JPH0961582A - Detecting the surface temperature of cladding of fuel rods - Google Patents

Detecting the surface temperature of cladding of fuel rods

Info

Publication number
JPH0961582A
JPH0961582A JP7236016A JP23601695A JPH0961582A JP H0961582 A JPH0961582 A JP H0961582A JP 7236016 A JP7236016 A JP 7236016A JP 23601695 A JP23601695 A JP 23601695A JP H0961582 A JPH0961582 A JP H0961582A
Authority
JP
Japan
Prior art keywords
surface temperature
cladding
cladding tube
core
temperature
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.)
Withdrawn
Application number
JP7236016A
Other languages
Japanese (ja)
Inventor
Tsutomu Ikeno
勉 池野
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Nuclear Fuel Industries Ltd
Original Assignee
Nuclear Fuel Industries Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Nuclear Fuel Industries Ltd filed Critical Nuclear Fuel Industries Ltd
Priority to JP7236016A priority Critical patent/JPH0961582A/en
Publication of JPH0961582A publication Critical patent/JPH0961582A/en
Withdrawn legal-status Critical Current

Links

Classifications

    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

(57)【要約】 【課題】 被覆管表面温度を中央制御室においてオンタ
イムで検出し監視する。また、被覆管表面温度計算部分
に近似式を用いることにより、計算負荷を軽減する。 【解決手段】 所定のパラメータにおいて、想定しうる
種々の状況のデータを炉心熱水力及び燃料温度解析コー
ドに入力することにより、予め種々の状況下の被覆管表
面温度を求めると共に、これら求めた被覆管表面温度と
上記各パラメータとを関係づける近似式を設定して、こ
の近似式の各パラメータにNIS盤等からリアルタイム
のデータを入力することにより、リアルタイムの被覆管
表面温度を検出することを特徴とする。
(57) 【Abstract】 PROBLEM TO BE SOLVED: To detect and monitor the surface temperature of a cladding tube in a main control room on time. In addition, the calculation load is reduced by using an approximate expression for the cladding tube surface temperature calculation part. SOLUTION: By inputting data of various conceivable situations into a core thermal-hydraulic and fuel temperature analysis code with predetermined parameters, cladding tube surface temperatures under various situations are obtained and obtained in advance. It is possible to detect the real-time cladding tube surface temperature by setting an approximate expression that relates the cladding tube surface temperature to each of the above parameters and inputting real-time data from the NIS panel or the like to each parameter of this approximate expression. Characterize.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【発明の属する技術分野】本発明は運転中のPWR軽水
炉プラントにおける燃料棒の被覆管表面温度の検出方法
に関するものである。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a method for detecting the surface temperature of a cladding of a fuel rod in an operating PWR light water reactor plant.

【0002】[0002]

【従来の技術】軽水炉における燃料の健全性判断におい
ては、被覆管表面温度を予測する手法が確立していない
ため、燃料棒の表面が核沸騰状態から離脱して熱伝達率
の低い膜沸騰状態へと移行するDNBが基準とされてい
る。また実際に被覆管の表面温度を予測するためには、
炉心熱水力解析と燃料棒温度解析とを、非定常的取扱い
により実施する必要があるため、データ容量や計算時間
が共に膨大となり、上記予測手法の実現は困難とみなさ
れている。
2. Description of the Related Art In determining the soundness of fuel in a light water reactor, since the method of predicting the cladding surface temperature has not been established, the surface of the fuel rod is separated from the nucleate boiling state and the film boiling state where the heat transfer coefficient is low. The standard is the DNB that shifts to. Also, in order to actually predict the surface temperature of the cladding tube,
Since it is necessary to carry out the core thermal-hydraulic analysis and the fuel rod temperature analysis by unsteady handling, both the data capacity and the calculation time become enormous, and it is considered difficult to realize the above prediction method.

【0003】しかしながら、従来のDNB基準のもつ安
全余裕が見直され、被覆管表面温度に基づく判断基準を
採用することになれば、当然この判断基準が原子炉の故
障・事故時の運転操作マニュアルに反映されるため、上
記被覆管表面温度を中央制御室で検出し監視することの
メリットは大きい。
However, if the safety margin of the conventional DNB standard is reviewed and a criterion based on the cladding tube surface temperature is adopted, this criterion is naturally used in the operation manual in the event of a reactor failure or accident. Since it is reflected, the merit of detecting and monitoring the surface temperature of the cladding tube in the central control room is great.

【0004】[0004]

【発明が解決しようとする課題】本発明はこのような背
景に鑑みて、中央制御室から上記被覆管表面温度の監視
をリアルタイムで行なうことにより、軽水炉の故障や事
故時に運転操作方法を最適化してこれに対応することを
目的とするものである。
In view of such a background, the present invention optimizes the operation method in the event of a light water reactor failure or accident by monitoring the surface temperature of the cladding tube from the central control room in real time. The purpose is to deal with this.

【0005】[0005]

【課題を解決するための手段】すなわち、上記目的に適
合する本発明の被覆管表面温度の検出方法は、冷却材温
度、炉心出力、炉心内圧力、出力ピーキング、出力分
布、および炉心・燃料の形状・寸法の各パラメータにお
いて、想定しうる種々の状況のデータを炉心熱水力及び
燃料温度解析コードに入力することにより、予め種々の
状況下の被覆管表面温度を求めると共に、これら求めた
被覆管表面温度と上記各パラメータとを関係づける近似
式を設定して、この近似式の上記冷却材温度、炉心出
力、炉心内圧力、出力ピーキング、および出力分布の各
パラメータにNIS盤等からの現時点でのデータを入力
することにより、現時点の被覆管表面温度を検出するこ
とを特徴とする。なお、ここでいうNISとは、Nuc
lear Instrumentation Syst
em、すなわち核計装システムのことである。
That is, the method for detecting the surface temperature of a cladding tube according to the present invention, which is adapted to the above-mentioned object, includes a coolant temperature, a core power, a core pressure, a power peaking, a power distribution, and a core / fuel. By inputting data of various conceivable situations for each parameter of shape and size into the core thermal hydraulic and fuel temperature analysis codes, the cladding tube surface temperature under various situations can be obtained in advance, and the obtained cladding can be obtained. Approximate equations that relate the pipe surface temperature and each of the above parameters are set, and the parameters of the coolant temperature, core power, core pressure, power peaking, and power distribution of this approximate equation are set to the current values from the NIS panel, etc. It is characterized in that the surface temperature of the cladding tube at the present time is detected by inputting the data in (1). The NIS here is Nuc.
lear Instrumentation System
em, or nuclear instrumentation system.

【0006】[0006]

【作用】上記本発明の方法においては、燃料健全性の判
断基準となる被覆管表面温度をオンタイムで直接的に監
視することができ、また被覆管表面温度とその温度の継
続時間を測定することにより、被覆管材料の健全性をさ
らに具体的に判断しうる。
In the above method of the present invention, the cladding surface temperature, which serves as a criterion for fuel integrity, can be directly monitored on-time, and the cladding surface temperature and the duration of the temperature can be measured. By doing so, the soundness of the cladding material can be determined more specifically.

【0007】[0007]

【実施例】以下さらに添付図面を参照して、本発明の実
施例を説明する。
Embodiments of the present invention will be described below with reference to the accompanying drawings.

【0008】図1は本発明実施例の被覆管表面温度の検
出方法を示すチャート図、図2は同実施例方法の近似式
の設定方法を示すチャート図である。
FIG. 1 is a chart showing a method of detecting the surface temperature of a cladding tube according to the embodiment of the present invention, and FIG. 2 is a chart showing a method of setting an approximate expression in the method of the embodiment.

【0009】前述したように、被覆管表面温度の計算
は、特に過渡変化時の非定常的な取り扱いでは膨大な計
算時間及び容量が必要となるため、本発明においては、
予め様々な入力条件に対して先に計算しておき、その計
算結果にフィッティングした近似式(RSM)を作成
し、これを代用して上記計算時間の短縮を図ったもので
ある。
As described above, the calculation of the surface temperature of the cladding tube requires an enormous amount of calculation time and a large amount of capacity, especially for unsteady handling during transient changes.
The calculation is performed in advance for various input conditions, an approximate expression (RSM) fitted to the calculation result is created, and the approximate expression (RSM) is used as a substitute to shorten the calculation time.

【0010】すなわち、本発明では先ず図2に示すよう
に、イ.冷却材温度、ロ.炉心出力、ハ.炉心内圧力、
ニ.出力ピーキング、ホ.出力分布、およびヘ.炉心・
燃料の形状・寸法の各入力パラメータにおいて、想定し
うる種々の状況のデータをコンピユータの炉心熱水力お
よび燃料温度解析コードに入力することにより、予め種
々の状況下の被覆管表面温度を求めると共に、これら求
めた被覆管表面温度と上記各パラメータとを関係づける
近似式(RSM)を設定する。
That is, in the present invention, first, as shown in FIG. Coolant temperature, b. Core power, c. Core pressure,
D. Output peaking, e. Output distribution, and f. Core
By inputting data of various conceivable situations for each input parameter of fuel shape and size into the core thermal hydraulic power and fuel temperature analysis code of the computer, the cladding tube surface temperature under various situations can be obtained in advance. , And an approximate expression (RSM) that relates the obtained cladding surface temperature to each of the above parameters is set.

【0011】そして、図1に示すように、上記近似式の
上記イ.冷却材温度、ロ.炉心出力、ハ.炉心内圧力、
ニ.出力ピーキング、およびホ.出力分布の各パラメー
タの部分に、各検出器または中央制御室のNIS盤等か
らの現時点でのデータを連続して入力することにより、
現時点の被覆管表面温度を継続して検出するようにす
る。なお、図1に示すシステムには、熱的に最も厳しい
燃料棒をサーベイする機能も付加する。このサーベイ機
能とは被覆管温度分布から最も高温の棒を特定すること
である。
Then, as shown in FIG. 1, the above a. Coolant temperature, b. Core power, c. Core pressure,
D. Output peaking, and e. By continuously inputting the current data from each detector or NIS panel of the main control room to each parameter part of the output distribution,
The current surface temperature of the cladding tube should be continuously detected. It should be noted that the system shown in FIG. 1 also has a function of surveying the fuel rod that is the most thermally severe. This survey function is to identify the hottest rod from the cladding temperature distribution.

【0012】上記近似式へのインプットデータとして
は、中央制御室の制御盤からオンタイムで入手可能なも
のは下記イ〜ハである。 イ.冷却材温度(Tin)・・・・炉心入口温度(℃) ロ.炉心出力(P)・・・・・・・炉心の出力(MW) ハ.圧力(W)・・・・・・・・・炉心の圧力(kg/
cm2 ) このほか、設計時に種々の定常、非定常状態に対して、
解析計算により求められているデータとして下記ニ、ホ
がある。 ニ.出力ピーキング(fz)・・・軸方向ピーキング係数 ホ.出力分布(f(x,y))・・最も高出力となる燃
料集合体内の各燃料棒の出力係数(径方向ピーキング係
数)。
As input data to the above approximate expression, the following data are available from the control panel of the main control room on time. I. Coolant temperature (Tin) ··· Core inlet temperature (° C) b. Core power (P) ..... Core power (MW) c. Pressure (W) ・ ・ ・ ・ Core pressure (kg /
cm 2 ) In addition, for various steady and unsteady states during design,
The following data are available as data obtained by analytical calculation. D. Output peaking (fz) ・ ・ ・ Axial peaking coefficient e. Power distribution (f (x, y)) ... Power coefficient (radial peaking coefficient) of each fuel rod in the fuel assembly that gives the highest power.

【0013】上記ニ、ホも制御盤記憶装置にメモリーし
ておき、その時の炉心の状態に応じて引き出せるように
しておく。したがって、上記イ〜ホによる近似式RSM
は、下記式数1の如く表される。
The above-mentioned D and E are also stored in the control panel memory so that they can be pulled out according to the state of the core at that time. Therefore, the approximate expression RSM by the above
Is expressed by the following equation 1.

【0014】[0014]

【数1】 RSM=F(Tin,P,W,fz,f(x,y))## EQU00001 ## RSM = F (Tin, P, W, fz, f (x, y))

【0015】しかして、上記本発明実施例の方法におい
ては、燃料健全性の判断基準となる被覆管表面温度をオ
ンタイムで直接的に検出し、監視することができ、また
被覆管表面温度とその温度の継続時間を測定することに
より、被覆管材料の健全性をさらに具体的に判断するこ
とが可能である。
In the method of the present invention, however, it is possible to directly detect and monitor the cladding tube surface temperature, which serves as a criterion for fuel integrity, on-time, and the cladding tube surface temperature and By measuring the duration of the temperature, it is possible to more specifically determine the soundness of the cladding material.

【0016】なお、この場合、燃料棒の健全性は、例え
ば「燃料棒表面温度が約600℃の状態での継続時間が
20秒以内であればその燃料棒は健全である」と定義す
るような材料の高温強度に直接立脚した評価方法が確立
されることも考えられていることから、本発明の方法と
しても、被覆管の健全性の限界を、温度とその継続時間
によって表すことが好ましい。
In this case, the soundness of the fuel rod is defined as, for example, "the fuel rod is sound if the duration of the fuel rod surface temperature is about 600 ° C. within 20 seconds". Since it is also considered that an evaluation method based directly on the high temperature strength of various materials will be established, it is preferable that the method of the present invention also represents the limit of the soundness of the cladding by the temperature and its duration. .

【0017】[0017]

【発明の効果】以上説明したように、本発明の被覆管表
面温度の検出方法は、所定のパラメータにおいて想定し
うる種々の状況データを炉心熱水力及び燃料温度解析コ
ードに入力することにより、予め求められた被覆管表面
温度と上記各パラメータとを関係づける近似式を設定し
て、この近似式のパラメータにリアルタイムのデータを
入力することによってリアルタイムの被覆管表面温度を
検出するものであり、燃料健全性の判断基準となる被覆
管表面温度をオンタイムで直接的に検出し監視すること
ができ、また、被覆管表面温度とその温度の継続時間を
測定することにより、被覆管材料の健全性をさらに具体
的に判断しうることから、これらを運転員が直接監視す
ることにより、設計基準事象は当然ながら、故障や事故
時の運転操作におけるより具体的判断材料ともすること
が可能である。
As described above, the method for detecting the surface temperature of the cladding tube according to the present invention is performed by inputting various situation data that can be assumed in predetermined parameters into the core thermal hydraulic and fuel temperature analysis codes. By setting an approximate expression relating the above-mentioned respective parameters to the cladding surface temperature previously obtained, and detecting the real-time cladding surface temperature by inputting real-time data to the parameters of this approximate expression, It is possible to directly detect and monitor the cladding surface temperature, which is the criterion for fuel integrity, on-time.By measuring the cladding surface temperature and the duration of that temperature, the integrity of the cladding material can be measured. Since it is possible to more concretely judge the characteristics, by directly monitoring these by the operator, the design reference event can be naturally applied to the driving operation at the time of failure or accident. It is possible to also Ruyori specific decisions.

【図面の簡単な説明】[Brief description of drawings]

【図1】本発明実施例の被覆管表面温度の検出方法を示
すチャート図である。
FIG. 1 is a chart showing a method for detecting a surface temperature of a cladding tube according to an embodiment of the present invention.

【図2】同実施例方法の近似式作成方法を示すチャート
図である。
FIG. 2 is a chart showing an approximate expression creating method of the method of the embodiment.

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 冷却材温度、炉心出力、炉心内圧力、出
力ピーキング、出力分布、および炉心・燃料の形状・寸
法の各パラメータにおいて、想定しうる種々の状況のデ
ータを炉心熱水力及び燃料温度解析コードに入力するこ
とにより、予め種々の状況下の被覆管表面温度を求める
と共に、これら求めた被覆管表面温度と上記各パラメー
タとを関係づける近似式を設定して、この近似式の上記
冷却材温度、炉心出力、炉心内圧力、出力ピーキング、
および出力分布の各パラメータにNIS盤等からの現時
点でのデータを入力することにより、現時点の被覆管表
面温度を検出することを特徴とする燃料棒の被覆管表面
温度の検出方法。
1. Data on various conceivable situations in the parameters of coolant temperature, core power, core pressure, power peaking, power distribution, and core / fuel shape / dimension are provided as core thermal hydraulic power and fuel. By inputting the temperature analysis code in advance, the cladding surface temperature under various circumstances is obtained, and an approximate expression that relates the obtained cladding surface temperature to each of the above parameters is set, and Coolant temperature, core power, core pressure, power peaking,
And a method for detecting the cladding tube surface temperature of a fuel rod, characterized in that the cladding tube surface temperature at the present time is detected by inputting the current data from the NIS panel or the like to each parameter of the output distribution.
JP7236016A 1995-08-21 1995-08-21 Detecting the surface temperature of cladding of fuel rods Withdrawn JPH0961582A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP7236016A JPH0961582A (en) 1995-08-21 1995-08-21 Detecting the surface temperature of cladding of fuel rods

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP7236016A JPH0961582A (en) 1995-08-21 1995-08-21 Detecting the surface temperature of cladding of fuel rods

Publications (1)

Publication Number Publication Date
JPH0961582A true JPH0961582A (en) 1997-03-07

Family

ID=16994531

Family Applications (1)

Application Number Title Priority Date Filing Date
JP7236016A Withdrawn JPH0961582A (en) 1995-08-21 1995-08-21 Detecting the surface temperature of cladding of fuel rods

Country Status (1)

Country Link
JP (1) JPH0961582A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2021512323A (en) * 2018-02-02 2021-05-13 ウエスチングハウス・エレクトリック・カンパニー・エルエルシー How to prevent damage to atomic fuel

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2021512323A (en) * 2018-02-02 2021-05-13 ウエスチングハウス・エレクトリック・カンパニー・エルエルシー How to prevent damage to atomic fuel

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