JPH038719B2 - - Google Patents
Info
- Publication number
- JPH038719B2 JPH038719B2 JP58159915A JP15991583A JPH038719B2 JP H038719 B2 JPH038719 B2 JP H038719B2 JP 58159915 A JP58159915 A JP 58159915A JP 15991583 A JP15991583 A JP 15991583A JP H038719 B2 JPH038719 B2 JP H038719B2
- Authority
- JP
- Japan
- Prior art keywords
- plug
- reactor
- small
- fuel
- control rod
- 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
Links
- 230000007246 mechanism Effects 0.000 claims description 27
- 239000000446 fuel Substances 0.000 claims description 26
- 238000010586 diagram Methods 0.000 description 4
- 239000003758 nuclear fuel Substances 0.000 description 4
- 239000000463 material Substances 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 239000002915 spent fuel radioactive waste Substances 0.000 description 2
- 238000007796 conventional method Methods 0.000 description 1
- 230000007423 decrease Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は、ループ型、タンク型の高速増殖炉型
(FBR)原子炉構造において、炉内燃料交換機構
を簡素化し、炉心の大きさを縮少することなしに
回転プラグ径を縮少してある高速増殖炉内燃料取
扱い機構に関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention simplifies the in-reactor refueling mechanism in loop-type and tank-type fast breeder reactor (FBR) nuclear reactor structures, and improves rotation speed without reducing the size of the reactor core. This relates to a fuel handling mechanism in a fast breeder reactor with a reduced plug diameter.
従来、この種の炉内燃料交換機構を第1図ない
し第3図に示すように、代表的なタンク型高速増
殖炉(FBR)の原子炉・構造に基づいて説明す
る。 Conventionally, this type of in-reactor fuel exchange mechanism will be explained based on the reactor structure of a typical tank-type fast breeder reactor (FBR), as shown in FIGS. 1 to 3.
第1図はタンク型FBRの原子炉構造の縦断面
図であり、1が原子炉容器、2がルーフスラブ、
3は大回転プラグ、4は小回転プラグ、5はオフ
セツトアーム式燃料交換機で、炉内に位置する案
内筒5′に炉内6又は炉内中継ラツク7に位置す
る燃料を引込むことができる。 Figure 1 is a vertical cross-sectional view of the reactor structure of a tank-type FBR, where 1 is the reactor vessel, 2 is the roof slab,
Numeral 3 is a large-rotation plug, 4 is a small-rotation plug, and 5 is an offset arm type fuel exchanger, which can draw fuel located in the furnace 6 or in the furnace relay rack 7 into a guide cylinder 5' located in the furnace.
すなわち、大回転プラグ3、小回転プラグ4、
オフセツトアーム式燃料交換機5が炉内燃料交換
機構であり、二重回転プラグオフセツトアーム方
式が採用されている。 That is, a large rotation plug 3, a small rotation plug 4,
The offset arm type fuel exchanger 5 is an in-core fuel exchange mechanism, and a double rotating plug offset arm system is adopted.
そこで案内筒5′の位置決めは大回転プラグ3、
小回転プラグ4及び燃料交換機5の回転角の組み
合せで行なわれ、炉心6と炉内中継ラツク7の間
に使用済燃料又は新規燃料を移送する。8は使用
済燃料を炉外へ取り出したり、新規燃料を炉内へ
搬入するためのシユートであり、9は制御棒駆動
機構で、この場合、小回転プラグ4に塔載され、
炉心6に挿入されている制御棒(図示せず)を上
下するが、燃料交換時は切離されている。10は
制御棒駆動機構9のハウジングであり、小回転プ
ラグ4の下端より吊り下げる構造となつている。 Therefore, the position of the guide tube 5' is determined by the large rotation plug 3,
This is done by a combination of the rotation angles of the small rotating plug 4 and the refueling machine 5, and spent fuel or new fuel is transferred between the reactor core 6 and the in-core relay rack 7. 8 is a chute for taking spent fuel out of the reactor and carrying new fuel into the reactor; 9 is a control rod drive mechanism; in this case, it is mounted on the small rotating plug 4;
Control rods (not shown) inserted into the reactor core 6 are moved up and down, but are separated during fuel exchange. Reference numeral 10 denotes a housing for the control rod drive mechanism 9, which is suspended from the lower end of the small rotation plug 4.
しかして、タンク型FBRでは、炉心6の外周
に複数個のポンプ14及びIHX(中間熱交換器、
図示せず)が配置されるので、大回転プラグ3の
径DLが大きくなれば、原子炉容器1の内径も大
きくなり、物量が増えてコスト高になる欠点があ
る。そこで低コストの原子炉構造とするために
は、大回転プラグ3の径DLを小さくすることが
必要である。なおループ型FBRについても大回
転プラグ径DLを小さくすることにより原子炉容
器1自体を小さくできるが、コスト的にはタンク
型FBRほどは効かないものである。 However, in a tank-type FBR, a plurality of pumps 14 and IHX (intermediate heat exchanger,
(not shown), if the diameter D L of the large-rotation plug 3 increases, the inner diameter of the reactor vessel 1 also increases, which has the disadvantage of increasing the amount of material and increasing costs. Therefore, in order to achieve a low-cost nuclear reactor structure, it is necessary to reduce the diameter D L of the large rotating plug 3. Although the reactor vessel 1 itself can be made smaller in the loop-type FBR by reducing the large-rotation plug diameter D L , it is not as effective as the tank-type FBR in terms of cost.
第2図は、代表的な大型FBRの炉心平面図で
あり、略DC中に位置するのがプラケツトを含む
燃料集合体11であり、12は制御棒、13は中
性子遮蔽体である。 FIG. 2 is a core plan view of a typical large FBR. Located approximately in DC is a fuel assembly 11 including a bracket, 12 is a control rod, and 13 is a neutron shield.
また、7は炉内の中継ラツクの位置を示す。 Further, 7 indicates the position of the relay rack inside the furnace.
ここで中性子遮蔽体13は交換する必要がない
ので、前記第1図に示した燃料交換機の案内筒5
が接近しなければならない範囲は径DC内及び中
継ラツク7の位置である。 Here, since the neutron shield 13 does not need to be replaced, the guide cylinder 5 of the refueling machine shown in FIG.
The range that must be approached is within the diameter D C and the location of the relay rack 7.
さらに第3図は、第1図で示した従来の2重回
転プラグオフセツトアーム方式で採用した場合の
DL,DCを示す図であり、aは小回転プラグ4の
偏心量、bは小回転プラグ4の中心に対する燃料
交換機の中の距離、cは燃料交換機5の中心から
案内筒5′までの距離であり、すなわちオフセツ
ト量である。 Furthermore, Fig. 3 shows the case when the conventional double-rotating plug offset arm method shown in Fig. 1 is adopted.
This is a diagram showing D L and D C , where a is the eccentricity of the small rotation plug 4, b is the distance inside the fuel exchanger from the center of the small rotation plug 4, and c is from the center of the fuel exchanger 5 to the guide cylinder 5'. In other words, it is the offset amount.
また径DRは制御棒駆動機構ハウジング10の
外径を示す。さらにdは案内筒5′の外径、DL,
DSは大小回転ブラグ駆動歯車部の幅を示す。 Further, the diameter D R indicates the outer diameter of the control rod drive mechanism housing 10. Furthermore, d is the outer diameter of the guide tube 5', D L ,
D S indicates the width of the large and small rotating plug drive gear.
しかるに上述したシステムにおいては、DRと
中継ラツク7の位置(a+b+c)で基本寸法が
決まる。 However, in the system described above, the basic dimensions are determined by the position (a+b+c) of the D R and the relay rack 7.
すなわち、
1/2DR+1/2d+2c=a+b+c ………
b=a+c ………
の関係にあるので式は1/2DR+1/2d+2c=2a
+2c
故に
a=1/4(DR+d) ………
又
DS=2(a+1/2DR+LS) ………
DL=2(a+1/2DS+LL) ………
ととを代入しDL=2(DR+LS+LL)+d
この様に、DLの寸法はDRが支配的であり、DR
は制御棒の配置で決まるので、炉心を小さくしな
い限り回転プラグ径を縮少することは不可能であ
る。 In other words, 1/2D R +1/2d+2c=a+b+c......b=a+c......The formula is 1/2D R +1/2d+2c=2a
+2c Therefore, a=1/4 (D R +d) ...... Also, D S =2 (a+1/2D R +L S ) ...... D L =2 (a+1/2D S +L L ) ...... Substitute and D L = 2 (D R + L S + L L ) + d In this way, the dimension of D L is dominated by D R , and D R
Since it is determined by the arrangement of the control rods, it is impossible to reduce the diameter of the rotating plug unless the core is made smaller.
本発明は、上述した事情に鑑みてなされたもの
であり、原子炉構造のプラントコストを低減する
とともに、炉心の大きさを縮少することなしに、
炉容器径を縮少するため、炉容器径の支配的要因
である回転プラグ径を縮少させることに着目した
ものであつて、小回転プラグを小型にし、制御棒
駆動機構の一部を小回転プラグに、他を大回転プ
ラグに塔載し、さらに大回転プラグを炉心中心に
対して偏心配置し、かつオフセツトアーム式燃料
交換機を採用することにより、従来の回転プラグ
径に対して約2分の1の大きさに縮少することを
可能にした高速増殖炉内燃料取扱い機構を提供す
るものである。 The present invention has been made in view of the above-mentioned circumstances, and it is an object of the present invention to reduce the plant cost of the nuclear reactor structure, and to reduce the size of the reactor core.
In order to reduce the diameter of the reactor vessel, we focused on reducing the diameter of the rotating plug, which is the dominant factor in the diameter of the reactor vessel. By mounting the rotating plug and the other components on the large rotating plug, arranging the large rotating plug eccentrically with respect to the center of the core, and using an offset arm type fuel exchanger, the diameter of the rotating plug is approximately 2 minutes smaller than that of the conventional rotating plug. The present invention provides a fuel handling mechanism in a fast breeder reactor that can be reduced in size to 1 in size.
以下、本発明による一実施例を第4図ないし第
5図に基づいて詳細に説明する。図において、従
来構造と対応する同一部品には同一符号を付して
説明を省略する。 Hereinafter, one embodiment of the present invention will be described in detail with reference to FIGS. 4 and 5. In the drawings, the same parts that correspond to the conventional structure are given the same reference numerals and their explanations will be omitted.
第4図は本発明による概念及びDS,DCを示す
図である。 FIG. 4 is a diagram illustrating the concept and D S and D C according to the present invention.
図に示すように小回転プラグ4をDC内(制御
棒駆動機構の包絡円領域と呼び、その径は、炉心
燃料集合体領域の直径に相当する)に喰い込むよ
うに配置し、制御棒12の一部を小回転プラグ4
に、残りを大回転プラグ3に配置する。従つて図
には記載していないが制御棒駆動機構ハウジング
10も大回転プラグ3側と小回転プラグ4側に分
離され、その断面は大回転プラグ3側は三ケ月
形、小回転プラグ4側は略半円形をしている。 As shown in the figure, the small rotation plug 4 is placed so as to fit inside D C (called the envelope circle area of the control rod drive mechanism, the diameter of which corresponds to the diameter of the core fuel assembly area), and Part of 12 is attached to small rotation plug 4
Then, place the rest in the large rotation plug 3. Therefore, although not shown in the figure, the control rod drive mechanism housing 10 is also separated into the large-rotation plug 3 side and the small-rotation plug 4 side, and its cross section is crescent-shaped on the large-rotation plug 3 side and approximately half-shaped on the small-rotation plug 4 side. It has a circular shape.
また、炉心中央部の燃料を取扱うため、大回転
プラグ3の回転中心を炉心に対しSだけ偏心させ
ると共に、オフセツトアーム式の燃料交換機5を
採用し、小回転プラグ4に塔載している。 In addition, in order to handle fuel in the center of the reactor core, the center of rotation of the large rotating plug 3 is offset by an amount S with respect to the core, and an offset arm type fuel exchanger 5 is used, which is mounted on the small rotating plug 4.
こうすることにより、制御棒駆動機構ハウジン
グ10が、案内筒5′の炉心中央部接近を阻害す
ることはない。 By doing so, the control rod drive mechanism housing 10 does not obstruct the guide tube 5' from approaching the center of the core.
なお、燃料交換機5を自由に回転すると、制御
棒ハウジングと干渉するので大回転プラグ3、小
回転プラグ4、燃料交換機5の回転は、相互干渉
を避けるよう、予めプログラミングされた手順に
したがい、制御しなければならない。 Note that if the fuel exchanger 5 rotates freely, it will interfere with the control rod housing, so the rotations of the large rotation plug 3, small rotation plug 4, and fuel exchanger 5 should be controlled according to a preprogrammed procedure to avoid mutual interference. There must be.
また偏心量S、a、b、c及びDSの寸法は御
棒12の配置もからめて適正値を決定する。 Further, the dimensions of the eccentricities S, a, b, c, and D S are determined to be appropriate values, taking into account the arrangement of the control rod 12.
第5図は、第4図に示す概念の縦断面を示すも
のである。小回転プラグ4の軸受4a、駆動歯車
4b及び図に書いていないがシール構造物等は、
制御棒駆動機構9の間に設置するため、この実施
例では、例えば、大小回転プラグの構成部材と一
体型の軸受を用いる等最小幅のものが選定されて
いる。 FIG. 5 shows a longitudinal section of the concept shown in FIG. The bearing 4a of the small rotation plug 4, the drive gear 4b, and the seal structure etc., which are not shown in the figure, are
In order to be installed between the control rod drive mechanisms 9, in this embodiment, the minimum width is selected, for example, by using a bearing integrated with the components of the large and small rotating plugs.
この実施例では、制御棒駆動機構9に管台方式
を採用している。すなわち制御棒駆動機構9の軸
が通る細径の案内管と、大径の駆動機構の接合部
を管台9aにより上部に延すことにより4a,4
bの設置のスペースを開ける構造としている。 In this embodiment, the control rod drive mechanism 9 employs a nozzle type. That is, by extending the joint between the small-diameter guide tube through which the shaft of the control rod drive mechanism 9 passes and the large-diameter drive mechanism upward through the nozzle holder 9a, 4a, 4
The structure is designed to open up space for the installation of b.
なお図中Vは炉心6の中心、Wは大回転プラグ
3、Xは小回転プラグ4、Yは燃料交換機5のそ
れぞれ回転中心を示している。又制御棒駆動機構
ハウジング10は大回転プラグ3側を小回転プラ
グ4側に分離されているので、原子炉運転中耐震
剛性が低下する問題があるが、これを防止するた
め、例えば第5図A部に示す様にキー構造により
耐震強度上の結合をする事も可能である。 In the figure, V indicates the center of the reactor core 6, W indicates the rotation center of the large rotation plug 3, X indicates the rotation center of the small rotation plug 4, and Y indicates the rotation center of the fuel exchanger 5. Furthermore, since the control rod drive mechanism housing 10 is separated into the large-rotation plug 3 side and the small-rotation plug 4 side, there is a problem that seismic rigidity decreases during reactor operation. As shown in the figure below, it is also possible to use a key structure to achieve seismic strength.
以上詳細に説明したように、本発明による高速
増殖炉内燃料取扱い機構によれば、大回転プラグ
の径を大幅に縮少することができる。 As described in detail above, according to the fast breeder reactor fuel handling mechanism according to the present invention, the diameter of the large rotating plug can be significantly reduced.
すなわち、本発明によれば、少なくとも大回転
プラグ及び小回転プラグを有する高速増殖炉にお
いて、複数本配設される制御棒駆動機構の一部お
よび燃料交換機を、小回転プラグに配置すること
ともに、上記複数本の制御棒駆動機構の残部を大
回転プラグに配置することにより大回転プラグ径
を縮少することを可能にした炉内燃料取扱い機構
である。 That is, according to the present invention, in a fast breeder reactor having at least a large-rotation plug and a small-rotation plug, part of a plurality of control rod drive mechanisms and a fuel exchanger are disposed in the small-rotation plug, and the above-mentioned This is an in-core fuel handling mechanism that makes it possible to reduce the diameter of the large-rotation plug by arranging the remainder of the multiple control rod drive mechanisms in the large-rotation plug.
例えばDR=3300mm、L7=2900mmの炉心に対し
て第3図に示す従来方式ではDL≒9000mmである
が、第4図に示す本発明ではDL≒5100mmですむ。 For example, for a core with D R =3300 mm and L 7 =2900 mm, in the conventional method shown in FIG. 3, D L is approximately 9000 mm, but in the present invention shown in FIG. 4, D L is approximately 5100 mm.
従つて従来は直径22mクラスであつた炉容器の
径が18m程度に縮少することが可能になる。 Therefore, the diameter of the furnace vessel, which was conventionally 22 m in diameter, can be reduced to about 18 m.
これは、原子炉構造のみならず、原子炉建屋の
縮少にもつながり物量の削減効果は顕著であり、
低コストに建設できる。 This not only reduces the reactor structure but also the reactor building, and the effect of reducing the amount of material is significant.
Can be constructed at low cost.
第1図は従来の代表的タンク型FBRの原子炉
構造を示す断面図、第2図は従来の代表的な大型
FBRの炉心平面図、第3図は従来の炉内燃料取
扱い機構を示す基本概念図、第4図は本発明によ
る炉内燃料取扱い機構を示す基本概念図、第5図
は本発明の炉内燃料取扱い機構の概略を示す縦断
面図である。
1……原子炉容器、3……大回転プラグ、4…
…小回転プラグ、5……燃料交換器、5′……案
内筒、6……炉心、7……中継ラツク、9……制
御棒駆動機構、9a……管台、10……ハウジン
グ、12……制御棒。
Figure 1 is a cross-sectional view showing the reactor structure of a typical conventional tank-type FBR, and Figure 2 is a typical large-scale conventional tank-type FBR reactor structure.
Figure 3 is a basic conceptual diagram showing the conventional in-reactor fuel handling mechanism, Figure 4 is a basic conceptual diagram showing the in-core fuel handling mechanism according to the present invention, and Figure 5 is a core plan view of the FBR. FIG. 2 is a vertical cross-sectional view schematically showing a fuel handling mechanism. 1... Reactor vessel, 3... Large rotating plug, 4...
...Small rotation plug, 5...Fuel exchanger, 5'...Guide tube, 6...Reactor core, 7...Relay rack, 9...Control rod drive mechanism, 9a...Nozzle stand, 10...Housing, 12 ...control rod.
Claims (1)
て、前記大回転プラグは回転中心を炉心に対し所
定量偏心して配置すると共に、小回転プラグは前
記大回転プラグの制御棒駆動機構の包絡円領域に
食い込むように配置し、前記包絡円領域に対応す
る大・小回転プラグに複数本の制御棒駆動機構
を、前記包絡円領域を除く他の部分の小回転プラ
グにオフセツトアーム式燃料交換機を配置したこ
とを特徴とする高速増殖炉内燃料取扱い機構。1. In a fast breeder reactor having large and small rotating plugs, the large rotating plug is arranged with its center of rotation eccentric to the reactor core by a predetermined amount, and the small rotating plug is arranged so as to bite into the envelope circle area of the control rod drive mechanism of the large rotating plug. A plurality of control rod drive mechanisms are arranged in the large and small rotating plugs corresponding to the envelope circle area, and an offset arm type fuel exchanger is arranged in the small rotating plugs in other parts other than the envelope circle area. A fuel handling mechanism in a fast breeder reactor featuring:
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58159915A JPS6052797A (en) | 1983-08-31 | 1983-08-31 | Fuel handling mechanism in fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58159915A JPS6052797A (en) | 1983-08-31 | 1983-08-31 | Fuel handling mechanism in fast breeder reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6052797A JPS6052797A (en) | 1985-03-26 |
| JPH038719B2 true JPH038719B2 (en) | 1991-02-06 |
Family
ID=15703931
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58159915A Granted JPS6052797A (en) | 1983-08-31 | 1983-08-31 | Fuel handling mechanism in fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6052797A (en) |
-
1983
- 1983-08-31 JP JP58159915A patent/JPS6052797A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6052797A (en) | 1985-03-26 |
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| JPH04223298A (en) | Fuel exchanger | |
| JPS61164193A (en) | Exchanger for fuel of fast breeder reactor | |
| JPS59137897A (en) | Refueling guide device | |
| JPH0782110B2 (en) | Refueling method in reactor | |
| JPH04132994A (en) | Fast breeder reactor | |
| JPS635297A (en) | Upper structure of fast breeder reactor |