JPH08136688A - Reactor core performance monitoring system - Google Patents
Reactor core performance monitoring systemInfo
- Publication number
- JPH08136688A JPH08136688A JP6274720A JP27472094A JPH08136688A JP H08136688 A JPH08136688 A JP H08136688A JP 6274720 A JP6274720 A JP 6274720A JP 27472094 A JP27472094 A JP 27472094A JP H08136688 A JPH08136688 A JP H08136688A
- Authority
- JP
- Japan
- Prior art keywords
- mcpr
- mlhgr
- monitoring system
- core performance
- performance monitoring
- 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
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
-
- 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)
Abstract
Description
【０００１】[0001]
【産業上の利用分野】本発明は、原子炉の高効率運転，
安全性向上に寄与するための炉心性能監視システムに関
する。BACKGROUND OF THE INVENTION The present invention relates to highly efficient operation of a nuclear reactor,
The present invention relates to a core performance monitoring system for improving safety.
【０００２】[0002]
【従来の技術】原子炉燃料の熱的限界値の基準は、以下
の二つである。一つは、燃料被覆管の温度を異常に高く
することなく安定に熱除去できる限界の熱出力、すなわ
ち、冷却材が沸騰遷移を起こさない限界の熱出力であ
り、もう一つは、燃料ペレットの膨張により被覆管に過
大な歪を与えることのない限界の線出力密度である。前
者に対しては最小限界出力比（ＭＣＰＲ：Minimum Crit
ical Power Ratio）、後者には最大線出力密度（ＭＬＨ
ＧＲ：Maximum Linear Heat Generation Ratio）に運転
上の制限値を設けることによって、燃料の健全性を保持
している。ここで、ＭＣＰＲは燃料集合体の限界熱出力
と運転出力との比のうち炉心内での最小値、また、ＭＬ
ＨＧＲは局所的な線出力密度の許容最大値である。ＭＣ
ＰＲおよびＭＬＨＧＲのいずれも、異常な過渡変化によ
る出力変化を考慮し、制限値に十分な安全余裕をとって
ある。2. Description of the Related Art There are two criteria for the thermal limit of reactor fuel. One is the limit heat output that can stably remove heat without raising the temperature of the fuel cladding tube abnormally, that is, the limit heat output that does not cause boiling transition of the coolant, and the other is fuel pellets. This is the limit of linear power density that does not give excessive strain to the cladding tube due to the expansion of. For the former, the minimum critical power ratio (MCPR: Minimum Crit
ical power ratio), the latter being the maximum linear power density (MLH
The soundness of the fuel is maintained by setting an operating limit value in GR (Maximum Linear Heat Generation Ratio). Here, MCPR is the minimum value in the core of the ratio of the limit heat output of the fuel assembly to the operation output, and ML
HGR is the maximum allowable linear power density. MC
Both PR and MLHGR have a sufficient safety margin for the limit value in consideration of the output change due to the abnormal transient change.
【０００３】沸騰水型原子炉の場合、ＭＣＰＲおよびＭ
ＬＨＧＲは、プロセス計算機によって１時間ごとに計算
され、運転員に監視されている。図２に、従来の炉心性
能計算の流れの概略を示す。炉心の状態データ（炉心流
量，ヒートバランス，制御棒パタンなど)および局所出
力領域モニタ(ＬＰＲＭ：Local Power Range Monitor)
信号から、三次元シミュレータによって炉心内の出力分
布が計算され、ＭＣＰＲおよびＭＬＨＧＲが求められ
る。燃料の限界出力は実規模熱水力試験に基づく実験式
によって計算されている。For boiling water reactors, MCPR and M
LHGR is calculated by the process computer every hour and is monitored by the operator. FIG. 2 shows an outline of the flow of the conventional core performance calculation. Core status data (core flow rate, heat balance, control rod pattern, etc.) and local power range monitor (LPRM)
From the signal, the power distribution in the core is calculated by a three-dimensional simulator, and MCPR and MLHGR are obtained. The fuel limit output is calculated by an empirical formula based on a full-scale thermal-hydraulic test.
【０００４】[0004]
【発明が解決しようとする課題】ＭＣＰＲおよびＭＬＨ
ＧＲには十分な安全余裕がとってあるので、原子炉の定
常運転時には１時間ごとのモニタでよい。しかし、異常
な過渡事象発生時には、炉心特性は数秒から数分のオー
ダで変化するので、１時間おきのモニタでは特性を評価
できない。燃料の信頼性維持の観点からは、異常な過渡
事象時のＭＣＰＲおよびＭＬＨＧＲの経時変化をモニタ
しておくことが望ましい。異常な過渡事象時の炉心特性
を解析しておけば、燃料破損に至らずとも熱的危機にさ
らされた燃料集合体を推定でき、定期検査時などにこの
ような燃料を交換しておくこともできる。[Problems to be Solved by the Invention] MCPR and MLH
Since the GR has a sufficient safety margin, it is sufficient to monitor every hour during steady operation of the reactor. However, when an abnormal transient event occurs, the core characteristics change on the order of several seconds to several minutes, and therefore the characteristics cannot be evaluated by a monitor every hour. From the viewpoint of maintaining fuel reliability, it is desirable to monitor changes over time in MCPR and MLHGR during abnormal transient events. By analyzing the core characteristics during abnormal transient events, it is possible to estimate the fuel assemblies that have been exposed to a thermal crisis even if the fuel has not been damaged.Replace such fuel during periodic inspections, etc. You can also
【０００５】[0005]
【課題を解決するための手段】炉心特性監視システム
に、異常な過渡事象時のＭＣＰＲおよびＭＬＨＧＲの変
化を、現象の推移と同程度の時間ステップで計算する機
能を付加する。[Means for Solving the Problems] A function for calculating changes in MCPR and MLHGR during an abnormal transient event is added to a core characteristic monitoring system at a time step similar to the transition of a phenomenon.
【０００６】[0006]
【作用】ＭＣＰＲまたはＭＬＨＧＲを非安全側に推移さ
せると考えられる過渡事象発生時に、警報信号とともに
自動起動される計算プログラムによって経時変化を計算
する。また、計算時間が現象の推移速度に追いつかない
場合には、炉心の状態データを記録しておき、事後に解
析する。これによって、異常な過渡事象の燃料への影響
を判定する。When a transient event that is considered to shift MCPR or MLHGR to the unsafe side occurs, the change over time is calculated by a calculation program that is automatically activated together with an alarm signal. If the calculation time cannot catch up with the transition speed of the phenomenon, the core state data is recorded and analyzed after the fact. This determines the effect of abnormal transients on fuel.
【０００７】[0007]
【実施例】図１に、本発明の計算システムにおけるＭＣ
ＰＲおよびＭＬＨＧＲの計算の流れを簡略的に示す。従
来のＢＷＲ炉心性能監視システムにおけるＭＣＰＲおよ
びＭＬＨＧＲの計算プログラム（図２）は、１時間おき
に起動される。本発明では、図１の計算を行うプログラ
ムを異常な過渡事象発生と同時に起動し、できる限りリ
アルタイムでＭＣＰＲおよびＭＬＨＧＲを計算する。し
たがって、三次元シミュレータには計算高速化の工夫が
必要である。計算が事象の推移速度に追いつけない場合
でも、炉心状態データおよびＬＰＲＭ出力データを記憶
装置に格納しておくことによって、定常運転復帰後に解
析することができる。また、従来のプログラムでは燃料
の限界出力計算に実験式を用いているが、図１の計算プ
ログラムでは沸騰遷移後の冷却材流動現象を扱える解析
コードなどを用いる。これによって、万一、ＭＣＰＲが
許容値を下回った場合でも、燃料棒表面温度履歴を推定
できるので燃料の健全性の判断材料となる。DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS FIG. 1 shows an MC in a computing system of the present invention.
The calculation flow of PR and MLHGR is shown briefly. The MCPR and MLHGR calculation programs (FIG. 2) in the conventional BWR core performance monitoring system are started every hour. In the present invention, the program for performing the calculation of FIG. 1 is started at the same time as the occurrence of an abnormal transient event, and MCPR and MLHGR are calculated in real time as much as possible. Therefore, it is necessary to devise a high-speed calculation for the 3D simulator. Even if the calculation cannot keep up with the transition speed of the event, by storing the core state data and the LPRM output data in the storage device, it is possible to analyze after returning to the steady operation. Further, in the conventional program, an empirical formula is used to calculate the fuel limit output, but in the calculation program of FIG. 1, an analysis code or the like that can handle the coolant flow phenomenon after the boiling transition is used. As a result, even if the MCPR falls below the allowable value, the fuel rod surface temperature history can be estimated, which serves as a criterion for the fuel integrity.
【０００８】[0008]
【発明の効果】炉心性能監視システムに、異常な過渡事
象時のＭＣＰＲおよびＭＬＨＧＲの経時変化を、現象の
推移と同程度の時間ステップで計算する機能を付加する
ことによって、燃料集合体の信頼性維持を図ることがで
きる。EFFECT OF THE INVENTION By adding to the core performance monitoring system the function of calculating changes in MCPR and MLHGR with time during an abnormal transient event at the same time step as the transition of the phenomenon, the reliability of the fuel assembly is improved. Can be maintained.
【図１】本発明の一実施例のＭＣＰＲおよびＭＬＨＧＲ
の計算のフローチャート。FIG. 1 shows MCPR and MLHGR according to an embodiment of the present invention.
Calculation flowchart.
【図２】従来の炉心性能監視システムにおけるＭＣＰＲ
およびＭＬＨＧＲの計算のフローチャート。FIG. 2 MCPR in a conventional core performance monitoring system
And a flow chart for calculating MLHGR.
───────────────────────────────────────────────────── フロントページの続き (51)Int.Cl.6 識別記号 庁内整理番号 ＦＩ 技術表示箇所 Ｇ２１Ｃ 17/06 ＧＤＢ Ｘ (72)発明者 茶木 雅夫 茨城県日立市大みか町七丁目２番１号 株 式会社日立製作所エネルギー研究所内─────────────────────────────────────────────────── ─── Continuation of the front page (51) Int.Cl. 6 Identification number Reference number within the agency FI Technical indication location G21C 17/06 GDB X (72) Inventor Masao Chaki 7-2-1, Mikamachi, Hitachi City, Ibaraki Prefecture Hitachi, Ltd. Energy Research Institute
Claims (1)
システムにおいて、原子炉燃料の健全性を監視するパラ
メータである最小限界出力比および／または最大線出力
密度の経時変化を１時間より短い時間間隔で計算する機
能を有することを特徴とする原子炉の炉心性能監視シス
テム。1. A computer system for monitoring core performance during operation of a reactor, wherein the change over time of the minimum critical power ratio and / or the maximum linear power density, which is a parameter for monitoring the health of the reactor fuel, is shorter than 1 hour. A reactor core performance monitoring system having a function of calculating at time intervals.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6274720A JPH08136688A (en) | 1994-11-09 | 1994-11-09 | Reactor core performance monitoring system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP6274720A JPH08136688A (en) | 1994-11-09 | 1994-11-09 | Reactor core performance monitoring system |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH08136688A true JPH08136688A (en) | 1996-05-31 |
Family
ID=17545638
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP6274720A Pending JPH08136688A (en) | 1994-11-09 | 1994-11-09 | Reactor core performance monitoring system |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH08136688A (en) |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2005172749A (en) * | 2003-12-15 | 2005-06-30 | Global Nuclear Fuel-Japan Co Ltd | Core monitor |
| WO2012095932A1 (en) * | 2011-01-12 | 2012-07-19 | 株式会社 東芝 | Reactor core monitoring system |
| JP2013047666A (en) * | 2011-07-27 | 2013-03-07 | Toshiba Corp | System, method, and program for monitoring reactor core |
| JP2013205379A (en) * | 2012-03-29 | 2013-10-07 | Mitsubishi Heavy Ind Ltd | Reactor core analysis program and analysis device |
-
1994
- 1994-11-09 JP JP6274720A patent/JPH08136688A/en active Pending
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2005172749A (en) * | 2003-12-15 | 2005-06-30 | Global Nuclear Fuel-Japan Co Ltd | Core monitor |
| WO2012095932A1 (en) * | 2011-01-12 | 2012-07-19 | 株式会社 東芝 | Reactor core monitoring system |
| JP2012145448A (en) * | 2011-01-12 | 2012-08-02 | Toshiba Corp | Reactor core monitoring system |
| US9842663B2 (en) | 2011-01-12 | 2017-12-12 | Kabushiki Kaisha Toshiba | Core monitoring system |
| JP2013047666A (en) * | 2011-07-27 | 2013-03-07 | Toshiba Corp | System, method, and program for monitoring reactor core |
| JP2013205379A (en) * | 2012-03-29 | 2013-10-07 | Mitsubishi Heavy Ind Ltd | Reactor core analysis program and analysis device |
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