JPS6122798B2 - - Google Patents

Info

Publication number
JPS6122798B2
JPS6122798B2 JP52157411A JP15741177A JPS6122798B2 JP S6122798 B2 JPS6122798 B2 JP S6122798B2 JP 52157411 A JP52157411 A JP 52157411A JP 15741177 A JP15741177 A JP 15741177A JP S6122798 B2 JPS6122798 B2 JP S6122798B2
Authority
JP
Japan
Prior art keywords
fuel
fuel assembly
reactor
receiving cylinder
reactor vessel
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
Application number
JP52157411A
Other languages
Japanese (ja)
Other versions
JPS5491698A (en
Inventor
Yasushi Mimura
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.)
Mitsubishi Heavy Industries Ltd
Original Assignee
Mitsubishi Heavy 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 Mitsubishi Heavy Industries Ltd filed Critical Mitsubishi Heavy Industries Ltd
Priority to JP15741177A priority Critical patent/JPS5491698A/en
Publication of JPS5491698A publication Critical patent/JPS5491698A/en
Publication of JPS6122798B2 publication Critical patent/JPS6122798B2/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
    • 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)

Description

【発明の詳細な説明】 本発明は原子炉の燃料交換装置の改良に関する
ものである。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to improvements in refueling devices for nuclear reactors.

原子炉においては、崩壊熱が大きいので、燃料
集合体をガス雰囲気中へ露出しないように冷却材
中に浸したまま炉心から引抜いて、燃料交換を行
う必要があるが、従来の原子炉は、燃料交換状態
を示す第1図、及び運転状態を示す第2図に示す
ように、複数の燃料集合体aを林立させた炉心b
と、同炉心bを取り囲む原子炉容器cと、炉内構
造物dと、上記容器cの上部を封止する遮断プラ
グeと、冷却材入口ノズルfと、冷却材出口ノズ
ルgと、制御棒駆動機構jと、炉内上部機構kと
で構成されており、燃料集合体aをガス雰囲気中
へ露出しないように冷却材h中に浸したまま炉心
bから引抜こうとすると、冷却材hの深さを燃料
集合体aの長さの2倍以上にしなければならな
い。そのため原子炉容器c及び制御棒駆動機構j
が上下方向に長尺化して、制御棒の挿入性が悪化
していた。また上記のように原子炉容器c及び制
御棒駆動機構jが長尺化するので、コストアツプ
するし、冷却材インベトリーを増大させる原因に
もなつていた。
In a nuclear reactor, the decay heat is large, so in order to prevent the fuel assembly from being exposed to the gas atmosphere, it is necessary to pull it out from the core while immersed in a coolant to replace the fuel. As shown in FIG. 1 showing the fuel exchange state and FIG. 2 showing the operating state, a reactor core b has a plurality of fuel assemblies a arranged in a row.
, a reactor vessel c surrounding the reactor core b, a reactor internal structure d, a shutoff plug e sealing the upper part of the vessel c, a coolant inlet nozzle f, a coolant outlet nozzle g, and a control rod. It is composed of a drive mechanism j and an in-core upper mechanism k, and if an attempt is made to pull out the fuel assembly a from the core b while immersed in the coolant h so as not to expose it to the gas atmosphere, the coolant h will be removed. The depth must be at least twice the length of fuel assembly a. Therefore, the reactor vessel c and control rod drive mechanism j
The control rods became longer in the vertical direction, making it difficult to insert the control rods. Furthermore, as described above, the reactor vessel c and the control rod drive mechanism j are elongated, which increases the cost and causes an increase in the coolant inventory.

本発明は前記の問題点に対処するもので、複数
の燃料集合体が林立した炉心を取り囲む原子炉容
器と、同原子炉容器内の炉心隣接位置に設けた燃
料貯蔵ポツトと、同原子炉容器の上部を封止する
遮蔽プラグの偏心位置に回転可能に設けた回転遮
蔽プラグとを有し、上記炉心及び上記燃料貯蔵ポ
ツトを上記原子炉容器内に出入する冷却材中に浸
漬した原子炉において、前記回転遮蔽プラグを多
重回転遮蔽プラグとし、同多重回転遮蔽プラグの
うち最内側の回転遮蔽プラグに燃料集合体受容筒
を貫設して、同燃料集合体受容筒の下端部を前記
原子炉容器内の冷却材中に開口するとともに、同
燃料集合体受容筒を前記炉心の直上位置と前記燃
料貯蔵ポツトの直上位置との間に移動可能にし、
燃料集合体を同燃料集合体受容筒内に吊上げか吊
下ろして交換する燃料交換機を同燃料集合体受容
筒の上部内に設け、同燃料集合体受容筒内を減圧
して前記原子炉容器の冷却材を同燃料集合体受容
筒内へ吸引する圧力調整器を同燃料集合体受容筒
の上部に設けたことを特徴とする原子炉の燃料交
換装置に係わり、その目的とする処は、原子炉容
器の上下方向の寸法を短縮しても、燃料交換を行
うことができて、原子炉容器をコンパクト化でき
る改良さた原子炉の燃料交換装置を供する点にあ
る。
The present invention addresses the above-mentioned problems, and includes: a reactor vessel surrounding a reactor core in which a plurality of fuel assemblies are arranged; a fuel storage pot provided adjacent to the core within the reactor vessel; a rotary shielding plug rotatably provided at an eccentric position of the shielding plug sealing the upper part of the reactor, and the reactor core and the fuel storage pot are immersed in a coolant flowing in and out of the reactor vessel. , the rotary shielding plug is a multiple rotary shielding plug, a fuel assembly receiving cylinder is provided through the innermost rotary shielding plug of the multiple rotary shielding plug, and the lower end of the fuel assembly receiving cylinder is connected to the nuclear reactor. opening into the coolant in the container, and making the fuel assembly receiving cylinder movable between a position directly above the reactor core and a position directly above the fuel storage pot;
A fuel exchange machine for exchanging fuel assemblies by lifting or lowering them into the fuel assembly receiving cylinder is installed in the upper part of the fuel assembly receiving cylinder, and the inside of the fuel assembly receiving cylinder is depressurized to replace the fuel assembly in the reactor vessel. This relates to a fuel exchange device for a nuclear reactor, characterized in that a pressure regulator for sucking coolant into the fuel assembly receiving cylinder is installed in the upper part of the fuel assembly receiving cylinder. An object of the present invention is to provide an improved fuel exchange device for a nuclear reactor that can perform fuel exchange even if the vertical dimension of the reactor vessel is shortened, and can make the reactor vessel more compact.

本発明は前記のように構成されており、多重回
転遮蔽プラグを回転して、燃料集合体受容筒を交
換すべき燃料集合体の上方へ移動し、次いで圧力
調整器を作動し、同燃料集合体受容筒内を減圧し
て、原子炉容器内の冷却材を同燃料集合体受容筒
内へ吸引し、次いで燃料交換機を作動して、上記
燃料集合体を同燃料集合体受容筒内へ吊上げ、次
いで多重回転遮蔽プラグを回転して、燃料集合体
受容筒を燃料貯蔵ポツトの直上位置へ移動する一
方、燃料交換機を作動して、上記燃料集合体を同
燃料貯蔵ポツト内へ入れ、次いで同燃料集合体を
同燃料貯蔵ポツトごとに原子炉容器外へ搬出す
る。また搬入は、上記と逆の要領で行う。
The present invention is constructed as described above, and the multi-rotation shielding plug is rotated to move the fuel assembly receiving cylinder above the fuel assembly to be replaced, and then the pressure regulator is actuated to The pressure inside the reactor vessel is reduced and the coolant in the reactor vessel is sucked into the fuel assembly receiving cylinder, and then the fuel exchange machine is operated to lift the fuel assembly into the fuel assembly receiving cylinder. Then, the multi-rotating shielding plug is rotated to move the fuel assembly receiver into a position directly above the fuel storage pot, while the refueling machine is activated to place the fuel assembly into the fuel storage pot and then into the fuel storage pot. The fuel assembly is carried out of the reactor vessel in each fuel storage pot. Also, carry out the process in reverse order to the above.

本発明は前記のように燃料集合体の交換に際
し、圧力調整器を作動して、燃料集合体受容筒内
を減圧し、原子炉容器内の冷却材を同燃料集合体
受容筒内へ吸引して、同燃料集合体受容筒を冷却
材で満たし、その中に燃料集合体を吊上げるか、
同燃料集合体受容筒内から吊下して、燃料交換を
行うので、炉心と遮蔽プラグとの間の距離が短く
ても、燃料集合体を冷却材に浸漬したまま交換で
きる。つまり原子炉容器の上下方向の寸法を短縮
しても、燃料交換を行うことができて、原子炉容
器をコンパクト化できる効果がある。
As described above, when replacing a fuel assembly, the present invention operates a pressure regulator to reduce the pressure inside the fuel assembly receiving cylinder and suck the coolant in the reactor vessel into the fuel assembly receiving cylinder. Fill the fuel assembly receiving cylinder with coolant and lift the fuel assembly into it, or
Since the fuel assembly is suspended from within the receiving cylinder and the fuel is replaced, even if the distance between the core and the shielding plug is short, the fuel assembly can be replaced while immersed in the coolant. In other words, even if the vertical dimensions of the reactor vessel are shortened, fuel exchange can be performed and the reactor vessel can be made more compact.

次に本発明の原子炉の燃料交換装置を第3図に
示す一実施例により説明すると、1が複数の燃料
集合体2を林立させた炉心、3が同炉心1を取り
囲む原子炉容器、4が上記炉心1を同容器3内に
支持するとともに炉心1に冷却材5を供給する炉
内構造物、6が同容器3の上部に固定した遮蔽プ
ラグ、7が同遮蔽プラグ6上に回転可能に装着し
た回転遮蔽プラグ、8が同回転遮蔽プラグ7上に
回転可能に装着した回転遮蔽プラグ、9が同回転
遮蔽プラグ8上に回転可能に装着した回転遮蔽プ
ラグ、10げ同回転遮蔽プラグ9の偏心位置を貫
設して下端が冷却材5中に開口した燃料集合体受
容筒で、上記プラグ7の回転中心7aと上記プラ
グ8の回転中心8aと上記プラグ9の回転中心9
aとはずれており、同各プラグ7〜9のうち、適
当なものを回転すると、受容筒10が炉心1に林
立した燃料集合体2のうち、所望のものの上方
へ、或は原子炉容器3内に設置した燃料貯蔵ポツ
ト11の上方へ、移動するようになつている。ま
た12が上記受容筒10内の上部に装着した燃料
交換機、13が上記受容筒10内に連通した圧力
調整器、14が前記回転遮蔽プラグ7に装着した
燃料出入器、15が冷却材入口ノズル、16が冷
却材出口ノズルである。
Next, the fuel exchange system for a nuclear reactor according to the present invention will be described with reference to an embodiment shown in FIG. is a reactor internal structure that supports the reactor core 1 in the container 3 and supplies the coolant 5 to the reactor core 1, 6 is a shielding plug fixed to the upper part of the container 3, and 7 is rotatable on the shielding plug 6. 8 is a rotary shielding plug rotatably mounted on the rotary shielding plug 7, 9 is a rotary shielding plug rotatably mounted on the rotary shielding plug 8, 10 is a rotary shielding plug 9 is a fuel assembly receiving cylinder whose lower end is opened into the coolant 5 by penetrating the eccentric position of the cylinder, and includes a rotation center 7a of the plug 7, a rotation center 8a of the plug 8, and a rotation center 9 of the plug 9.
When a suitable one of the plugs 7 to 9 is rotated, the receiving tube 10 moves above the desired one among the fuel assemblies 2 arranged in the reactor core 1, or into the reactor vessel 3. It is designed to move above the fuel storage pot 11 installed inside. Further, 12 is a fuel exchanger attached to the upper part of the receiving tube 10, 13 is a pressure regulator communicating with the receiving tube 10, 14 is a fuel inlet/output device attached to the rotary shielding plug 7, and 15 is a coolant inlet nozzle. , 16 is a coolant outlet nozzle.

次に前記原子炉の燃料交換作用を説明する。ま
ず受容筒10を回転遮蔽プラグ9に貫設して受容
筒10の下端を原子炉容器3内の冷却材5中に開
口し、次いで回転遮蔽プラグ7〜9を適宜回転し
て受容筒10を交換すべき燃料集合体2の上方へ
移動し、次いで圧力調整器13を作動し、受容筒
10内を減圧して、原子炉容器3内の冷却材5を
受容筒10内へ吸引し、次いで燃料交換機12を
作動して燃料集合体2を引き上げ、次いで回転遮
蔽プラグ7〜9を適宜回転して受容筒10を燃料
貯蔵ポツト11の上方へ移動し、次いで燃料交換
機12を作動して燃料集合体2を燃料貯蔵ポツト
11の中へ入れる。それからは燃料出入機14を
用いて燃料集合体2を燃料貯蔵ポツト11ごとに
搬出する。
Next, the fuel exchange operation of the nuclear reactor will be explained. First, the receiving tube 10 is inserted through the rotating shielding plug 9 to open the lower end of the receiving tube 10 into the coolant 5 in the reactor vessel 3, and then the rotating shielding plugs 7 to 9 are rotated appropriately to open the receiving tube 10. Move above the fuel assembly 2 to be replaced, then operate the pressure regulator 13 to reduce the pressure inside the receiving cylinder 10, suck the coolant 5 in the reactor vessel 3 into the receiving cylinder 10, and then The fuel exchanger 12 is operated to pull up the fuel assembly 2, the rotary shielding plugs 7 to 9 are rotated appropriately to move the receiving tube 10 above the fuel storage pot 11, and the fuel exchanger 12 is operated to lift the fuel assembly 2. The body 2 is placed into the fuel storage pot 11. Thereafter, the fuel assembly 2 is transported out of each fuel storage pot 11 using the fuel loading/unloading machine 14.

以上本発明を実施例について説明したが、勿論
本発明はこのような実施例にだけ局限されるもの
ではなく、本発明の精神を逸脱しない範囲内で
種々の設計の改変を施しうるものである。
Although the present invention has been described above with reference to embodiments, it goes without saying that the present invention is not limited to such embodiments, and that various design modifications can be made without departing from the spirit of the present invention. .

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

第1図は従来の原子炉の燃料交換状態を示す縦
断側面図、第2図は同原子炉の運転状態を示す縦
断側面図、第3図は本発明に係る原子炉の燃料交
換装置の一実施例を示す縦断側面図である。 1……炉心、2……燃料集合体、3……原子炉
容器、5……冷却材、6〜9……偏心回転遮蔽プ
ラグ、10……燃料集合体受容筒、12……燃料
交換機、13……圧力調整器。
FIG. 1 is a vertical side view showing the fuel exchange state of a conventional nuclear reactor, FIG. 2 is a vertical side view showing the operating state of the same reactor, and FIG. 3 is a part of the nuclear reactor fuel exchange system according to the present invention. FIG. 2 is a longitudinal side view showing an example. DESCRIPTION OF SYMBOLS 1...Reactor core, 2...Fuel assembly, 3...Reactor vessel, 5...Coolant, 6-9...Eccentric rotation shielding plug, 10...Fuel assembly receiving tube, 12...Fuel exchange machine, 13...Pressure regulator.

Claims (1)

【特許請求の範囲】[Claims] 1 複数の燃料集合体が林立した炉心を取り囲む
原子炉容器と、同原子炉容器内の炉心隣接位置に
設けた燃料貯蔵ポツトと、同原子炉容器の上部を
封止する遮蔽プラグの偏心位置に回転可能に設け
た回転遮蔽プラグとを有し、上記炉心及び上記燃
料貯蔵ポツトを上記原子炉容器内に出入する冷却
材中に浸漬した原子炉において、前記回転遮蔽プ
ラグを多重回転遮蔽プラグとし、同多重回転遮蔽
プラグのうち最内側の回転遮蔽プラグに燃料集合
体受容筒を貫設して、同燃料集合体受容筒の下端
部を前記原子炉容器内の冷却材中に開口するとと
もに、同燃料集合体受容筒を前記炉心の直上位置
と前記燃料貯蔵ポツトの直上位置との間に移動可
能にし、燃料集合体を同燃料集合体受容筒内に吊
上げか吊下ろして交換する燃料交換機を同燃料集
合体受容筒の上部内に設け、同燃料集合体受容筒
内を減圧して前記原子炉容器内の冷却材を同燃料
集合体受容筒内へ吸引する圧力調整器の同燃料集
合体受容筒の上部に設けたことを特徴とする原子
炉の燃料交換装置。
1. The reactor vessel surrounding the reactor core where multiple fuel assemblies are lined up, the fuel storage pot located adjacent to the reactor core within the reactor vessel, and the eccentric position of the shielding plug that seals the top of the reactor vessel. A nuclear reactor having a rotatably provided rotary shielding plug, wherein the reactor core and the fuel storage pot are immersed in a coolant flowing into and out of the reactor vessel, the rotary shielding plug being a multiple rotary shielding plug, A fuel assembly receiving cylinder is installed through the innermost rotating shielding plug among the multiple rotating shielding plugs, and the lower end of the fuel assembly receiving cylinder is opened into the coolant in the reactor vessel. The fuel assembly receiving cylinder is movable between a position directly above the reactor core and a position directly above the fuel storage pot, and a fuel exchange machine for exchanging fuel assemblies by lifting or lowering them into the fuel assembly receiving cylinder is provided. A pressure regulator is installed in the upper part of the fuel assembly receiving cylinder and reduces the pressure inside the fuel assembly receiving cylinder and sucks the coolant in the reactor vessel into the fuel assembly receiving cylinder. A nuclear reactor fuel exchange device characterized by being installed at the top of a cylinder.
JP15741177A 1977-12-28 1977-12-28 Atomic reactor Granted JPS5491698A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP15741177A JPS5491698A (en) 1977-12-28 1977-12-28 Atomic reactor

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP15741177A JPS5491698A (en) 1977-12-28 1977-12-28 Atomic reactor

Publications (2)

Publication Number Publication Date
JPS5491698A JPS5491698A (en) 1979-07-20
JPS6122798B2 true JPS6122798B2 (en) 1986-06-03

Family

ID=15649037

Family Applications (1)

Application Number Title Priority Date Filing Date
JP15741177A Granted JPS5491698A (en) 1977-12-28 1977-12-28 Atomic reactor

Country Status (1)

Country Link
JP (1) JPS5491698A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111009330B (en) * 2019-12-25 2022-12-02 中广核研究院有限公司 Reactor uncovering and reloading rotary shielding device

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS4846792A (en) * 1971-10-14 1973-07-03
JPS5029995A (en) * 1973-07-11 1975-03-26
JPS5221593A (en) * 1975-08-08 1977-02-18 Westinghouse Electric Corp Reactor

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS4846792A (en) * 1971-10-14 1973-07-03
JPS5029995A (en) * 1973-07-11 1975-03-26
JPS5221593A (en) * 1975-08-08 1977-02-18 Westinghouse Electric Corp Reactor

Also Published As

Publication number Publication date
JPS5491698A (en) 1979-07-20

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