JPS60131488A - Light-water cooling low deceleration reactor - Google Patents
Light-water cooling low deceleration reactorInfo
- Publication number
- JPS60131488A JPS60131488A JP58241455A JP24145583A JPS60131488A JP S60131488 A JPS60131488 A JP S60131488A JP 58241455 A JP58241455 A JP 58241455A JP 24145583 A JP24145583 A JP 24145583A JP S60131488 A JPS60131488 A JP S60131488A
- Authority
- JP
- Japan
- Prior art keywords
- control rod
- fuel
- core
- follower
- rods
- 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
Links
Classifications
-
- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Motor Or Generator Cooling System (AREA)
- Physical Or Chemical Processes And Apparatus (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】
本発明は、高転換型軽水冷却加圧水型原子炉等において
、炉心および炉内構造物の改善を図った軽水冷却低減速
型原子炉に関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a light water-cooled low moderation nuclear reactor in which the reactor core and reactor internal structures are improved in high conversion light water-cooled pressurized water reactors and the like.
従来の加圧水型軽水炉の制御棒は、燃料棒とほぼ伺程の
被覆合金棒を制御棒要素として、燃料集合体内置分散し
た１本の燃料棒を置換した制御棒案内シンプル内を作動
する構造となっている。The control rods of conventional pressurized water reactors have a structure in which the control rod elements are coated alloy rods that are almost the same size as the fuel rods, and operate within a simple control rod guide that replaces one fuel rod dispersed within the fuel assembly. It has become.
上記制御棒引抜に伴なって案内シンプル内に残存した冷
却水領域の集中は（小面積分散であり、熱中性子炉であ
るので減速効果による隣接燃料棒の出力ビーキングの問
題は少ない。The concentration of the cooling water area remaining in the guide simple due to the withdrawal of the control rods is small (distributed over a small area), and since this is a thermal neutron reactor, there is little problem of power peaking of adjacent fuel rods due to moderation effects.
しかし゛、軽水冷却低減速型炉心では、稠密格子炉心と
なシ、燃料棒径は細く、燃料棒は三角格子配列となるの
が□通例で１）−中性子エネルギ領域が高いため、ボロ
ン水の効きも少なく、制御棒への反応価値依存が高くな
′シー制御棒要素本数の増大は逸れない。その結果、炉
内構造物等の制御棒支持と振動防止上の難かしい構造上
の問題を誘起することとなっていた。However, in a light water-cooled, low-moderation core, the core is not a dense lattice core, the diameter of the fuel rods is small, and the fuel rods are arranged in a triangular lattice. The effectiveness is low, and the reaction value is highly dependent on the control rods.The increase in the number of control rod elements cannot be avoided. As a result, difficult structural problems have arisen in supporting the control rods and preventing vibrations in the reactor internals.
さらに、上述したように、低減速型炉心では、制御棒へ
の依存性が高く制御棒要素数も多いので、すべての燃料
集合体に挿入することとなり、炉内構造物の設計上の問
題点を少なくするため、制御棒集合体当りの制御棒要素
数を少なくシ、かつ制御棒要素の直径を太くして剛性を
上げることが挙げられる。Furthermore, as mentioned above, low moderation cores are highly dependent on control rods and have a large number of control rod elements, so they must be inserted into all fuel assemblies, leading to problems in the design of reactor internals. In order to reduce this, it is possible to reduce the number of control rod elements per control rod assembly and increase the rigidity by increasing the diameter of the control rod elements.
そこで、三角格子配列燃料においては第１図の制御棒案
内シンプルに示すように燃料棒２の７本分と、それらに
囲れた冷却水領域を制御棒案内領域とし、たとえば、六
角形の外形の制御棒案内シンプル１と円形断面の大径の
制御棒要素３が考えられる。Therefore, in the triangular lattice array fuel, the control rod guide area is the seven fuel rods 2 and the cooling water area surrounded by them, as shown in the simple control rod guide diagram in Figure 1, and the control rod guide area is, for example, a hexagonal outer shape. A simple control rod guide 1 and a large diameter control rod element 3 with a circular cross section are considered.
しかしながら、低減速型炉心では、中性子のスペクトル
レベルが中・高領域にあシ、大径の制御棒の引抜に伴な
い、残存する冷却水の過度な集中による減速効果による
隣接燃料棒の出力の歪みが生じ、炉心特性上好ましくな
い等の問題があった。However, in a low-moderation core, the neutron spectral level is in the medium to high range, and as large-diameter control rods are withdrawn, the output of adjacent fuel rods is reduced due to the moderation effect caused by excessive concentration of remaining cooling water. There were problems such as distortion and unfavorable core characteristics.
従来、正方格子配列の正方形断面燃料集合体で杜、十字
形制御棒で、フォロアとして、ジルカロイ−２など低減
速材料や燃料を用いた例があるが、本発明の如き構成の
ものはなかった。In the past, there have been examples of fuel assemblies with a square cross section in a square lattice arrangement, cross-shaped control rods, and low deceleration materials such as Zircaloy-2 and fuel used as followers, but there has been no such structure as the present invention. .
本発明は上述した事情に鑑みてなされたものであシ、軽
水冷却低減速型炉心において、剛性の高い、燃料棒の直
径より太い制御棒要素を用いる場合、制御棒の引抜に伴
なう炉心内の冷却水による減速領域の集中を防ぐため、
フォロア付の制御棒を用いて、制御棒案内シンプル内の
冷却水を排除することとし、そのフォロアの案内を燃料
集合体内に留めることにした燃料集合体を考案し、原子
炉内部構造を複雑しないことを目的とした軽水冷却低減
速型原子炉を提供するものであって、かがる目的を達成
するために、本発明では０分散型制御棒の制御棒要素の
個々にフォロアを付け、■制御棒の挿入中及び完全挿入
時のフォロアの案内は燃料集合体の中で行ない、■燃料
集合体には炉心下方でフォロア案内構造を設け、■炉内
構造物には専用のフォロア案内構造を設は左い、構造と
なっている。The present invention has been made in view of the above-mentioned circumstances.When using control rod elements having high rigidity and having a diameter larger than that of the fuel rods in a light water-cooled, low-moderation type reactor core, the present invention has been made in view of the above circumstances. In order to prevent concentration of deceleration area due to cooling water inside the
We devised a fuel assembly that uses control rods with followers to eliminate the cooling water in the simple control rod guide, and keeps the guide of the follower within the fuel assembly, thereby not complicating the internal structure of the reactor. In order to achieve this purpose, the present invention provides a light water cooled low moderation nuclear reactor for the purpose of: Guidance of the follower during control rod insertion and complete insertion is performed in the fuel assembly, ■ A follower guide structure is provided in the fuel assembly below the core, and ■ A dedicated follower guide structure is provided in the reactor internals. The structure is on the left.
以下、本発明による実施例を第２図表いし第５図に基づ
いて詳構に説明する。Embodiments according to the present invention will be described in detail below with reference to FIGS. 2 to 5.
第２図は本発明による原子炉の構造を示す断面図であシ
、フォロア案内部５を炉心部４あるいは燃料棒束下方に
有する燃料集合体６は、下部炉内構造物８に設けた餐心
板９上に装荷され、上部炉内構造物１０で支持されてい
る。また、制御棒７け原子炉容器１２に取付けた制御棒
駆動装置１１の駆動軸１３に結合されて・操作され、炉
心部４から完全引抜時には第５図に示すように１中性子
吸収材部分２５を上部炉内構造物１０内にフォロア部２
６を炉心部４に位置決めするように制御されている。FIG. 2 is a cross-sectional view showing the structure of a nuclear reactor according to the present invention. A fuel assembly 6 having a follower guide part 5 in the core part 4 or below the fuel rod bundle is a It is loaded onto the core plate 9 and supported by the upper reactor internals 10. In addition, the seven control rods are coupled to and operated by the drive shaft 13 of the control rod drive device 11 attached to the reactor vessel 12, and when completely withdrawn from the reactor core 4, as shown in FIG. The follower part 2 is installed in the upper reactor internals 10.
6 in the reactor core section 4.
第３図ないし第４図は、燃料集合体を示す一部破断した
正面図、及び横断面図であり、燃料棒２は、三角格子に
配列され、螺旋状鋼線または、支持格子１７で支持され
、下部を中間支持板１８に固定され、上部を自由とした
ものである。3 and 4 are a partially cutaway front view and a cross-sectional view of the fuel assembly, in which the fuel rods 2 are arranged in a triangular lattice and are supported by spiral steel wires or a support lattice 17. The lower part is fixed to the intermediate support plate 18, and the upper part is free.
また、燃料棒２の束の下方には、フォロア案内部５を中
間支持板１８から下部ノズル２１０間に設け、燃料棒２
の重量を中間支持板１８から下部側板１９を介して下部
ノズル２１に伝える構造となっている６、に
こで、図中１４は、燃料集合体６の上部ノズル、１５は
上部ノズル端板、１６はタイロッド、２０はフォロア案
内シンプル、２２は下端板である。 ・
また、上記制御棒要素３０案内のため、下部ノズル２１
の下端板２２に固定し、中間支持板１８と、上部ノズル
端板１５で支持された中空六角棒の制御棒案内シンプル
１が設けられている。これによシ、制御棒集合体７を炉
心４への完全挿入の時には、中性子吸収部２５を炉心部
４で、フォロア部２６ｉｔ炉心下方のガスプレナム部と
フォロア案内部５を軸方向に分けて設置し、上部ノズル
１４から下端の下部ノズル２１まで、連続して制御棒案
内シンプル１を貫通したものである。Further, a follower guide section 5 is provided below the bundle of fuel rods 2 between the intermediate support plate 18 and the lower nozzle 210, and a follower guide section 5 is provided between the intermediate support plate 18 and the lower nozzle 210.
The structure is such that the weight of the fuel assembly 6 is transmitted from the intermediate support plate 18 to the lower nozzle 21 via the lower side plate 19. In the figure, 14 is the upper nozzle of the fuel assembly 6, 15 is the upper nozzle end plate, 16 is a tie rod, 20 is a follower guide simple, and 22 is a lower end plate. - Also, for guiding the control rod element 30, the lower nozzle 21
A control rod guide simple 1 is provided which is a hollow hexagonal rod fixed to the lower end plate 22 of the nozzle and supported by the intermediate support plate 18 and the upper nozzle end plate 15. With this, when the control rod assembly 7 is completely inserted into the reactor core 4, the neutron absorbing part 25 is installed in the reactor core part 4, and the follower part 26 is installed separately in the gas plenum part below the core and the follower guide part 5 in the axial direction. However, the control rod guide simple 1 is continuously penetrated from the upper nozzle 14 to the lower nozzle 21 at the lower end.
第５図は、本発明による制御棒集合体７を示す正面図で
あシ、制御棒集合体７はスパイダ２３部分にとりつけた
フィンガ２４に結合された複数の制御棒要素３からなる
分散型である。FIG. 5 is a front view showing a control rod assembly 7 according to the present invention, and the control rod assembly 7 is a distributed type consisting of a plurality of control rod elements 3 connected to fingers 24 attached to a spider 23 portion. be.
上記制御棒要素３は、長手方向に被覆した中性子吸収材
部分２５と核***性物質あるいは低減速材からなるフォ
ロア２６から構成されている。The control rod element 3 is comprised of a neutron absorbing material portion 25 coated in the longitudinal direction and a follower 26 made of a fissile material or a low moderator.
従って、上述したように構成された原子炉では、燃料棒
２よりも太径の制御棒要素３を用いた軽水冷却低減速型
炉心において、制御棒２の炉心からの引抜時に生ずる冷
却水の減速効果の集中を防止内シンプル１を延長し、完
全挿入時にフォロア２θを案内することができる。Therefore, in a nuclear reactor configured as described above, in a light water-cooled low-moderation reactor core that uses control rod elements 3 with a larger diameter than the fuel rods 2, the cooling water deceleration that occurs when the control rods 2 are withdrawn from the core Preventing the concentration of effects, the inner simple 1 can be extended and the follower 2θ can be guided when fully inserted.
以上詳細に説明したように、本発明による原子炉によれ
ば、炉心から制御棒を引抜いた時、フォロアで冷却水を
排除し、隣接燃料棒の出力ビーキングを抑えることがで
きる。As described above in detail, according to the nuclear reactor according to the present invention, when the control rod is pulled out from the core, cooling water can be removed by the follower, and power peaking of adjacent fuel rods can be suppressed.
また、低減速型炉心は、一般に扁平炉心でも成立し、燃
料集合体を過度に長くしなくとも、燃料集合体内に限定
して分散型制御棒要素に連結したフォロアを案内するこ
とができる。In addition, a low moderation core can generally be realized even with a flat core, and it is possible to guide the followers connected to the distributed control rod elements within the fuel assembly without making the fuel assembly excessively long.
さらに、燃料集合体内にフォロア案内管を設けるので、
炉内構造物側に特別にフォロア案内を設ける必要がない
。Furthermore, since a follower guide pipe is provided within the fuel assembly,
There is no need to provide a special follower guide on the reactor internal structure side.
第１図は、制御棒案内シンプルと燃料棒との関係を示す
説明図、第２図は本発明によるフォロア付制御棒とそれ
と嵌合する燃料集合体を用いた原子炉の縦断面図、第３
図は本発明によるフォロア案内構造を燃料棒束下方に設
けた燃料集合体の一部破断した正面図、第４図は制御棒
案内シンプルを配置した燃料集合体の横断面図、第５図
は本発明による中性子吸収体の下方にフォロアを結合し
た棒分散型制御棒集合体の正面図である。
１・・・制御棒案内シンプル、 ２・・・燃料棒、３・
・・制御棒要素、４・・・炉心部、５・・・フォロア案
内部、６・・・燃料集合体、 ７・・・制御棒集 ゛合
体、８・・・下部炉内構造物、９・・・炉心板、１０・
・・上部炉内構造物、１１・・・制御棒駆動装置、１２
・・・原子炉容器、１３・・・制御棒駆動軸、１４・・
・上部ノズル、１５・・・上部ノズル端板、１６・・・
タイロッド、１７・・・支持格子、１８・・・中間支持
板、１９・・・下部側板、２０、 ・・・フォロア案内
シンプル、２１・・・下部ノズル、２２・・・下端板、
２３・・・スパイダー、２４・・・・・・フィンガー、
２５・−中性子吸収体、２６・ンフオロア
特許出願人 三菱原子カニ業株式会社
代理人 弁理士佐 藤 英 昭FIG. 1 is an explanatory diagram showing the relationship between a simple control rod guide and a fuel rod, and FIG. 2 is a vertical sectional view of a nuclear reactor using a control rod with a follower according to the present invention and a fuel assembly fitted thereto. 3
The figure is a partially cutaway front view of a fuel assembly in which a follower guide structure according to the present invention is provided below a fuel rod bundle, FIG. 4 is a cross-sectional view of a fuel assembly in which a simple control rod guide is arranged, and FIG. FIG. 2 is a front view of a rod-distributed control rod assembly in which a follower is coupled below a neutron absorber according to the present invention. 1... Simple control rod guide, 2... Fuel rod, 3...
...Control rod element, 4...Reactor core part, 5...Follower guide part, 6...Fuel assembly, 7...Control rod assembly, 8...Lower reactor internal structure, 9 ...Core plate, 10.
... Upper reactor internal structure, 11 ... Control rod drive device, 12
...Reactor vessel, 13...Control rod drive shaft, 14...
- Upper nozzle, 15... Upper nozzle end plate, 16...
Tie rod, 17...Support grid, 18...Intermediate support plate, 19...Lower side plate, 20,...Follower guide simple, 21...Lower nozzle, 22...Lower end plate,
23...Spider, 24...Finger,
25.-Neutron absorber, 26.Nfuoroa Patent applicant Hideaki Sato, Patent attorney, Mitsubishi Atomic Crab Industry Co., Ltd.
Claims (1)
料集合体の燃料棒下端を中間支持板に固定し、該中間支
持板と下部ノズル間に全周に亘って側板を設け、上記燃
料集谷体の互に隣り合う複数本の燃料棒と置換して配置
し、該置換された複数本の燃料棒の横断面に囲まれた領
域とほぼ等しい領域を占めると共に、上記燃料集合体の
燃料棒間に分散した制御棒案内シンプルを、長手方向に
炉心部のみでなく炉心部を通り、フォロア案内部の中間
支持板を経て下部ノズルまで延長し、上記分散した制御
棒案内シンプルに、燃料棒よ多も大径で中性子吸収体下
方に水排除用のフォロアを結合した制御棒要素を用いた
分散型の制御棒集合体の上記制御棒要素をそれぞれ嵌挿
することによシ、制御棒を炉心から引抜い九とき、制御
棒要素のフォロアが制御棒案内シンプル中の冷却水を排
除して、隣接する燃料棒に出力ビーキングが過度に生
□じないようにしたことを特徴とする軽水冷却低減速型
原子炉。 □In a dense lattice core having fuel rods arranged in a triangular lattice, the lower ends of the fuel rods of the fuel assembly are fixed to an intermediate support plate, a side plate is provided along the entire circumference between the intermediate support plate and the lower nozzle, and the fuel collector is arranged to replace a plurality of fuel rods adjacent to each other, and occupies an area approximately equal to the area surrounded by the cross section of the replaced plurality of fuel rods, and has a space between the fuel rods of the fuel assembly. The dispersed control rod guide simples are extended longitudinally not only through the reactor core, but also through the reactor core, through the intermediate support plate of the follower guide part, and to the lower nozzle. By inserting each of the control rod elements of a distributed control rod assembly using control rod elements with a large diameter and a follower for water removal connected below the neutron absorber, the control rods can be removed from the core. During withdrawal, the follower of the control rod element displaces the cooling water in the control rod guide, causing excessive power beaking in the adjacent fuel rod.
□A light water-cooled, low-speed nuclear reactor that is characterized by its ability to prevent □
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58241455A JPS60131488A (en) | 1983-12-21 | 1983-12-21 | Light-water cooling low deceleration reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58241455A JPS60131488A (en) | 1983-12-21 | 1983-12-21 | Light-water cooling low deceleration reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS60131488A true JPS60131488A (en) | 1985-07-13 |
Family
ID=17074562
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58241455A Pending JPS60131488A (en) | 1983-12-21 | 1983-12-21 | Light-water cooling low deceleration reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS60131488A (en) |
-
1983
- 1983-12-21 JP JP58241455A patent/JPS60131488A/en active Pending
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