JPH0464438B2 - - Google Patents
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- Publication number
- JPH0464438B2 JPH0464438B2 JP60104599A JP10459985A JPH0464438B2 JP H0464438 B2 JPH0464438 B2 JP H0464438B2 JP 60104599 A JP60104599 A JP 60104599A JP 10459985 A JP10459985 A JP 10459985A JP H0464438 B2 JPH0464438 B2 JP H0464438B2
- Authority
- JP
- Japan
- Prior art keywords
- gamma ray
- spent fuel
- fuel assembly
- detection sensitivity
- measuring device
- 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
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- 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
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- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
［発明の技術分野］
本発明は使用済燃料集合体の非破壊測定方法に
係わり、特に使用済燃料集合体中の平均核分裂生
成核種（FP）の濃度絶対値を非破壊ガンマ線ス
ペクトル測定により定量する使用済燃料集合体の
非破壊測定方法に関する。[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a method for non-destructive measurement of spent fuel assemblies, and in particular to non-destructive measurement of the average fission product (FP) concentration in a spent fuel assembly. This invention relates to a non-destructive measurement method for spent fuel assemblies that is quantified by destructive gamma ray spectrum measurement.
［発明の技術的背景］
一般に、原子炉内で用いられた使用済燃料集合
体内には、種々の核分裂生成核種またはその娘核
種（これらを以下FPという）が蓄積されており、
これらの核種の多くはFP濃度に比例した強いガ
ンマ線を放出している。[Technical Background of the Invention] Generally, various fission product nuclides or their daughter nuclides (hereinafter referred to as FP) are accumulated in spent fuel assemblies used in nuclear reactors.
Many of these nuclides emit strong gamma rays that are proportional to the FP concentration.
従来から、長半減期のFP、例えば半減期約30
年の137Csの濃度が燃料の燃焼度にほぼ比例する
ことを利用して、このガンマ線の強度を高分解能
のガンマ線検出器とガンマ線コリメータ等からな
るガンマ線スペクトル測定装置を用いて測定し、
ガンマ線計数率からFPの濃度相対値、さらには
燃料の燃焼度を導出する手法が広く知られてい
る。 Traditionally, FPs with long half-lives, e.g.
Taking advantage of the fact that the concentration of 137 Cs in 2017 is almost proportional to the burnup of the fuel, the intensity of this gamma ray is measured using a gamma ray spectrum measurement device consisting of a high resolution gamma ray detector and a gamma ray collimator.
The method of deriving the relative value of FP concentration and further the burnup of fuel from the gamma ray count rate is widely known.
FPのガンマ線計数率からFP濃度あるいは燃焼
度の絶対値を得るためには較正が必要であり、従
来、FP濃度あるいは燃焼度の絶対値が既知の使
用済燃料集合体を用いてこれについて予め測定す
ることにより較正を行なうことが行われている。 Calibration is required to obtain the absolute value of FP concentration or burnup from the FP gamma ray count rate, and conventionally, this has been measured in advance using a spent fuel assembly whose absolute value of FP concentration or burnup is known. Calibration is performed by doing this.
このような予め行なわれる測定方法には次のよ
うなものがある。 Examples of such measurement methods performed in advance include the following.
使用済燃料集合体内の一部の燃料試料につい
ての破壊測定を行ない、148Nd、137Cs等の濃度の
分析を行なう方法。 A method of performing destructive measurements on some fuel samples in spent fuel assemblies and analyzing the concentrations of 148 Nd, 137 Cs, etc.
測定感度較正済の測定装置を用い、使用済燃
料集合体の各燃料棒のガンマ線スペクトル測定
を行なう方法。 A method of measuring the gamma ray spectrum of each fuel rod in a spent fuel assembly using a measuring device with calibrated measurement sensitivity.
炉内出力計装管測定値および原子炉電気出力
積算値を基にオンライン計算により求める方
法。 A method of calculating on-line calculations based on the measured values of the in-core power instrumentation tube and the integrated value of the reactor electrical output.
［背景技術の問題点］
しかしながら、前述したおよびの方法で
は、多大な時間と費用がかかるという問題があ
る。また、前述したの計算値による方法では、
平均値をとるため多数本の使用済燃料集合体を用
いての測定が必要であり、直接の測定値を求める
ことができないという問題がある。[Problems with Background Art] However, the above-mentioned methods have a problem in that they require a great deal of time and cost. In addition, in the method using calculated values mentioned above,
In order to obtain an average value, measurements using a large number of spent fuel assemblies are required, and there is a problem in that direct measurements cannot be obtained.
［発明の目的］
本発明はかかる従来の事情に対処してなされた
もので、ガンマ線標準線源を用いた較正方法を使
用し、使用済燃料集合体の非破壊ガンマ線スペク
トル測定により使用済燃料集合体内の平均のFP
濃度の絶対値を精度よく求めることのできる使用
済燃料集合体の非破壊測定方法を提供しうとする
ものである。[Object of the Invention] The present invention has been made in response to the conventional situation, and uses a calibration method using a gamma-ray standard source to determine the spent fuel assembly by non-destructive gamma-ray spectrum measurement of the spent fuel assembly. Average FP in the body
The present invention aims to provide a nondestructive measurement method for spent fuel assemblies that can accurately determine the absolute value of concentration.
［発明の概要］
(a)ガンマ線測定装置のガンマ線入射方向上に測
定すべき使用済燃料集合体を対角線を一致させて
配置し、該使用済燃料集合体のガンマ線測定装置
に最も近い燃料棒の位置にガンマ線放出強度の既
知のガンマ線標準線源を配置して前記測定装置の
ガンマ線検出感度絶対較正値を求めるステツプ
と、(b)ガンマ線輸送計算により得られた、前記測
定装置の前記使用済燃料集合体とそのうちの前記
ガンマ線測定装置に最も近い１本の燃料棒に対す
る当該ガンマ線検出感度の比を求めるステツプ
と、(c)ステツプａで求めた前記測定装置のガンマ
線検出感度絶対較正値と、ステツプｂで得た前記
ガンマ線測定装置に最も近い１本の燃料棒に対す
る当該ガンマ線検出感度の比を用い、かつ、使用
済燃料集合体内および使用済燃料棒内線源分布の
半経験値を用いてガンマ線検出感度の補正を行つ
て、前記使用済燃料集合体に対する前記測定装置
の当該ガンマ線の検出感度絶対値を求めるステツ
プと、(d)前記使用済燃料集合体に対する前記測定
装置の当該ガンマ線の検出感度絶対値を用いて、
前記使用済燃料集合体の対角線上の対向する２あ
るいは４方向から測定して得られた核分裂生成核
種のガンマ線計数率平均値から、前記使用済燃料
集合体平均の核分裂生成核種のガンマ線放出強度
を求めるステツプと、(e)前記使用済燃料集合体平
均の核分裂生成核種のガンマ線放出強度を用い
て、該核分裂生成核種の半減期およびガンマ線分
岐比から前記使用済燃料集合体平均の核分裂生成
核種の濃度絶対値を求めるステツプとを含むこと
を特徴とする使用済燃料集合体の非破壊測定方法
である。[Summary of the invention] (a) Spent fuel assemblies to be measured are placed in the gamma ray incident direction of the gamma ray measuring device with their diagonals aligned, and the spent fuel assemblies of the fuel rods closest to the gamma ray measuring device are (b) obtaining an absolute calibration value of the gamma ray detection sensitivity of the measurement device by arranging a gamma ray standard source with known gamma ray emission intensity at a location; (c) determining the ratio of the gamma ray detection sensitivity of the fuel rod to the fuel rod closest to the gamma ray measurement device; (c) the absolute calibration value of the gamma ray detection sensitivity of the measurement device obtained in step a; Gamma ray detection is performed using the ratio of the gamma ray detection sensitivity to the one fuel rod closest to the gamma ray measuring device obtained in step b, and the semi-empirical value of the radiation source distribution within the spent fuel assembly and within the spent fuel rod. (d) determining the absolute value of the gamma ray detection sensitivity of the measuring device for the spent fuel assembly by correcting the sensitivity; Using the value,
From the average gamma ray count rate of fission product nuclides obtained by measurements from two or four diagonally opposite directions of the spent fuel assembly, calculate the average gamma ray emission intensity of fission product nuclides of the spent fuel assembly. and (e) calculate the average fission product nuclide of the spent fuel assembly from the half-life and gamma ray branching ratio of the fission product nuclide using the gamma ray emission intensity of the fission product nuclide average of the spent fuel assembly. The present invention is a method for non-destructive measurement of spent fuel assemblies, characterized in that it includes a step of determining an absolute value of concentration.
［発明の実施例］ 以下本発明の詳細を図面を用いて説明する。[Embodiments of the invention] The details of the present invention will be explained below with reference to the drawings.
第１図は本発明の使用済燃料集合体の非破壊測
定方法の一実施例のフローチヤートを示すもの
で、この実施例では、以下〜のステツプを経
て最終的に使用済燃料集合体平均のFP濃度絶対
値が求められる。 Figure 1 shows a flowchart of an embodiment of the method for non-destructive measurement of spent fuel assemblies according to the present invention. The absolute value of FP concentration is determined.
まず測定装置のガンマ線検出感度（絶対値）
が測定される。 First, gamma ray detection sensitivity (absolute value) of the measuring device
is measured.
第２図は使用済燃料集合体ガンマ線スペクト
ル測定体系を示すもので、図において符号１は
ガンマ線コリメータを示している。このガンマ
線コリメータ１の一端には高分解能の、例えば
ゲルマニウム検出器からなるガンマ線検出出器
２が配置されている。また、ガンマ線コリメー
タ１の前方にはガンマ線強度の既知のガンマ線
標準線源３が配置されている。このガンマ線標
準線源３の位置は非破壊測定すべき断面四角形
状の使用済燃料集合体４の最もガンマ線コリメ
ータ１に近い燃料棒の位置に相当する位置とさ
れ、またガンマ線コリメータ１のスリツトの中
心軸上の位置とされている。なお、これらの測
定体系はプール水中に収容されている。 FIG. 2 shows a spent fuel assembly gamma ray spectrum measurement system, and in the figure, reference numeral 1 indicates a gamma ray collimator. At one end of this gamma ray collimator 1, a high resolution gamma ray detector 2 made of, for example, a germanium detector is arranged. Further, in front of the gamma ray collimator 1, a gamma ray standard source 3 with a known gamma ray intensity is arranged. The position of this standard gamma ray source 3 corresponds to the position of the fuel rod closest to the gamma ray collimator 1 in the spent fuel assembly 4 with a rectangular cross section to be measured non-destructively, and also at the center of the slit of the gamma ray collimator 1. It is said to be located on the axis. Note that these measurement systems are housed in the pool water.
すなわち、まずこのような測定装置のガンマ
線検出感度が、ガンマ線強度既知のガンマ線標
準線源３により測定される。 That is, first, the gamma ray detection sensitivity of such a measuring device is measured using a gamma ray standard source 3 whose gamma ray intensity is known.
第３図の直線ａは横軸にガンマ線コリメータ
１と標準線源３との間の距離を、縦軸に137Cs
（662KeV）のガンマ線に対する検出感度をと
つてこれらの相関関係を示すもので、検出感度
を対数目盛でとると検出感度はほぼガンマ線コ
リメータ１と標準線源３との間の距離に対して
直線的な関係を有している。 Straight line a in Figure 3 shows the distance between the gamma ray collimator 1 and the standard radiation source 3 on the horizontal axis, and 137 Cs on the vertical axis.
(662KeV) gamma rays to show these correlations.If the detection sensitivity is measured on a logarithmic scale, the detection sensitivity is almost linear with respect to the distance between the gamma ray collimator 1 and the standard radiation source 3. They have a strong relationship.
次に前述した測定体系の使用済燃料集合体内
の各燃料棒に対するガンマ線検出感度（相対
値）がガンマ線輸送計算により求められ、使用
済燃料集合体内および燃料棒内の線源濃度分布
が一様と仮定した場合の使用済燃料集合体全体
に対するガンマ線コリメータ１に最も近接する
燃料棒のガンマ線検出感度の比が求められる。 Next, the gamma ray detection sensitivity (relative value) for each fuel rod in the spent fuel assembly using the measurement system described above is determined by gamma ray transport calculations, and the source concentration distribution within the spent fuel assembly and fuel rods is uniform. The ratio of the gamma ray detection sensitivity of the fuel rod closest to the gamma ray collimator 1 to the entire spent fuel assembly in the hypothetical case is determined.
なお、ガンマ線輸送計算では、測定体系の幾
何学的形状寸法および使用済燃料集合体内の燃
料の各要素から放出されたガンマ線のガンマ線
検出器２に至る間のすべての物質中の透過吸収
が考慮される。また、計算精度については、解
体可能な模擬燃料集合体を用いた模擬実験結果
との比較により検証しておくことが望ましい。 In addition, in the gamma ray transport calculation, the geometrical dimensions of the measurement system and the transmission and absorption of gamma rays emitted from each element of the fuel in the spent fuel assembly into the gamma ray detector 2 are taken into account. Ru. In addition, it is desirable to verify the calculation accuracy by comparing with the results of a simulation experiment using a simulated fuel assembly that can be dismantled.
第４図の曲線ｂは横軸に四角形状の使用済燃
料集合体の対角線方向の燃料棒位置を、縦軸に
FPの一例として137Cs（662keV）ガンマ線に対
する検出感度をとり、これらの相関関係の一例
を示すもので、〇はガンマ線輸送計算値を、●
は模擬実験測定値を示しており、計算値と模擬
実験測定値とは非常に一致した値を示してい
る。なお、図において符号４は使用済燃料集合
体を示しており、図の左側がガンマ線検出器２
の方向である。 Curve b in Figure 4 shows the fuel rod position in the diagonal direction of the rectangular spent fuel assembly on the horizontal axis and the vertical axis on the vertical axis.
As an example of FP, we take the detection sensitivity for 137 Cs (662keV) gamma rays and show an example of their correlation, where 〇 is the calculated value of gamma ray transport, and ●
indicates the simulated experiment measured value, and the calculated value and the simulated experiment measured value are in close agreement. In addition, in the figure, the code 4 indicates the spent fuel assembly, and the left side of the figure is the gamma ray detector 2.
The direction is
次に前述した，の結果を組合せて一様線
源分布の使用済燃料集合体に対するガンマ線検
出感度絶対値が求められる。ただし、この際ガ
ンマ線検出器２からコリメータスリツトを通し
て見込む燃料集合体の近接する燃料棒の長さお
よびこの燃料棒中のガンマ線の自己吸収を考慮
した補正がなされるものとする。 Next, by combining the results described above, the absolute value of gamma ray detection sensitivity for a spent fuel assembly with a uniform source distribution is determined. However, at this time, correction is made in consideration of the length of adjacent fuel rods of the fuel assembly as seen from the gamma ray detector 2 through the collimator slit, and the self-absorption of gamma rays in these fuel rods.
使用済燃料集合体内および燃料棒内のガンマ
線源分布については、一般的な場合の燃焼計算
による理論値と経験的測定値を用いて推定し、
これらのガンマ線検出感度に対する補正係数
（一様分布を仮定した場合の値との比）が求め
られる。なお、この補正は精度をあげるために
のみ必要である。 The distribution of gamma ray sources within spent fuel assemblies and fuel rods is estimated using theoretical values based on combustion calculations in the general case and empirically measured values.
Correction coefficients (ratio to the value assuming uniform distribution) for these gamma ray detection sensitivities are determined. Note that this correction is necessary only to improve accuracy.
次に前述したおよびの結果から使用済燃
料集合体のガンマ線測定体系における使用済燃
料集合体全体に対するガンマ線検出感度の絶対
値が求められる。 Next, the absolute value of the gamma ray detection sensitivity for the entire spent fuel assembly in the gamma ray measurement system for spent fuel assemblies is determined from the results of (1) and (2) described above.
次に測定対象である断面四角形状の使用済燃
料集合体の対向する２あるいは４方向から測定
して得られたFPガンマ線計数率平均値から使
用済燃料集合体のガンマ線放出強度の平均値が
求められる。 Next, the average value of the gamma ray emission intensity of the spent fuel assembly is calculated from the average value of the FP gamma ray count rate obtained by measuring from two or four opposing directions of the spent fuel assembly with a square cross section. It will be done.
次にFP核種の半減期、ガンマ線分岐比を用
いて使用済燃料集合体平均のFP濃度絶対値が
求められる。 Next, the average absolute value of FP concentration in the spent fuel assembly is determined using the half-life of the FP nuclide and the gamma ray branching ratio.
なお、このような方法により得られた使用済燃
料集合体のFP濃度絶対値、例えば137Cs濃度絶対
値を用いて使用済燃料集合体平均の燃焼度の絶対
値を容易に求めることができる。 Note that using the absolute value of the FP concentration of the spent fuel assembly obtained by such a method, for example, the absolute value of the 137 Cs concentration, the absolute value of the average burnup of the spent fuel assembly can be easily determined.
また、本方法は沸騰水型原子炉あるいは加圧水
型原子炉の使用済燃料集合体に限定されるもので
はなく、高速増殖炉等の使用済燃料集合体に対し
ても適用することができる。また、前述したの
計算は燃料集合体のタイプ毎に一度行なつておけ
ばよい。さらに前述したの測定は１つの測定装
置に対して標準線源の位置を変化し任意の複数の
位置で一度行なつておけば、距離が変化しても内
外挿によりガンマ線検出感度を求めるこができ
る。 Furthermore, this method is not limited to spent fuel assemblies of boiling water reactors or pressurized water reactors, but can also be applied to spent fuel assemblies of fast breeder reactors and the like. Furthermore, the calculations described above need only be performed once for each type of fuel assembly. Furthermore, if the above-mentioned measurement is performed once at any number of positions by changing the position of the standard radiation source for one measuring device, the gamma ray detection sensitivity can be determined by interpolation even if the distance changes. can.
［発明の効果］
以上述べたように本発明の使用済燃料集合体の
非破壊測定方法によれば、一点のガンマ線標準線
源を用いた測定体系のガンマ線検出感度絶対較正
値と、ガンマ線輸送計算による使用済燃料集合体
全体に対する１本の燃料棒のガンマ線検出感度と
の比を用いることにより、使用済燃料集合体の破
壊測定や解体測定等による多大な労力を要する較
正を行なうことなしに容易、かつ精度よく使用済
燃料集合体平均のFP濃度絶値を求めることがで
きる。[Effects of the Invention] As described above, according to the method for non-destructive measurement of spent fuel assemblies of the present invention, the gamma ray detection sensitivity absolute calibration value of the measurement system using a single point gamma ray standard source and the gamma ray transport calculation can be calculated. By using the ratio of the gamma ray detection sensitivity of a single fuel rod to the entire spent fuel assembly, it is possible to easily calibrate the spent fuel assembly without the need for labor-intensive calibration such as destruction or disassembly measurements of the spent fuel assembly. , and the average FP concentration peak value of the spent fuel assembly can be determined with high accuracy.
第１図は本発明の使用済燃料集合体の非破壊測
定方法の一実施例を示すフローチヤート、第２図
は使用済燃料ガンマ線スペクトル測定体系を示す
説明図、第３図はコリメータ・線源間距離と
137Csガンマ線に対する検出感度との関係を示す
グラフ、第４図は燃料集合体内対角方向燃料棒位
置とFPガンマ線検出感度との関係を示すグラフ
である。
１…ガンマ線コリメータ、２…ガンマ線検出
器、３…ガンマ線標準線源、４…燃料集合体。
Fig. 1 is a flowchart showing an embodiment of the method for non-destructive measurement of spent fuel assemblies of the present invention, Fig. 2 is an explanatory diagram showing a spent fuel gamma ray spectrum measurement system, and Fig. 3 is a collimator/ray source. distance and
A graph showing the relationship between the detection sensitivity for 137 Cs gamma rays, and FIG. 4 is a graph showing the relationship between the diagonal fuel rod position within the fuel assembly and the FP gamma ray detection sensitivity. 1... Gamma ray collimator, 2... Gamma ray detector, 3... Gamma ray standard source, 4... Fuel assembly.
Claims (1)
に測定すべき使用済燃料集合体を対角線を一致
させて配置し、該使用済燃料集合体のガンマ線
測定装置に最も近い燃料棒の位置にガンマ線放
出強度の既知のガンマ線標準線源を配置して前
記測定装置のガンマ線検出感度絶対較正値を求
めるステツプと、 (b) ガンマ線輸送計算により得られた、前記測定
装置の前記使用済燃料集合体とそのうちの前記
ガンマ線測定装置に最も近い１本の燃料棒に対
する当該ガンマ線検出感度の比を求めるステツ
プと、 (c) ステツプａで求めた前記測定装置のガンマ線
検出感度絶対較正値と、ステツプｂで得た前記
ガンマ線測定装置に最も近い１本の燃料棒に対
する当該ガンマ線検出感度の比を用い、かつ、
使用済燃料集合体内および使用済燃料棒内線源
分布の半経験値を用いてガンマ線検出感度の補
正を行つて、前記使用済燃料集合体に対する前
記測定装置の当該ガンマ線の検出感度絶対値を
求めるステツプと、 (d) 前記使用済燃料集合体に対する前記測定装置
の当該ガンマ線の検出感度絶対値を用いて、前
記使用済燃料集合体の対角線上の対向する２あ
るいは４方向から測定して得られた核分裂生成
核種のガンマ線計数率平均値から、前記使用済
燃料集合体平均の核分裂生成核種のガンマ線放
出強度を求めるステツプと (e) 前記使用済燃料集合体平均の核分裂生成核種
のガンマ線放出強度を用いて、該核分裂生成核
種の半減期およびガンマ線分岐比から前記使用
済燃料集合体平均の核分裂生成核種の濃度絶対
値を求めるステツプと を含むことを特徴とする使用済燃料集合体の非破
壊測定方法。[Claims] 1 (a) Spent fuel assemblies to be measured are arranged with their diagonals aligned in the gamma ray incident direction of the gamma ray measuring device, and the spent fuel assemblies that are closest to the gamma ray measuring device of the spent fuel assemblies are (b) determining the absolute calibration value of the gamma ray detection sensitivity of the measuring device by placing a gamma ray standard source with known gamma ray emission intensity at the position of the rod; (c) determining the gamma ray detection sensitivity absolute calibration value of the measurement device obtained in step a; , using the ratio of the gamma ray detection sensitivity to the one fuel rod closest to the gamma ray measuring device obtained in step b, and
correcting the gamma ray detection sensitivity using semi-empirical values of the radiation source distribution within the spent fuel assembly and within the spent fuel rod, and determining the absolute value of the gamma ray detection sensitivity of the measuring device for the spent fuel assembly; and (d) obtained by measuring from two or four diagonally opposite directions of the spent fuel assembly using the absolute value of the detection sensitivity of the gamma ray of the measurement device to the spent fuel assembly. (e) calculating the average gamma ray emission intensity of the fission product nuclides in the spent fuel assembly from the average value of the gamma ray count rate of the fission product nuclides; and (e) using the gamma ray emission intensity of the fission product nuclides average in the spent fuel assembly. a method for non-destructive measurement of spent fuel assemblies, the method comprising: calculating the absolute value of the average concentration of fission product nuclides in the spent fuel assembly from the half-life of the fission product nuclides and the gamma ray branching ratio; .
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60104599A JPS61262693A (en) | 1985-05-16 | 1985-05-16 | Nondestructive measurement method of spent fuel aggregate |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP60104599A JPS61262693A (en) | 1985-05-16 | 1985-05-16 | Nondestructive measurement method of spent fuel aggregate |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS61262693A JPS61262693A (en) | 1986-11-20 |
| JPH0464438B2 true JPH0464438B2 (en) | 1992-10-14 |
Family
ID=14384887
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60104599A Granted JPS61262693A (en) | 1985-05-16 | 1985-05-16 | Nondestructive measurement method of spent fuel aggregate |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS61262693A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP6038575B2 (en) * | 2012-09-27 | 2016-12-07 | 株式会社東芝 | Nuclear fuel burnup evaluation apparatus, method and program |
| JP6448221B2 (en) * | 2014-05-30 | 2019-01-09 | 株式会社東芝 | Fuel debris burnup measuring device and burnup measuring method thereof |
-
1985
- 1985-05-16 JP JP60104599A patent/JPS61262693A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS61262693A (en) | 1986-11-20 |
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