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JP2009128038A - Lower support structure with debris capturing function - Google Patents

Lower support structure with debris capturing function Download PDF

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JP2009128038A
JP2009128038A JP2007300361A JP2007300361A JP2009128038A JP 2009128038 A JP2009128038 A JP 2009128038A JP 2007300361 A JP2007300361 A JP 2007300361A JP 2007300361 A JP2007300361 A JP 2007300361A JP 2009128038 A JP2009128038 A JP 2009128038A
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support structure
debris
lower support
bwr
boiling water
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Hisamichi Inoue
久道 井䞊
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Hitachi GE Nuclear Energy Ltd
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Hitachi GE Nuclear Energy Ltd
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    • 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

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Abstract

<P>PROBLEM TO BE SOLVED: To provide a method for preventing debris from flowing into fuel assemblies in a boiling water reactor (BWR), and to eliminate or reduce defects of a porous debris filter adopted at present. <P>SOLUTION: In a lower support structure which supports the fuel assemblies and includes the inlet port for cooling water on its lateral face to guide a cooling water flow channel upward by bending it from the inlet port, the debris in the cooling water is captured in a debris capture pot by placing it between the inside of the upper part of the lower support structure and a nozzle wall below the fuel assemblies, and the debris capture pot is a debris capture groove equipped with protrusions for preventing the inflow debris from reflowing out. <P>COPYRIGHT: (C)2009,JPO&INPIT

Description

本発明は、沞隰氎型原子炉(BWR)においお、燃料集合䜓内ぞのデブリ(debris)流入を防止し、フレッティング(fretting)による燃料棒砎損を回避するのに奜適な䞋郚支持構造郚に関する。   The present invention relates to a lower support structure suitable for preventing debris from flowing into a fuel assembly and avoiding fuel rod breakage due to fretting in a boiling water reactor (BWR).

たず、本発明の背景ずなる沞隰氎型原子炉(BWR)の圧力容噚内の抂芁に぀いお、以䞋に説明する。   First, an outline of a pressure vessel of a boiling water reactor (BWR) as the background of the present invention will be described below.

図は、沞隰氎型原子炉(BWR)の圧力容噚内の䞀郚を抂念的に瀺す。たた、図は、沞隰氎型原子炉の燃料棒を受ける䞋郚支持構造郚を瀺す。   FIG. 1 conceptually illustrates a portion of a boiling water reactor (BWR) pressure vessel. FIG. 2 also shows the lower support structure that receives the fuel rods of the boiling water reactor.

図に瀺すように、沞隰氎型原子炉の圧力容噚1内には、ゞェットポンプ2が蚭眮されおいる。冷华氎は、再埪環ポンプ3で駆動され、圧力容噚に接続された吞蟌管4から圧力容噚壁1ずシュラりド壁5で仕切られたダりンカマ6内の冷华氎7を、再埪環ポンプの吐出管8を経由しお、ゞェットポンプ2のノズル9に䟛絊される。ノズル9から噎出した冷华氎は、ダりンカマ6内の冷华氎7を巻き蟌み流線で瀺す、氎量を増加させお䞋郚プレナム10に流入流線で瀺すする。䞋郚プレナム10に流入した冷华氎は、䞋郚支持構造郚11のオリフィス12から入り䞋郚タむプレヌト13を経由しお、燃料集合䜓14内に流入する。この燃料集合䜓14内は、スペヌサ15で集合された燃料棒16が収玍されおいる。   As shown in FIG. 1, a jet pump 2 is installed in a pressure vessel 1 of a boiling water reactor. The cooling water is driven by the recirculation pump 3, and the cooling water 7 in the downcomer 6 partitioned by the pressure vessel wall 1 and the shroud wall 5 from the suction pipe 4 connected to the pressure vessel is discharged to the discharge pipe 8 of the recirculation pump. To be supplied to the nozzle 9 of the jet pump 2. The cooling water ejected from the nozzle 9 entrains the cooling water 7 in the downcomer 6 (indicated by the streamline a), increases the amount of water, and flows into the lower plenum 10 (indicated by the streamline b). Cooling water flowing into the lower plenum 10 enters from the orifice 12 of the lower support structure 11 and flows into the fuel assembly 14 via the lower tie plate 13. In this fuel assembly 14, fuel rods 16 assembled by spacers 15 are stored.

燃料集合䜓14内を通過する冷华氎は、燃料集合䜓14内で熱を受けお気液二盞流ずなり䞊昇し、気氎分離噚図瀺省略で分離された蒞気は、ドラむダヌ図瀺省略を経由しお、倖郚の蒞気タヌビン図瀺省略に導かれる。䞀方、気氎分離噚で分離された高枩氎は、ダりンカマ6の䞊郚に攟出される。ここで、䞋郚支持構造11は、図に瀺すように、燃料集合䜓14の䜓を支えるもので、䞋郚タむプレヌト13が挿入される挿入口17ずオリフィス12が、各燃料集合䜓14に察応しお蚭けられおいる。   The cooling water passing through the fuel assembly 14 receives heat in the fuel assembly 14 and rises into a gas-liquid two-phase flow, and the vapor separated by the steam separator (not shown) is removed from the dryer (not shown). ) Through an external steam turbine (not shown). On the other hand, the high-temperature water separated by the steam separator is discharged to the upper part of the downcomer 6. Here, as shown in FIG. 2, the lower support structure 11 supports four fuel assemblies 14, and an insertion port 17 into which the lower tie plate 13 is inserted and an orifice 12 are provided in each fuel assembly 14. Correspondingly provided.

䞊蚘の沞隰氎型原子炉(BWR)においお、建蚭時に䜿甚した工具、特にワむダヌブラシの残骞、さらに切削切子等が、冷华氎の流れに乗り、燃料集合䜓内に流入し、スペヌサに匕っかかり、冷华氎の流動で誘起される振動を生じながら燃料棒ず接觊するこずにより、燃料棒を砎損するずいう問題があった。この問題に察凊するため、フむルタを蚭けるこずが提案されおいる。   In the above boiling water reactor (BWR), tools used during construction, especially wire brush remnants, and cutting chips, etc., ride on the flow of cooling water, flow into the fuel assembly, get caught by the spacer, and cool water There is a problem that the fuel rod is broken by contacting with the fuel rod while generating vibration induced by the flow of the fuel. In order to deal with this problem, it has been proposed to provide a filter.

䟋えば、特蚱文献は、沞隰氎型原子炉の燃料支持金具および燃料集合䜓においお、燃料集合䜓の䞋郚タむプレヌトがセットされる燃料支持金具内に、冷华材䞭の異物を捕獲するフむルタを蚭眮する技術を開瀺しおいる。たた、特蚱文献は、沞隰氎型原子炉の燃料支持金具および燃料集合䜓においお、燃料支持金具の冷华材流入口に、ネット状の異物フむルタを蚭眮するこずを開瀺しおいる。   For example, in Patent Document 1, in a fuel support fitting and fuel assembly of a boiling water reactor, a filter for capturing foreign matter in the coolant is installed in the fuel support fitting in which the lower tie plate of the fuel assembly is set. The technology to do is disclosed. Patent Document 2 discloses that in a fuel support fitting and a fuel assembly of a boiling water reactor, a net-like foreign matter filter is installed at a coolant inlet of the fuel support fitting.

図は、図ず図に瀺された沞隰氎型原子炉の燃料集合䜓の䞋郚内に、デブリフむルタを蚭眮した䟋を瀺す。図は、図の瀺すデブリフむルタ郚の䞀郚を拡倧しお瀺す。   FIG. 3 shows an example in which a debris filter is installed in the lower part of the fuel assembly of the boiling water reactor shown in FIGS. 1 and 2. FIG. 4 shows an enlarged part of the debris filter shown in FIG.

図に瀺すように、デブリフむルタ19は、燃料棒16の䞋郚端栓18が差し蟌たれる䞋郚タむプレヌト13に蚭けられる。デブリ20は、オリフィス12から流入する流䜓により運ばれ、䞋郚タむプレヌト13に蚭けられたデブリフむルタ19により捕捉される。図に瀺すように、デブリフむルタは、燃料棒端栓が差し蟌たれる穎21の呚蟺に蚭けられた小孔22を有する。実機では、この小孔は、玄〜の盎埄のテヌパ小孔ずなっおいる。   As shown in FIG. 3, the debris filter 19 is provided in the lower tie plate 13 into which the lower end plug 18 of the fuel rod 16 is inserted. The debris 20 is carried by the fluid flowing from the orifice 12 and is captured by the debris filter 19 provided in the lower tie plate 13. As shown in FIG. 4, the debris filter has a small hole 22 provided around the hole 21 into which the fuel rod end plug is inserted. In the actual machine, this small hole is a tapered small hole having a diameter of about 2 to 3 mm.

特開−号公報Japanese Patent Laid-Open No. 2003-232879 特開−号公報JP-A-2005-49132

沞隰氎型原子炉(BWR)における燃料集合䜓内ぞのデブリ流入を防止するため、䞊蚘したようなフむルタを甚いる察策には、次の問題点があった。
・フむルタの小孔図に瀺されたデブリフむルタではテヌパ小孔22を物理的に通過できるデブリは、床フむルタに捕捉されたものでも、流量の倉化や流れの有無の倉化を繰り返し受けるず、最終的には、フむルタを通過し、燃料集合䜓内に流入しおしたう。そうするず、集合䜓内に匕っかかったデブリが冷华材の流れにより振動しお燃料棒衚面の被芆管を磚耗しお損傷する可胜性があり、この損傷が進むず、内郚の栞燃料ペレットからのりランや栌分裂生成物等を冷华材䞭に挏出させるので、プラントを停止しお亀換䜜業が必芁ずなるなど、運転効率を悪化させる。
・フむルタの圢状ず性状によっお、フむルタ自䜓が砎損する可胜性があり、砎損した堎合には、フむルタ自䜓の砎損片が燃料集合䜓内に流入しおしたい、䞊蚘したデブリの流入ず同様の問題を発生させる。
・フむルタを蚭けるこずで、フむルタ郚での圧力損倱が発生する。図は、実機においお流量に察するデブリフむルタによる圧力損倱を蚈枬した結果を瀺すものであり、流量が増倧するに぀れお圧力損倱が倧きくなり、定栌流量時においお、玄kaの圧力損倱があった。
In order to prevent the debris from flowing into the fuel assembly in the boiling water reactor (BWR), the measures using the filter as described above have the following problems.
・ The debris that can physically pass through the small hole in the filter (tapered small hole 22 in the debris filter shown in FIG. 4) repeatedly changes the flow rate and whether or not there is a flow even if it is once captured by the filter. When it is received, it eventually passes through the filter and flows into the fuel assembly. Then, the debris caught in the assembly may vibrate due to the coolant flow and wear and damage the cladding on the fuel rod surface. When this damage progresses, uranium and splitting from the inner nuclear fuel pellets may occur. Since the products and the like are leaked into the coolant, the operation efficiency is deteriorated, for example, the plant is stopped and replacement work is required.
-Depending on the shape and properties of the filter, the filter itself may be damaged. In such a case, the damaged piece of the filter itself will flow into the fuel assembly, causing the same problem as the inflow of debris described above. Let
-By providing a filter, pressure loss occurs in the filter section. FIG. 5 shows the result of measuring the pressure loss by the debris filter with respect to the flow rate in an actual machine. The pressure loss increases as the flow rate increases, and the pressure loss is about 3 kPa at the rated flow rate (80 m 3 / h). was there.

本発明は、䞊蚘した問題点の解決を課題ずしお、この課題を達成する新たなデブリ捕捉方法を提䟛する。   The present invention provides a new debris capturing method that achieves this problem, with the solution of the above-described problems as a problem.

䞊蚘の課題を解決するために、本発明の沞隰氎型原子炉(BWR)の䞋郚支持構造郚は、燃料集合䜓を支持するず共に冷华氎の入口郚を偎面に備えお、冷华氎の流路を該入口郚から曲げお䞊方に導く䞋郚支持構造郚においお、前蚘䞋郚支持構造郚の䞊郚内偎ず前蚘燃料集合䜓の䞋方のノズル壁の間にデブリ捕捉ポットを蚭けお、冷华氎䞭のデブリを該ポット内に捕捉するこずを特城ずする。   In order to solve the above problems, the lower support structure part of the boiling water reactor (BWR) of the present invention supports a fuel assembly and has a cooling water inlet on the side surface, and a cooling water flow path. In the lower support structure that bends from the inlet and guides it upward, a debris catching pot is provided between the upper inner side of the lower support structure and the nozzle wall below the fuel assembly, and debris in cooling water is Capturing in a pot.

たた、本発明の沞隰氎型原子炉(BWR)の䞋郚支持構造郚は、䞊蚘の特城に加えお、前蚘デブリ捕捉ポットは、流入したデブリの再流出を防ぐ突起を備えたデブリ捕捉溝であるこずを特城ずする。   Further, the lower support structure part of the boiling water reactor (BWR) of the present invention, in addition to the above-mentioned features, the debris trapping pot is a debris trapping groove provided with a projection for preventing reflow of the introduced debris. It is characterized by that.

たた、本発明の沞隰氎型原子炉(BWR)の䞋郚支持構造郚は、䞊蚘の特城に加えお、前蚘デブリ捕捉溝は、前蚘䞋郚支持構造郚の䞊郚内偎の党呚にわたり蚭けられおいるこずを特城ずする。   In addition to the above features, the lower support structure part of the boiling water reactor (BWR) of the present invention, the debris capture groove is provided over the entire inner periphery of the upper part of the lower support structure part It is characterized by.

たた、本発明の沞隰氎型原子炉(BWR)の䞋郚支持構造郚は、䞊蚘の特城に加えお、前蚘デブリ捕捉溝は、その溝の深さが、前蚘䞋郚支持構造郚の埄方向においお前蚘冷华氎入口郚ず反察䜍眮においお最も浅く、該反察䜍眮から呚方向に離れるに぀れお深くなるように圢成されおいるこずを特城ずする。   Further, the lower support structure part of the boiling water reactor (BWR) of the present invention, in addition to the above features, the debris capture groove has a depth of the groove in the radial direction of the lower support structure part. It is characterized in that it is shallowest at a position opposite to the cooling water inlet and deeper as it goes away from the opposite position in the circumferential direction.

たた、本発明の沞隰氎型原子炉(BWR)の䞋郚支持構造郚は、䞊蚘の特城に加えお、前蚘デブリ捕捉溝は、前蚘䞋郚支持構造郚の埄方向においお前蚘冷华氎入口郚ず反察䜍眮の近傍から前蚘冷华氎入口郚の䜍眮に向けお䞡偎に圢成され、か぀、その溝の深さは、前蚘冷华氎入口郚の䜍眮に近づくに぀れお深くなるように圢成されおいるこずを特城ずする。   Further, the lower support structure part of the boiling water reactor (BWR) according to the present invention, in addition to the above features, the debris trapping groove is positioned opposite to the cooling water inlet part in the radial direction of the lower support structure part. The groove is formed on both sides from the vicinity toward the position of the cooling water inlet portion, and the depth of the groove is formed so as to become deeper as the position of the cooling water inlet portion is approached. .

たた、本発明の沞隰氎型原子炉(BWR)の䞋郚支持構造郚は、䞊蚘の特城に加えお、前蚘䞋郚支持構造郚の内壁には、前蚘埄方向における前蚘冷华氎入口郚の前蚘反察䜍眮に、䞊䞋にわたっおデブリ案内溝が圢成されおいるこずを特城ずする。   Further, the lower support structure part of the boiling water reactor (BWR) of the present invention, in addition to the above features, the inner wall of the lower support structure part is positioned opposite to the cooling water inlet part in the radial direction. In addition, a debris guide groove is formed on the upper and lower sides.

たた、本発明の沞隰氎型原子炉(BWR)の䞋郚支持構造郚は、䞊蚘の特城に加えお、前蚘デブリ捕捉溝は、前蚘䞋郚支持構造郚の内偎に䞀䜓構成されおいるこずを特城ずする。   Further, the lower support structure part of the boiling water reactor (BWR) of the present invention is characterized in that, in addition to the above characteristics, the debris capturing groove is integrally formed inside the lower support structure part. To do.

本発明によれば、冷华氎䞭に含たれるデブリをデブリ捕捉ポット内に捕捉しお燃料集合䜓内ぞの浞入を防ぐこずができるので、埓来の沞隰氎型原子炉(BWR)で甚いおいたデブリフむルタを䜿甚しないこずが可胜ずなるので、圧力損倱がないだけでなく、コスト䞊も有利ずなる。たた、デブリフむルタを䜵甚する堎合でも、倧きく重いデブリをデブリ捕捉ポットで捕捉するので、デブリフむルタの目詰たりの可胜性およびフレッテむングによる燃料棒ぞのダメヌゞを倧きく䜎枛するこずが可胜ずなる。   According to the present invention, the debris contained in the cooling water can be captured in the debris capturing pot and prevented from entering the fuel assembly. Therefore, the debris filter used in the conventional boiling water reactor (BWR) Since it is possible not to use, there is no pressure loss, which is advantageous in terms of cost. Even when a debris filter is used in combination, large and heavy debris is captured by the debris capturing pot, so that the possibility of clogging of the debris filter and damage to the fuel rod due to fretting can be greatly reduced.

たた、本発明によれば、流動が倉化しおも䞀旊捕捉したデブリの再流出を防止するこずができるこず、さらに捕捉したデブリをデブリ捕捉ポットぞの流入䜍眮から離れた䜍眮に集䞭するように流すこずにより、デブリ捕捉ポット内の収玍容量を最倧化するこずができる。   Further, according to the present invention, it is possible to prevent the debris once captured from flowing out even if the flow changes, and to flow the captured debris so as to concentrate at a position away from the inflow position to the debris capturing pot. Thus, the storage capacity in the debris catching pot can be maximized.

たた、本発明によれば、デブリ捕捉ポットは、䞋郚支持構造郚ず同じ金属で補䜜し、䞋郚支持構造郚内の䞊郚壁偎の流れがさほど䜜甚しない郚分に蚭けるこずにより、砎損するこずはなく、安党性に優れおいる。   Further, according to the present invention, the debris catching pot is made of the same metal as the lower support structure, and is not damaged by being provided in a portion where the flow on the upper wall side in the lower support structure does not act so much, Excellent safety.

たた、本発明によれば、デブリ捕捉ポットは、冷华氎の流路䞊ではなく、䞋郚支持構造郚の内䞊郚壁偎に蚭けおいるので、冷华氎の流れの抵抗ずなるこずはないのでデブリ捕捉ポットの蚭眮による圧力損倱の増加はなく、原子炉の性胜向䞊が期埅できる。   Further, according to the present invention, the debris trapping pot is provided not on the cooling water flow path but on the inner upper wall side of the lower support structure portion, so that it does not become a resistance to the flow of the cooling water, so that the debris trapping is performed. There is no increase in pressure loss due to the installation of pots, and improvement in reactor performance can be expected.

本発明に係るデブリ捕捉機胜付䞋郚支持構造の実斜圢態を以䞋に説明する。   An embodiment of a lower support structure with a debris capturing function according to the present invention will be described below.

図は本発明に係る実斜䟋を瀺す。実斜䟋では、デブリ捕捉ポット23が䞋郚支持構造郚11内の䞊郚に蚭けられおいるものであり、図に瀺されおいるように、䞋郚タむプレヌト13の燃料棒支持郚には、デブリフむルタの蚭眮がなく、倧開口穎24が開いおいる。そのため、デブリフむルタによる圧力損倱はない。デブリ捕捉ポット23の圢状は、䞋郚支持構造11の䞊郚内偎にリング状の溝を蚭け、その溝の内偎には、䞀床捕捉したデブリ20が逃げないように、円呚状の突起25が蚭けられおいる。   FIG. 6 shows Example 1 according to the present invention. In the first embodiment, the debris catching pot 23 is provided at the upper part in the lower support structure 11, and as shown in FIG. There is no filter installed, and the large opening hole 24 is open. Therefore, there is no pressure loss due to the debris filter. The shape of the debris catching pot 23 is provided with a ring-shaped groove inside the upper part of the lower support structure 11, and a circumferential projection 25 is provided inside the groove so that the debris 20 once captured does not escape. ing.

䞋郚支持構造郚11に蚭けられたオリフィス12から流入する冷华氎は、図においお流線で瀺すように、流入埌盎ぐに盎角に曲げられお䞊昇し、䞋郚タむプレヌト13の䞋方のノズルに流入する。冷华氎が盎角に曲げられる際に、比重の倧きいデブリ20は、遠心力の䜜甚により矢印26が瀺すように、䞋郚支持構造郚の内壁際たで移動し、内壁に沿っお䞊昇する。䞊昇したデブリ20は、䞋郚タむプレヌトノズル壁面27ず円呚状突起25の隙間28を通りデブリ捕捉ポット23内に収玍される。䞀床収玍されたデブリ20は、円呚状突起25があるこずで、このデブリ捕捉ポット23から逃げ出すこずはできない。   The cooling water flowing in from the orifice 12 provided in the lower support structure 11 is bent at a right angle and rises immediately after flowing in, as shown by the streamline in FIG. 6, and flows into the nozzle below the lower tie plate 13. . When the cooling water is bent at a right angle, the debris 20 having a large specific gravity moves to the inner wall of the lower support structure portion and rises along the inner wall as indicated by an arrow 26 by the action of centrifugal force. The debris 20 that has risen passes through the gap 28 between the lower tie plate nozzle wall surface 27 and the circumferential protrusion 25 and is stored in the debris catching pot 23. The debris 20 once stored cannot escape from the debris catching pot 23 due to the circumferential protrusion 25.

図は本発明に係る実斜䟋を瀺す。実斜䟋では、䞋郚タむプレヌト13の燃料棒支持郚にデブリフむルタ19が蚭眮されおいる図参照。たた、実斜䟋では、捕捉ポット23の溝が、実斜䟋ず同様に、党呚にわたっお蚭けられおいるが、その深さは、図においお砎線で瀺すように、オリフィス12が蚭けられおいる偎の反察偎の䜍眮図においおで瀺す䜍眮からオリフィスの蚭けられおいる偎の䜍眮図においおで瀺す䜍眮に向けお、溝の底郚を傟斜させより深くなるようにしおいる。このようにした理由は、流れの圱響で、図䞭で瀺す郚分が図䞭で瀺す郚分より枛圧されるので、デブリ捕捉領域高圧郚からデブリ捕捉領域䜎圧郚に向かい流れが発生し、図䞭の郚分にデブリ20が運ばれ、そこに溜たるようにしたものである。   FIG. 8 shows a second embodiment according to the present invention. In the second embodiment, a debris filter 19 is installed on the fuel rod support portion of the lower tie plate 13 (see FIG. 9). Further, in the second embodiment, the groove of the capture pot 23 is provided over the entire circumference in the same manner as in the first embodiment, but the depth thereof is such that the orifice 12 is provided as shown by a broken line in FIG. The bottom of the groove is inclined deeper from the position on the opposite side (position indicated by a in FIG. 8) to the position where the orifice is provided (position indicated by b in FIG. 8). ing. The reason for this is that the part indicated by b in the figure is depressurized more than the part indicated by a in the figure due to the influence of the flow, so that a flow is generated from the debris trapping area high pressure part a to the debris trapping area low pressure part b. The debris 20 is carried to the portion b in the figure and accumulated there.

実斜䟋では、デブリフむルタ19ずデブリ捕捉ポット23を䜵甚するこずにより、デブリ20の燃料集合䜓14内ぞの流入を䞀局確実に阻止するこずができる。なお、デブリフむルタ19を䜵甚するこずにより、䞊蚘したフむルタの圧力損倱の問題を完党に解消するこずはできないが、デブリ捕捉ポットの䜵甚により、フレッテむングによる燃料棒ぞのダメヌゞを䞎える倧きく重いデブリのすべおず、小さく軜いデブリでもその倚くをデブリ捕捉ポットで捉えるので、フむルタの目詰たりによる圧力損倱の問題を倧いに軜枛するこずができるのである。   In the second embodiment, the combined use of the debris filter 19 and the debris trapping pot 23 can more reliably prevent the debris 20 from flowing into the fuel assembly 14. In addition, the combined use of the debris filter 19 cannot completely eliminate the above-mentioned problem of the pressure loss of the filter, but the combined use of the debris catching pot can cause large and heavy debris that damages the fuel rods due to fretting. All, even small and light debris, are captured by the debris catch pot, greatly reducing the pressure loss problem caused by filter clogging.

図は本発明に係る実斜䟋を瀺す。実斜䟋では、実斜䟋ず同様に、デブリフむルタ19ずデブリ捕捉ポット23を䜵甚しおいる図参照が、捕捉ポット23の圢状は、実斜䟋およびで瀺したような党呚にわたり溝を蚭けたものではなく、デブリ捕捉ポット23の溝をオリフィス12の偎の反察偎で切り離した圢状図参照にしお、䞋郚支持構造郚11の䞊郚内偎ず䞋郚タむプレヌトノズル壁面27ずの隙間28を広くし、デブリがより流入しやすくしたものである。なお、図においお、矢印29は、流䜓の流れ方向を瀺しおいる。   FIG. 10 shows a third embodiment according to the present invention. In the third embodiment, the debris filter 19 and the debris catching pot 23 are used in combination as in the second embodiment (see FIG. 11). However, the shape of the catching pot 23 is the same as that shown in the first and second embodiments. The groove of the debris catching pot 23 is not provided with a groove over the circumference, but is cut off on the opposite side of the orifice 12 (see FIG. 12), and the upper inner side of the lower support structure 11 and the wall surface of the lower tie plate nozzle The gap 28 with 27 is widened to facilitate the inflow of debris. In FIG. 12, an arrow 29 indicates the flow direction of the fluid.

実斜䟋では、デブリフむルタ19ずデブリ捕捉ポット23の䜵甚に加えお、デブリを補足ポットにより容易に流入させお溜めやすくするこずにより、デブリの燃料集合䜓14内ぞの流入をより確実に阻止するこずができる。なお、デブリフむルタ19を䜵甚するこずにより、䞊蚘したフむルタの圧力損出の問題を完党に解消するこずはできないが、デブリ捕捉ポットの䜵甚により、実斜䟋に぀いお説明したフむルタの目詰たりによる圧力損倱の問題を倧いに軜枛するこずができるのである。   In the third embodiment, in addition to the combined use of the debris filter 19 and the debris catching pot 23, the debris can be easily flown into the supplement pot and easily stored, thereby preventing the debris from flowing into the fuel assembly 14 more reliably. can do. Although the above-mentioned problem of the pressure loss of the filter cannot be completely solved by using the debris filter 19 together, the pressure loss due to the clogging of the filter described in the second embodiment can be achieved by using the debris catching pot. This problem can be greatly reduced.

図は本発明に係る実斜䟋を瀺す。図は、実斜䟋の䞋郚タむプレヌトに蚭けられたデブリフむルタの䞀郚の詳现を瀺す。図は、実斜䟋の切り離されたデブリ捕捉ポット23の端郚を瀺す。   FIG. 13 shows a fourth embodiment according to the present invention. FIG. 14 shows details of a part of the debris filter provided in the lower tie plate of the fourth embodiment. FIG. 15 shows the end of the debris catching pot 23 separated in Example 4.

実斜䟋では、実斜䟋ず同様に、デブリフむルタ19ずデブリ捕捉ポット23を䜵甚しおいるが、䞋郚支持構造郚11におけるオリフィス12の反察偎における切り離されたデブリ捕捉ポット23の二぀の端郚間の内壁に、䞊䞋にわたるデブリ案内溝30を斜した点で、実斜䟋ず異なる。このデブリ案内溝30を斜したこずにより、䞋郚支持構造郚11においおオリフィス12から遠い偎の内壁に沿っお䞊昇するデブリ20をデブリ捕捉ポット23に導いお䞀局捕捉しやすくしおいる。なお、デブリフむルタ19を䜵甚するこずにより、䞊蚘したフむルタの圧力損出の問題を完党に解消するこずはできないが、デブリ捕捉ポットの䜵甚により、フむルタの䜿甚による䞊蚘の問題を倧いに軜枛できるこずは、実斜䟋およびず同様である。   In the fourth embodiment, as in the third embodiment, the debris filter 19 and the debris catching pot 23 are used together, but the two ends of the separated debris catching pot 23 on the opposite side of the orifice 12 in the lower support structure 11 are used. The third embodiment differs from the third embodiment in that a debris guide groove 30 extending vertically is provided on the inner wall between the portions. By providing the debris guide groove 30, the debris 20 rising along the inner wall on the side farther from the orifice 12 in the lower support structure 11 is guided to the debris catching pot 23 to make it easier to catch. In addition, by using the debris filter 19 in combination, the above-mentioned problem of the pressure loss of the filter cannot be completely solved, but the combined use of the debris capturing pot can greatly reduce the above problem due to the use of the filter, The same as in Examples 2 and 3.

以䞊、実斜䟋からたでの぀の䟋を瀺したが、いずれの実斜䟋も䞋郚支持構造郚内にデブリ捕捉ポットを蚭けるものであり、燃料集合䜓の䞋郚タむプレヌトの構造倉曎を行う必芁はなく、埓来のものを利甚するこずができる。したがっお、珟状の原子炉燃料に甚いられおいる×、×、×の燃料集合䜓をそのたた利甚しお、これに適甚するこずが可胜である。   As mentioned above, although four examples from Example 1 to 4 were shown, each example provides a debris trapping pot in the lower support structure, and it is necessary to change the structure of the lower tie plate of the fuel assembly. However, a conventional one can be used. Therefore, it is possible to use the fuel assemblies of 8 × 8, 9 × 9, and 10 × 10, which are used for the current nuclear reactor fuel, as they are.

本発明は、沞隰氎型原子炉(BWR)の冷华郚の入口郚ずなる䞋郚支持構造郚に利甚可胜であるが、その他の郚䜍においおも冷华氎䞭のデブリを捕捉する目的で利甚可胜である。   The present invention can be used for a lower support structure part that serves as an inlet of a cooling part of a boiling water reactor (BWR), but can also be used for the purpose of capturing debris in cooling water in other parts.

沞隰氎型原子炉(BWR)の圧力容噚内の䞀郚を抂念的に瀺す。A part of the inside of a boiling water reactor (BWR) pressure vessel is shown conceptually. 沞隰氎型原子炉の燃料棒を受ける䞋郚支持構造郚を瀺す。The lower support structure that receives the fuel rods of the boiling water reactor is shown. 沞隰氎型原子炉の燃料集合䜓の䞋郚内に、デブリフむルタを蚭眮した䟋を瀺す。An example in which a debris filter is installed in the lower part of a fuel assembly of a boiling water reactor is shown. 図に瀺したデブリフむルタの䞀郚を詳现に瀺す。A part of the debris filter shown in FIG. 3 is shown in detail. 実機においお流量に察するデブリフむルタによる圧力損倱を蚈枬した結果を瀺す。The result of measuring the pressure loss by the debris filter with respect to the flow rate in the actual machine is shown. 本発明に係る実斜䟋を瀺す。Example 1 which concerns on this invention is shown. 実斜䟋における䞋郚タむプレヌトの䞀郚を拡倧しお瀺す。A part of lower tie plate in Example 1 is expanded and shown. 本発明に係る実斜䟋を瀺す。Example 2 which concerns on this invention is shown. 実斜䟋における䞋郚タむプレヌトに蚭けられたデブリフむルタの䞀郚を拡倧しお瀺す。The part of debris filter provided in the lower tie plate in Example 2 is expanded and shown. 本発明に係る実斜䟋を瀺す。Example 3 according to the present invention will be described. 実斜䟋における䞋郚タむプレヌトに蚭けられたデブリフむルタの䞀郚を拡倧しお瀺す。The part of debris filter provided in the lower tie plate in Example 3 is expanded and shown. 図における−矢芖図であり、実斜䟋の切り離されたデブリ捕捉ポット23の端郚を瀺す。FIG. 11 is an AA arrow view in FIG. 10 and shows an end portion of the debris catching pot 23 separated in Example 3. 本発明に係る実斜䟋を瀺す。Example 4 which concerns on this invention is shown. 実斜䟋の䞋郚タむプレヌトに蚭けられたデブリフむルタの䞀郚を拡倧しお瀺す。The part of debris filter provided in the lower tie plate of Example 4 is expanded and shown. 図における−矢芖図であり、実斜䟋の切り離されたデブリ捕捉ポット23の端郚を瀺す。It is an AA arrow line view in FIG. 13, and shows the edge part of the debris capture | acquisition pot 23 cut away of Example 4. FIG.

笊号の説明Explanation of symbols

1 原子炉圧力容噚、2 ゞェットポンプ、3 再埪環ポンプ、4 吞蟌管、5 シュラりド壁、6 ダりンカマ、7 冷华氎、8 吐出管、9 ノズル、10 䞋郚プレナム、11 䞋郚支持構造郚、12 オリフィス、13 䞋郚タむプレヌト、14 燃料集合䜓、15 スペヌサ、16 燃料棒、17 挿入口、18 燃料郚䞋郚端栓、19 デブリフむルタ、20 デブリ、21 燃料棒端栓が差し蟌たれる穎、22 テヌパ小孔、23 デブリ捕捉ポット、24 倧開口穎、25 円呚状突起、26 デブリの流線、27 䞋郚タむプレヌトノズル壁面、29 隙間、29 デブリ流線、30 デブリ案内溝、a デブリ捕捉領域高圧郚、b デブリ捕捉領域䜎圧郚   1 ... Reactor pressure vessel, 2 ... Jet pump, 3 ... Recirculation pump, 4 ... Suction pipe, 5 ... Shroud wall, 6 ... Downcomer, 7 ... Cooling water, 8 ... Discharge pipe, 9 ... Nozzle, 10 ... Lower plenum , 11 ... Lower support structure, 12 ... Orifice, 13 ... Lower tie plate, 14 ... Fuel assembly, 15 ... Spacer, 16 ... Fuel rod, 17 ... Insertion port, 18 ... Fuel unit lower end plug, 19 ... Debris filter 20 ... Debris, 21 ... Hole into which fuel rod end plug is inserted, 22 ... Tapered small hole, 23 ... Debris trapping pot, 24 ... Large opening hole, 25 ... Circular projection, 26 ... Debris streamline, 27 ... Lower tie plate nozzle wall, 29 ... gap, 29 ... debris streamline, 30 ... debris guide groove, a ... debris capture region high pressure part, b ... debris capture region low pressure part

Claims (7)

燃料集合䜓を支持するず共に冷华氎の入口郚を偎面に備えお、冷华氎の流路を該入口郚から曲げお䞊方に導く䞋郚支持構造郚においお、
前蚘䞋郚支持構造郚の䞊郚内偎ず前蚘燃料集合䜓の䞋方のノズル壁の間にデブリ捕捉ポットを蚭けお、冷华氎䞭のデブリを該ポット内に捕捉するこずを特城ずする沞隰氎型原子炉(BWR)の䞋郚支持構造郚。
In the lower support structure that supports the fuel assembly and includes a cooling water inlet on the side surface, and bends the cooling water flow path upward from the inlet.
A boiling water reactor characterized in that a debris trapping pot is provided between the upper inner side of the lower support structure and the nozzle wall below the fuel assembly, and traps debris in the cooling water. BWR) lower support structure.
請求項に蚘茉された沞隰氎型原子炉(BWR)の䞋郚支持構造郚においお、
前蚘デブリ捕捉ポットは、流入したデブリの再流出を防ぐ突起を備えたデブリ捕捉溝であるこずを特城ずする沞隰氎型原子炉(BWR)の䞋郚支持構造郚。
In the lower support structure part of the boiling water reactor (BWR) according to claim 1,
The debris trapping pot is a debris trapping groove provided with a protrusion that prevents reflow of the debris that has flowed in. A lower support structure part of a boiling water reactor (BWR).
請求項に蚘茉された沞隰氎型原子炉(BWR)の䞋郚支持構造郚においお、
前蚘デブリ捕捉溝は、前蚘䞋郚支持構造郚の䞊郚内偎の党呚にわたり蚭けられおいるこずを特城ずする沞隰氎型原子炉(BWR)の䞋郚支持構造郚。
In the lower support structure of a boiling water reactor (BWR) as claimed in claim 2,
The debris trapping groove is provided over the entire inner periphery of the upper part of the lower support structure, and the lower support structure of a boiling water reactor (BWR).
請求項に蚘茉された沞隰氎型原子炉(BWR)の䞋郚支持構造郚においお、
前蚘デブリ捕捉溝は、その溝の深さが、前蚘䞋郚支持構造郚の埄方向においお前蚘冷华氎入口郚ず反察䜍眮においお最も浅く、該反察䜍眮から呚方向に離れるに぀れお深くなるように圢成されおいるこずを特城ずする沞隰氎型原子炉(BWR)の䞋郚支持構造郚。
In the lower support structure of a boiling water reactor (BWR) as claimed in claim 2,
The debris capturing groove is formed such that the depth of the groove is shallowest at a position opposite to the cooling water inlet portion in the radial direction of the lower support structure portion, and becomes deeper as the distance from the opposite position in the circumferential direction increases. Boiling water reactor (BWR) lower support structure, characterized by
請求項に蚘茉された沞隰氎型原子炉(BWR)の䞋郚支持構造郚においお、
前蚘デブリ捕捉溝は、前蚘䞋郚支持構造郚の埄方向においお前蚘冷华氎入口郚ず反察䜍眮の近傍から前蚘冷华氎入口郚の䜍眮に向けお䞡偎に圢成され、か぀、その溝の深さは、前蚘冷华氎入口郚の䜍眮に近づくに぀れお深くなるように圢成されおいるこずを特城ずする沞隰氎型原子炉(BWR)の䞋郚支持構造郚。
In the lower support structure of a boiling water reactor (BWR) as claimed in claim 2,
The debris catching grooves are formed on both sides in the radial direction of the lower support structure part from the vicinity of the position opposite to the cooling water inlet part toward the position of the cooling water inlet part, and the depth of the groove is A lower support structure portion of a boiling water reactor (BWR), wherein the lower support structure portion is formed so as to become deeper as it approaches the position of the cooling water inlet portion.
請求項に蚘茉された沞隰氎型原子炉(BWR)の䞋郚支持構造郚においお、
前蚘䞋郚支持構造郚の内壁には、前蚘埄方向における前蚘冷华氎入口郚の前蚘反察䜍眮に、䞊䞋にわたっおデブリ案内溝が圢成されおいるこずを特城ずする沞隰氎型原子炉(BWR)の䞋郚支持構造郚。
In a lower support structure of a boiling water reactor (BWR) according to claim 5,
The lower wall of the boiling water reactor (BWR) is characterized in that a debris guide groove is formed on the inner wall of the lower support structure portion at the opposite position of the cooling water inlet portion in the radial direction. Support structure.
請求項からのいずれか䞀項に蚘茉された沞隰氎型原子炉(BWR)の䞋郚支持構造郚においお、
前蚘デブリ捕捉溝は、前蚘䞋郚支持構造郚の内偎に䞀䜓構成されおいるこずを特城ずする沞隰氎型原子炉(BWR)の䞋郚支持構造郚。
In the lower support structure of a boiling water reactor (BWR) according to any one of claims 2 to 6,
The debris trapping groove is integrally formed inside the lower support structure, and the lower support structure of a boiling water reactor (BWR).
JP2007300361A 2007-11-20 2007-11-20 Lower support structure with debris capturing function Pending JP2009128038A (en)

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