第1
図および第2図を参照して説明する。なお、図中第5図
と同一部分には同一符号を付して重複する部分の説明は
省略する。(Example) The first example of the radioactive material storage container according to the present invention is shown in the first example.
This will be explained with reference to the figures and FIG. In addition, the same parts in the figure as in FIG. 5 are given the same reference numerals, and the explanation of the overlapping parts will be omitted.
第1図において、上端が蓋3て密封された筒状容器本体
1には中性子検出器4を中心部に向けて挿入できるよう
に挿入部1aか形成されている。In FIG. 1, an insertion portion 1a is formed in a cylindrical container body 1 whose upper end is sealed with a lid 3 so that a neutron detector 4 can be inserted toward the center.
この挿入部1aは容器本体1の底面から中心部に向けて
形成されたウェル型くぼみである。The insertion portion 1a is a well-shaped recess formed from the bottom of the container body 1 toward the center.
容器本体コ内には例えば二酸化ウラン2か収容されてい
る。この二酸化ウラン2の総量を測定する場合には中性
子検出器4を挿入部1a内に挿入する。中性子検出器4
からの信号は測定回路5に接続されている。For example, uranium dioxide 2 is contained within the container body. When measuring the total amount of uranium dioxide 2, a neutron detector 4 is inserted into the insertion portion 1a. Neutron detector 4
The signal from is connected to the measuring circuit 5.
このように中性子検出器4か中心部に設置できる挿入部
1aを設けた放射性物質容器の作用を説明する。第2図
は従来例として説明したと同様に第1図において測定回
路5てカウントする中性子のカウント数を縦軸に、容器
の径を横軸にとってグラフ化したものである。The operation of the radioactive substance container provided with the insertion part 1a that can be installed in the center of the neutron detector 4 will be explained. FIG. 2 is a graph in which the number of neutrons counted by the measuring circuit 5 in FIG. 1 is plotted on the vertical axis and the diameter of the container is plotted on the horizontal axis, as in the conventional example.
第2図から明らかなように中性子吸収体となる二酸化ウ
ランの量が少なくなるため容器本体1の中央部では中性
子のカウント数か多くなる。両端へ向うにつれてカウン
ト数は少なくなる。As is clear from FIG. 2, since the amount of uranium dioxide which acts as a neutron absorber decreases, the number of neutrons counted increases in the center of the container body 1. The count decreases toward both ends.
第3図は本発明の第2の実施例を示したもので、この実
施例では容器本体1の中心部を貫通したトンネル状の挿
入部1aを形成したことにある。他の部分は第1の実施
例と同様なのでその説明を省略する。この実施例によれ
ば中性子検出器4を左右から挿入することかできる利点
がある。FIG. 3 shows a second embodiment of the present invention, in which a tunnel-shaped insertion portion 1a is formed passing through the center of the container body 1. The other parts are the same as those in the first embodiment, so their explanation will be omitted. This embodiment has the advantage that the neutron detector 4 can be inserted from either the left or the right.
第4図は本発明の第3の実施例を示したもので、この実
施例では蓋3に挿入部1aを備えたことにある。この実
施例によれば上方から中性子検出器4を挿入するので操
作性が容易である。FIG. 4 shows a third embodiment of the present invention, in which the lid 3 is provided with an insertion portion 1a. According to this embodiment, since the neutron detector 4 is inserted from above, operability is easy.
第3図および第4図で示した容器及び放射線測定装置の
動作は前記第1の実施例の場合と同様である。The operations of the container and radiation measuring device shown in FIGS. 3 and 4 are the same as in the first embodiment.
尚、上記各々の実施例では燃料加工工場での二酸化ウラ
ンを入れる核燃料物質保管容器を例に説明したが、例え
ば再処理工場で生産する核燃料物質を入れる核燃料物質
保管容器についても同様に実施できる。更に中性子測定
以外の例えばγ線測定の場合においても同様な作用か得
られる。In each of the above embodiments, a nuclear fuel material storage container containing uranium dioxide at a fuel fabrication plant was described as an example, but the same can be applied to a nuclear fuel material storage container containing nuclear fuel material produced at a reprocessing plant, for example. Furthermore, similar effects can be obtained in cases other than neutron measurements, such as gamma ray measurements.
[発明の効果]
本発明によれば非破壊で放射線の検出効率を高め精度よ
く放射線測定することができる。[Effects of the Invention] According to the present invention, radiation detection efficiency can be increased and radiation can be measured with high accuracy in a non-destructive manner.
第1図は本発明に係る放射性物質保管容器の第1の実施
例を示す構成図、第2図は第1図における作用を示す特
性図、第3図及び第4図はそれぞれ本発明の第2および
第3の実施例を示す構成図、第5図は従来の放射性物質
保管容器を示す構成図、第6図は第5図における作用を
示す特性図である。
1・・容器本体
1
a・・・挿入部
・・二酸化ウラン
3・・蓋
4・・・中性子検出器
5・・測定回路
(8733)FIG. 1 is a configuration diagram showing a first embodiment of a radioactive material storage container according to the present invention, FIG. 2 is a characteristic diagram showing the action in FIG. 1, and FIGS. FIG. 5 is a configuration diagram showing a conventional radioactive material storage container, and FIG. 6 is a characteristic diagram showing the operation in FIG. 5. 1... Container body 1 a... Insertion section... Uranium dioxide 3... Lid 4... Neutron detector 5... Measurement circuit (8733)
Claims (1)
沿って設けられ該容器本体内に収容された放射性物質の
放射線を検出するための放射線検出器を挿入する挿入部
とからなることを特徴とする放射性物質保管容器。It is characterized by comprising a container body with a sealed structure, and an insertion part provided along the center direction of the container body and into which a radiation detector for detecting radiation of the radioactive substance contained in the container body is inserted. radioactive material storage container.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2525890A JPH03231196A (en) | 1990-02-06 | 1990-02-06 | Radioisotope container |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP2525890A JPH03231196A (en) | 1990-02-06 | 1990-02-06 | Radioisotope container |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH03231196A true JPH03231196A (en) | 1991-10-15 |
Family
ID=12160997
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP2525890A Pending JPH03231196A (en) | 1990-02-06 | 1990-02-06 | Radioisotope container |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH03231196A (en) |
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5274239A (en) * | 1992-07-23 | 1993-12-28 | Sunol Technologies, Inc. | Shielded dose calibration apparatus |
CN102879797A (en) * | 2012-10-09 | 2013-01-16 | 贝谷科技股份有限公司 | Food and water radioactivity detection instrument |
-
1990
- 1990-02-06 JP JP2525890A patent/JPH03231196A/en active Pending
Cited By (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US5274239A (en) * | 1992-07-23 | 1993-12-28 | Sunol Technologies, Inc. | Shielded dose calibration apparatus |
CN102879797A (en) * | 2012-10-09 | 2013-01-16 | 贝谷科技股份有限公司 | Food and water radioactivity detection instrument |
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