JP2017187402A - Setting method of operation limit range of nuclear reactor - Google Patents
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本発明は、原子炉を安全に運転するために運転範囲を設定するための原子炉の運転限界範囲の設定方法に関するものである。 The present invention relates to a method for setting an operation limit range of a nuclear reactor for setting an operation range in order to operate the nuclear reactor safely.
原子炉の運転限界範囲は、従来、高温側配管沸騰制限（冷却材温度差測定による炉心出力計測の確保）とＤＮＢ制限（燃料棒被覆管の熱的損傷の防止）で定まり、その運転限界範囲に所定の余裕度を加味した原子炉を停止するトリップ限界を規定している。このような原子炉の運転限界範囲の規定方法としては、下記非特許文献１に記載されたものがある。 The operation limit range of a nuclear reactor is conventionally determined by the high temperature side piping boiling limit (ensuring core power measurement by measuring the coolant temperature difference) and the DNB limit (preventing thermal damage to the fuel rod cladding tube). The trip limit for shutting down the reactor with a predetermined margin is added. As a method for defining the operation limit range of such a reactor, there is one described in Non-Patent Document 1 below.
ところが、原子炉を安全に運転する必要から、精度の高い原子炉の運転限界範囲、つまり、トリップ限界を規定する方法が望まれている。 However, since it is necessary to operate the reactor safely, there is a demand for a method for defining a highly accurate operation limit range of the reactor, that is, a trip limit.
本発明は、上述した課題を解決するものであり、高精度で安全性の高い原子炉の運転限界範囲の設定方法を提供することを目的とする。 The present invention solves the above-described problems, and an object of the present invention is to provide a method for setting the operation limit range of a nuclear reactor with high accuracy and high safety.
上記の目的を達成するための本発明の原子炉の運転限界範囲の設定方法は、炉心を冷却する冷却材の温度差測定による炉心出力計測を確保するための高温側配管沸騰制限値を求める工程と、燃料棒被覆管の熱的損傷を防止するためのＤＮＢ制限値を求める工程と、冷却材のクオリティ制限値を求める工程と、前記高温側配管沸騰制限値と前記ＤＮＢ制限値と前記クオリティ制限値に基づいて原子炉のトリップ制限値を求める工程と、を有することを特徴とするものである。 The method for setting the operation limit range of the reactor of the present invention to achieve the above object is a process for obtaining a high temperature side pipe boiling limit value for ensuring core power measurement by measuring a temperature difference of a coolant that cools the core. A step of determining a DNB limit value for preventing thermal damage to the fuel rod cladding tube, a step of determining a quality limit value of the coolant, the high temperature side pipe boiling limit value, the DNB limit value, and the quality limit And a step of determining a reactor trip limit value based on the value.
従って、高温側配管沸騰制限値とＤＮＢ制限値とクオリティ制限値に基づいて原子炉のトリップ制限値を求めることで、精度が高くてより安全性の高い原子炉の運転限界範囲を設定することができる。 Therefore, by determining the reactor trip limit value based on the high temperature side piping boiling limit value, the DNB limit value, and the quality limit value, it is possible to set a highly safe and safe operation limit range of the reactor. it can.
本発明の原子炉の運転限界範囲の設定方法では、９５％×９５％基準（９５％信頼度で９５％確率）を考慮すると共に、少なくともＤＮＢＲ評価入力パラメータの不確定性と、ＤＮＢ熱流束予測の不確定性と、圧力損失の異なる燃料の混在によるＤＮＢＲのペナルティとを考慮して定めた９５％下限値からクオリティ制限値を求めることを特徴としている。 In the method for setting the operation limit range of the reactor of the present invention, 95% × 95% criterion (95% probability with 95% reliability) is considered, at least the uncertainty of the DNBR evaluation input parameter, and the DNB heat flux prediction The quality limit value is obtained from the 95% lower limit value that is determined in consideration of the uncertainty of the above and the DNBR penalty due to the mixture of fuels having different pressure losses.
従って、クオリティ制限値を求めるにあたり、ＤＮＢＲ評価入力パラメータの不確定性と、ＤＮＢ熱流束予測の不確定性と、圧力損失の異なる燃料の混在によるＤＮＢＲのペナルティとを用いることで、モンテカルロ計算を使用することができ、クオリティ制限値となる炉心入口温度を容易に求めることができる。 Therefore, in determining the quality limit value, the Monte Carlo calculation is used by using the uncertainty of the DNBR evaluation input parameter, the uncertainty of the DNB heat flux prediction, and the DNBR penalty due to the mixture of fuels with different pressure losses. Therefore, it is possible to easily obtain the core inlet temperature that is the quality limit value.
本発明の原子炉の運転限界範囲の設定方法では、前記クオリティ制限値は、クオリティが１０％から２５％の領域に設定されることを特徴としている。 In the setting method of the operation limit range of the nuclear reactor according to the present invention, the quality limit value is set in a region where the quality is 10% to 25%.
従って、クオリティ制限値を所定領域に設定することで、クオリティを考慮した運転限界範囲を設定することができ、原子炉設計の安全性を向上することができる。 Therefore, by setting the quality limit value in a predetermined region, it is possible to set the operation limit range in consideration of the quality, and it is possible to improve the safety of the reactor design.
本発明の原子炉の運転限界範囲の設定方法によれば、高温側配管沸騰制限値とＤＮＢ制限値とクオリティ制限値に基づいて原子炉のトリップ制限値を求めることで、精度が高くてより安全性の高い原子炉の運転限界範囲を設定することができる。 According to the method for setting the operation limit range of the reactor of the present invention, the trip limit value of the reactor is obtained based on the high-temperature side piping boiling limit value, the DNB limit value, and the quality limit value, thereby providing high accuracy and safety. It is possible to set the operational limit range of highly reliable reactors.
以下に添付図面を参照して、本発明に係る原子炉の運転限界範囲の設定方法の好適な実施形態を詳細に説明する。なお、この実施形態により本発明が限定されるものではなく、また、実施形態が複数ある場合には、各実施形態を組み合わせて構成するものも含むものである。 Exemplary embodiments of a method for setting a reactor operating limit range according to the present invention will be described below in detail with reference to the accompanying drawings. In addition, this invention is not limited by this embodiment, and when there are two or more embodiments, what comprises combining each embodiment is also included.
図１は、本実施形態の原子炉の運転限界範囲の設定方法におけるＤＮＢ制限範囲を特定するための改良統計的熱設計手法の概念図、図２は、原子炉の運転限界範囲の設定方法におけるクオリティ制限範囲を特定するための評価手法の概念図である。 FIG. 1 is a conceptual diagram of an improved statistical thermal design method for specifying the DNB limit range in the method for setting the operation limit range of the reactor according to the present embodiment. FIG. 2 is a diagram in the method for setting the operation limit range of the reactor. It is a conceptual diagram of the evaluation method for specifying a quality restriction | limiting range.
本実施形態の原子炉の運転限界範囲の設定方法は、冷却材の温度差測定による炉心出力計測を確保するための高温側配管沸騰制限値を求める工程と、燃料棒被覆管の熱的損傷を防止するためのＤＮＢ制限値を求める工程と、冷却材のクオリティ制限値を求める工程と、高温側配管沸騰制限値とＤＮＢ制限値とクオリティ制限値に基づいて原子炉のトリップ制限値を求める工程とを有している。 The method of setting the operation limit range of the reactor according to this embodiment includes a step of obtaining a high temperature side pipe boiling limit value for ensuring core power measurement by measuring a coolant temperature difference, and thermal damage of the fuel rod cladding tube. A step of determining a DNB limit value to prevent, a step of determining a coolant quality limit value, a step of determining a reactor trip limit value based on the high temperature side piping boiling limit value, the DNB limit value, and the quality limit value; have.
従来、原子炉の運転限界範囲は、高温側配管沸騰制限（冷却材の温度差測定による炉心出力計測の確保）と、ＤＮＢ制限（燃料棒被覆管の熱的損傷の防止）で定まり、その運転限界範囲に所定の余裕度を加味した原子炉を停止するトリップ限界を規定している。ところが、高温条件のプラントの安全性を向上させるために、本実施形態では、冷却材のクオリティを考慮して原子炉の運転限界範囲（トリップ限界）を求める。 Conventionally, the operation limit range of a nuclear reactor is determined by the high temperature side piping boiling limit (ensuring core power measurement by measuring the temperature difference of the coolant) and the DNB limit (preventing thermal damage of the fuel rod cladding tube). A trip limit for shutting down the reactor with a specified margin added to the limit range is specified. However, in order to improve the safety of a plant under a high temperature condition, in this embodiment, the operation limit range (trip limit) of the reactor is obtained in consideration of the quality of the coolant.
ＤＮＢ相関式は、サブチャンネル解析を介して得られる冷却材の局所パラメータ（圧力、質量速度、クオリティ）から限界熱流束を評価する式であり、ＤＮＢ相関式の適用範囲は、これらの各パラメータに対して定められている。各パラメータに対する適用範囲は、ＤＮＢ試験において、データが取得されたパラメータの範囲に基づいて定められる。ここで、圧力と質量速度については、運転時の異常な過渡変化を含む原子炉のＤＮＢＲ評価範囲をカバーするように試験条件が定義されるが、クオリティは試験条件（圧力、質量速度、入口温度）に加えて、試験結果である限界熱流束（出力）に依存するため、試験の「結果」として得られるパラメータ範囲となる。 The DNB correlation equation is an equation for evaluating the critical heat flux from the local parameters (pressure, mass velocity, quality) of the coolant obtained through the subchannel analysis, and the application range of the DNB correlation equation is as follows. It is prescribed for this. The applicable range for each parameter is determined based on the parameter range from which data was acquired in the DNB test. Here, with regard to pressure and mass velocity, the test conditions are defined so as to cover the DNBR evaluation range of the reactor including abnormal transient changes during operation, but the quality is determined based on the test conditions (pressure, mass velocity, inlet temperature). ) In addition to the critical heat flux (output) which is the test result, the parameter range is obtained as the “result” of the test.
例えば、ＭＩＲＣ−１相関式のＤＮＢ試験データベースは、概ね、最大約３２％程度までのクオリティ範囲のデータが得られ、これを適用範囲としてきたが、高温条件のプラントの安全性を向上させるために、従来、３２％としていたＭＩＲＣ−１相関式のクオリティの最大値を、例えば、１０％から２５％として新たな制限値を追加した。 For example, the MIRC-1 correlation type DNB test database has generally obtained data in the quality range up to about 32%, and this has been applied, but in order to improve the safety of plants under high temperature conditions For example, the maximum value of the quality of the MIRC-1 correlation equation, which was conventionally 32%, is set to, for example, 10% to 25%, and a new limit value is added.
以下、本実施形態の原子炉の運転限界範囲の設定方法について詳細に説明する。 Hereinafter, a method for setting the operation limit range of the nuclear reactor according to the present embodiment will be described in detail.
高温側配管沸騰制限値（制限線）を求める工程は、冷却材が低圧力又は高圧力条件の際に、最小ＤＮＢＲが許容限界値まで低下する前に原子炉容器出口エンタルピが飽和に至らない炉心入口温度を設定するものであり、冷却材温度差（ΔＴ）測定による炉心熱出力の計測不能を起因とする過大温度ΔＴ高原子炉トリップの機能喪失を防止する。 The process of obtaining the high temperature side piping boiling limit value (limit line) is the core where the reactor vessel outlet enthalpy does not reach saturation before the minimum DNBR falls to the allowable limit value when the coolant is at low pressure or high pressure conditions. The inlet temperature is set, and the loss of the function of the excessive temperature ΔT high reactor trip due to the inability to measure the core thermal power due to the coolant temperature difference (ΔT) measurement is prevented.
また、燃料棒被覆管の熱的損傷を防止するためのＤＮＢ制限値（制限線）を求める工程は、図１に示すように、改良統計的熱設計手法であり、ＤＮＢが９５％×９５％基準（９５％信頼度で９５％確率）で発生しないことを保証するために、下記のＡ，Ｂ，Ｃ，Ｄ，ＥのＤＮＢＲ変動要因を考慮して評価するものである。ここで、９５％確率とは、確率分布の９５％下限値あるいは上限値を表している。また、９５％信頼度とは、有限の標本の統計量（平均値や標準偏差など）から母集団の統計量を９５％確率で推定することである。 Further, as shown in FIG. 1, the process of obtaining the DNB limit value (limit line) for preventing thermal damage of the fuel rod cladding tube is an improved statistical thermal design method, and the DNB is 95% × 95%. In order to ensure that it does not occur at the standard (95% probability with 95% reliability), evaluation is performed in consideration of the following DNBR fluctuation factors A, B, C, D, and E. Here, the 95% probability represents the 95% lower limit value or the upper limit value of the probability distribution. The 95% confidence level is to estimate a population statistic with a 95% probability from a statistic (average value, standard deviation, etc.) of a finite sample.
Ａ．ＤＮＢＲ評価入力パラメータの不確定性（計測機器、製作の誤差）
Ｂ．ＤＮＢ熱流束予測の不確定性（ＤＮＢ相関式の不確定性）
Ｃ．燃料棒曲りによるＤＮＢＲペナルティ
Ｄ．圧力損失の異なる燃料の混在によるペナルティ
Ｅ．その他の余裕
A. Uncertainty of DNBR evaluation input parameters (measurement equipment, manufacturing errors)
B. Uncertainty of DNB heat flux prediction (Uncertainty of DNB correlation)
C. DNBR penalty due to fuel rod bending Penalty due to mixing of fuels with different pressure losses Other margin
即ち、ＤＮＢＲの許容限界値は、ＤＮＢＲ評価入力パラメータの不確定性Ａ及びＤＮＢ熱流束予測の不確定性Ｂを考慮した制限値（設計限界値）を求め、この制限値に燃料棒曲りによるＤＮＢＲペナルティＣと圧力損失の異なる燃料の混在によるペナルティＤとその他の余裕Ｅを加えて設定する。設計限界値は、入力データ等の不確定性を考慮した最小ＤＮＢＲの確率分布において、その９５％確率下限値が１．０となるようなＤＮＢＲ最確値として定義される。この最小ＤＮＢＲの９５％確率下限値は、モンテカルロ計算によって得られるが、この評価は、熱的に厳しい条件でのＤＮＢＲ評価となること、本来、クオリティの悪化要因ではないＤＮＢ熱流束予測の不確定性Ｂを含むモンテカルロ計算であることから、クオリティが高い条件が含まれることとなる。 That is, the allowable limit value of DNBR is obtained as a limit value (design limit value) in consideration of the uncertainty A of the DNBR evaluation input parameter and the uncertainty B of the DNB heat flux prediction, and the DNBR due to the fuel rod bending is obtained as the limit value. Penalty C and penalty D due to the mixture of fuels with different pressure loss and other margin E are set. The design limit value is defined as the DNBR most probable value such that the 95% probability lower limit value is 1.0 in the probability distribution of the minimum DNBR in consideration of uncertainties such as input data. The 95% probability lower limit value of this minimum DNBR can be obtained by Monte Carlo calculation. This evaluation is a DNBR evaluation under a thermally severe condition, and the uncertainty of the DNB heat flux prediction that is not inherently a quality deterioration factor is uncertain Since this is a Monte Carlo calculation including the property B, a condition with high quality is included.
冷却材のクオリティ制限値（制限線）を求める工程は、図２に示すように、前述した改良統計的熱設計手法と同様に、ＤＮＢが９５×９５基準（９５％信頼度で９５％確率）で発生しないことを保証するものであるが、上述したＡ，Ｂ，Ｃ，Ｄ，ＥのＤＮＢＲ変動要因のうち、実際に局所クオリティの変動に伴うＤＮＢＲの変動要因となるＡ，Ｄのみを考慮して評価するものである。但し、Ｂは、クオリティの変動を伴わないものの、改良統計的熱設計手法の定義上分離ができないためにＡと同様に扱うが、Ａに対してＢが分離できれば、Ａ，Ｄのみを考慮する。また、Ｅは、現行設計の妥当性確認においては必ずしも確保される必要はない。 As shown in FIG. 2, the process of obtaining the coolant quality limit value (limit line) is similar to the improved statistical thermal design method described above, with a DNB of 95 × 95 standard (95% probability with 95% reliability). However, among the above-mentioned DNBR fluctuation factors of A, B, C, D, and E, only A and D, which are the DNBR fluctuation factors due to local quality fluctuations, are considered. To evaluate. However, although B is not accompanied by quality variation, it can be treated in the same way as A because it cannot be separated in the definition of the improved statistical thermal design method. However, if B can be separated from A, only A and D are considered. . Further, E is not necessarily ensured in the validity confirmation of the current design.
即ち、圧力損失の異なる燃料の混在によるペナルティＤをサブチャンネル解析で直接考慮し、ＤＮＢＲ評価入力パラメータの不確定性Ａ及びＤＮＢ熱流束予測の不確定性ＢによるＤＮＢＲ変動幅をモンテカルロ計算で評価することで９５％確率下限値が定まる。その９５％確率内の最大クオリティ値がα以下（例えば、１０％から２５％）となる炉心入口温度を求め、その炉心入口温度を運転限界範囲として設定する。また、本評価を実施する際は、９５％確率下限値に対して燃料棒曲りによるＤＮＢＲペナルティＣを考慮した値が１．０以上であることを確認する必要がある。 In other words, the penalty D due to the mixture of fuels with different pressure losses is directly considered in the subchannel analysis, and the DNBR fluctuation range due to the uncertainty A of the DNBR evaluation input parameter and the uncertainty B of the DNB heat flux prediction is evaluated by Monte Carlo calculation. This sets the 95% probability lower limit. The core inlet temperature at which the maximum quality value within the 95% probability is less than or equal to α (for example, 10% to 25%) is obtained, and the core inlet temperature is set as the operation limit range. Further, when carrying out this evaluation, it is necessary to confirm that the value considering the DNBR penalty C due to the fuel rod bending is 1.0 or more with respect to the 95% probability lower limit value.
このように冷却材の温度差測定による炉心出力計測を確保するための高温側配管沸騰制限値（制限線）と、燃料棒被覆管の熱的損傷を防止するためのＤＮＢ制限値（制限線）と、冷却材のクオリティ制限値（制限線）が求められると、原子炉のトリップ制限値（制限線）を求めることができる。図３は、原子炉の運転限界範囲を表すグラフである。 In this way, the high temperature side piping boiling limit value (limit line) for ensuring core power measurement by measuring the temperature difference of the coolant, and the DNB limit value (limit line) for preventing thermal damage to the fuel rod cladding tube. When the coolant quality limit value (limit line) is determined, the reactor trip limit value (limit line) can be determined. FIG. 3 is a graph showing the operation limit range of the nuclear reactor.
図３に示すように、高温側配管沸騰制限値（高温側配管沸騰制限線）１１と、ＤＮＢ制限値（ＤＮＢ制限線）１２と、クオリティ制限値（クオリティ制限線）１３が求められると、各制限値以下となる原子炉に流入する冷却材の入口温度と原子炉の出力の関係を導き出し、３種類の制限線を引いて冷却材の入口温度と原子炉の出力における安全領域を設定する。そして、３種類の制限線から設定される安全領域に対して所定の余裕度を考慮して原子炉のトリップ制限値（トリップ制限線）１４を求める。 As shown in FIG. 3, when a high temperature side pipe boiling limit value (high temperature side pipe boiling limit line) 11, a DNB limit value (DNB limit line) 12, and a quality limit value (quality limit line) 13 are obtained, The relationship between the inlet temperature of the coolant flowing into the reactor below the limit value and the output of the reactor is derived, and three types of limit lines are drawn to set a safe region for the coolant inlet temperature and the reactor output. Then, a trip limit value (trip limit line) 14 of the reactor is obtained in consideration of a predetermined margin with respect to the safety region set from the three types of limit lines.
このように本実施形態の原子炉の運転限界範囲の設定方法にあっては、冷却材の温度差測定による炉心出力計測を確保するための高温側配管沸騰制限値を求める工程と、燃料棒被覆管の熱的損傷を防止するためのＤＮＢ制限値を求める工程と、冷却材のクオリティ制限値を求める工程と、高温側配管沸騰制限値とＤＮＢ制限値とクオリティ制限値に基づいて原子炉のトリップ制限値を求める工程とを有する。 As described above, in the method of setting the operation limit range of the reactor according to the present embodiment, the step of obtaining the high-temperature side pipe boiling limit value for ensuring the core power measurement by measuring the temperature difference of the coolant, and the fuel rod coating A step of determining a DNB limit value for preventing thermal damage to the pipe, a step of determining a quality limit value of the coolant, and a trip of the reactor based on the high temperature side pipe boiling limit value, the DNB limit value, and the quality limit value And obtaining a limit value.
従って、高温側配管沸騰制限値とＤＮＢ制限値とクオリティ制限値に基づいて原子炉のトリップ制限値を求めることで、精度が高くてより安全性の高い原子炉の運転限界範囲を設定することができる。 Therefore, by determining the reactor trip limit value based on the high temperature side piping boiling limit value, the DNB limit value, and the quality limit value, it is possible to set a highly safe and safe operation limit range of the reactor. it can.
本実施形態の原子炉の運転限界範囲の設定方法では、９５％×９５％基準を考慮すると共に、少なくともＤＮＢＲ評価入力パラメータの不確定性と、ＤＮＢ熱流束予測の不確定性と、圧力損失の異なる燃料の混在によるＤＮＢＲのペナルティとを用いることで、モンテカルロ計算を使用することができ、クオリティ制限値となる炉心入口温度を容易に求めることができる。 In the setting method of the operation limit range of the reactor according to the present embodiment, the 95% × 95% criterion is considered, at least the uncertainty of the DNBR evaluation input parameter, the uncertainty of the DNB heat flux prediction, and the pressure loss By using the DNBR penalty due to the mixture of different fuels, Monte Carlo calculation can be used, and the core inlet temperature that is the quality limit value can be easily obtained.
本実施形態の原子炉の運転限界範囲の設定方法では、クオリティ制限値は、クオリティが１０％から２５％の領域に設定されている。従って、クオリティ制限値を所定領域に設定することで、クオリティを考慮した運転限界範囲を設定することができ、原子炉設計の安全性を向上することができる。 In the method of setting the operation limit range of the reactor according to the present embodiment, the quality limit value is set in a region where the quality is 10% to 25%. Therefore, by setting the quality limit value in a predetermined region, it is possible to set the operation limit range in consideration of the quality, and it is possible to improve the safety of the reactor design.
１１ 高温側配管沸騰制限値（高温側配管沸騰制限線）
１２ ＤＮＢ制限値（ＤＮＢ制限線）
１３ クオリティ制限値（クオリティ制限線）
１４ トリップ制限値（トリップ制限線）
11 High temperature side piping boiling limit value (High temperature side piping boiling limit line)
12 DNB limit value (DNB limit line)
13 Quality limit value (quality limit line)
14 Trip limit value (trip limit line)
Claims (3)
燃料棒被覆管の熱的損傷を防止するためのＤＮＢ制限値を求める工程と、
冷却材のクオリティ制限値を求める工程と、
前記高温側配管沸騰制限値と前記ＤＮＢ制限値と前記クオリティ制限値に基づいて原子炉のトリップ制限値を求める工程と、
を有することを特徴とする原子炉の運転限界範囲の設定方法。 A step of obtaining a high-temperature side piping boiling limit value for ensuring core power measurement by measuring a temperature difference of the coolant;
Determining a DNB limit value to prevent thermal damage to the fuel rod cladding;
A process for determining the quality limit value of the coolant;
Obtaining a reactor trip limit value based on the high temperature side piping boiling limit value, the DNB limit value, and the quality limit value;
A method for setting an operating limit range of a nuclear reactor characterized by comprising:
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