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JPH0524476B2 - - Google Patents
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JPH0524476B2 - - Google Patents

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Publication number
JPH0524476B2
JPH0524476B2 JP60044901A JP4490185A JPH0524476B2 JP H0524476 B2 JPH0524476 B2 JP H0524476B2 JP 60044901 A JP60044901 A JP 60044901A JP 4490185 A JP4490185 A JP 4490185A JP H0524476 B2 JPH0524476 B2 JP H0524476B2
Authority
JP
Japan
Prior art keywords
control rod
neutron absorption
fuel
absorption effect
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.)
Expired - Lifetime
Application number
JP60044901A
Other languages
Japanese (ja)
Other versions
JPS61204586A (en
Inventor
Masaaki Yoshioka
Katsuaki Takai
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 JP60044901A priority Critical patent/JPS61204586A/en
Publication of JPS61204586A publication Critical patent/JPS61204586A/en
Publication of JPH0524476B2 publication Critical patent/JPH0524476B2/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
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)

Description

【発明の詳細な説明】[Detailed description of the invention]

〔産業上の利用分野〕 本発明は原子炉の炉心に関し、更に詳しくは中
性子に対する反応効果が大きく異なる二種類以上
の燃料を同時に装荷した炉心の制御棒クラスタの
配置方式に関する。 〔従来の技術〕 酸化ウラン燃料、ガドリニア含有酸化ウラン燃
料、或いはウラン・プルトニウム混合酸化物燃料
(MOX:Mixed Oxide)など、中性子に対する
反応効果が大きく異なる二種以上の燃料を同時に
装荷した炉心では、原子炉を制御棒によつて安全
に停止するため、および制御棒に故障が生じても
炉の安全性を確保するために、従来より燃料種別
構成を含む炉心燃料装荷方式に種々の制限が付さ
れており、設計の柔軟性に欠ける問題点があつ
た。 一例として、加圧水型軽水炉(PWR)に酸化
ウラン燃料とMOX燃料を同時に装荷する場合を
挙げると以下の通りである。 すなわち、まず炉心の燃料装荷方式を決定する
場合、制御棒クラスタのうちの一体が固着等によ
り炉心に挿入できなくなつても残りの制御棒によ
り炉の停止が余裕をもつて可能であると共に、制
御棒の挿入時に制御棒クラスタのうちの一体が炉
から飛び出しても炉が損傷を受けないという条件
を満たす必要があるが、そのためには、各制御棒
クラスタの中性子吸収効果が、その挿入対象の燃
料の中性子吸収効果と比べて差が無いのが望まし
い。 従来より、炉心に配置する制御棒クラスタは一
種類のものを用いるのが通常であるが、酸化ウラ
ン燃料とMOX燃料とを同時装荷する場合は、
MOX燃料の中性子吸収効果のほうが酸化ウラン
燃料のそれよりも大きいので、同一種類の制御棒
クラスタではその中性子吸収効果に差ができてし
まい、燃料の装荷方式如何によつては前述の炉停
止余裕及び安全上の条件を満足できない場合が生
じるという問題点がある。 〔解決すべき問題点〕 本発明は、前述の従来技術の問題点を解決し
て、燃料装荷方式に応じて制御棒クラスタの種類
及び配置を変えることにより、原子炉の安全性を
確保したうえで燃料の装荷方式の制限を緩和し、
燃料装荷方式に柔軟性を持たせた原子炉炉心を提
供しようとするものである。 〔問題点の解決手段と作用〕 本発明によれば、中性子に対する反応効果が大
きく異なる複数種類の燃料を同時に装荷してなる
原子炉炉心を予め定められた制御棒クラスタ位置
に、中性子吸収効果の異なる二種類以上の制御棒
クラスタが、燃料の装荷方式に応じて最適の原子
炉安全性を与えるように配置される。この場合、
各制御棒クラスタの中性子吸収効果が、その挿入
対象の燃料の中性子吸収効果となるべく差が生じ
ないように配置パターンが選定され、ひとつの実
施態様によれば、中性子吸収効果の大きい燃料領
域の挿入位置に中性子吸収効果の大きい制御棒ク
ラスタが配置され、中性子吸収効果の小さい燃料
領域の挿入位置に中性子吸収効果の小さい制御棒
クラスタが配置される。 本発明においては、異種燃料の同時装荷による
炉心内での中性子吸収効果の差が異種制御棒クラ
スタの相補的な配置により均一化され、従つて充
分な炉停止余裕を確保し且つ出力ピーキングの平
坦化により高い安全性を保持したまま、燃料装荷
方式に柔軟性を持たせることが可能である。 本発明の一層の理解のために本発明の実施例を
示せば以下の通りである。 〔実施例〕 第1〜3図は、加圧水型原子炉(PWR)の炉
心にMOX燃料を60体、酸化ウラン燃料を61体装
荷した場合の本発明の実施例を示すもので、第1
図は炉心内の制御棒クラスタ挿入位置を○印で示
した横断面模式図、第2図はMOX燃料(×印)
と酸化ウラン燃料(無印)の装荷方式を示す横断
面模式図、第3図は本発明に従つて配置した異種
の制御棒クラスタ(○印および◎印)の挿入位置
を示す横断面模式図である。 第1図に示したように予め定められた制御棒ク
ラスタ挿入位置に対して、燃料装荷は第2図に示
したパターンで行われる。ここで、各挿入位置に
同種の制御棒クラストを挿入しても、炉心周辺部
の酸化ウラン燃料領域に挿入される制御棒クラス
タの中性子吸収効果が、炉心中央部のMOX燃料
領域に挿入される制御棒クラスタのそれに対して
相対的に大きくなるため、周辺部の制御棒クラス
タの飛出事故等が生じた際にその中性子吸収効果
の消失度合が大きく、急激な反応度増加を招いて
激しい出力ピーキングを起こすなど、原子炉の安
全性を確保することができない。これに対して本
発明では第3図に示すように中性子吸収効果の異
なる複数種の制御棒クラスタを異種燃料の装荷方
式に合せて配置して挿入するものである。すなわ
ち第3図の実施例では、中央部の中性子吸収効果
の大きいMOX燃料11の領域内に中性子吸収効
果の大きい制御棒クラスタ21を5体配し、また
中央部の周辺近傍にある4体のMOX燃料11a
〜11dに対しても各1体ずつの同様の制御棒ク
ラスタ21を配し、さらに中性子吸収効果が比較
的小さい酸化ウラン燃料12によつて形成される
炉心周辺部領域には、前記制御棒クラスタ21よ
りも中性子吸収効果の小さい別種の制御棒クラス
タ22を合計20体略方形状している。 第2図のような酸化ウラン燃料とMOX燃料を
略半々に配分して装荷したPWRにおいて、全て
の制御棒クラスタを同種のものとした場合と本発
明に従つて中性子吸収効果の異なる二種類の制御
クラスタを用いた場合との炉停止余裕とクラスタ
の飛出事故時の出力ピーキングの比較の一例を示
せば次表の通りであり、表中に併せて示した安全
性に対する制限値に照して本発明によれば同種制
御棒クラスタの使用では達成できないような異種
燃料装荷方式での炉の安全性を確保できることが
判る。
[Industrial Field of Application] The present invention relates to a nuclear reactor core, and more particularly to a method for arranging control rod clusters in a reactor core simultaneously loaded with two or more types of fuel having significantly different reaction effects on neutrons. [Prior art] In a reactor core loaded simultaneously with two or more types of fuel that have significantly different reaction effects against neutrons, such as uranium oxide fuel, gadolinia-containing uranium oxide fuel, or uranium-plutonium mixed oxide fuel (MOX: Mixed Oxide), In order to safely shut down the reactor using the control rods, and to ensure the safety of the reactor even if a control rod fails, various restrictions have been placed on the core fuel loading system, including the fuel type configuration. The problem was that the design lacked flexibility. As an example, the case where uranium oxide fuel and MOX fuel are simultaneously loaded into a pressurized water reactor (PWR) is as follows. In other words, when determining the fuel loading method for the reactor core, it is necessary to ensure that even if one of the control rod clusters cannot be inserted into the reactor core due to sticking or the like, the reactor can be shut down with sufficient time using the remaining control rods, and It is necessary to satisfy the condition that the reactor will not be damaged even if one of the control rod clusters flies out of the reactor when the control rods are inserted. To do this, the neutron absorption effect of each control rod cluster must be It is desirable that there be no difference in the neutron absorption effect compared to the neutron absorption effect of the fuel. Traditionally, it has been normal to use one type of control rod cluster placed in the reactor core, but when loading uranium oxide fuel and MOX fuel at the same time,
Since the neutron absorption effect of MOX fuel is greater than that of uranium oxide fuel, there is a difference in the neutron absorption effect between control rod clusters of the same type, and depending on the fuel loading method, the above-mentioned reactor shutdown margin may be reduced. There are also problems in that safety conditions may not be satisfied. [Problems to be Solved] The present invention solves the above-mentioned problems of the prior art and changes the type and arrangement of control rod clusters depending on the fuel loading method, thereby ensuring the safety of a nuclear reactor. Relaxing restrictions on fuel loading methods,
The aim is to provide a nuclear reactor core with flexibility in fuel loading methods. [Means for Solving Problems and Effects] According to the present invention, a reactor core with a neutron absorption effect is placed at a predetermined control rod cluster position in a nuclear reactor core which is simultaneously loaded with a plurality of types of fuel having greatly different reaction effects on neutrons. Two or more different types of control rod clusters are arranged to provide optimal reactor safety depending on the fuel loading scheme. in this case,
The arrangement pattern is selected so that the neutron absorption effect of each control rod cluster differs as little as possible from the neutron absorption effect of the fuel into which it is inserted, and according to one embodiment, a fuel region with a large neutron absorption effect is inserted. A control rod cluster with a large neutron absorption effect is placed at a position where a control rod cluster with a small neutron absorption effect is inserted, and a control rod cluster with a small neutron absorption effect is placed at an insertion position of a fuel region with a small neutron absorption effect. In the present invention, differences in neutron absorption effects within the reactor core due to simultaneous loading of different types of fuel are equalized by the complementary arrangement of different types of control rod clusters, thereby ensuring sufficient reactor shutdown margin and flattening power peaking. It is possible to provide flexibility in the fuel loading method while maintaining a high level of safety. Examples of the present invention will be shown below for a better understanding of the present invention. [Example] Figures 1 to 3 show an example of the present invention when 60 units of MOX fuel and 61 units of uranium oxide fuel are loaded in the core of a pressurized water reactor (PWR).
The figure is a schematic cross-sectional view showing the control rod cluster insertion position in the reactor core with ○ marks, and Figure 2 shows MOX fuel (x marks).
Fig. 3 is a schematic cross-sectional view showing the loading method of uranium oxide fuel (unmarked), and Fig. 3 is a schematic cross-sectional view showing the insertion positions of different control rod clusters (marked with ○ and ◎) arranged according to the present invention. be. As shown in FIG. 1, fuel loading is performed in the pattern shown in FIG. 2 with respect to the control rod cluster insertion position determined in advance. Here, even if the same type of control rod crust is inserted at each insertion position, the neutron absorption effect of the control rod cluster inserted into the uranium oxide fuel region at the periphery of the core will be absorbed by the MOX fuel region at the center of the core. Because the control rod cluster is relatively large compared to that of the control rod cluster, in the event of an ejection accident of the control rod cluster in the surrounding area, the degree of loss of its neutron absorption effect is large, leading to a rapid increase in reactivity and severe output. The safety of the reactor cannot be ensured due to peaking, etc. In contrast, in the present invention, as shown in FIG. 3, a plurality of types of control rod clusters having different neutron absorption effects are arranged and inserted in accordance with the loading method of different types of fuel. That is, in the embodiment shown in FIG. 3, five control rod clusters 21 having a large neutron absorption effect are arranged in the area of the MOX fuel 11 having a large neutron absorption effect in the center, and four control rod clusters 21 near the periphery of the center are arranged. MOX fuel 11a
Similar control rod clusters 21 are arranged for each of the control rod clusters 21 to 11d, and the control rod clusters 21 are arranged in the peripheral region of the reactor core formed by the uranium oxide fuel 12, which has a relatively small neutron absorption effect. A total of 20 control rod clusters 22 of a different type having a smaller neutron absorption effect than the control rod clusters 21 have a substantially rectangular shape. In a PWR loaded with uranium oxide fuel and MOX fuel distributed approximately half and half, as shown in Figure 2, there are two types of control rod clusters, one in which all the control rod clusters are of the same kind, and the other in accordance with the present invention, which have different neutron absorption effects. An example of a comparison of the reactor shutdown margin and output peaking in the event of a cluster ejection accident when using a control cluster is shown in the table below. It can be seen that according to the present invention, the safety of the reactor can be ensured in a dissimilar fuel loading system, which cannot be achieved with the use of homogeneous control rod clusters.

【表】【table】

〔発明の効果〕〔Effect of the invention〕

以上に述べたように、本発明によれば、中性子
に対する反応効果が異なる複数種の燃料を同時に
装荷する炉心において、その燃料装荷方式に応じ
て中性子吸収効果の異なる複数種の制御棒クラス
タを配置するので、炉の安全性を充分確保したう
えで異種燃料装荷方式の制限を緩和でき、その柔
軟化が達成できるものである。
As described above, according to the present invention, in a reactor core where multiple types of fuel with different reaction effects to neutrons are simultaneously loaded, multiple types of control rod clusters with different neutron absorption effects are arranged according to the fuel loading method. Therefore, while ensuring the safety of the reactor, the restrictions on different fuel loading methods can be relaxed, and flexibility can be achieved.

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

図面は本発明の一実施例に係るもので、第1図
は炉心内の制御棒クラスタの所定挿入位置を○印
で示した炉心横断面模式図、第2図はMOX燃料
(×印)と酸化ウラン燃料(無印)の装荷方式を
示す炉心横断面模式図、第3図は本発明に従つて
配置した異種制御棒クラスタの挿入位置を示す炉
心横断面模式図である。 11,11a〜d:MOX燃料、12:酸化ウ
ラン燃料、21:中性子吸収効果の比較的大きい
制御棒クラスタ、22:中性子吸収効果の比較的
小さい制御棒クラスタ。
The drawings relate to one embodiment of the present invention, and Fig. 1 is a schematic cross-sectional view of the reactor core with O marks indicating the predetermined insertion positions of control rod clusters in the reactor core, and Fig. 2 shows MOX fuel (x marks) and FIG. 3 is a schematic cross-sectional view of the core showing the loading method of uranium oxide fuel (unmarked), and FIG. 3 is a schematic cross-sectional view of the core showing the insertion positions of heterogeneous control rod clusters arranged according to the present invention. 11, 11a-d: MOX fuel, 12: Uranium oxide fuel, 21: Control rod cluster with relatively large neutron absorption effect, 22: Control rod cluster with relatively small neutron absorption effect.

Claims (1)

【特許請求の範囲】 1 中性子に対する反応効果が大きく異なる酸化
ウランとMOX燃料とを同時に装荷してなる原子
炉炉心において、 前記酸化ウランとMOX燃料との装荷方式に応
じて中性子吸収効果の相違する制御棒クラスタの
相補的な配置により、中性子吸収効果の差が均一
化するように、 前記中性子吸収効果の大きいMOX燃料領域の
挿入位置に中性子吸収効果の大きい制御棒クラス
タを配置し、 前記中性子吸収効果の小さい酸化ウラン燃料領
域の挿入位置に中性子吸収効果の小さい制御棒ク
ラスタを配置してなることを特徴とする原子炉炉
心。
[Scope of Claims] 1. In a nuclear reactor core in which uranium oxide and MOX fuel are simultaneously loaded, which have greatly different reaction effects against neutrons, the neutron absorption effects differ depending on the loading method of the uranium oxide and MOX fuel. A control rod cluster with a large neutron absorption effect is arranged at the insertion position of the MOX fuel region with a large neutron absorption effect so that the difference in neutron absorption effect is equalized by the complementary arrangement of the control rod clusters, A nuclear reactor core characterized in that a control rod cluster having a small neutron absorption effect is arranged at an insertion position of a uranium oxide fuel region having a small effect.
JP60044901A 1985-03-08 1985-03-08 Nuclear reactor core Granted JPS61204586A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP60044901A JPS61204586A (en) 1985-03-08 1985-03-08 Nuclear reactor core

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP60044901A JPS61204586A (en) 1985-03-08 1985-03-08 Nuclear reactor core

Publications (2)

Publication Number Publication Date
JPS61204586A JPS61204586A (en) 1986-09-10
JPH0524476B2 true JPH0524476B2 (en) 1993-04-07

Family

ID=12704374

Family Applications (1)

Application Number Title Priority Date Filing Date
JP60044901A Granted JPS61204586A (en) 1985-03-08 1985-03-08 Nuclear reactor core

Country Status (1)

Country Link
JP (1) JPS61204586A (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP4653342B2 (en) * 2001-06-14 2011-03-16 原子燃料工業株式会社 Boiling water reactor core
GB2590102A (en) * 2020-07-24 2021-06-23 Rolls Royce Plc Refuelling and/or storage neutron-absorbing rods

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59116578A (en) * 1982-12-24 1984-07-05 株式会社日立製作所 Reactor

Also Published As

Publication number Publication date
JPS61204586A (en) 1986-09-10

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