JPS6123996A - Transient relaxing method of heat in liquid-metal cooling fast breeder reactor - Google Patents

Transient relaxing method of heat in liquid-metal cooling fast breeder reactor

Info

Publication number
JPS6123996A
JPS6123996A JP14402184A JP14402184A JPS6123996A JP S6123996 A JPS6123996 A JP S6123996A JP 14402184 A JP14402184 A JP 14402184A JP 14402184 A JP14402184 A JP 14402184A JP S6123996 A JPS6123996 A JP S6123996A
Authority
JP
Japan
Prior art keywords
reactor
fast breeder
pump
transient
breeder reactor
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.)
Granted
Application number
JP14402184A
Other languages
Japanese (ja)
Other versions
JPH0412440B2 (en
Inventor
増井 章裕
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Atomic Power Industries Inc
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 Mitsubishi Atomic Power Industries Inc filed Critical Mitsubishi Atomic Power Industries Inc
Priority to JP14402184A priority Critical patent/JPS6123996A/en
Publication of JPS6123996A publication Critical patent/JPS6123996A/en
Publication of JPH0412440B2 publication Critical patent/JPH0412440B2/ja
Granted 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
    • 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

Abstract

(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。
(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

【発明の詳細な説明】 〈産業上の利用分野〉 本発明は、ループ型おまひタンク屋の液体金属冷却高速
増殖炉における熱過渡緩和方法に関する。
DETAILED DESCRIPTION OF THE INVENTION <Industrial Application Field> The present invention relates to a method for thermal transient mitigation in a liquid metal cooled fast breeder reactor of a loop-type tanker.

〈従来技術〉 一般に、液体金属冷却高速増殖炉(LMFBR)におい
て、出力運転時に異常事態が発生した場合にけ、原子炉
がスクラムさ力、崩壊熱除去運転に移行する。
<Prior Art> Generally, in a liquid metal cooled fast breeder reactor (LMFBR), when an abnormal situation occurs during power operation, the reactor shifts to scram force and decay heat removal operation.

すなわち、第4図の従来のプラントインターロック回路
のブロック図に示すように、手動トリップ、1次ポンプ
回転数低下、2次ポンプ回転数低下@による原子炉スク
ラム(トリップ)時には、同時に一次および二次系主循
環ポンプ主モータをトリップし、各ポンプは回転慣性に
よるコーストタウンをしながら設定した回転数となった
時点で最終的に起動してあった一次および二次系主ポン
プポニーモータの低速運転に引き継がれて崩壊熱除去運
転に移る方法が採られている。
That is, as shown in the block diagram of the conventional plant interlock circuit in Figure 4, when a reactor scram (trip) occurs due to a manual trip, a decrease in the primary pump rotation speed, or a decrease in the secondary pump rotation speed, the primary and secondary pumps are simultaneously activated. The main motor of the secondary main circulation pump is tripped, and when each pump reaches the set rotation speed while coasting due to rotational inertia, the low speed of the primary and secondary main pump pony motors that were finally started A method is adopted in which the operation is taken over and then the decay heat removal operation is carried out.

〈従来技術の欠点〉 しかしながら、上述した従来の方法では、原子炉容器ブ
レナム部に温度成層化現象が生じ、構成機器に大きな熱
過渡荷重が加わるという問題がおった。
<Disadvantages of Prior Art> However, the conventional method described above has the problem that a temperature stratification phenomenon occurs in the brenum portion of the reactor vessel, and a large thermal transient load is applied to the component equipment.

そこで、これらの問題点を解決するkめに、ポンプの慣
性を大きくするという方法もあるが、構成機器の温度変
化を最適にすることは困難であつた。
In order to solve these problems, there is a method of increasing the inertia of the pump, but it has been difficult to optimize the temperature change of the component equipment.

〈発明が解決しようとする問題点〉 本発8Aは、液体金属冷却高速増殖炉CLMFBR)こ
とを目的としている。
<Problems to be Solved by the Invention> The present invention 8A is aimed at a liquid metal cooled fast breeder reactor (CLMFBR).

く問題点を解決するための手段〉 上述した目的を達成するために、原子炉スクラム時に、
主循環ポンプ主モータをトリップさせることなく回転数
全適当々速度で低下させていき、崩壊熱除去運転に移行
させるものでアリ、上記回転数の低下方法として、構5
1y機器にかかる熱過渡が最も緩やかになるようなロー
コーストダウン曲線を予め解析等によって求めて、ポン
プ回転数のデジタルコントローラに記憶させておき、原
子炉スクラム時には、上記曲線に泪ってポンプ回転数全
制御するようにしたことを特徴とする液体金属冷却高速
増殖炉における熱過渡緩和方法を提供するものである。
Means to solve problems〉 In order to achieve the above-mentioned purpose, during reactor scram,
The rotation speed of the main circulation pump main motor is lowered at an appropriate speed without tripping, and the operation is shifted to decay heat removal operation.
A low coast down curve that will make the thermal transient on the 1y equipment the gentlest is found in advance through analysis, etc., and stored in the digital controller for the pump rotation speed. During a reactor scram, the pump rotation is determined based on the above curve. The present invention provides a method for thermal transient relaxation in a liquid metal cooled fast breeder reactor, which is characterized in that it is fully controlled.

〈作 用〉 本発明は、原子炉スクラム後、炉心部からの低温流体か
、従来に比べて大量に土部プレ、ナム部に流入し、高温
流体との混合が促進されるため、温度成層化現象が抑え
られて各構成機器にかかる熱過渡が大幅に緩やかになる
<Function> In the present invention, after the reactor scram, a large amount of low-temperature fluid from the reactor core flows into the earth pre and nam parts compared to the conventional method, and mixing with high-temperature fluid is promoted, so temperature stratification is prevented. As a result, thermal transients applied to each component device are greatly slowed down.

〈実施例〉 ν下、本発明による実施例全第1図なめし第3図に基づ
いて詳細に説明する。
<Example> ν Below, all examples according to the present invention will be described in detail based on FIG. 1 and FIG. 3.

第3図は、プラント制御系の基本概念?示すブロック図
であり、プラント制御系内の各制御系で(は、デジタル
コントローラにより、制御棒位置、ポンプ回転数等がコ
ントロールされる。
Figure 3 shows the basic concept of plant control system? It is a block diagram showing that each control system in the plant control system (in which the control rod position, pump rotation speed, etc. are controlled by a digital controller.

また、本発明では上述したプラント制御系のうち、原子
炉出力制御系を除く各制御系のデジタルコントローラの
プログラムを一部変更し、原子炉スクラム発生時、ラン
バック曲線として、予め設定された値全時系列としてポ
ンプ側に出力するようにしである。
In addition, in the present invention, among the above-mentioned plant control systems, the program of the digital controller of each control system except the reactor power control system is partially changed, and when a reactor scram occurs, a preset value is set as the runback curve. The entire time series is output to the pump side.

第2図は、本発明による回転数のランバンク曲線の一実
施例を示す図表でオp、デジタルコントローラ内では、
本曲線klo点程度の折れ線で近似してプログラム化し
ている。
FIG. 2 is a chart showing an example of a run bank curve of rotational speed according to the present invention.
The program is approximated by a polygonal line at about the klo point of this curve.

さらに、上記原子炉スクラム後、炉心部からの低温流体
が上部ブレナム部に流入して起る温度成層化現象防止の
ためには、原子炉スクラム後に上部ブレナム部の高温ナ
トリウムと、炉心から流れ出る低温ナトリウムとをよく
混合させなければならず、低出力運転時には炉心流量が
小感いので、コーストダウンの時間を引き伸ばすことが
必要となる。
Furthermore, in order to prevent the temperature stratification phenomenon that occurs when low-temperature fluid from the reactor core flows into the upper brenum after the reactor scram, it is necessary to Since the reactor must be thoroughly mixed with sodium and the core flow rate is small during low power operation, it is necessary to extend the coastdown time.

そこで、運転Wカレベルに応じて伺種類かのポンプ回転
数ランバック曲線?用意しておキ、最も適切にものを選
択して出力させる。
So, what kind of pump rotation speed runback curve should I ask depending on the operating power level? Prepare it, select the most appropriate one, and output it.

一方、W1図は本発明のプラントインターロック回路の
ブロック図であり、従来は、第4図に示すようにポンプ
主モータをトリップして、コーストダウンより設定した
回転数となった時点で、予め起動してあったポニーモー
タに引き継がせる方法であったが、本発明によれは、主
モータヲトリップはせることなく、回転数を低下させ、
崩壊熱運転も主モータにより設定回転数で運転を継続さ
せている。
On the other hand, Figure W1 is a block diagram of the plant interlock circuit of the present invention. Conventionally, as shown in Figure 4, the main motor of the pump is tripped, and when the rotation speed reaches the set speed from the coast down, the pump main motor is tripped. The method was to have the pony motor that had already started take over, but according to the present invention, the rotation speed is reduced without tripping the main motor.
Decay heat operation is also continued by the main motor at the set rotation speed.

したかつて、予め起動させておくポニーモータは不要と
なるものである。
This eliminates the need for a pony motor to be activated in advance.

〈発明の効果〉 以上詳細に説明したように、本発明による液体金属冷却
高速増殖炉における熱過渡緩和方法は、既存のプラント
制御系を利用して、デジタルコントローラ用のプログラ
ムを一部変更するとともに、プラントインターロック回
路に−mW更するだけの簡単な構成で実施できるもので
あるからポニーモータも不要となり、大幅なコストダウ
ンが図れる。
<Effects of the Invention> As explained in detail above, the method of thermal transient mitigation in a liquid metal cooled fast breeder reactor according to the present invention utilizes the existing plant control system and partially changes the program for the digital controller. Since it can be implemented with a simple configuration that requires only -mW addition to the plant interlock circuit, a pony motor is not required, and costs can be significantly reduced.

また、本発明によれば、原子炉スクラム時、炉r9部か
らの低温流体が大量に上部ブレナム部に流入して、高温
流体との混合が促進されるため、温度成層化現象が抑え
られるとともに、初期の温度成機器にかかる熱過渡負荷
が大幅に緩和きれる等の効果を奏する。
Further, according to the present invention, during a reactor scram, a large amount of low-temperature fluid from the reactor r9 section flows into the upper blenheim section and mixing with the high-temperature fluid is promoted, so that the temperature stratification phenomenon is suppressed and , the thermal transient load applied to the initial temperature control equipment can be significantly alleviated.

【図面の簡単な説明】[Brief explanation of the drawing]

第1図は本発明のプラントインターロック回路のブロッ
ク図、第2図は本発明によるポンプ回転数のランバック
曲線の一実施例を示す固嵌、第3図はプラント制御系の
基本概念を示すブロック図、第4図は従来のプラントイ
ンターロック回路のブロック図である。
Fig. 1 is a block diagram of the plant interlock circuit of the present invention, Fig. 2 is a fixed fit showing an example of a runback curve of the pump rotation speed according to the present invention, and Fig. 3 is a diagram showing the basic concept of the plant control system. Block Diagram FIG. 4 is a block diagram of a conventional plant interlock circuit.

Claims (1)

【特許請求の範囲】[Claims] 液体金属冷却高速増殖炉において、該原子炉スクラム時
に、1次ポンプ、2次ポンプ及び給水ポンプ等の主循環
ポンプの回転数を、該主循環ポンプの流量を制御する、
デジタルコントローラ等の回転数制御装置に記憶させた
上記原子炉の構成機器にかかる熱過度を最も緩やかにす
る曲線にそつてプログラム制御しつつ低下させることを
特徴とする熱過渡緩和方法。
In a liquid metal cooled fast breeder reactor, during the reactor scram, controlling the rotation speed of main circulation pumps such as a primary pump, a secondary pump, and a feed water pump, and the flow rate of the main circulation pumps.
A method for mitigating thermal transients, characterized in that the thermal excess applied to the components of the nuclear reactor stored in a rotational speed control device such as a digital controller is reduced under program control along a curve that makes the thermal excess applied to the components of the nuclear reactor the gentlest.
JP14402184A 1984-07-11 1984-07-11 Transient relaxing method of heat in liquid-metal cooling fast breeder reactor Granted JPS6123996A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP14402184A JPS6123996A (en) 1984-07-11 1984-07-11 Transient relaxing method of heat in liquid-metal cooling fast breeder reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP14402184A JPS6123996A (en) 1984-07-11 1984-07-11 Transient relaxing method of heat in liquid-metal cooling fast breeder reactor

Publications (2)

Publication Number Publication Date
JPS6123996A true JPS6123996A (en) 1986-02-01
JPH0412440B2 JPH0412440B2 (en) 1992-03-04

Family

ID=15352480

Family Applications (1)

Application Number Title Priority Date Filing Date
JP14402184A Granted JPS6123996A (en) 1984-07-11 1984-07-11 Transient relaxing method of heat in liquid-metal cooling fast breeder reactor

Country Status (1)

Country Link
JP (1) JPS6123996A (en)

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS57179697A (en) * 1981-04-28 1982-11-05 Nippon Atomic Ind Group Co Lmfbr type reactor plant

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS57179697A (en) * 1981-04-28 1982-11-05 Nippon Atomic Ind Group Co Lmfbr type reactor plant

Also Published As

Publication number Publication date
JPH0412440B2 (en) 1992-03-04

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