JPH03214097A - Operating method of reactor - Google Patents

Operating method of reactor

Info

Publication number
JPH03214097A
JPH03214097A JP2007210A JP721090A JPH03214097A JP H03214097 A JPH03214097 A JP H03214097A JP 2007210 A JP2007210 A JP 2007210A JP 721090 A JP721090 A JP 721090A JP H03214097 A JPH03214097 A JP H03214097A
Authority
JP
Japan
Prior art keywords
fuel
cycle
reactor
initially loaded
replaced
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
JP2007210A
Other languages
Japanese (ja)
Inventor
Hisao Suzuki
壽生 鈴木
Kazutaka Hida
和毅 肥田
Ritsuo Yoshioka
律夫 吉岡
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.)
Toshiba Corp
Original Assignee
Toshiba Corp
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 Toshiba Corp filed Critical Toshiba Corp
Priority to JP2007210A priority Critical patent/JPH03214097A/en
Publication of JPH03214097A publication Critical patent/JPH03214097A/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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

PURPOSE:To improve an average takeout burnup of an initially loaded fuel and to reduce the number of rods to be replaced, by a method wherein the initially loaded fuel taken out at the time of completion of the second cycle at least is replaced by a fuel located inside a core and having a low reactivity. CONSTITUTION:As to a boiling water reactor having an electrical output of 1,350,000KW and 872 fuel loading rods, for instance, the enrichment of an initially loaded fuel loaded in a core at the time of a rise of the reactor is set at about 3.1wt.%. According to the core of the reactor thus prepared, the reactor is stopped in a state of control rods being left inserted, at the time of completion of the first cycle. At the time of completion this first cycle, 146 rods out of those of the initially loaded fuel are replaced by those of a fuel to be substituted which has an enrichment of about 3.5wt.%, and a second-cycle operation is conducted. At the time of completion of the second cycle and each subsequent cycle, the reactor is stopped in a state of all the control rods being drawn out. After the completion of the second cycle, 146 rods of the initially loaded fuel are reloaded since they have still a remaining combustion energy, while the other 314 rods are replaced by the fuel to be substituted, and then an operation of the third cycle is executed.

Description

【発明の詳細な説明】 [発明の目的〕 (産業上の利用分野) 本発明は原子炉の運転方法に関する。[Detailed description of the invention] [Purpose of the invention] (Industrial application field) The present invention relates to a method of operating a nuclear reactor.

(従来の技術) 一般に、原子炉が建設されて初めて炉心に装荷される初
装荷炉心の燃料の濃縮度は、予め計画された一定の期間
(これを1サイクルと呼ぶ)原子炉が運転可能なように
決定される。沸騰水型原子炉では、運転期間が15ケ月
の場合には、初装荷燃料の濃縮度は約2.5wt%とさ
れている。このように初装荷燃料の濃縮度を2.5wt
%とすると、原子炉を1サイクル運転した後には炉心の
余剰反応度は零となり、制御棒をすべて引き抜いた状態
でちょうど臨界となる。
(Prior art) In general, the enrichment of the fuel in the first loaded reactor core, which is loaded into the reactor core for the first time after a nuclear reactor is constructed, is determined in advance for a pre-planned fixed period (this is called one cycle) at which the reactor can operate. It is determined as follows. In a boiling water reactor, if the operating period is 15 months, the enrichment of the initially loaded fuel is approximately 2.5 wt%. In this way, the enrichment of the initially loaded fuel is set to 2.5w.
%, the surplus reactivity of the core will be zero after one cycle of operation of the reactor, and it will just become critical when all the control rods are withdrawn.

このような沸騰水型原子炉では、第1サイクルの運転終
了後、初装荷燃料の約1/3が取替燃料に交換されて第
2サイクルの運転が行われ、1サイクル経過後にさらに
初装荷燃料の約1/3が取替燃料に交換されて第3サイ
クルの運転が行われる。そして、このような原子炉の炉
心では、たとえば第2サイクルにおいては、第1サイク
ルで使用された初装荷燃料の約2/3がこのまま装荷さ
れて使用されるため、第2サイクルで最初に炉心内に装
荷される取替燃料の濃縮度を初装荷燃料の濃縮度よりも
高くする必要があり、この第2サイクルで装荷される取
替燃料の濃縮度は約3.5wt%とされている。なお、
この取替燃料の濃縮度は燃料の交換計画、すなわち各サ
イクルにおいて、炉心内に取替燃料を何体装荷するかに
より決定される。
In such a boiling water reactor, after the first cycle of operation, approximately 1/3 of the initially loaded fuel is replaced with replacement fuel and a second cycle of operation is performed, and after one cycle, the initial loading is continued. Approximately 1/3 of the fuel is replaced with replacement fuel and a third cycle of operation is performed. In the core of such a nuclear reactor, for example, in the second cycle, about two-thirds of the initially loaded fuel used in the first cycle is loaded and used as is, so in the second cycle, the core It is necessary to make the enrichment of the replacement fuel loaded in the tank higher than that of the initially loaded fuel, and the enrichment of the replacement fuel loaded in this second cycle is approximately 3.5 wt%. . In addition,
The enrichment of this replacement fuel is determined by the fuel replacement plan, that is, how many replacement fuels are loaded into the core in each cycle.

(発明が解決しようとする課題) このような運転方法において、初装荷燃料の航1/3は
1サイクルしか炉内に滞在せず、従って燃料は燃焼度の
低いまま炉外に取り出されてしまうことになる。そこで
、初装荷燃料の取出燃焼度を伸張させ、同時に、取替燃
料の装荷体数を減少させるため、第1回目の燃料交換時
に炉心からホり出された初装荷燃料を第2回目以降の燃
料交換時に、炉心内にあってより反応度の低いものと交
換する運転方法(初装荷燃料の再装荷)が行われている
が、取替燃料の装荷体数を減少させるためには必ずしも
十分ではなく、初装荷燃料の平均取出燃焼度の向上の観
点からも、まだ改善の余地が残されている。
(Problem to be solved by the invention) In this operating method, 1/3 of the initially loaded fuel stays in the reactor for only one cycle, and therefore the fuel is taken out of the reactor with a low burnup. It turns out. Therefore, in order to extend the removal burnup of the initial loading fuel and at the same time reduce the number of replacement fuel loads, the initial loading fuel that was pumped out from the reactor during the first fuel exchange is used for the second and subsequent fuel exchanges. At the time of fuel exchange, an operating method (reloading of the initially loaded fuel) is carried out in which the fuel is replaced with one that is in the core and has a lower reactivity, but this is not always sufficient to reduce the number of replacement fuels loaded. However, there is still room for improvement from the perspective of improving the average discharge burnup of the initially loaded fuel.

[発明の構成コ (課題を解決するための手段) 上記目的を達成するために、本発明は、初装荷燃料によ
り一定期間運転を行い、この後前記初装荷燃料の一部を
取替燃料に燃料交換する原子炉の運転方法において、少
なくとも第2サイクル終了後燃料交換のため取り出され
た前記初装荷燃料を第3サイクル終了後以降の燃料交換
時に、炉心内にあってより反応度の低い燃料と交換する
ようにしたことを特徴とする。
[Configuration of the Invention (Means for Solving the Problem) In order to achieve the above object, the present invention operates with the initially loaded fuel for a certain period of time, and then a part of the initially loaded fuel is used as replacement fuel. In a method of operating a nuclear reactor for refueling, at least the initially loaded fuel taken out for refueling after the end of the second cycle is replaced with fuel that is in the core and has a lower reactivity at the time of refueling after the end of the third cycle. The feature is that it can be exchanged with.

(作 用) 本発明の原子炉の運転方法によれば、少なくとも第2サ
イクル終了後燃料交換のため取り出された初装荷燃料を
、第3サイクル終了後以降の燃料交換時に炉心内にあっ
てより反応度の低い燃料と交換するので、取替燃料の装
荷体数を減少させるばかりでなく、初装荷燃料の平均取
出燃焼度も向上する。
(Function) According to the nuclear reactor operating method of the present invention, at least the initially loaded fuel taken out for fuel exchange after the end of the second cycle is stored in the reactor core at the time of fuel exchange after the end of the third cycle. Since the fuel is replaced with a fuel having a low reactivity, not only the number of replacement fuels to be loaded is reduced, but also the average discharged burnup of the initially loaded fuel is improved.

(実施例I) 本発明の実施例を、電気出力135万kW、燃料装荷体
数872体の原子炉を例に説明する。
(Example I) An example of the present invention will be described using a nuclear reactor with an electrical output of 1.35 million kW and a fuel loading of 872 bodies.

沸騰水型原子炉の立ち上がり時に炉心内に装荷される初
装荷燃料の濃縮度を3,1.wt%とする。
The enrichment of the initial fuel loaded into the reactor core at startup of a boiling water reactor is set to 3.1. Let it be wt%.

このような原子炉の炉心によれば、第1サイクル終了時
には制御棒を挿入したままの状態で原子炉が停止される
。そして第1サイクル終了時において初装荷燃料の中性
子無限増倍率は図のaとなる。ここで、図は燃焼度と中
性子無限増倍率の関係を示すものであり、実線は初装荷
燃料の場合破線は取替燃料の場合を示している。
According to such a nuclear reactor core, at the end of the first cycle, the reactor is stopped with the control rods still inserted. At the end of the first cycle, the neutron infinite multiplication factor of the initially loaded fuel becomes a in the figure. Here, the figure shows the relationship between burnup and infinite neutron multiplication factor, where the solid line shows the case of the initially loaded fuel and the broken line shows the case of the replacement fuel.

この第1サイクル終了時に、初装荷燃料のうち146体
を濃縮度3.5wt%の取替燃料と交換し、第2サイク
ルの運転を行なう。第2サイクル以降のサイクル終了時
には制御棒を全て引き抜いた状態で原子炉が停止される
At the end of this first cycle, 146 units of the initially loaded fuel are replaced with replacement fuel with an enrichment of 3.5 wt%, and a second cycle operation is performed. At the end of the second cycle and subsequent cycles, the reactor is shut down with all control rods pulled out.

第2サイクル終了後の燃料交換時には、炉心内にある初
装荷燃料の中性子無限増倍率は図のbとなり、炉内にあ
る初装荷燃料726体のうち460体が次のような方法
で交換される。すなわち、第1サイクル終了後に取り出
された初装荷燃料146体の中性子無限増倍率は図のa
に示すようにまだ燃焼余力を有するので、この146体
を炉心内に再装荷し、残り314体の初装荷燃料は取替
燃料と交換して、第3サイクルの運転が行われる。
When the fuel is replaced after the second cycle, the infinite neutron multiplication factor of the initial fuel in the reactor core becomes b in the figure, and 460 of the 726 initial fuels in the reactor are replaced in the following way. Ru. In other words, the neutron infinite multiplication factor of the 146 initially loaded fuels taken out after the end of the first cycle is a in the figure.
As shown in Figure 2, there is still a surplus of combustion power, so these 146 bodies are reloaded into the core, and the remaining 314 bodies' initially loaded fuel is replaced with replacement fuel, and a third cycle of operation is performed.

第3サイクル終了後の燃料交換時には、炉心内にある初
装荷燃料の中性子無限増倍率は図のCとなり、この炉心
内に残っていた初装荷燃料266体は全て次のように交
換される。すなわち、この266体のうち5体を、第2
サイクル終了時に取り出された初装荷燃料(中性子無限
増倍率が図のb)と交換し、残り261体を取替燃料と
交換して、第4サイクルの運転が行われる。
When the fuel is replaced after the third cycle, the neutron infinite multiplication factor of the initially loaded fuel in the reactor core becomes C in the diagram, and all 266 initially loaded fuels remaining in the core are replaced as follows. In other words, 5 of these 266 bodies were transferred to the second
At the end of the cycle, the initial loaded fuel (the infinite neutron multiplication factor is b in the figure) taken out is replaced with the fuel, and the remaining 261 bodies are replaced with replacement fuel, and the fourth cycle of operation is performed.

第4サイクル終了後の燃料交換では、第2サイクル終了
時に再装荷された146体と第3サイクル終了後に再装
荷された5体の初装荷燃料の中性子無限増倍率は図のC
であり、第1サイクル終了後に装荷された146体の取
替燃料の中性子無限増倍率は図のgとなることから、こ
れらの297体の燃料は図のbに示す第2サイクル終了
後に取り出された初装荷燃料の中性子無限増倍率よりも
小さくなる。このため、第2サイクル終了後に取り出さ
れた初装荷燃料を炉心内にあってより反応度の低い燃料
28体と交換し、残り269体は取替燃料と交換する。
In the fuel exchange after the end of the 4th cycle, the neutron infinite multiplication factor of the initially loaded fuel for the 146 bodies reloaded at the end of the 2nd cycle and the 5 bodies reloaded after the end of the 3rd cycle is C in the diagram.
Since the neutron infinite multiplication factor of the 146 replacement fuels loaded after the end of the first cycle is g in the figure, these 297 fuels are taken out after the end of the second cycle as shown in b in the figure. is smaller than the infinite neutron multiplication factor of the initially loaded fuel. For this reason, the initially loaded fuel removed after the second cycle is replaced with 28 pieces of fuel with lower reactivity in the reactor core, and the remaining 269 pieces are replaced with replacement fuel.

以降、同様にしてサイクル終了時の燃料交換において、
交換される燃料の一部は第2サイクル終了時に取り出さ
れた初装荷燃料と炉心内にあってより反応度の低い燃料
とを交換し、残りを取替燃料と交換する。
From then on, in the same way, when changing fuel at the end of the cycle,
A portion of the replaced fuel is used to replace the initially loaded fuel taken out at the end of the second cycle with fuel that is in the reactor core and has a lower reactivity, and the rest is replaced with replacement fuel.

以」二述べたような原子炉の運転方法によれば、原子炉
の立ち上がり時に装荷する初装荷燃料の平均取出燃焼度
が向−トするとともに取替燃料の取替体数を減らずこと
ができる。
According to the method of operating a nuclear reactor as described above, the average discharge burnup of the initial fuel loaded at the start-up of the reactor is increased, and the number of replacement fuels is not reduced. can.

すなわち、第1サイクル終r時に取り出された初装荷燃
料のみを再装荷する原子炉の運転方法では、初装荷燃料
を全く再装荷しない運転方法き比べ、初装荷燃料の平均
取出燃焼度は5.9%向上し、取替燃料の総装荷体数は
54体減少するにとどまるのに対し、本発明のように第
1サイクル終了時に取り出された初装荷燃料のみでなく
第2サイクル終了時に取り出された初装荷燃料をも再装
荷すれば、初装荷燃料平均取出燃焼度は28.2%向上
し、取替燃料の総装荷体数は、102体減少させること
ができる。
That is, in the reactor operating method in which only the initially loaded fuel removed at the end of the first cycle is reloaded, the average extracted burnup of the initially loaded fuel is 5.5% compared to the operating method in which the initially loaded fuel is not reloaded at all. 9% improvement, and the total number of replacement fuels loaded is reduced by only 54. However, unlike the present invention, not only the initially loaded fuel is removed at the end of the first cycle, but also the fuel removed at the end of the second cycle. If the initially loaded fuel is also reloaded, the average extracted burnup of the initially loaded fuel will improve by 28.2%, and the total number of replacement fuels loaded can be reduced by 102.

(実施例2) 籾袋6(j燃料の一部または全部の濃縮度をさらに高め
、例えば取替燃料と同じ3.5wt%とした炉心では、
第1サイクル終了時に初装荷燃料の交換を一切行わずに
第2サイクルの運転を行い、第2サイクル終了後初めて
初装荷燃料の一部を取替燃料と交換し、第3サイクルを
運転することができる。第3サイクル終了後以降の燃料
交換においては、第2サイクル終了後に取り出された初
装荷燃料を、炉心内にあってより反応度の低い燃料と交
換し、残りを取替燃料と交換する。以上では、第1サイ
クル終r後の燃料交換において、初装荷燃料が一切交換
されないが、実施例1と同様に第1サイクル終了後に初
装荷燃料の一部を取替燃料と交換して第2サイクルの運
転を行い、第2サイクル終了後の燃料交換において、第
1サイクル終了時に取り出された初装荷燃料を、炉心内
にあってより反応度の低い燃料と交換し、残りを取替燃
料と交換して、第3サイクルの運転を行ってもよい。
(Example 2) In a core where the enrichment of part or all of the rice bag 6 (j fuel is further increased, for example, to 3.5 wt%, which is the same as the replacement fuel,
At the end of the first cycle, the second cycle is operated without any exchange of the initially loaded fuel, and after the second cycle, part of the initially loaded fuel is replaced with replacement fuel, and the third cycle is operated. I can do it. In the fuel exchange after the end of the third cycle, the initially loaded fuel taken out after the end of the second cycle is replaced with fuel that is in the core and has a lower reactivity, and the remaining fuel is replaced with replacement fuel. In the above, in the fuel exchange after the end of the first cycle, the initially loaded fuel is not replaced at all, but as in Example 1, after the end of the first cycle, a part of the initially loaded fuel is exchanged with the replacement fuel and the second fuel is replaced. The cycle is operated, and in the fuel exchange after the second cycle, the initial fuel loaded at the end of the first cycle is replaced with fuel that is in the core and has a lower reactivity, and the remainder is used as replacement fuel. You may replace it and perform the third cycle operation.

[発明の効果] 以上説明したように、本発明によれば少なくとも第2サ
イクル終了時に取り出された初装荷燃料を炉心内にあっ
てより反応度の低い燃料と交換するために、初装荷燃料
の平均取出燃焼度が大幅に向上するだけでなく、取替燃
料への交換体数も減らすことができるので燃料を効率的
に使用できる。
[Effects of the Invention] As explained above, according to the present invention, in order to replace the initially loaded fuel taken out at least at the end of the second cycle with fuel that is in the core and has a lower reactivity, the initially loaded fuel is removed. Not only is the average extracted burnup significantly improved, but the number of replacement fuels can also be reduced, so fuel can be used efficiently.

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

図は本発明における燃焼度と初装荷燃料および取替燃料
の中性子無限増倍率との関係を示すグラフである。 (8733)代理人 弁理士 猪 股 祥 晃(ばか 
1名) JEc 2ΔEc 燃焼度 3ΔEc jEc
The figure is a graph showing the relationship between the burnup and the neutron infinite multiplication factors of the initially loaded fuel and the replacement fuel in the present invention. (8733) Agent Patent Attorney Yoshiaki Inomata (Baka
1 person) JEc 2ΔEc Burnup 3ΔEc jEc

Claims (1)

【特許請求の範囲】[Claims] (1)初装荷燃料により一定期間運転を行い、この後前
記初装荷燃料の一部を取替燃料に燃料交換する原子炉の
運転方法において、少なくとも第2サイクル終了後燃料
交換のため取り出された前記初装荷燃料を第3サイクル
終了後以降の燃料交換時に、炉心内にあってより反応度
の低い燃料と交換する原子炉の運転方法。
(1) In a method of operating a nuclear reactor in which the reactor is operated for a certain period of time using the initially loaded fuel and then a portion of the initially loaded fuel is replaced with replacement fuel, the reactor is removed for fuel replacement after at least the second cycle. A method for operating a nuclear reactor, in which the initially loaded fuel is replaced with a fuel with lower reactivity within the reactor core during fuel replacement after the end of the third cycle.
JP2007210A 1990-01-18 1990-01-18 Operating method of reactor Pending JPH03214097A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP2007210A JPH03214097A (en) 1990-01-18 1990-01-18 Operating method of reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP2007210A JPH03214097A (en) 1990-01-18 1990-01-18 Operating method of reactor

Publications (1)

Publication Number Publication Date
JPH03214097A true JPH03214097A (en) 1991-09-19

Family

ID=11659643

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2007210A Pending JPH03214097A (en) 1990-01-18 1990-01-18 Operating method of reactor

Country Status (1)

Country Link
JP (1) JPH03214097A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5787139A (en) * 1996-05-20 1998-07-28 Hitachi, Ltd. Fuel loading method
JP2006234396A (en) * 2005-02-22 2006-09-07 Nuclear Fuel Ind Ltd Reactor fuel operation method

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5787139A (en) * 1996-05-20 1998-07-28 Hitachi, Ltd. Fuel loading method
JP2006234396A (en) * 2005-02-22 2006-09-07 Nuclear Fuel Ind Ltd Reactor fuel operation method

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