JPH05240982A - Fuel assembly for variable pressure loss pressurized water reactor - Google Patents

Fuel assembly for variable pressure loss pressurized water reactor

Info

Publication number
JPH05240982A
JPH05240982A JP3146988A JP14698891A JPH05240982A JP H05240982 A JPH05240982 A JP H05240982A JP 3146988 A JP3146988 A JP 3146988A JP 14698891 A JP14698891 A JP 14698891A JP H05240982 A JPH05240982 A JP H05240982A
Authority
JP
Japan
Prior art keywords
pressure loss
fuel assembly
fuel
power
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.)
Withdrawn
Application number
JP3146988A
Other languages
Japanese (ja)
Inventor
Masaaki Yoshikuni
正明 吉国
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 JP3146988A priority Critical patent/JPH05240982A/en
Publication of JPH05240982A publication Critical patent/JPH05240982A/en
Withdrawn legal-status Critical Current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 increase flow rate of coolant in the core center with high power, mitigate power peaking limit and obtain a fuel loading pattern with improved neutron economy. CONSTITUTION:On the lower surface of lower nozzle 1 on a fuel assembly, a pressure loss control plate 3 is fixed with fixing screws 6 in the four corners detachably. By attaching the pressure loss control plates 3 to the fuel assemblies, water channel cross sctional area is reduced to increase the pressure loss. This fuel assembly with the pressure loss control plate 3 is arranged in the core periphery where power is low and heat removal is not a problem. By this, the coolant flow is increased in the fuel assembly in the core center where power is high to mitigate power peaking limit and a fuel loading pattern with improved neutron economy is obtained. As the pressure loss control plate is detachable, it can be removed when the assembly is used in the core center with high power in the next cycle.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は、加圧水型原子炉用燃料
集合体の圧損を調節可能な構成にすることに関するもの
である。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a pressure water reactor fuel assembly having an adjustable pressure loss.

【0002】[0002]

【従来の技術】加圧水型原子炉(PWR)においては、
各燃料集合体への入口流量は均一であり、各燃料集合体
の圧損も等しいため、出力の高低にかかわらず流量もほ
ぼ等しい。このため、熱除去が問題となる特定の燃料集
合体への流量を増やすことができなかった。また、下部
ノズルの構造を変更してしまうと、燃料集合体の位置は
燃料交換時に変わるために、圧損の炉心内分布を出力ピ
ーキングの状況に応じて自由かつ適正に調節することが
できないという問題があった。
2. Description of the Related Art In a pressurized water reactor (PWR),
The inlet flow rate to each fuel assembly is uniform, and the pressure loss of each fuel assembly is also equal, so that the flow rate is almost equal regardless of the output level. Therefore, it was not possible to increase the flow rate to a specific fuel assembly in which heat removal is a problem. Further, if the structure of the lower nozzle is changed, the position of the fuel assembly will change at the time of refueling, so the core distribution of pressure loss cannot be adjusted freely and appropriately according to the power peaking situation. was there.

【0003】また、PWRでは炉心の燃料装荷パターン
を工夫することにより、中性子漏洩量を減少させて炉心
周辺部の出力が低く、炉心中央部の出力が高くなること
が多いため、炉心の出力ピーキングが大きくなり、局所
的な熱除去の制限が原子炉運転上の問題となっていた。
Further, in the PWR, by devising the fuel loading pattern of the core, the amount of neutron leakage is reduced, the output in the peripheral portion of the core is low, and the output in the central portion of the core is high in many cases. Has become a problem, and the limitation of local heat removal has been a problem in reactor operation.

【0004】[0004]

【発明が解決しようとする課題】解決しようとする問題
点は、PWR用燃料集合体の圧損を燃料交換時に可変に
調節することにより常に出力ピーキングの大きい燃料集
合体の冷却水流量を増やし、中性子の漏洩が少なく、か
つ安全な装荷パターンを可能とすることである。
The problem to be solved is to variably adjust the pressure loss of the PWR fuel assembly at the time of refueling so as to increase the cooling water flow rate of the fuel assembly having a large output peaking and It is possible to realize a safe loading pattern with little leakage.

【0005】[0005]

【課題を解決するための手段】本発明は、上述の課題を
解決するために、図1(A)の下部ノズル1(図2のP
WR用燃料集合体Fの下部ノズルの斜視図)に、圧損調
節板3(下部ノズルの流水孔2と外径がほぼ同一で、中
心に通水の穴5を有する圧損調節素子4が配置され、四
隅に固定用ネジ穴6が設けてある)を下部ノズル1の下
面の固定用ネジ穴に取外し可能なように取り付けた燃料
集合体とした。上記圧損調節板を燃料集合体に取り付け
て水路断面積を小さくして圧損を増やすことにし、そし
てこの圧損調節板を取り付けた燃料集合体を出力が低
く、熱除去があまり問題とならない炉心周辺部に配置す
ることにした。
In order to solve the above problems, the present invention is directed to a lower nozzle 1 (P in FIG. 2) of FIG.
A pressure loss adjusting plate 3 (having a diameter substantially the same as that of the water flow hole 2 of the lower nozzle and having a water passage hole 5 at the center thereof) is arranged in the lower nozzle of the fuel assembly F for WR. The fixing screw holes 6 are provided at the four corners) to the fixing screw holes on the lower surface of the lower nozzle 1 so as to be removably attached. The pressure loss adjusting plate is attached to the fuel assembly to reduce the cross-sectional area of the water channel to increase the pressure loss, and the fuel assembly to which the pressure loss adjusting plate is attached has a low output and the core peripheral portion where heat removal is not a serious problem. I decided to place it.

【0006】[0006]

【作用】圧損調節板を取り付けた燃料集合体を出力が低
く熱除去があまり問題とならない炉心周辺部に配置する
ことにより、炉心周辺部の流量を減少し、その減少分が
圧損調節板を取り付けていない出力の高い炉心中央部の
燃料集合体の熱除去にまわるため、炉心全体の熱的制限
に対する余裕が大きくなる。
[Function] By arranging the fuel assembly having the pressure loss adjusting plate in the peripheral portion of the core where the output is low and heat removal is not a serious problem, the flow rate in the peripheral portion of the core is reduced, and the reduced amount is attached to the pressure loss adjusting plate. Since it is related to the heat removal of the fuel assembly in the central part of the core, which has a high output, the margin for the thermal limitation of the entire core becomes large.

【0007】この圧損調節板は取外し可能なため、次サ
イクルで出力の高くなる炉心中央部に装荷される場合に
は、燃料交換時に取外して使用できる。
Since this pressure loss adjusting plate can be removed, it can be removed and used at the time of refueling when it is loaded in the central portion of the core where the output becomes high in the next cycle.

【0008】[0008]

【実施例】1次,2次冷却系の熱交換システムが3つあ
る原子炉即ち3ループ炉心(157燃料集合体により構
成)の最外周燃料集合体36体の下部ノズルの圧損を5
0%増やした場合に解析によれば、中央部燃料集合体の
流量は約10%増加し、出力ピーキング制限を約5%緩
和させることができる。これにより熱的安全余裕を減じ
ることなく、中性子の漏洩の少ない中性子経済の向上し
た燃料装荷パターンを採用できる。
EXAMPLE A reactor having three primary and secondary cooling heat exchange systems, namely a three-loop core (consisting of 157 fuel assemblies), has a pressure loss of 5 at the lower nozzle of the outermost fuel assembly 36.
According to the analysis when increasing by 0%, the flow rate of the central fuel assembly is increased by about 10%, and the output peaking limit can be relaxed by about 5%. This makes it possible to adopt a fuel loading pattern with improved neutron economy with less neutron leakage without reducing the thermal safety margin.

【0009】この圧損調節板は、例えば図1(B)のよ
うに下部ノズル1(図1(A))の下面に取り付け可能
な外寸を有し、また該調節板3には下部ノズルの流水孔
2に対応した位置に穴が設けられ、この穴の箇所の上面
には該流水孔2にかん合できる外径で、かつ圧損を増加
させる量に応じた所要の内径を有する円筒状の圧損調節
素子4が多数固定されている。
The pressure loss adjusting plate has an outer size that can be attached to the lower surface of the lower nozzle 1 (FIG. 1A) as shown in FIG. 1B, and the adjusting plate 3 has a lower nozzle size. A hole is provided at a position corresponding to the water flow hole 2, and a cylindrical shape having an outer diameter that can be fitted into the water flow hole 2 and a required inner diameter according to the amount of increasing the pressure loss is provided on the upper surface of the hole. A large number of pressure loss adjusting elements 4 are fixed.

【0010】圧損調節板3の下部ノズル1への取り付け
は、例えば下部ノズル下面にネジで固定してもよく、こ
のため四隅に固定用ネジ穴6を有している。取り外すに
は燃料交換時にこのネジを解除すればよい。圧損調節板
はこの例に限定されるものではなく、下部ノズルの形状
に応じて種々の形態のものが考えられることは言うまで
もない。
The pressure loss adjusting plate 3 may be attached to the lower nozzle 1 by, for example, fixing it to the lower surface of the lower nozzle with screws. For this reason, there are fixing screw holes 6 at the four corners. To remove it, just unscrew this screw when refueling. It goes without saying that the pressure loss adjusting plate is not limited to this example, and various forms can be considered depending on the shape of the lower nozzle.

【0011】[0011]

【発明の効果】以上説明したように、本発明の圧損可変
PWR用燃料集合体は、圧損調節板を下部ノズル下面に
取り付けたものを出力の低い最外周燃料集合体に配置す
ることによって、出力の高い炉心中央部の冷却水流量を
増加し、出力ピーキングの制限緩和、中性子経済の向上
した燃料装荷パターンを得ることができる。
As described above, according to the fuel assembly for variable pressure loss PWR of the present invention, the one having the pressure loss adjusting plate attached to the lower surface of the lower nozzle is arranged in the outermost fuel assembly having a low output, so that the fuel output can be improved. It is possible to increase the flow rate of the cooling water in the central part of the high core, relax the restriction of power peaking, and obtain a fuel loading pattern with improved neutron economy.

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

【図1】(A)圧損調節板を取り付けるための下部ノズ
ルの説明図である。
FIG. 1A is an explanatory diagram of a lower nozzle for mounting a pressure loss adjusting plate.

【図1】(B)圧損調節板の構成説明図である。FIG. 1 (B) is a structural explanatory view of a pressure loss adjusting plate.

【図2】PWR用燃料集合体の説明図である。FIG. 2 is an explanatory diagram of a PWR fuel assembly.

【符号の説明】[Explanation of symbols]

1 下部ノズル 2 下部ノズル流水孔 3 圧損調節板 4 圧損調節素子 5 圧損調節素子の通水穴 6 固定用ネジ穴 F PWR用燃料集合体 1 Lower Nozzle 2 Lower Nozzle Flow Hole 3 Pressure Loss Adjusting Plate 4 Pressure Loss Adjusting Element 5 Water Passage Hole for Pressure Loss Adjusting Element 6 Fixing Screw Hole F PWR Fuel Assembly

Claims (1)

【特許請求の範囲】[Claims] 【請求項1】 加圧水型原子炉用燃料集合体において、
通水穴を中心に有する円筒状の圧損調節素子を配した圧
損調節板を、該調節板に設けたネジ穴等を用いて、複数
の流水孔を有する下部ノズルの下面に取外し可能に装着
してなることを特徴とする圧損可変加圧水型原子炉用燃
料集合体。
1. A fuel assembly for a pressurized water reactor,
A pressure loss adjusting plate having a cylindrical pressure loss adjusting element having a water passage hole at the center is detachably attached to the lower surface of the lower nozzle having a plurality of water flow holes by using screw holes provided in the adjusting plate. A variable pressure loss pressurized water reactor fuel assembly characterized in that:
JP3146988A 1991-03-07 1991-03-07 Fuel assembly for variable pressure loss pressurized water reactor Withdrawn JPH05240982A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP3146988A JPH05240982A (en) 1991-03-07 1991-03-07 Fuel assembly for variable pressure loss pressurized water reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP3146988A JPH05240982A (en) 1991-03-07 1991-03-07 Fuel assembly for variable pressure loss pressurized water reactor

Publications (1)

Publication Number Publication Date
JPH05240982A true JPH05240982A (en) 1993-09-21

Family

ID=15420080

Family Applications (1)

Application Number Title Priority Date Filing Date
JP3146988A Withdrawn JPH05240982A (en) 1991-03-07 1991-03-07 Fuel assembly for variable pressure loss pressurized water reactor

Country Status (1)

Country Link
JP (1) JPH05240982A (en)

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0862185A1 (en) * 1997-02-28 1998-09-02 Siemens Power Corporation Water channel flow control in a nuclear fuel assembly
EP2400502A2 (en) 2010-06-25 2011-12-28 Mitsubishi Heavy Industries, Ltd. Pressure-loss adjusting member and nuclear reactor
EP2402954A2 (en) 2010-06-29 2012-01-04 Mitsubishi Heavy Industries, Ltd. Pressure-loss adjusting-member installation tool
EP2418649A2 (en) 2010-07-13 2012-02-15 Mitsubishi Heavy Industries Pressure-loss adjusting member and reactor

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0862185A1 (en) * 1997-02-28 1998-09-02 Siemens Power Corporation Water channel flow control in a nuclear fuel assembly
EP2400502A2 (en) 2010-06-25 2011-12-28 Mitsubishi Heavy Industries, Ltd. Pressure-loss adjusting member and nuclear reactor
EP2400502A3 (en) * 2010-06-25 2012-06-06 Mitsubishi Heavy Industries, Ltd. Pressure-loss adjusting member and nuclear reactor
EP2402954A2 (en) 2010-06-29 2012-01-04 Mitsubishi Heavy Industries, Ltd. Pressure-loss adjusting-member installation tool
US8640327B2 (en) 2010-06-29 2014-02-04 Mitsubishi Heavy Industries, Ltd. Pressure-loss adjusting-member installation tool
EP2418649A2 (en) 2010-07-13 2012-02-15 Mitsubishi Heavy Industries Pressure-loss adjusting member and reactor

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Legal Events

Date Code Title Description
A300 Withdrawal of application because of no request for examination

Free format text: JAPANESE INTERMEDIATE CODE: A300

Effective date: 19980514