JPH0219916B2 - - Google Patents
Info
- Publication number
- JPH0219916B2 JPH0219916B2 JP56086860A JP8686081A JPH0219916B2 JP H0219916 B2 JPH0219916 B2 JP H0219916B2 JP 56086860 A JP56086860 A JP 56086860A JP 8686081 A JP8686081 A JP 8686081A JP H0219916 B2 JPH0219916 B2 JP H0219916B2
- Authority
- JP
- Japan
- Prior art keywords
- gamma ray
- fuel
- gamma
- fuel assembly
- ray detector
- 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.)
- Expired - Lifetime
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Classifications
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Measurement Of Radiation (AREA)
Description
【発明の詳細な説明】
本発明は原子力発電所の原子炉用燃料集合体か
らのガンマ線強度を測定し、各燃料棒からのガン
マ線強度を求めるガンマスキヤン装置に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a gamma scan device that measures the gamma ray intensity from a fuel assembly for a nuclear reactor in a nuclear power plant and determines the gamma ray intensity from each fuel rod.
従来、原子炉の燃料の燃焼度や、運転中の出力
を非破壊的に測定するための装置として、燃料か
ら発生するガンマ線を測定する装置がある。この
装置は燃料中に蓄積する核分裂生成物の崩壊によ
るガンマ線を測定し、燃焼度や運転中の出力の大
きさを求めるものである。従来の装置の配置図を
第１図ａ，ｂおよび第２図ａ，ｂに示す。第１図
ａ，ｂは燃料集合体１１を対象とした場合のガン
マ線コリメータ１２とガンマ線検出器１３との幾
何学的配置図で、同図ａは縦断面、同図ｂは横断
面の配置を示す。又、第２図ａ，ｂは燃料棒１４
を対象とした場合のガンマ線コリメータ１２とガ
ンマ線検出器１３との幾何学的配置図で、同図ａ
は縦断面、同図ｂは横断面の配置を示す。この第
２図ａ，ｂで示す後者の場合は、燃料集合体１１
を解体し、燃料棒１４を一体ずつ測定している。
燃料管理、炉心管理の立場からすると、この方が
より詳細で正確な情報を得られるので、望ましい
手段である。しかしながら、燃料集合体１１の解
体作業に伴なう放射線被曝や、作業時間ならびに
測定時間が大きいという欠点がある。 Conventionally, as a device for non-destructively measuring the burn-up of fuel in a nuclear reactor and the output during operation, there is a device that measures gamma rays generated from fuel. This device measures gamma rays produced by the decay of fission products that accumulate in the fuel, and determines the burnup and output during operation. Layout diagrams of conventional devices are shown in FIGS. 1a, b and 2 a, b. Figures 1a and 1b are geometrical layout diagrams of the gamma ray collimator 12 and gamma ray detector 13 when targeting the fuel assembly 11. show. In addition, Fig. 2 a and b show the fuel rods 14.
This is a geometric layout diagram of the gamma ray collimator 12 and the gamma ray detector 13 when the target is
shows the arrangement in longitudinal section, and Fig. b shows the arrangement in cross section. In the latter case shown in FIG. 2 a and b, the fuel assembly 11
The fuel rods 14 were dismantled and measured one by one.
From the standpoint of fuel management and core management, this method is preferable because it allows more detailed and accurate information to be obtained. However, there are disadvantages in that the dismantling work of the fuel assembly 11 involves radiation exposure, and that the working time and measurement time are long.
本発明の目的は、燃料集合体を対象として測定
を行ない、それを構成する燃料棒毎のガンマ線強
度を求め得る燃料集合体のガンマスキヤン装置を
提供し、放射線被曝を逃れ、作業時間ならびに測
定時間を短かくし得ることにある。 An object of the present invention is to provide a gamma scanning device for a fuel assembly that can perform measurements on a fuel assembly and determine the gamma ray intensity of each fuel rod constituting the fuel assembly, thereby avoiding radiation exposure and reducing working time and measurement time. The reason is that it can be made shorter.
以下、本発明の一実施例について、第３図およ
び第４図ａ，ｂを参照して説明する。第３図は装
置全体を示している。燃料集合体１１は燃料集合
体支持装置２３に固定されている。この支持装置
２３は燃料集合体１１を乗せ、回転駆動装置２５
によつてガンマ線コリメータ１２およびガンマ線
検出器１３を備えたガンマ線検出器系１５に対し
て燃料棒に平行な軸の周りで回転する。燃料集合
体支持装置２３と回転駆動装置２５は、さらに回
転系支持装置２６に固定されており、この回転系
支持装置２６は上下駆動装置２４によつて、上下
軸２２に沿い、上下に移動する。上下軸２２、上
下駆動装置２４は駆動系支持装置２１に取付けら
れている。回転駆動装置２５および上下動駆動装
置２４は駆動制御装置３３によつて制御させる。
燃料集合体１１から発生するガンマ線は、ガンマ
線コリメータ１２によつてコリメートさせ、ガン
マ線検出器１３によつて検出させる。ガンマ線検
出器１３からの信号は計数駆動制御装置３１を通
して演算装置３２に入力させ、後述の演算処理を
させる。 An embodiment of the present invention will be described below with reference to FIG. 3 and FIGS. 4a and 4b. FIG. 3 shows the entire device. The fuel assembly 11 is fixed to a fuel assembly support device 23. This support device 23 carries the fuel assembly 11, and the rotary drive device 25
rotates about an axis parallel to the fuel rods relative to a gamma ray detector system 15 comprising a gamma ray collimator 12 and a gamma ray detector 13. The fuel assembly support device 23 and the rotation drive device 25 are further fixed to a rotation system support device 26, and this rotation system support device 26 is moved up and down along the vertical axis 22 by the vertical drive device 24. . The vertical shaft 22 and the vertical drive device 24 are attached to the drive system support device 21. The rotation drive device 25 and the vertical drive device 24 are controlled by a drive control device 33.
Gamma rays generated from the fuel assembly 11 are collimated by a gamma ray collimator 12 and detected by a gamma ray detector 13. The signal from the gamma ray detector 13 is input to the arithmetic unit 32 through the counting drive control device 31, and is subjected to arithmetic processing as described below.
第４図ａ，ｂはガンマ線検出器系１５と燃料集
合体１１をさらに詳細に示している。第４図ａは
横断面図、第４図ｂは縦断面図である。ガンマ線
コリメータ１２の立体角の燃料集合体に向ける横
幅Ｗは燃料集合体１１横幅のうち、燃料棒１４の
約0.8本を見込む大きさとし、ガンマ線コリメー
タ１２によつて燃料棒１４のガンマ線コリメータ
し、ガンマ線検出器１３によつて検出させる。 4a and 4b show the gamma ray detector system 15 and the fuel assembly 11 in more detail. FIG. 4a is a cross-sectional view, and FIG. 4b is a longitudinal cross-sectional view. The width W of the solid angle of the gamma ray collimator 12 toward the fuel assembly is set to a size that allows approximately 0.8 of the fuel rods 14 out of the width of the fuel assembly 11. It is detected by the detector 13.
次にこの実施例によつて各燃料棒１４のガンマ
線強度を測定する原理を説明する。 Next, the principle of measuring the gamma ray intensity of each fuel rod 14 will be explained using this embodiment.
第４図ａに示すような配置で検出されるガンマ
線は第４図ａ中斜線を施して示した部分の燃料か
らのものに制限される。回転角θiを変えて測定を
繰返し、回転角とガンマ線強度との対のデータを
得る。このようにして得られたガンマ線強度をCi
（ｉ＝１〜Ｎ；Ｎ＝測定データ個数）とする。燃
料集合体１１中の燃料棒１４本数をＭとすると、
Ciは
Ci＝M
〓j=1
RijPj ……(101)
として表わすことができる。この（101）式でPj
は燃料棒ｊのガンマ線強度、Rijは応答関数と称
され、各燃料棒のガンマ線検出器系への寄与度を
表わす関数であつて、回転角θiと燃料棒ｊ（ｊ＝
１〜Ｍ）に依存し、
Rij＝Tij Ωij ……(102)
と表わすことができる。ここでTijは燃料棒ｊと
ガンマ線検出器１３との間にある燃料棒によるし
やへい効果を表わすもので、注目しているガンマ
線の透過率である。またΩijは燃料棒ｊのガンマ
線検出器１３に対する立体角である。例えば第４
図ａのような配置では、Ωijは斜線で示した燃料
棒以外０である。この応答関数は燃料棒のガンマ
線強度に無関係にあらかじめ計算することができ
る。 Gamma rays detected in the arrangement shown in FIG. 4a are limited to those from the fuel in the shaded area in FIG. 4a. The measurement is repeated by changing the rotation angle θ i to obtain paired data of rotation angle and gamma ray intensity. The gamma ray intensity obtained in this way is C i
(i=1 to N; N=number of measurement data). If the number of 14 fuel rods in the fuel assembly 11 is M,
C i can be expressed as C i = M 〓 j=1 R ij P j ……(101). In this equation (101), P j
is the gamma ray intensity of fuel rod j , and R ij is called a response function, which represents the contribution of each fuel rod to the gamma ray detector system.
1 to M), and can be expressed as R ij =T ij Ω ij (102). Here, T ij represents the shielding effect due to the fuel rod between the fuel rod j and the gamma ray detector 13, and is the gamma ray transmittance of interest. Further, Ω ij is the solid angle of the fuel rod j with respect to the gamma ray detector 13. For example, the fourth
In the arrangement shown in Figure a, Ω ij is 0 except for the fuel rods indicated by diagonal lines. This response function can be calculated in advance regardless of the gamma ray intensity of the fuel rod.
したがつて、Ｎ＞Ｍすなわち、燃料棒本数Ｍに
比べ、測定角度点Ｎが多いと言う条件のもとに、
（101）式から燃料棒ｊのガンマ線強度Pjを最小二
乗法等の方法で求めることができる。 Therefore, under the condition that N>M, that is, there are more measurement angle points N than the number of fuel rods M,
From equation (101), the gamma ray intensity P j of the fuel rod j can be determined by a method such as the least squares method.
燃料集合体を見込むガンマ線コリメータ１２の
立体角の燃料集合体に向ける横幅Ｗは、これを大
きくすると、ガンマ線検出器１３に入射するガン
マ線の数が多くなり、計数率が高くなるため、測
定時間が短くなるが、（101）式からPjを求める精
度が悪くなる。この関係を第５図に示す。第５図
曲線ａはコリメータが見込む燃料棒本数に対する
Pjの誤差を示し、曲線ｂは前記本数に対する測定
時間を示し、実用可能な立体角の燃料集合体に向
ける横幅は0.5〜３本の燃料棒を見込む程度であ
ることを示している。この実用可能な立体角の燃
料集合体に向ける横幅Ｗは、沸騰水形原子炉の燃
料では0.5〜５cm程度である。 When the width W of the solid angle of the gamma ray collimator 12 facing the fuel assembly is increased, the number of gamma rays incident on the gamma ray detector 13 increases, the counting rate increases, and the measurement time increases. Although it is shorter, the accuracy of determining P j from equation (101) becomes worse. This relationship is shown in FIG. Curve a in Figure 5 corresponds to the number of fuel rods expected by the collimator.
The curve b shows the measurement time for the number of rods, and shows that the width of the fuel assembly with a practical solid angle is about 0.5 to 3 fuel rods. The width W of a fuel assembly having a practical solid angle is about 0.5 to 5 cm for boiling water reactor fuel.
次に第３図の構成の作用について説明する。 Next, the operation of the configuration shown in FIG. 3 will be explained.
回転駆動装置２５はガンマ線検出器系１５に対
して、燃料集合体１１を回転させ、所望の回転角
にセツトする。この回転駆動装置２５は駆動制御
装置３３によつて制御されるが、この駆動制御装
置３３はさらに計数駆動制御装置３１によつて制
御され、燃料集合体１１の回転とガンマ線の測定
とを交互に繰返すルーチンを制御する。上下駆動
装置２４は燃料集合体１１を上下に移動するもの
で、燃料集合体１１の軸方向の任意の高さでの測
定を可能とし、ガンマ線の計数と連動して駆動す
るよう計数駆動制御装置３１によつて制御する。
演算装置３２は予め用意した応答関数Rijを内蔵
し、計数駆動制御装置３１を通して計数したガン
マ線の強度Ciから、（101）式によつて燃料棒のガ
ンマ線強度Pjを演算する。従つて、各燃料棒のガ
ンマ線強度を、燃料集合体１１を解体せずに測定
することができ、燃料集合体１１の解体作業に伴
なう放射線被曝を不必要とし、また燃料棒を一本
ずつ測定する方法に比べ、測定時間をかなり短く
することができる。そのうえ、回転駆動装置２
５、上下駆動装置２４とガンマ線検出器系１５と
を同時に制御することができるので、自動的にガ
ンマスキヤンを行なうことができ、ガンマスキヤ
ンに伴なう放射線被曝を低減することができる。 The rotation drive device 25 rotates the fuel assembly 11 with respect to the gamma ray detector system 15 and sets it at a desired rotation angle. This rotation drive device 25 is controlled by a drive control device 33, which is further controlled by a counting drive control device 31, which alternately rotates the fuel assembly 11 and measures gamma rays. Control repeating routines. The vertical drive device 24 moves the fuel assembly 11 up and down, and enables measurement at any height in the axial direction of the fuel assembly 11. A counting drive control device is used to drive the fuel assembly 11 in conjunction with gamma ray counting. 31.
The calculation device 32 incorporates a response function R ij prepared in advance, and calculates the gamma ray intensity P j of the fuel rod from the gamma ray intensity C i counted through the counting drive control device 31 using equation (101). Therefore, the gamma ray intensity of each fuel rod can be measured without dismantling the fuel assembly 11, eliminating the need for radiation exposure associated with dismantling the fuel assembly 11, and reducing the need for only one fuel rod. Compared to the method of measuring increments, the measurement time can be considerably shortened. Moreover, the rotary drive device 2
5. Since the vertical drive device 24 and the gamma ray detector system 15 can be controlled simultaneously, gamma scanning can be performed automatically, and radiation exposure accompanying gamma scanning can be reduced.
尚、本発明は上記し、かつ図面に示した実施例
のみに限定されるのみではなく、その要旨を変更
しない範囲で、種々変形して実施できることは勿
論である。 It should be noted that the present invention is not limited only to the embodiments described above and shown in the drawings, but can of course be implemented with various modifications without changing the gist thereof.
以上説明したように、本発明によれば、燃料集
合体を解体せずに、燃料集合体の周囲から、ガン
マ線コリメータを介してガンマ線検出器にて燃料
棒から出るガンマ線を測定することにより、燃料
集合体の解体作業に伴なう放射線被曝を不必要と
し、燃料棒を一本ずつ測定する従来の方法に比べ
測定時間をかなり短くし、さらにガンマ線コリメ
ータの燃料集合体に対する立体角の燃料集合体に
向ける横幅を、燃料棒の0.5〜３本を見込む大き
さとしたことにより、各燃料棒のガンマ線強度を
高精度で測定できる燃料集合体のガンマスキヤン
装置が得られる。 As explained above, according to the present invention, gamma rays emitted from the fuel rods are measured from around the fuel assembly using a gamma ray detector via a gamma ray collimator without disassembling the fuel assembly. It eliminates the need for radiation exposure associated with the dismantling of the assembly, considerably shortens the measurement time compared to the conventional method of measuring fuel rods one by one, and furthermore, the gamma ray collimator's solid angle with respect to the fuel assembly can be adjusted. By setting the width of the fuel assembly to a size that allows for 0.5 to 3 fuel rods, a fuel assembly gamma scan device that can measure the gamma ray intensity of each fuel rod with high accuracy can be obtained.
第１図ａ，ｂは燃料集合体を対象として行なう
従来のガンマスキヤン装置の概念を示すもので、
ａは縦断面図、ｂは横断面図、第２図ａ，ｂは燃
料棒を対象として行なう従来のガンマスキヤン装
置の概念を示すもので、ａは縦断面図、ｂは横断
面図、第３図は本発明の燃料集合体のガンマスキ
ヤン装置の一実施例を示す縦断面図、第４図ａ，
ｂは第３図のガンマ線検出器系と燃料集合体とを
詳細に示すもので、ａは横断面図、ｂは縦断面
図、第５図はガンマ線コリメータが燃料棒本数に
対する必要な測定時間と、演算した燃料棒のガン
マ線強度の誤差の関係を示す曲線図である。
Ｗ……コリメータ立体角の燃料集合体に向ける
横幅、１１……燃料集合体、１２……ガンマ線コ
リメータ、１３……ガンマ線検出器、１４……燃
料棒、１５……ガンマ線検出器系、２１……駆動
系支持装置、２２……上下軸、２３……燃料集合
体支持装置、２４……上下駆動装置、２５……回
転駆動装置、２６……回転系支持装置、３１……
計数駆動制御装置、３２……演算装置、３３……
駆動制御装置。
Figures 1a and 1b show the concept of a conventional gamma scan device that targets fuel assemblies.
a is a vertical sectional view, b is a horizontal sectional view, and Figures 2a and 2b show the concept of a conventional gamma scan device that targets fuel rods; 3 is a longitudinal sectional view showing an embodiment of the gamma scan device for a fuel assembly of the present invention, and FIG. 4a,
b shows the gamma ray detector system and fuel assembly in Fig. 3 in detail, a is a cross-sectional view, b is a longitudinal sectional view, and Fig. 5 shows how the gamma-ray collimator measures the required measurement time and the number of fuel rods. , is a curve diagram showing the relationship between the calculated gamma ray intensity errors of the fuel rods. W... Width of collimator solid angle toward fuel assembly, 11... Fuel assembly, 12... Gamma ray collimator, 13... Gamma ray detector, 14... Fuel rod, 15... Gamma ray detector system, 21... ... Drive system support device, 22 ... Vertical shaft, 23 ... Fuel assembly support device, 24 ... Vertical drive device, 25 ... Rotation drive device, 26 ... Rotation system support device, 31 ...
Counting drive control device, 32... Arithmetic device, 33...
Drive control device.
Claims (1)
支持する燃料集合体支持手段と、 前記燃料棒の軸方向に対しほぼ垂直な面に設定
され、立体角の燃料集合体に向ける横幅が0.5〜
３本を見込む大きさに設定されたガンマ線コリメ
ータを介して、ガンマ線検出器にて前記燃料棒か
ら出るガンマ線を測定するガンマ線検出器系と、 前記燃料集合体および前記燃料集合体支持手段
を前記燃料棒に平行な軸の周りで回転させる回転
駆動手段と、 この回転駆動手段による回転と前記ガンマ線検
出器系によるガンマ線の測定とを交互に繰返すル
ーチンを制御し、ガンマ線の強度Ci（ｉ＝１〜
Ｎ；Ｎ＝測定データ個数、ただしＮ＞燃料棒数
Ｍ）を得る計数駆動制御手段と、 この計数駆動制御手段を通して測定したガンマ
線の強度Ciを用いて Ci＝M 〓j=1 RijPj ただし、 Rij＝TijΩij Pj；燃料棒ｊのガンマ線強度 Tij；燃料棒ｊと前記ガンマ線検出器との間にあ
る燃料棒による遮蔽効果 Ωij；燃料棒ｊのガンマ線検出器に対する立体角 なる式から燃料棒ｊのガンマ線強度Pjを演算する
演算手段、 とからなることを特徴とする燃料集合体のガンマ
スキヤン装置。[Scope of Claims] 1. Fuel assembly support means for supporting a fuel assembly constituted by a plurality of fuel rods; Width facing the body is 0.5~
a gamma ray detector system that measures gamma rays emitted from the fuel rods with a gamma ray detector via a gamma ray collimator set to a size that allows for three gamma rays; A rotary drive means for rotating around an axis parallel to the rod, and a routine that alternately repeats rotation by this rotary drive means and measurement of gamma rays by the gamma ray detector system are controlled, and gamma ray intensity C i (i=1 ~
Using a counting drive control means to obtain N; N = number of measured data, where N > number of fuel rods M) and intensity C i of gamma rays measured through this counting drive control means, C i = M 〓 j=1 R ij P j However, R ij = T ij Ω ij P j ; Gamma ray intensity of fuel rod j T ij ; Shielding effect by the fuel rod between fuel rod j and the gamma ray detector Ω ij ; Gamma ray detection of fuel rod j 1. A gamma scan device for a fuel assembly, comprising: calculation means for calculating the gamma ray intensity P j of a fuel rod j from an expression of a solid angle with respect to the vessel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56086860A JPS57201893A (en) | 1981-06-08 | 1981-06-08 | Gamma scan device for fuel assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP56086860A JPS57201893A (en) | 1981-06-08 | 1981-06-08 | Gamma scan device for fuel assembly |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS57201893A JPS57201893A (en) | 1982-12-10 |
| JPH0219916B2 true JPH0219916B2 (en) | 1990-05-07 |
Family
ID=13898560
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP56086860A Granted JPS57201893A (en) | 1981-06-08 | 1981-06-08 | Gamma scan device for fuel assembly |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS57201893A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2880178B1 (en) * | 2004-12-28 | 2007-02-23 | Framatome Anp Sas | METHOD AND DEVICE FOR DETERMINING THE COMBUSTION RATE OF A FUEL ASSEMBLY OF THE HEART OF A NUCLEAR REACTOR AND USE |
| JP5582402B2 (en) * | 2010-11-29 | 2014-09-03 | 日立Ｇｅニュークリア・エナジー株式会社 | Gamma scanning device |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2461337A1 (en) * | 1979-07-06 | 1981-01-30 | Centre Etd Energie Nucleaire | METHOD FOR LOCATING A FUYARD BAR IN A NUCLEAR FUEL ASSEMBLY |
-
1981
- 1981-06-08 JP JP56086860A patent/JPS57201893A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS57201893A (en) | 1982-12-10 |
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