JPS63154994A - Fuel exchanger controller - Google Patents

Fuel exchanger controller

Info

Publication number
JPS63154994A
JPS63154994A JP61301273A JP30127386A JPS63154994A JP S63154994 A JPS63154994 A JP S63154994A JP 61301273 A JP61301273 A JP 61301273A JP 30127386 A JP30127386 A JP 30127386A JP S63154994 A JPS63154994 A JP S63154994A
Authority
JP
Japan
Prior art keywords
fuel
procedure
refueling
input
core
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
Application number
JP61301273A
Other languages
Japanese (ja)
Inventor
裕一 東川
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.)
Hitachi Ltd
Original Assignee
Hitachi 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 Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP61301273A priority Critical patent/JPS63154994A/en
Publication of JPS63154994A publication Critical patent/JPS63154994A/en
Pending 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

  • Sorption Type Refrigeration Machines (AREA)
  • Fuel Cell (AREA)
  • Feeding And Controlling Fuel (AREA)

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〕 本発明は原子力発電所の燃料を交換するための燃料取替
機に係り、特に、迅速な燃料取替制御を行うのに好適な
燃料取替機制御装置に関する。
[Detailed Description of the Invention] [Industrial Application Field] The present invention relates to a fuel exchanger for exchanging fuel in a nuclear power plant, and in particular to a fuel exchanger suitable for performing quick fuel exchange control. This invention relates to a changeover control device.

〔従来の技術〕[Conventional technology]

原子力発電所は、通常、年に一回計画的に運転を停止し
、その設備の点検を行ない、燃料の取替を行う。この取
替作業では、誤って燃料を破損させないように、従来よ
り自動化されている。
Nuclear power plants normally undergo a planned shutdown once a year to inspect their equipment and replace the fuel. This replacement work has traditionally been automated to avoid accidentally damaging the fuel.

一方、発電所の停止期間中にどの燃料を取替えるかを決
定するため、原子炉運転中に炉内中性子束検出器の情報
を入力し、燃料の燃焼度を常時モニタするプログラムが
プラント計算機に1!2誼されており、従来より熟練し
た技術者がこのプラント計算機プログラムのぼう大な計
算情報に基づき。
On the other hand, in order to determine which fuel to replace during a power plant shutdown period, a program is installed in the plant computer that inputs information from the in-reactor neutron flux detector during reactor operation and constantly monitors the fuel burnup. !2), and more experienced engineers than before can use this plant computer program's extensive calculation information.

最適な燃料取替計画を立案している。そして、熟練した
技術者の立案した燃料取替計画は、手順書の形で原子力
発電所の運転員に提呂され、運転員は手順書に規定され
ている燃料取替手順を自動化された燃料取替機制御装置
にインプットし、そのインプットされた手順が誤りのな
い事を確認後、燃料取替機制御装置を用いて自動的に燃
料を取替えている。
We are formulating an optimal fuel change plan. The refueling plan drawn up by a skilled engineer is provided to the nuclear power plant operators in the form of a procedure manual, and the operators follow the refueling procedure stipulated in the procedure manual to the automated fuel exchange plan. After inputting the input into the fuel exchanger control device and confirming that the input procedure is correct, the fuel is automatically exchanged using the fuel exchanger control device.

〔発明が解決しようとする問題点〕[Problem that the invention seeks to solve]

しかし、近年、原子力発電所の設備利用率の向上をめざ
して1M転停止期間を最短とするような計画がなされて
おり、プラントの基数も増えるに従い、熟練した技術者
の作業は迅速な対応が要求されるようになっており、技
術者に対する負担が大きいものとなっている。
However, in recent years, plans have been made to minimize the 1M shutdown period with the aim of improving the capacity utilization rate of nuclear power plants, and as the number of plants increases, skilled engineers are required to respond quickly. This has placed a heavy burden on engineers.

本発明の目的は、専門家でなくとも効率的に燃料取替計
画が立案できるような燃料取替計画支援装置の計画した
運転手順を容易にインプット可能な燃料取替機制御装置
費提供することにある。
An object of the present invention is to provide a fuel change machine control device that can easily input the planned operating procedure of a fuel change plan support device so that even non-experts can efficiently formulate a fuel change plan. It is in.

〔問題点を解決するための手段〕[Means for solving problems]

上記の目的は、プラントの計算機が燃料の燃料度合をモ
ニタした結果を、常時、記憶しておくデータメモリ装置
、及び、プラントが計画的に停止した時には、データメ
モリ装置に記憶されている燃料の燃料度合に関するデー
タをもとに、燃料取替計画手順を決定するプログラム、
及び、そのプログラムによつ決定された燃料取替手順を
燃料取替機制御装置に入力するための入力装置から構成
される燃料取替計画支援装置によって達成される。
The above purpose is to provide a data memory device that constantly stores the results of monitoring the fuel level of fuel by a plant computer, and to provide a data memory device that constantly stores the results of monitoring the fuel level of fuel by a plant computer, and to A program that determines refueling planning procedures based on data regarding fuel level;
This is achieved by a refueling plan support device comprising an input device for inputting the refueling procedure determined by the program to the refueling machine control device.

〔作用〕 燃料取替手順を作成するプログラムは、データメモリ装
置に記憶されている情報を参考にしながら、必要とされ
る計画条件の自動設定を行なう。
[Operation] The program for creating the refueling procedure automatically sets the necessary planning conditions while referring to the information stored in the data memory device.

さらに、決定された燃料取替手順は、データメモリ装置
に記憶されている情報を用いて妥当性の確認が可能とな
るため、安全で確実が燃料取替制御が専門家の手を借り
ずに実施できる。
In addition, the determined refueling procedure can be validated using information stored in the data memory device, ensuring safe and reliable refueling control without the need for expert assistance. Can be implemented.

〔実施例〕〔Example〕

以下、本発明の一実施例を、第1図により説明する。原
子炉1の炉心2には炉内中性子検出器3を多数本設置し
ており、運転中の時々刻々の燃料出力は中性子検出器3
により検出され、プラントの計算機4に信号が入力され
る。プラントの計算機4では1通常、一時間に一回づつ
、現在の中性子束信号入力をもとに、炉心2内の燃料の
燃焼の度合を計算するプログラムをもち、その結果は記
録装置11に出力され、燃料取替計画支援装置5に入力
される。燃料取替機制御装置5では、プラントの運転中
の燃料の燃焼の度合を燃料管理データ6として記憶して
いる。プラントが計画的に停止した場合には、運転員が
燃料取替計画支援袋fi5の入出力端末装置12によっ
て、本装置に必要な条件を設定する事により、本装置の
燃料取替手順作成プログラム7が作動し、燃料管理デー
タ6として記憶されていた燃料の燃焼の度合いを評価し
ながら今回取替えるべき燃料を決定する。その結果、燃
料の取替え手順が定まり、定まった手順はフレキシブル
ディスク装M8に出力される。
An embodiment of the present invention will be described below with reference to FIG. Numerous in-core neutron detectors 3 are installed in the core 2 of the nuclear reactor 1, and the momentary fuel output during operation is monitored by the neutron detectors 3.
, and the signal is input to the computer 4 of the plant. The plant computer 4 normally has a program that calculates the degree of fuel combustion in the reactor core 2 once an hour based on the current neutron flux signal input, and outputs the result to the recording device 11. and input into the fuel replacement plan support device 5. The fuel exchanger control device 5 stores the degree of fuel combustion during plant operation as fuel management data 6. In the event of a planned shutdown of the plant, the operator can use the input/output terminal device 12 of the fuel replacement planning support bag fi5 to set the necessary conditions for this equipment, thereby starting the fuel replacement procedure creation program of this equipment. 7 is activated, and the fuel to be replaced this time is determined while evaluating the degree of combustion of the fuel stored as fuel management data 6. As a result, the fuel replacement procedure is determined, and the determined procedure is output to the flexible disk device M8.

燃料取替機制御装置9にもフレキシブルディスク装置8
を設けてあり、燃料取替計画支援装置■で決定された燃
料取替え手順はフレキシブルディスク装置8を介して燃
料取替機制御袋M9に記憶される。その結果、燃料取替
機制御袋e9は計画された燃料取替手順に従って、燃料
取替機10を自動的に制御し、所定の燃料を取替えるこ
とができる。
The flexible disk device 8 is also included in the fuel exchanger control device 9.
The fuel exchange procedure determined by the fuel exchange plan support device (2) is stored in the fuel exchange machine control bag M9 via the flexible disk device 8. As a result, the refueling machine control bag e9 can automatically control the refueling machine 10 and replace the predetermined fuel according to the planned refueling procedure.

次に、燃料取替計画支援装置子の燃料取替手順作成プロ
グラム7について第2図を用いて、詳細に説明する。第
2図は、燃料取替手順作成プログラムの処理フローを示
したものである。燃料取替計画支援装置5の入出力端末
装置12から運転員によって本プログラムの起動が要求
されると、本プログラムでは、燃料管理データ6よりサ
イクル末期炉心状態、前サイクルでの燃料仕様等、必要
な計画立案条件を自動的に読み出し、本プログラムに設
定する(201)、次に、取替燃料体数が設定され(2
02)、設定された体数を目標値として、燃料管理デー
タ6を参照しながら、燃料度合の高い燃料から順番に取
出し燃料が決定される(203)、取出す事が決定した
燃料の位置には新しい燃料が装荷されるため、新しい燃
料の燃焼特性データを入出力装置ff12から入力する
(新燃料装荷位置の設定)、これにより1次のサイクル
でも引続き燃焼させる燃料及び、新しい燃料に交換する
位置が決定された訳であり(204) 、全燃料の次サ
イクルでの装荷位置が決定されたことになる(205)
、以下のフローは、上記により決定された燃料位置が妥
当かどうかの確認のための処理である。
Next, the fuel change procedure creation program 7 of the fuel change plan support device will be described in detail with reference to FIG. FIG. 2 shows the processing flow of the fuel replacement procedure creation program. When an operator requests startup of this program from the input/output terminal device 12 of the fuel exchange planning support device 5, this program will retrieve necessary information such as the core state at the end of the cycle, fuel specifications in the previous cycle, etc. from the fuel management data 6. The planning conditions are automatically read out and set in this program (201), and then the number of replacement fuel bodies is set (201).
02), With the set number of bodies as a target value, the fuel to be taken out is determined in order from the fuel with the highest fuel content while referring to the fuel management data 6 (203).The position of the fuel decided to be taken out is Since new fuel is loaded, the combustion characteristic data of the new fuel is input from the input/output device ff12 (new fuel loading position setting). This determines the fuel to be continuously burned in the first cycle and the position to be replaced with new fuel. has been determined (204), and the loading position of all fuels in the next cycle has been determined (205).
, The following flow is a process for checking whether the fuel position determined above is appropriate.

「燃料履歴データ再編処理J  (206)では。“Fuel history data reorganization processing J (206).

プラント停止直前の燃料の燃料の度合いを記憶した燃料
管理データ6を読み出し、また、「新燃料装荷位置の設
定J  (204)処理で入力された新燃料の燃焼特性
データにより全燃料の次サイクル最初での炉心状態を編
成する。
The fuel management data 6 that stores the fuel level of the fuel immediately before the plant is stopped is read out, and the new fuel combustion characteristic data input in the "Setting new fuel loading position" process (204) is used to determine the fuel level at the beginning of the next cycle for all fuels. Organize the core state at

これにより、炉心のシミュレーション計算により、炉心
末期までの燃焼シミュレーションが実施される(207
)、この結果得られたサイクル長さ及びサイクル末期炉
心特性が規定値以内であれば、次の「炉停止余裕計算」
処理へ進む(208)。
As a result, combustion simulation up to the final stage of the core is performed through core simulation calculations (207
), if the cycle length and core characteristics at the end of the cycle obtained are within the specified values, proceed to the next "reactor shutdown margin calculation".
Proceed to processing (208).

もし、結果が妥当でなければ「取替燃料体数設定」処理
あるいは「取出し燃料選定」処理へ戻って燃料取替計画
が再計算される。
If the result is not valid, the process returns to the ``number of replacement fuel bodies setting'' process or the ``removal fuel selection'' process to recalculate the fuel replacement plan.

「炉停止余裕計算J  (209)処理では、炉心初期
状態から末期までの燃料シミュレーションにより燃料の
燃焼段階で原子炉が停止された場合の、停止に必要な反
応度に対する余裕度が計算される。
"Reactor Shutdown Margin Calculation J (209) process calculates the margin for the reactivity required for shutdown when the reactor is shut down in the fuel combustion stage by fuel simulation from the initial core state to the final stage.

この結果、必要な余裕度が得られた場合、燃料位置が妥
当と判断する(210)、これにより、前サイクルでの
燃料位置から次サイクルでの新燃料に交換すべき燃料位
置及びその体数が決定され、その結果が燃料取替手順と
してフレキシブルディスク装置8に出力される。
As a result, if the necessary margin is obtained, the fuel position is judged to be appropriate (210). This determines the fuel position and number of fuels to be replaced with new fuel in the next cycle from the fuel position in the previous cycle. is determined, and the result is output to the flexible disk device 8 as a fuel replacement procedure.

〔発明の効果〕〔Effect of the invention〕

本発明によれば、プラントの計算機によって常時モニタ
され記憶されていた燃料管理データに基づき安全で確実
な燃料取替手順が、専門家の手を借りずども迅速に計算
され、その手順を燃料取替機制御装置に容易にインプッ
トすることができる。
According to the present invention, a safe and reliable fuel change procedure can be quickly calculated without the help of an expert based on fuel management data that is constantly monitored and stored by a plant computer, and the fuel change procedure can be quickly calculated without the help of an expert. It can be easily input to the switching machine control device.

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

第1図は本発明の一実施例の全体構成図、第2図は本発
明の実施例による燃料取替手順作成プログラムの処理フ
ローチャートである。 1・・・原子炉、2・・・炉心、3・・・中性子束検出
装置、4・・・プラント計算機、■・・・運転計画支援
装置、6・・・燃料管理データ、7・・・燃料取替手順
作成プログラム、8・・・フレキシブルディスク装置、
9・・・燃料取替機制御装置、10・・・燃料取替機。
FIG. 1 is an overall configuration diagram of an embodiment of the present invention, and FIG. 2 is a processing flowchart of a fuel change procedure creation program according to the embodiment of the present invention. DESCRIPTION OF SYMBOLS 1... Nuclear reactor, 2... Core, 3... Neutron flux detection device, 4... Plant computer, ■... Operation planning support device, 6... Fuel management data, 7... Fuel replacement procedure creation program, 8...Flexible disk device,
9... Fuel exchange machine control device, 10... Fuel exchange machine.

Claims (1)

【特許請求の範囲】[Claims] 1、原子力発電所の炉心に設置された中性子束検出装置
から燃料の燃焼度合を求める計算機と、前記計算機の計
算結果を記憶する装置と、記憶した結果により前記燃料
の取替手順を作成する装置と、作成された手順を出力す
る装置と、前記出力された手順を入力する装置を備えた
ことを特徴とする燃料取替機制御装置。
1. A computer that determines the burn-up degree of fuel from a neutron flux detection device installed in the core of a nuclear power plant, a device that stores the calculation results of the computer, and a device that creates the fuel replacement procedure based on the stored results. A refueling machine control device comprising: a device for outputting the created procedure; and a device for inputting the output procedure.
JP61301273A 1986-12-19 1986-12-19 Fuel exchanger controller Pending JPS63154994A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP61301273A JPS63154994A (en) 1986-12-19 1986-12-19 Fuel exchanger controller

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP61301273A JPS63154994A (en) 1986-12-19 1986-12-19 Fuel exchanger controller

Publications (1)

Publication Number Publication Date
JPS63154994A true JPS63154994A (en) 1988-06-28

Family

ID=17894834

Family Applications (1)

Application Number Title Priority Date Filing Date
JP61301273A Pending JPS63154994A (en) 1986-12-19 1986-12-19 Fuel exchanger controller

Country Status (1)

Country Link
JP (1) JPS63154994A (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2013510313A (en) * 2009-11-06 2013-03-21 シーレイト リミテッド ライアビリティー カンパニー Method and system for moving a nuclear fuel assembly in a fission reactor
US9786392B2 (en) 2009-11-06 2017-10-10 Terrapower, Llc Methods and systems for migrating fuel assemblies in a nuclear fission reactor
US9799416B2 (en) 2009-11-06 2017-10-24 Terrapower, Llc Methods and systems for migrating fuel assemblies in a nuclear fission reactor
US9922733B2 (en) 2009-11-06 2018-03-20 Terrapower, Llc Methods and systems for migrating fuel assemblies in a nuclear fission reactor
US10008294B2 (en) 2009-11-06 2018-06-26 Terrapower, Llc Methods and systems for migrating fuel assemblies in a nuclear fission reactor

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2013510313A (en) * 2009-11-06 2013-03-21 シーレイト リミテッド ライアビリティー カンパニー Method and system for moving a nuclear fuel assembly in a fission reactor
JP2013510314A (en) * 2009-11-06 2013-03-21 シーレイト リミテッド ライアビリティー カンパニー Method and system for moving a nuclear fuel assembly in a fission reactor
US9786392B2 (en) 2009-11-06 2017-10-10 Terrapower, Llc Methods and systems for migrating fuel assemblies in a nuclear fission reactor
US9799416B2 (en) 2009-11-06 2017-10-24 Terrapower, Llc Methods and systems for migrating fuel assemblies in a nuclear fission reactor
US9922733B2 (en) 2009-11-06 2018-03-20 Terrapower, Llc Methods and systems for migrating fuel assemblies in a nuclear fission reactor
US10008294B2 (en) 2009-11-06 2018-06-26 Terrapower, Llc Methods and systems for migrating fuel assemblies in a nuclear fission reactor

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