JPS63159736A - Concentration measuring method for uranium or plutonium - Google Patents
Concentration measuring method for uranium or plutoniumInfo
- Publication number
- JPS63159736A JPS63159736A JP61306349A JP30634986A JPS63159736A JP S63159736 A JPS63159736 A JP S63159736A JP 61306349 A JP61306349 A JP 61306349A JP 30634986 A JP30634986 A JP 30634986A JP S63159736 A JPS63159736 A JP S63159736A
- Authority
- JP
- Japan
- Prior art keywords
- light
- plutonium
- uranium
- concentration
- optical system
- 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
- 229910052778 Plutonium Inorganic materials 0.000 title claims abstract description 28
- 229910052770 Uranium Inorganic materials 0.000 title claims abstract description 28
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 title claims abstract description 28
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 title claims abstract description 28
- 238000000034 method Methods 0.000 title claims description 6
- 239000013307 optical fiber Substances 0.000 claims abstract description 9
- 238000010521 absorption reaction Methods 0.000 claims description 15
- 239000007788 liquid Substances 0.000 claims description 9
- 239000006059 cover glass Substances 0.000 claims description 4
- 238000003780 insertion Methods 0.000 claims description 3
- 230000037431 insertion Effects 0.000 claims description 3
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 2
- 239000000126 substance Substances 0.000 claims description 2
- 230000003287 optical effect Effects 0.000 abstract description 12
- 238000005259 measurement Methods 0.000 abstract description 5
- 239000000835 fiber Substances 0.000 abstract description 3
- 230000002238 attenuated effect Effects 0.000 abstract description 2
- 239000003795 chemical substances by application Substances 0.000 description 3
- 238000011109 contamination Methods 0.000 description 3
- 238000002835 absorbance Methods 0.000 description 2
- 230000031700 light absorption Effects 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 238000012958 reprocessing Methods 0.000 description 2
- XUIMIQQOPSSXEZ-UHFFFAOYSA-N Silicon Chemical compound [Si] XUIMIQQOPSSXEZ-UHFFFAOYSA-N 0.000 description 1
- 238000000862 absorption spectrum Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 229910052710 silicon Inorganic materials 0.000 description 1
- 239000010703 silicon Substances 0.000 description 1
- 238000012360 testing method Methods 0.000 description 1
- 229910052721 tungsten Inorganic materials 0.000 description 1
- 239000010937 tungsten Substances 0.000 description 1
- -1 tungsten halide Chemical class 0.000 description 1
Landscapes
- Investigating Or Analysing Materials By Optical Means (AREA)
Abstract
Description
【発明の詳細な説明】
〔産業上の利用分野〕
本発明は核燃料再処理施設におけるウランまたはプルト
ニウムの濃度測定方法に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of Industrial Application] The present invention relates to a method for measuring the concentration of uranium or plutonium in a nuclear fuel reprocessing facility.
ウランまたはプルトニウムの吸光性を利用して濃度を測
定する挿入型濃度計は、光源、特定の波長を選択する干
渉フィルター、選定波長光を伝送する光ファイバ、接液
カバーガラス、液中を透過する光を反射するミラー反射
光を伝送する光ファイバ、反射光の強さを電気信号に変
換する受光素子よりなり、ウランまたはプルトニウムの
吸光度を測定することによシ、濃度を求めている。Insertion type densitometers, which measure concentration using the light absorption properties of uranium or plutonium, consist of a light source, an interference filter that selects a specific wavelength, an optical fiber that transmits light of the selected wavelength, a cover glass in contact with the liquid, and a light that passes through the liquid. It consists of an optical fiber that transmits the reflected light, and a light receiving element that converts the intensity of the reflected light into an electrical signal.The concentration is determined by measuring the absorbance of uranium or plutonium.
ところが、吸光性を利用する濃度分析計では試料液と接
液カバーガラス及び反射ミラーよりなる光学系の接触が
避けられないため、光学系の汚染、損傷により測定値が
ドリフトする欠点があった。特に、核燃料再処理施設に
おいて使用される場合には、高放射線下にさらされるた
め光学系の損傷は著しく、従って、損傷による測定値の
ドリフトを校正する技術が重要であつた。However, in concentration analyzers that utilize light absorption, contact between the sample liquid and the optical system consisting of a liquid-contacted cover glass and a reflecting mirror is unavoidable, resulting in the disadvantage that measured values may drift due to contamination or damage to the optical system. In particular, when used in a nuclear fuel reprocessing facility, the optical system is exposed to high radiation, resulting in significant damage, and therefore, a technique for calibrating the drift of measured values due to damage is important.
本発明は従来の光学系を用いるウランまたはプルトニウ
ムの濃度測定方法の欠点を解消し、光学系の損傷による
測定値のドリフトを確実に校正し、精度の高い濃度測定
を可能とするウランまたはプルトニウムの濃度測定方法
を提供しようとするものである。The present invention eliminates the drawbacks of the conventional method for measuring the concentration of uranium or plutonium using an optical system, reliably calibrates the drift of measured values due to damage to the optical system, and enables highly accurate concentration measurement of uranium or plutonium. This paper attempts to provide a method for measuring concentration.
本発明は使用済核燃料を再処理する施設で、ウランまた
はプルトニウムを含む液の濃度を該物質の吸光性を利用
して、測定する光源及び特定の波長を選択する干渉フィ
ルタ、選択波長光を伝送する光ファイバ、接液カバーガ
ラス、液中を透過する光を反射するミラー、反射光を伝
送する光ファイバ、反射光の強さを電気信号に変換する
受光素子よりなるウランまたはプルトニウムの挿入型濃
度計においてウランまたはプルトニウムの吸収波長光の
吸収強度及びつ2ランまたはプルトニウムの非吸収波長
光の吸収強度を利用する事を特徴とするウランまたはプ
ルトニウムの濃度測定方法である。The present invention is a facility that reprocesses spent nuclear fuel, and uses a light source to measure the concentration of a liquid containing uranium or plutonium by utilizing the light absorbing properties of the substance, an interference filter that selects a specific wavelength, and a light source with a selected wavelength that is transmitted. An insertion-type concentration of uranium or plutonium consisting of an optical fiber that transmits the light, a cover glass that comes into contact with the liquid, a mirror that reflects the light that passes through the liquid, an optical fiber that transmits the reflected light, and a photodetector that converts the intensity of the reflected light into an electrical signal. This is a method for measuring the concentration of uranium or plutonium, which uses the absorption intensity of light at an absorption wavelength of uranium or plutonium and the absorption intensity of light at a non-absorption wavelength of uranium or plutonium.
〔作用〕
本発明者等は、光学系の損傷について研究する中で、原
子価4価のウラン、6価のウラン、3価のプルトニウム
、4価のプルトニウム、及び6価のプルトニウムの可視
領域における吸収スペクトルを詳細に観察したところ、
波長700um において、ウラン及びプルトニウムの
吸収係数が著しく小さくなシ、濃度にほとんど影響され
ないことが確認できた。そこで、この波長700nmの
光を参照光として、ウランまたはプルトニウムの吸光度
を測定した結果、光学系の汚染損傷による測定値のドリ
フトが著しく小さくすることができた。[Function] While researching damage to optical systems, the present inventors discovered that tetravalent uranium, hexavalent uranium, trivalent plutonium, tetravalent plutonium, and hexavalent plutonium in the visible region. A detailed observation of the absorption spectrum revealed that
It was confirmed that at a wavelength of 700 um, the absorption coefficients of uranium and plutonium are extremely small and are almost unaffected by concentration. Therefore, as a result of measuring the absorbance of uranium or plutonium using this light with a wavelength of 700 nm as a reference light, it was possible to significantly reduce the drift in measured values due to contamination and damage to the optical system.
第1図に本発明の1実施例である挿入型分光々度肝の全
体図を示す。本計器は発光・受光部1、光導部2、セン
サー3よシなる。第2図に発光・受光部の詳細を示す。FIG. 1 shows an overall view of an insertion type spectrophotometer according to an embodiment of the present invention. This meter consists of a light emitting/receiving section 1, a light guide section 2, and a sensor 3. Figure 2 shows details of the light emitting/light receiving section.
発光部は、電源装置4、ランプ5(吸収波長がウランや
プルトニウムの場合可視光域となるため、タングステン
ハライド光源等を用いる)集光レンズ6及び特定の波長
が選択できる干渉フィルタの取り付けられたセクタ7よ
妙なる。干渉フィルタは、ウラン及びプルトニウムの原
子価により次の様な波長を用いる。The light emitting unit is equipped with a power supply device 4, a lamp 5 (a tungsten halide light source or the like is used since the absorption wavelength is in the visible light range in the case of uranium or plutonium), a condensing lens 6, and an interference filter that can select a specific wavelength. Sector 7 is strange. The interference filter uses the following wavelengths depending on the valence of uranium and plutonium.
σ(IV)・・・650nm U (M) ・ψ・420nm Pu (n[) ・−拳 s 6o n。σ(IV)...650nm U (M)・ψ・420nm Pu (n[) ・-Fist s 6o n.
pu(■) −−−470nm
Pu(■)・@11852nm
また、参照光用の700 nmの干渉フィルタを用いる
。これらの干渉フィルタが取付けられたセクターはモー
タ8により回転され、交互に各々の波長を送光する。pu(■)---470nm Pu(■)@11852nm Also, a 700 nm interference filter for reference light is used. The sectors to which these interference filters are attached are rotated by a motor 8, and transmit each wavelength alternately.
各々の干渉光は反射ミラー9等の光学系により、投光用
光ファイバ10に送られる。Each of the interference lights is sent to a projection optical fiber 10 by an optical system such as a reflection mirror 9.
次にウランやプルトニウムにより吸収され減衰した光は
、センサー3で受光された後、受光用ファイバ11によ
り発光・受光部1に送られる。ここでは集光レンズ12
により集められた光をシリコン13等からなる受光素子
に受はブリメインアンプ14で増幅した後自動ゲインコ
ントロール(ムGo ) 15にて、前述の参照光強度
が同一となる様に調整される。すなわち、ここでウラン
またはプルトニウムの吸収強度は参照光強度の比の値に
変換されることになる。Next, the light absorbed and attenuated by uranium or plutonium is received by the sensor 3 and then sent to the light emitting/light receiving section 1 by the light receiving fiber 11. Here, the condenser lens 12
The light collected is received by a light receiving element made of silicon 13 or the like, and after being amplified by a main amplifier 14, it is adjusted by an automatic gain control (Go) 15 so that the above-mentioned reference light intensity becomes the same. That is, the absorption intensity of uranium or plutonium is converted into a value of the ratio of the reference light intensity.
その後サンプルホールド(8/H)16にてセクター7
の回転周期信号により認識されるサンプル番号により同
定した後濃度信号として出力計17よシ出力される。Then sector 7 at sample hold (8/H) 16
After identification by the sample number recognized by the rotation period signal, the output total 17 outputs it as a concentration signal.
本実施例によυ得られた原子価4価のウランの測定例を
第3図に示す。測定波長は520nm。FIG. 3 shows an example of measurement of tetravalent uranium obtained in this example. The measurement wavelength was 520 nm.
参照光波長は700nm、被検液のウラン濃度は120
fウラン/lであった。第S図より、520nm の
吸収光度は時間とともに減少しているにもかかわらず、
吸収強度と参照光強度の比は安定した値を示すことがわ
かる。The reference light wavelength is 700 nm, and the uranium concentration of the test liquid is 120.
f uranium/l. From Figure S, even though the absorption luminous intensity at 520 nm decreases with time,
It can be seen that the ratio between the absorption intensity and the reference light intensity shows a stable value.
〔発明の効果〕
本発明は上記構成を採用することにより、特に、参照光
として、波長700nmの光を利用し、ウランまたはプ
ルトニウムの吸収強度を参照光強度の比の値として測定
し、ウランまたはプルトニウムの濃度を決定することに
より、光学系の汚染、損傷による測定値のドリフトが著
しく小さくなシ、安定した計測が行えるようになった。[Effects of the Invention] By adopting the above configuration, the present invention uses light with a wavelength of 700 nm as a reference light, measures the absorption intensity of uranium or plutonium as a ratio value of the reference light intensity, and By determining the concentration of plutonium, it has become possible to perform stable measurements with significantly less drift in measured values due to contamination or damage to the optical system.
第1図は本発明の1実施例の全体図、第2図は第1図の
発光・受光部詳細図、第3図は実施例の吸収光度を示す
グラフである。
復代理人 内 1) 明
復代理人 萩 原 亮 −
復代理人 安 西 篤 夫FIG. 1 is an overall view of one embodiment of the present invention, FIG. 2 is a detailed view of the light emitting/light receiving portion of FIG. 1, and FIG. 3 is a graph showing the absorption luminous intensity of the embodiment. Sub-Agents 1) Meifuku Agent Ryo Hagiwara − Sub-Agent Atsuo Anzai
Claims (1)
ニウムを含む液の濃度を該物質の吸光性を利用して、測
定する光源及び特定の波長を選択する干渉フイルタ、選
択波長光を伝送する光フアイバ、接液カバーガラス、液
中を透過する光を反射するミラー、反射光を伝送する光
フアイバ、反射光の強さを電気信号に変換する受光素子
よりなるウランまたはプルトニウムの挿入型濃度計にお
いてウランまたはプルトニウムの吸収波長光の吸収強度
及びウランまたはプルトニウムの非吸収波長光の吸収強
度を利用する事を特徴とするウランまたはプルトニウム
の濃度測定方法。A facility that reprocesses spent nuclear fuel uses a light source to measure the concentration of a liquid containing uranium or plutonium by using the light absorbing properties of the substance, an interference filter that selects a specific wavelength, and an optical fiber that transmits light of the selected wavelength. , a uranium or plutonium insertion type densitometer consisting of a liquid-contacted cover glass, a mirror that reflects light transmitted through the liquid, an optical fiber that transmits the reflected light, and a photodetector that converts the intensity of the reflected light into an electrical signal. Alternatively, a method for measuring the concentration of uranium or plutonium, characterized by using the absorption intensity of light at an absorption wavelength of plutonium and the absorption intensity of light at a non-absorption wavelength of uranium or plutonium.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61306349A JPS63159736A (en) | 1986-12-24 | 1986-12-24 | Concentration measuring method for uranium or plutonium |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61306349A JPS63159736A (en) | 1986-12-24 | 1986-12-24 | Concentration measuring method for uranium or plutonium |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS63159736A true JPS63159736A (en) | 1988-07-02 |
Family
ID=17956012
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP61306349A Pending JPS63159736A (en) | 1986-12-24 | 1986-12-24 | Concentration measuring method for uranium or plutonium |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS63159736A (en) |
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2007536534A (en) * | 2004-05-07 | 2007-12-13 | ヘルマ ゲゼルシャフト ミット ベシュレンクテル ハフツング ウント コンパニー コマンディートゲゼルシャフト | Equipment for analyzing or absorbing small amounts of liquid media by light |
JP2017125747A (en) * | 2016-01-13 | 2017-07-20 | 三菱重工業株式会社 | Probe-type elemental analysis device, and elemental analysis method |
JP2018025527A (en) * | 2016-08-09 | 2018-02-15 | ケプコ ニュークリア フューエル カンパニー リミテッド | METHOD FOR ANALYZING SINTERED DENSITY FOR URANIUM OXIDE (UOx), USING SPECTROPHOTOMETER |
CN114136883A (en) * | 2021-11-22 | 2022-03-04 | 杭州谱育科技发展有限公司 | Detection system and method for multivalent plutonium element in nuclear fuel reprocessing |
-
1986
- 1986-12-24 JP JP61306349A patent/JPS63159736A/en active Pending
Cited By (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2007536534A (en) * | 2004-05-07 | 2007-12-13 | ヘルマ ゲゼルシャフト ミット ベシュレンクテル ハフツング ウント コンパニー コマンディートゲゼルシャフト | Equipment for analyzing or absorbing small amounts of liquid media by light |
JP2017125747A (en) * | 2016-01-13 | 2017-07-20 | 三菱重工業株式会社 | Probe-type elemental analysis device, and elemental analysis method |
JP2018025527A (en) * | 2016-08-09 | 2018-02-15 | ケプコ ニュークリア フューエル カンパニー リミテッド | METHOD FOR ANALYZING SINTERED DENSITY FOR URANIUM OXIDE (UOx), USING SPECTROPHOTOMETER |
CN114136883A (en) * | 2021-11-22 | 2022-03-04 | 杭州谱育科技发展有限公司 | Detection system and method for multivalent plutonium element in nuclear fuel reprocessing |
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