JPH0329893A - Refuelling device - Google Patents
Refuelling deviceInfo
- Publication number
- JPH0329893A JPH0329893A JP1163785A JP16378589A JPH0329893A JP H0329893 A JPH0329893 A JP H0329893A JP 1163785 A JP1163785 A JP 1163785A JP 16378589 A JP16378589 A JP 16378589A JP H0329893 A JPH0329893 A JP H0329893A
- Authority
- JP
- Japan
- Prior art keywords
- plug
- gripper
- core
- support tube
- fuel
- 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
- 239000000446 fuel Substances 0.000 claims abstract description 52
- 239000002826 coolant Substances 0.000 claims abstract description 15
- 239000008358 core component Substances 0.000 claims description 36
- 238000000605 extraction Methods 0.000 claims description 3
- 230000000149 penetrating effect Effects 0.000 claims description 2
- 238000012423 maintenance Methods 0.000 abstract description 11
- 230000004323 axial length Effects 0.000 abstract description 4
- 238000001514 detection method Methods 0.000 abstract description 4
- 230000007246 mechanism Effects 0.000 description 11
- 210000000078 claw Anatomy 0.000 description 6
- 229910001338 liquidmetal Inorganic materials 0.000 description 5
- 230000005540 biological transmission Effects 0.000 description 4
- DGAQECJNVWCQMB-PUAWFVPOSA-M Ilexoside XXIX Chemical compound C[C@@H]1CC[C@@]2(CC[C@@]3(C(=CC[C@H]4[C@]3(CC[C@@H]5[C@@]4(CC[C@@H](C5(C)C)OS(=O)(=O)[O-])C)C)[C@@H]2[C@]1(C)O)C)C(=O)O[C@H]6[C@@H]([C@H]([C@@H]([C@H](O6)CO)O)O)O.[Na+] DGAQECJNVWCQMB-PUAWFVPOSA-M 0.000 description 2
- 238000001816 cooling Methods 0.000 description 2
- 229910052708 sodium Inorganic materials 0.000 description 2
- 239000011734 sodium Substances 0.000 description 2
- 238000002485 combustion reaction Methods 0.000 description 1
- 230000008602 contraction Effects 0.000 description 1
- 230000009977 dual effect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000003028 elevating effect Effects 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 239000011435 rock Substances 0.000 description 1
- 238000007789 sealing 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
Abstract
Description
【発明の詳細な説明】
〔発明の目的〕
（産業上の利用分野）
本発明は液体金属冷却型高速増殖炉の燃判交換装置に関
する。DETAILED DESCRIPTION OF THE INVENTION [Object of the Invention] (Industrial Application Field) The present invention relates to a fuel exchanger for a liquid metal cooled fast breeder reactor.
（従来の技術〉
液体金属冷却型高速増Ｔｌｔ１ｆは、原子炉容器の上部
開口部を覆う遮蔽プラグに炉心上部機構および燃料交換
装置を搭載し、この燃料交換装置において、燃料集合体
等の炉心構成要素を炉内で移動させ、燃料交換等を行な
うようになっている。(Conventional technology) The liquid metal cooled high-speed increase Tlt1f has a core upper mechanism and a fuel exchange device mounted on a shielding plug that covers the upper opening of the reactor vessel. Elements are moved within the furnace to perform fuel exchange, etc.
ところで、原子炉が大型化すると、炉心が大径となり、
また炉心構成要素の数も多《なるので、燃料交換装置等
の構造が複雑化する傾向にある。By the way, as nuclear reactors become larger, the core becomes larger in diameter,
Furthermore, as the number of core components increases, the structure of fuel exchange equipment and the like tends to become more complex.
例えば、大型原子炉用の燃料交換装置としては、大、中
、小の３つの回転プラグを重ねて設置し、小回転プラグ
上に１つの直動式燃料交換装置を搭載したもの、大小２
つの回転プラグを重ねて設匝し、小回転プラグ上に直動
式あるいはオフセットアーム式の燃料交換装置を設画し
たもの、１つの回転プラグ上にオフセットアーム式の燃
料交換装置を搭載したもの等が知られている。For example, as a fuel exchange device for a large nuclear reactor, three rotating plugs (large, medium, and small) are installed one on top of the other, and one direct-acting fuel exchange device is mounted on the small rotating plug.
One in which two rotating plugs are installed one on top of the other, and a direct acting or offset arm type fuel exchange device is installed on the small rotating plug, and an offset arm type fuel exchange device is installed on one rotating plug, etc. It has been known.
上記３重回転プラグ直動式の燃料交換装置にあっては、
原子炉上部における回転プラグの構成が複雑大型化し、
燃料交換のために原子炉上部構造が大型化する傾向にあ
る。これは、２重回転プラグ直動式の燃料交換方式にお
いても同様である。In the above-mentioned triple rotating plug direct-acting fuel exchange device,
The configuration of the rotating plug at the top of the reactor has become more complex and larger.
There is a trend toward larger reactor superstructures for fuel exchange. This also applies to the dual rotary plug direct drive type fuel exchange system.
また、オフセットアームを有する２重回転プラグ方式お
よび単回転プラグ方式は、原子炉の大型化に伴いオフセ
ットアームの長さが長くなる傾向にある。Further, in the double-rotation plug type and the single-rotation plug type having an offset arm, the length of the offset arm tends to increase as the size of the nuclear reactor increases.
（発明が解決しようとする課題）
ところで、高速増殖炉の燃料交換装置として、原子炉容
器の上部開口部を覆う遮蔽プラグが固定プラグに回転自
在に設けられる大回転プラグと、この大回転プラグに偏
心位置で回転自在に設けられる小回転プラグとから成り
、小回転プラグに直動式の燃料移送機力く備えられ、大
回転プラグにオフセットアーム方式の燃料交換機が備え
られて、これら燃料移送機と燃刺交換磯の組合せにＪ：
り炉心構成要素を取り扱うようにしたものが開発されて
いる。(Problem to be Solved by the Invention) By the way, as a fuel exchange device for a fast breeder reactor, there is a large-rotation plug in which a shielding plug that covers the upper opening of the reactor vessel is rotatably provided on a fixed plug, and an eccentric position on the large-rotation plug. The small rotating plug is equipped with a direct-acting fuel transfer machine, and the large rotating plug is equipped with an offset arm type fuel exchange machine. J to the combination of exchange rocks:
A system has been developed that deals with core components.
しかしながら、直動式の燃刺移送機は、炉心構成要素を
取り扱うために非常に長尺形状に形成ざれる。そのため
、燃料移送機のメインテナンスのために長大な取扱機が
必要となる。また、原子炉運転中に炉心構成要素出口冷
却祠温度を検出するために燃料交換装置とは別に炉心構
成要素出口冷却材温度計装を取り付ける必要がある。However, direct acting sting transfer machines are formed in a very elongated shape in order to handle the core components. Therefore, a large handling machine is required for maintenance of the fuel transfer machine. Furthermore, in order to detect the core component outlet cooling shrine temperature during reactor operation, it is necessary to install a core component outlet coolant temperature instrument separately from the fuel exchange device.
本発明は上記の事情を考慮してなさたれもので、燃料移
送機を伸縮自在として取扱機のコンパクト化を図ること
ができるとともに、炉心構成要素出口冷却材温度計装を
備えることにより原子炉運転中における炉心構成要素出
口冷却材温度の検出を合理的に行なうことができる燃料
交換装置を提供することを目的とする。The present invention has been made in consideration of the above-mentioned circumstances, and it is possible to make the handling machine more compact by making the fuel transfer machine expandable and retractable, and to operate the reactor by providing a coolant temperature instrumentation at the exit of the reactor core components. It is an object of the present invention to provide a fuel exchange device that can rationally detect the temperature of the coolant at the outlet of a core component in the reactor core.
３
４
〔発明の構成〕
〈課題を解決するための手段）
本発明は、原子炉容器の上部開口部を覆う遮蔽プラグが
固定プラグに回転自在に設【プられる大回転プラグと、
この大回転プラグに偏心位置で回転自在に設【プられる
小回転プラグとを有してなり、その小回転プラグに炉心
燃料領域の範囲内に設けられた中継点より内側の範囲の
炉心構成要素を取り扱う燃料移送機が備えられ、上記大
回転プラグに上記中継点より外側の炉心構成要素を炉外
取出し点まで移送するオフセットアーム方式の燃料交換
機が備えられた燃料交換装置において、上記燃料移送機
は小回転プラグより取り外し可能に設けられるとともに
、先端に炉心構成要素把持用グリッパを備えたグリッパ
支持筒および上部支持筒が軸方向に伸縮自在に形成され
、上記上部支持筒およびグリッパ支持筒を貫通してグリ
ッパ近傍に炉心構成要素出口冷却材温度計装を設けたも
のである。3 4 [Structure of the Invention] (Means for Solving the Problems) The present invention provides a large rotating plug in which a shielding plug that covers the upper opening of a reactor vessel is rotatably installed on a fixed plug;
This large-rotation plug has a small-rotation plug that is rotatably installed at an eccentric position, and the small-rotation plug has core components in the area inside the relay point provided within the range of the core fuel area. In the fuel exchange equipment, the fuel exchange equipment is equipped with a fuel transfer machine for handling the fuel, and the large-rotary plug is equipped with an offset arm type fuel exchange machine for transferring the core components outside the relay point to the extraction point from the reactor. A gripper support tube and an upper support tube are provided to be removable from the rotating plug and have a gripper for gripping core components at the tip thereof, and are formed to be extendable and retractable in the axial direction. A core component outlet coolant temperature instrument is installed near the gripper.
（作用〉
燃料移送機はグリツバ支持筒および上部支持筒により軸
方向に伸縮することができ、軸方向長さを短くした状態
で小回転プラグより取り外してメインテナンスを行なう
ことができるため、取扱槻のコンパクト化を図ることが
できる。また、上部支持筒およびグリッパ支持筒を貫通
してグリッパ近傍に炉心構成要素出口冷却材温度計装′
を設｛づたから、原子炉運転中にお１プる炉心構成要素
出口冷却材温度の検出を合理的に行なうことができる。(Function) The fuel transfer device can be expanded and contracted in the axial direction using the Gritsuba support cylinder and the upper support cylinder, and can be removed from the small rotation plug with the axial length shortened for maintenance. The core component outlet coolant temperature instrumentation can be installed near the gripper through the upper support tube and the gripper support tube.
By establishing this, it is possible to rationally detect the temperature of the coolant at the exit of one of the core components during reactor operation.
（実施例）
本発明に係る燃料交換装置の一実ｍ例について添付図面
を参照して説明する。(Example) An example of a fuel exchange device according to the present invention will be described with reference to the accompanying drawings.
液体金属冷却型の高速増殖炉は、第１図および第２図に
示すように、原子炉容器１内に炉心２が収容され、上部
開口部が上蓋としての遮蔽プラグ３により覆われる。遮
蔽ブラグ３は固定ブラグ４に大回転プラグ５が回転自在
に設けられ、この大回転ブラグ５に小回転ブラグ６が偏
心位直で回転自在に設けられる。In a liquid metal cooled fast breeder reactor, as shown in FIGS. 1 and 2, a reactor core 2 is housed in a reactor vessel 1, and an upper opening is covered by a shielding plug 3 serving as an upper lid. In the shielding plug 3, a large rotation plug 5 is rotatably provided on a fixed plug 4, and a small rotation plug 6 is provided on the large rotation plug 5 so as to be eccentrically rotatable.
炉心２は全炉心領域８と炉心燃料領域９に区画され、炉
心燃Ｆｌ領域９には炉心構成要素１０を移送ずるための
中継点１１が配置される。また、炉心２の外側近傍には
、炉心構成要素を原子炉外に取り出すための炉外取出点
１２が配置ざれる。The core 2 is divided into a total core region 8 and a core fuel region 9, and a relay point 11 for transferring core components 10 is arranged in the core fuel Fl region 9. Further, near the outside of the reactor core 2, an out-of-core take-out point 12 is arranged for taking out core components out of the reactor.
小回転プラグ６には炉心上部機ＭＩｉ１４と、この炉心
上部機構１４の中心に配置される燃料移送機１５とが搭
載される。燃斜移送機１５は大回転プラグ５および小回
転プラグ６の回転により中継点１１に到達することがで
きるとどもに、この中継点１１よりも内側の炉心燃斜領
域９に設けられた炉心構成要素１０を取り扱うこどがで
きるように配設される。また、大回転ブラグ５には、大
回転プラグ５の回転とオフセットアームの伸縮により中
継点１１より外方の炉心燃料領域９と炉外取出点１２と
の間の炉心構成要素１０の移送が可能な燃料交換機１６
が搭載される。The small rotating plug 6 is equipped with an upper core machine MIi 14 and a fuel transfer machine 15 arranged at the center of the upper core machine 14. The fuel angle transfer device 15 can reach the relay point 11 by the rotation of the large-rotation plug 5 and the small-rotation plug 6. It is arranged so that children can handle 10 items. The large-rotation plug 5 also contains fuel that allows the transfer of the core components 10 between the core fuel region 9 outside the relay point 11 and the extraction point 12 by the rotation of the large-rotation plug 5 and the expansion and contraction of the offset arm. Exchange machine 16
will be installed.
Ｍ３図および第４図は燃料移送機１５を示す断面図であ
る。燃料移送機１５は炉心上部機構１４の中心軸と同軸
状に設けられ、周囲に制御棒駆動機構（主炉停止系〉１
８により囲まれる。燃料移送機１５の全体の軸方向支持
は、炉心上部機構１４上面に取り付けられる支持台１９
により行なわれ、水平方向支持は支持台１９と炉心上部
機＋１’ｆｆ １４内に設けられた支持部２０により行
なわれる。FIG. M3 and FIG. 4 are cross-sectional views showing the fuel transfer device 15. The fuel transfer device 15 is provided coaxially with the central axis of the upper core mechanism 14, and is surrounded by a control rod drive mechanism (main reactor shutdown system) 1.
Surrounded by 8. The entire axial support of the fuel transfer device 15 is provided by a support stand 19 attached to the upper surface of the core upper mechanism 14.
Horizontal support is provided by a support stand 19 and a support section 20 provided within the core upper machine +1'ff 14.
燃料移送機１５は外管を構成するホールドダウン筒２２
内に上部支持筒２３およびグリッパ支持筒２４が軸方向
に摺動可能に収容される。上部支持筒２３およびグリッ
パ支持筒２７Ｉは軸方向に伸縮可能に嵌合される。The fuel transfer device 15 has a hold-down tube 22 that constitutes an outer tube.
An upper support tube 23 and a gripper support tube 24 are housed inside the upper support tube 23 so as to be slidable in the axial direction. The upper support tube 23 and the gripper support tube 27I are fitted together so that they can expand and contract in the axial direction.
ホールドダウン筒２２は支持台１つの上部７ランジ１９
ａからグリッパ支持筒２４の先端に設リられた炉心構成
要素掴み用のグリッパ２５の先端の位置まで延びており
、ホールドダウン機構２６により昇降される。The hold down tube 22 is the upper 7 langes 19 of one support base.
a to the tip of a gripper 25 provided at the tip of the gripper support cylinder 24 for gripping core components, and is raised and lowered by a hold-down mechanism 26.
上部支持筒２３はグリッパ支持筒２４を収納可能に形成
され、グリッパ支持呵２４を収納した状態で、グリッパ
２５の先端が冷却材としての液体金属ナトリウム液面上
に出る長さに形成される。The upper support tube 23 is formed to be able to accommodate the gripper support tube 24, and is formed to a length such that the tip of the gripper 25 projects above the surface of the liquid metal sodium as a coolant when the gripper support tube 24 is accommodated.
上部支持筒２３からグリッパ支持筒２４が延びて炉心構
成要素１０を取り扱う状態では、グリッパ２５の先端グ
リッパ２５の先端は液体金属ナトリウム中にある。When the gripper support tube 24 extends from the upper support tube 23 to handle the core component 10, the tip of the gripper 25 The tip of the gripper 25 is in the liquid metal sodium.
上部支持筒２３は炉心上部機構１４の遮蔽プラグ３下面
に相当する位置で下端が支持され、上部の旋回歯車２７
およびキー２８を介してグリッパ支持筒２４とどもに回
転されるようになっている。The upper support cylinder 23 has its lower end supported at a position corresponding to the lower surface of the shielding plug 3 of the core upper mechanism 14, and has a rotating gear 27 at the upper part.
and the gripper support tube 24 via the key 28.
グリッパ支持筒２４は上部にガイドローラ２９が設（プ
られ、炉心構成要素１０との相対位置ずれが生じた際に
先端がホールドダウン筒２２との隙間分だけ傾くことが
できるようになっている。The gripper support cylinder 24 is provided with a guide roller 29 at the top, so that when a relative positional shift with respect to the core component 10 occurs, the tip can be tilted by the gap with the hold-down cylinder 22. .
グリッパ支持筒２４の先端に設けられたグリッパ２５は
、燃料移送！Ｉ１５上部の駆動装置３０に設けられた爪
開閉駆動装置３１により伝導軸３２および爪開閉ロツド
３３を介して伝達される駆動力により爪３４を開閉し、
炉心構成要素１０を把持するようになっている。The gripper 25 provided at the tip of the gripper support tube 24 transfers fuel! The pawl 34 is opened and closed by the driving force transmitted via the transmission shaft 32 and the pawl opening/closing rod 33 by the pawl opening/closing drive device 31 provided on the drive device 30 at the top of the I15,
The core component 10 is gripped.
また、グリッパ支持筒２４の伸縮は、駆動装置３０に備
えられた昇降駆動装置３５から伝導軸３６を介して伝達
される駆動力により行なわれる。Furthermore, the gripper support cylinder 24 is expanded and contracted by a driving force transmitted from an elevating drive device 35 provided in the drive device 30 via a transmission shaft 36.
これらの伝導軸３２．３６はグリッパ支持筒２４が傾い
た際にも駆動力を伝達できるように、上部にユニバーサ
ルジョイント３７が設けられる。上記爪開閉ロツド３３
の中心部には貫通孔が形成され、この爪開閉ロッド３３
、グリッパ支持筒２４および上部支持筒２３を貫通して
グリッパ２５先端に例えば熱電対等の炉心構成要素出口
冷却拐温度計装が設けられる。A universal joint 37 is provided at the top of these transmission shafts 32, 36 so that driving force can be transmitted even when the gripper support tube 24 is tilted. The above claw opening/closing rod 33
A through hole is formed in the center of the claw opening/closing rod 33.
A core component outlet cooling temperature instrument, such as a thermocouple, is provided at the tip of the gripper 25, passing through the gripper support tube 24 and the upper support tube 23.
なお、炉内のカバーガスの漏洩防止のため、支持体１９
の上部フランジ１９ａ近傍にシール装置３９が配置され
、バックアップのために原子炉運転中は支持台１９の上
＠部に上蓋４０が設置され、密閉される。Note that in order to prevent leakage of cover gas in the furnace, the support 19
A sealing device 39 is disposed near the upper flange 19a of the reactor, and for backup purposes, an upper lid 40 is installed on the upper part of the support base 19 during reactor operation to seal it.
メインテナンス時には、第５図に示すように、上蓋４０
を撤去し、固定側ドアバルブ４１を取り付【フ、その後
取扱器４２を設置して燃料移送機１５を引き抜く。この
際、グリッパ支持筒２４は上部支持筒２３内に収納され
、軸方向長さが短くなった状態にあり、上部支持筒２３
、グリッパ支持筒２４および駆動装置３０が一休的に引
き抜かれる。引抜後は、内部の他の駆動機構（ホールド
ダウン機構２６）等のメインテナンスおよび遮蔽のため
に、ブラグ４３が挿入される。また、制御捧駆動機構１
８のメインテナンス時には、支持台１つの上部フランジ
１９ａに形成された開口から上方に引き抜くことがでぎ
る。During maintenance, as shown in FIG.
Remove the fixed side door valve 41 and then install the handling device 42 and pull out the fuel transfer device 15. At this time, the gripper support tube 24 is housed in the upper support tube 23 and its axial length is shortened, and the upper support tube 24
, the gripper support tube 24 and the drive device 30 are temporarily pulled out. After being pulled out, the plug 43 is inserted for maintenance and shielding of other internal drive mechanisms (hold-down mechanism 26), etc. In addition, the control drive mechanism 1
At the time of maintenance of the support stand 8, it is possible to pull it out upward through the opening formed in the upper flange 19a of one support stand.
次に上記実施例の作用について説明する。Next, the operation of the above embodiment will be explained.
燃料移送機１５により炉心構成要素１０を取り扱う場合
には、大回転ブラグ５および小回転プラグ６の回転によ
り燃料移送機１５の位置決めを行ない、その後グリッパ
支持筒２４を昇降駆動装置３５により交換させ、グリッ
パ２５を炉心構成要素１０の上部に到達させる。到達後
、爪開閉駆動装置３１により爪開閉ロツド３３を上下さ
せてグリッパ２５を開閉させ、炉心構成要素１０を掴み
、そのままグリッパ支持筒２４を昇降駆動装置３５によ
り上昇させて炉心２から引き抜く。そして、大回転プラ
グ５および小回転プラグ６を回転させ、炉心構成要素１
０を中継点１１上方へ移送し、上記と逆の手順で中継点
１１内に設置する。When handling the core components 10 with the fuel transfer device 15, the fuel transfer device 15 is positioned by rotating the large rotation plug 5 and the small rotation plug 6, and then the gripper support cylinder 24 is replaced by the lifting drive device 35, and the gripper 25 to reach the top of the core component 10. After reaching the gripper, the gripper 25 is opened and closed by moving the claw opening/closing rod 33 up and down by the claw opening/closing drive device 31 to grasp the core component 10, and then the gripper support cylinder 24 is raised by the lifting drive device 35 and pulled out from the core 2. Then, the large rotation plug 5 and the small rotation plug 6 are rotated, and the core components 1
0 above the relay point 11 and install it inside the relay point 11 by following the procedure reverse to the above.
燃料移送機１５のメインテナンス時には、炉心構成要素
１０の引抜ど同様に昇降駆動装置３５によりグリッパ支
持筒２４を上限まで上界させて−Ｌ部支持筒２３内に収
納し、軸方向長さをできるだけ短尺としてから、上蓋４
０を撤去し、固定側ドアバルブ４１を取り付け、取扱機
４２を設置して燃料移送機１５の引抜を行なう。したが
って、取扱機４２は長大なものが必要でなく、取扱機４
２のコンパクト化を図ることができる。その結果、取扱
時の地震に対する支持構造の大幅な簡素化を図ることが
できる。During maintenance of the fuel transfer device 15, the gripper support tube 24 is raised to the upper limit by the lifting drive device 35 and stored in the -L section support tube 23 in the same manner as when the core component 10 is pulled out, thereby reducing the axial length as much as possible. After making it a short length, attach the top lid 4
0 is removed, a fixed side door valve 41 is attached, a handling machine 42 is installed, and the fuel transfer machine 15 is pulled out. Therefore, the handling machine 42 does not need to be long, and the handling machine 42 does not need to be long.
2 can be made more compact. As a result, the support structure against earthquakes during handling can be significantly simplified.
また、上部支持筒２３、グリッパ支持筒２４および爪開
閉ロツド３３を貫通してグリッパ２５の先端に炉心構成
要素出口冷却材温度計装を設けたから、他の温度検出手
段を別個に設ける必要がなく、炉心構成要素出口冷却材
温度の検出を合理的に行なうことがでぎる。しかも、炉
心構成要素出口冷却材温度計装を必要に応じて炉外に取
り出して交換することがでぎるため、信頼性の向上を図
ることができる。In addition, since the core component outlet coolant temperature instrument is provided at the tip of the gripper 25 through the upper support tube 23, gripper support tube 24, and claw opening/closing rod 33, there is no need to separately provide other temperature detection means. , it is possible to rationally detect the coolant temperature at the outlet of the core components. Furthermore, since the core component outlet coolant temperature instrumentation can be taken out of the reactor and replaced as necessary, reliability can be improved.
１１
１２
本発明は、燃料移送機が小回転プラグより取り外してメ
インテナンス可能に設けられるとともに、先端に炉心構
戒要素把持用グリッパを備えたグリッパ支持筒および上
部支持筒が軸方向に伸縮自在に形成されたから、メイン
テナンス時に軸方向に伸縮させて全長を短くして取り出
すことができる。したがって、メインテナンス時に使用
する取扱機のコンバク１〜化を図ることができる。11 12 The present invention provides a fuel transfer device that can be removed from a small rotation plug for maintenance, and that a gripper support cylinder and an upper support cylinder equipped with a gripper for gripping core control elements at the tip are formed to be expandable and retractable in the axial direction. Therefore, during maintenance, it can be expanded and contracted in the axial direction to shorten the overall length and be removed. Therefore, it is possible to reduce the number of handling machines used during maintenance.
また、上部支持筒およびグリッパ支持筒を貫通してグリ
ッパ近傍に炉心構成要素出口冷却材温度計装を設けたか
ら、他の温度検出手段を別個に設ける必要がなく、炉心
構成要素出口冷却材温度の検出を合理的に行なうことが
できる。In addition, since the core component outlet coolant temperature instrumentation is provided near the gripper by penetrating the upper support tube and the gripper support tube, there is no need to separately provide other temperature detection means, and the core component outlet coolant temperature can be measured. Detection can be performed rationally.
送機の上部を示す拡大断面図、第５図は上記実施例にお
いて燃料移送機のメインテナンス時にお（ブる取外し作
業を示す断面図である。FIG. 5 is an enlarged cross-sectional view showing the upper part of the fuel transfer device, and FIG. 5 is a cross-sectional view showing the removal work performed during maintenance of the fuel transfer device in the above embodiment.
１・・・原子炉容器、２・・・炉心、３・・・遮蔽プラ
グ、４・・・固定プラグ、５・・・大回転プラグ、６・
・・小回転プラグ、８・・・全炉心領域、９・・・炉心
燃斜領域、１０・・・炉心構成要素、１１・・・中継点
、１２・・・炉外取出点、１４・・・炉心上部機構、１
５・・・燃料移送機、１６・・・燃料交換機、１８・・
・制御棒駆動機構、１つ・・・支持台、２２・・・ホー
ルドダウン筒、２３・・・上部支持筒、２４・・・グリ
ッパ支持筒、２５・・・グリツバ、３０・・・駆動装置
、３２．３６・・・伝導軸、３３・・・爪開閉ロツド。DESCRIPTION OF SYMBOLS 1... Reactor vessel, 2... Reactor core, 3... Shielding plug, 4... Fixed plug, 5... Large rotating plug, 6...
...Small rotation plug, 8.. Entire core region, 9.. Core combustion angle region, 10.. Core components, 11.. Relay point, 12.. Output point, 14..・Core upper mechanism, 1
5... Fuel transfer machine, 16... Fuel exchange machine, 18...
・Control rod drive mechanism, 1...Support stand, 22...Hold down tube, 23...Upper support tube, 24...Gripper support tube, 25...Gripper, 30...Drive device , 32.36...Transmission shaft, 33...Claw opening/closing rod.
Claims (1)
グに回転自在に設けられる大回転プラグと、この大回転
プラグに偏心位置で回転自在に設けられる小回転プラグ
とを有してなり、その小回転プラグに炉心燃料領域の範
囲内に設けられた中継点より内側の範囲の炉心構成要素
を取り扱う燃料移送機が備えられ、上記大回転プラグに
上記中継点より外側の炉心構成要素を炉外取出し点まで
移送するオフセットアーム方式の燃料交換機が備えられ
た燃料交換装置において、上記燃料移送機は小回転プラ
グより取り外し可能に設けられるとともに、先端に炉心
構成要素把持用グリッパを備えたグリッパ支持筒および
上部支持筒が軸方向に伸縮自在に形成され、上記上部支
持筒およびグリッパ支持筒を貫通してグリッパ近傍に炉
心構成要素出口冷却材温度計装を設けたことを特徴とす
る燃料交換装置。A shielding plug that covers the upper opening of the reactor vessel has a large rotation plug that is rotatably provided on a fixed plug, and a small rotation plug that is rotatably provided on the large rotation plug at an eccentric position. is equipped with a fuel transfer machine that handles the core components inside the relay point provided within the range of the core fuel area, and transfers the core components outside the relay point to the large rotation plug to the extraction point. In a refueling device equipped with an offset arm type refueling device, the fuel transfer device is provided removably from a small rotation plug, and includes a gripper support cylinder and an upper support cylinder equipped with a gripper for gripping core components at the tip. 1. A refueling device, characterized in that a core component outlet coolant temperature instrument is provided in the vicinity of the gripper by penetrating the upper support tube and the gripper support tube.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1163785A JPH0329893A (en) | 1989-06-28 | 1989-06-28 | Refuelling device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1163785A JPH0329893A (en) | 1989-06-28 | 1989-06-28 | Refuelling device |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0329893A true JPH0329893A (en) | 1991-02-07 |
Family
ID=15780664
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1163785A Pending JPH0329893A (en) | 1989-06-28 | 1989-06-28 | Refuelling device |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0329893A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2013509584A (en) * | 2009-11-02 | 2013-03-14 | シーレイト リミテッド ライアビリティー カンパニー | Standing wave fission reactor and method |
-
1989
- 1989-06-28 JP JP1163785A patent/JPH0329893A/en active Pending
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2013509584A (en) * | 2009-11-02 | 2013-03-14 | シーレイト リミテッド ライアビリティー カンパニー | Standing wave fission reactor and method |
| US9236150B2 (en) | 2009-11-02 | 2016-01-12 | Terrapower, Llc | Standing wave nuclear fission reactor and methods |
| US9653187B2 (en) | 2009-11-02 | 2017-05-16 | Terrapower, Llc | Standing wave nuclear fission reactor and methods |
| US11482344B2 (en) | 2009-11-02 | 2022-10-25 | Terrapower, Llc | Standing wave nuclear fission reactor and methods |
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