JPH0375594A - Fast breeder reactor - Google Patents
Fast breeder reactorInfo
- Publication number
- JPH0375594A JPH0375594A JP1211409A JP21140989A JPH0375594A JP H0375594 A JPH0375594 A JP H0375594A JP 1211409 A JP1211409 A JP 1211409A JP 21140989 A JP21140989 A JP 21140989A JP H0375594 A JPH0375594 A JP H0375594A
- Authority
- JP
- Japan
- Prior art keywords
- reactor
- plenum
- support structure
- coolant circulation
- core
- 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
- 239000002826 coolant Substances 0.000 claims abstract description 31
- 230000008439 repair process Effects 0.000 claims abstract description 29
- 230000035515 penetration Effects 0.000 claims abstract description 5
- 238000005192 partition Methods 0.000 claims description 11
- 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 abstract description 10
- 229910052708 sodium Inorganic materials 0.000 abstract description 10
- 239000011734 sodium Substances 0.000 abstract description 10
- 239000007788 liquid Substances 0.000 abstract description 9
- 230000004888 barrier function Effects 0.000 abstract 4
- 239000000446 fuel Substances 0.000 description 2
- 230000000149 penetrating effect Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 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)
Abstract
Description
【発明の詳細な説明】
[発明の目的]
(産業上の利用分野)
本発明は高速増殖炉に係り、特に炉内の補修性に関する
ものである。[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to a fast breeder reactor, and particularly relates to repairability within the reactor.
(従来の技術)
一般に冷却材として液体ナトリウム等の液体金属を用い
る高速増殖炉は、原子炉容器内を高温領域(ホットプレ
ナム)と低温領域(コールドプレナム)とに断熱分離す
る隔壁を有し、原子炉容器の上部を閉塞するループスラ
ブ上には複数台の中間熱交換器と冷却材循環ポンプが搭
載されている。これらの搭載機器は上記隔壁を貫通して
炉心の周囲に配設されており、ホットプレナムから中間
熱交換器に流入した高温の冷却材(液体ナトリウム)は
ここで二次冷却材と熱交換を行ない、冷却されてコール
ドプレナムに流出する構造となっている。(Prior Art) A fast breeder reactor that generally uses liquid metal such as liquid sodium as a coolant has a partition wall that adiabatically separates the inside of the reactor vessel into a high temperature region (hot plenum) and a low temperature region (cold plenum). Multiple intermediate heat exchangers and coolant circulation pumps are mounted on the loop slab that closes off the top of the reactor vessel. These onboard devices penetrate the bulkhead and are installed around the core, and the high-temperature coolant (liquid sodium) that flows from the hot plenum into the intermediate heat exchanger exchanges heat with the secondary coolant. The structure is such that it is cooled and flows out into the cold plenum.
一方、コールドプレナムから冷却材循環ポンプに流入し
た低温の冷却材は、炉内配管を通って炉心支持構造物の
人口プレナムに流入する。そして、人口プレナムに流入
した冷却材は高圧プレナムから炉心内に流入し、炉心内
を下方から上方へ流通する。この間に冷却材は燃料の核
反応熱によって高温に加熱され、炉心上部からホットプ
レナムに流出して上述した流路を循環するようになって
いる。On the other hand, the low-temperature coolant flowing into the coolant circulation pump from the cold plenum flows into the artificial plenum of the core support structure through the reactor piping. The coolant that has flowed into the artificial plenum flows into the reactor core from the high-pressure plenum and flows from the bottom to the top in the core. During this time, the coolant is heated to a high temperature by the nuclear reaction heat of the fuel, flows out from the upper part of the core to the hot plenum, and circulates through the above-mentioned flow path.
(発明が解決しようとする課題)
ところで、このような高速増殖炉では炉心支持構造物や
隔壁などの炉内構造物が損傷しないように設計余裕を十
分にとり、損傷発生の可能性が極めて少ない設計として
いるが、たとえばコールドプレナム内で万が一補修の必
要性が生じた場合には中間熱交換器や冷却材循環ポンプ
などの搭載機器を引き抜き、ループスラブおよび隔壁の
貫通孔から補修箇所への接近を図ることになる。この場
合、補修装置としては種々のものが考えられるが、例え
ば棒状のコラムにマニピュレータを取り付けたものでは
マニピュレータの長さに限界があり、コールドプレナム
内の全ての領域に接近することは構造上困難という問題
があった。(Problem to be solved by the invention) By the way, in such a fast breeder reactor, sufficient design margin is provided to prevent damage to core support structures, bulkheads, and other reactor internal structures, and the design is designed to minimize the possibility of damage occurring. However, in the unlikely event that repairs are required in the cold plenum, it is possible to pull out installed equipment such as intermediate heat exchangers and coolant circulation pumps, and access the repair area through through holes in the loop slab and bulkhead. I will try to figure it out. In this case, various repair devices can be considered, but for example, if a manipulator is attached to a rod-shaped column, there is a limit to the length of the manipulator, and it is structurally difficult to access all areas within the cold plenum. There was a problem.
本発明の目的はこのような問題点に鑑みてなされたもの
で、補修装置をコールドプレナム内の全ての領域に接近
させることのできる高速増殖炉を堤供することにある。SUMMARY OF THE INVENTION An object of the present invention has been made in view of these problems, and is to provide a fast breeder reactor that allows repair equipment to approach all areas within the cold plenum.
[発明の構成]
(課題を解決するための手段)
上記目的を達成するために本発明は、冷却材を収容した
原子炉容器と、この原子炉容器内に炉心支持構造物を介
して設置された炉心と、上記原子炉容器内を高温領域と
低温領域に断熱分離する隔壁と、上記原子炉容器の上部
を閉塞するループスラブと、このループスラブ上に搭載
され上記隔壁を貫通して炉心の周囲に配設された複数台
の冷却材循環ポンプおよび中間熱交換器とを有する高速
増殖炉において、前記冷却材循環ポンプまたは前記中間
熱交換器の隔壁貫通部に端部を有する補修装置走行用レ
ールを前記炉心支持構造物の外周に沿って敷設したもの
である。[Structure of the Invention] (Means for Solving the Problems) In order to achieve the above object, the present invention includes a reactor vessel containing a coolant, and a nuclear reactor vessel installed within the reactor vessel via a core support structure. a bulkhead that adiabatically separates the inside of the reactor vessel into a high-temperature region and a low-temperature region; a loop slab that closes off the upper part of the reactor vessel; In a fast breeder reactor having a plurality of coolant circulation pumps and intermediate heat exchangers disposed around the reactor, a repair device for running has an end at a partition wall penetrating portion of the coolant circulation pump or the intermediate heat exchanger. Rails are laid along the outer periphery of the core support structure.
(作 用)
すなわち、本発明は冷却材循環ポンプまたは中間熱交換
器の隔壁貫通部に端部を有する補修装置走行用レールを
炉心支持構造物の外周に沿って敷設することにより、補
修装置を炉心支持構造物の外周に沿って設けられた補修
装置走行用レール上を走行させることができ、これによ
り補修装置をコールドブレナム内の全ての領域に接近さ
せることが可能となる。(Function) That is, the present invention installs a repair device running rail having an end at the partition wall penetrating portion of the coolant circulation pump or the intermediate heat exchanger along the outer periphery of the core support structure. The repair equipment can run on rails provided along the outer periphery of the core support structure, allowing the repair equipment to approach all areas within the cold brenum.
(実施例) 以下、図面を参照して本発明の詳細な説明する。(Example) Hereinafter, the present invention will be described in detail with reference to the drawings.
第1図ないし第3図は本発明の一実施例を示し、第1図
は高速増殖炉の概略構成を示したものである。同図にお
いて、原子炉容器1内には冷却材として液体ナトリウム
2が収容されていると共に炉心3が炉心支持構造物4上
に設置されている。この炉心支持構造物4は原子炉容器
1の底部に溶接結合された炉心支持スカート5上にボル
ト固定されており、炉心支持構造物4の外周部には人口
プレナム6が形成されている。1 to 3 show one embodiment of the present invention, and FIG. 1 shows a schematic configuration of a fast breeder reactor. In the figure, a reactor vessel 1 contains liquid sodium 2 as a coolant, and a reactor core 3 is installed on a core support structure 4. The core support structure 4 is bolted onto a core support skirt 5 welded to the bottom of the reactor vessel 1, and an artificial plenum 6 is formed around the outer periphery of the core support structure 4.
一方、原子炉容器1の上部にはループスラブ7が設置さ
れ、このループスラブ7によって原子炉容器1の上部開
口が気密に閉塞されている。そして、上記ループスラブ
7上には複数台の中間熱交換器8と冷却材循環ポンプ9
が搭載されている。On the other hand, a loop slab 7 is installed at the top of the reactor vessel 1, and the loop slab 7 hermetically closes the upper opening of the reactor vessel 1. A plurality of intermediate heat exchangers 8 and a coolant circulation pump 9 are disposed on the loop slab 7.
is installed.
これらの中間熱交換器8および冷却材循環ポンプ9は、
原子炉容器1内をホットプレナム10とコールドプレナ
ム11に断熱分離する隔壁12゜13を貫通して炉心3
の周囲に配設されており、冷却材循環ポンプ9の吐出口
には炉内配管14が接続されている。この炉内配管14
は前記入口プレナム6に接続されており、コールドプレ
ナム11から冷却材循環ポンプ9に流入した低温の液体
ナトリウム2は炉内配管14を通って入口プレナム6に
流入する構造となっている。These intermediate heat exchanger 8 and coolant circulation pump 9 are
The reactor core 3 penetrates through partition walls 12 and 13 that adiabaticly separate the inside of the reactor vessel 1 into a hot plenum 10 and a cold plenum 11.
The furnace piping 14 is connected to the discharge port of the coolant circulation pump 9 . This furnace piping 14
is connected to the inlet plenum 6, and the low temperature liquid sodium 2 flowing into the coolant circulation pump 9 from the cold plenum 11 flows into the inlet plenum 6 through the furnace piping 14.
また、上記人口プレナム6の内側には高圧プレナム15
が形成されており、人口プレナム6に流入した液体ナト
リウム2は高圧プレナム15から炉心3内に流入し、炉
心3内を下方から上方へ流通する。そして、この間に液
体ナトリウム2は図示しない炉心燃料の核反応熱によっ
て高温に加熱され、炉心3の上部からホットプレナム1
0に流出するようになっている。なお、炉心3の上部か
らホットプレナム10に流出した高温の液体ナトリウム
2は中間熱交換器8に流入し、ここで二次冷却材と熱交
換を行った後、コールドプレナム11に流出するように
なっている。Also, inside the artificial plenum 6, there is a high pressure plenum 15.
The liquid sodium 2 that has flowed into the artificial plenum 6 flows into the reactor core 3 from the high-pressure plenum 15 and flows within the reactor core 3 from below to above. During this time, the liquid sodium 2 is heated to a high temperature by the nuclear reaction heat of the core fuel (not shown), and is passed from the top of the core 3 to the hot plenum 1.
It is designed to flow out to 0. The high-temperature liquid sodium 2 flowing out from the upper part of the core 3 into the hot plenum 10 flows into the intermediate heat exchanger 8, where it exchanges heat with the secondary coolant, and then flows out into the cold plenum 11. It has become.
また、前記原子炉容器1内には補修装置走行用レール1
6が設けられている。この補修装置走行用レール16は
冷却材循環ポンプ9の周囲に設けられたスタンドパイプ
17と隔壁13との接合部付近に一端部を持ち、炉心支
持構造物4の外周に沿ってスタッド18により隔壁13
の壁面に取り付けられている。Furthermore, inside the reactor vessel 1, there is a rail 1 for running the repair equipment.
6 is provided. This repair equipment running rail 16 has one end near the joint between the stand pipe 17 provided around the coolant circulation pump 9 and the bulkhead 13, and has a stud 18 along the outer periphery of the core support structure 4 to form the bulkhead. 13
is attached to the wall.
このような構成において、原子炉容器1と隔壁13およ
び炉心支持構造物4で囲まれた空間すなわちコールドプ
レナム11内で補修を必要とする事態が生じた場合には
、まず炉心3を撤去すると共に肢体ナトリウム2を全量
ドレンし、さらに冷却材循環ポンプ9を引き抜く。そし
て、ループスラブ7の貫通孔からマニピュレータを搭載
した補修装置(図示せず)を吊り降ろし、補修装置走行
用レール16に掘え付けることにより、補修装置を炉心
支持構造物4の外周に沿って設けられた補修装置走行用
レール16上を走行させることができる。したがって、
本実施例ではコールドブレナム11内で補修を必要とす
る事態が生じた場合でも補修装置のマニピュレータを遠
隔操作により補修箇所に接近させることができる。In such a configuration, if a situation that requires repair occurs in the space surrounded by the reactor vessel 1, bulkhead 13, and core support structure 4, that is, within the cold plenum 11, the reactor core 3 is first removed and The entire limb sodium 2 is drained, and the coolant circulation pump 9 is pulled out. Then, by suspending a repair device (not shown) equipped with a manipulator from the through hole of the loop slab 7 and digging it into the repair device traveling rail 16, the repair device is moved along the outer periphery of the core support structure 4. The repair device can run on the provided repair device running rails 16. therefore,
In this embodiment, even if a situation requiring repair occurs within the cold blemish 11, the manipulator of the repair device can be brought close to the repair location by remote control.
なお、上記実施例では補修装置走行用レール16の端部
を冷却材循環ポンプ9の隔壁貫通部付近に設けたが、中
間熱交換器8の隔壁貫通部付近に補修装置走行用レール
16の端部を設けてもよい。In the above embodiment, the end of the repair equipment running rail 16 was provided near the partition wall penetration part of the coolant circulation pump 9, but the repair equipment running rail 16 was provided with an end near the partition wall penetration part of the intermediate heat exchanger 8. A section may be provided.
[発明の効果〕
以上説明したように本発明は、冷却材を収容した原子炉
容器と、この原子炉容器内に炉心支持構造物を介して設
置された炉心と、上記原子炉容器内を高温領域と低温領
域に断熱分離する隔壁と、上記原子炉容器の上部を閉塞
するループスラブと、このループスラブ上に搭載され上
記隔壁を貫通して炉心の周囲に配設された複数台の冷却
材循環ポンプおよび中間熱交換器とを有する高速増殖炉
において、前記冷却材循環ポンプまたは前記中間熱交換
器の隔壁貫通部に端部を有する補修装置走行用レールを
前記炉心支持構造物の外周に沿って敷設したものである
。[Effects of the Invention] As explained above, the present invention provides a reactor vessel containing a coolant, a reactor core installed in the reactor vessel via a core support structure, and a reactor vessel that is heated to high temperatures. A bulkhead that insulates and separates the reactor vessel from the low-temperature zone, a loop slab that closes off the upper part of the reactor vessel, and a plurality of coolant units that are mounted on the loop slab, penetrate the bulkhead, and are arranged around the reactor core. In a fast breeder reactor having a circulation pump and an intermediate heat exchanger, a repair device running rail having an end at a partition wall penetration portion of the coolant circulation pump or the intermediate heat exchanger is provided along the outer periphery of the core support structure. It was installed by
したがって、コールドプレナム内で補修を必要とする事
態が生じた場合に補修装置を炉心支持構造物の外周に沿
って設けられた捕修装置走行用レール上を走行させるこ
とができ、これにより補修装置をコールドプレナム内の
全ての領域に接近させることが可能となるので、炉内の
補修性を向上させることができる。Therefore, when a situation requiring repair occurs in the cold plenum, the repair equipment can be run on the rails for running the repair equipment installed along the outer periphery of the core support structure. Since it becomes possible to approach all areas within the cold plenum, repairability within the furnace can be improved.
第1図ないし第3図は本発明の一実施例を示し、第1図
は高速増殖炉の概略構成図、第2図は第1図に示す矢印
方向から見た補修装置走行用レールの展開図、第3図は
第1図のA部を示す詳細図である。
1・・・原子炉容器、2・・・液体ナトリウム、3・・
・炉心、4・・・炉心支持構造物、5・・・炉心支持ス
カート、6・・・人口プレナム、7・・・ループスラブ
、8・・・中間熱交換器、9・・・冷却材循環ポンプ、
10・・・ホットプレナム、11・・・コールドプレナ
ム、12.13・・・隔壁、14・・・炉内配管、15
・・・高圧プレナム、16・・・補修装置走行用レール
。1 to 3 show one embodiment of the present invention, FIG. 1 is a schematic diagram of a fast breeder reactor, and FIG. 2 is a development of the rail for running the repair equipment as seen from the direction of the arrow shown in FIG. 1. 3 are detailed views showing section A in FIG. 1. 1... Reactor vessel, 2... Liquid sodium, 3...
- Core, 4... Core support structure, 5... Core support skirt, 6... Population plenum, 7... Loop slab, 8... Intermediate heat exchanger, 9... Coolant circulation pump,
10... Hot plenum, 11... Cold plenum, 12.13... Partition wall, 14... Furnace piping, 15
...High pressure plenum, 16...Repair equipment running rail.
Claims (1)
心支持構造物を介して設置された炉心と、上記原子炉容
器内を高温領域と低温領域に断熱分離する隔壁と、上記
原子炉容器の上部を閉塞するループスラブと、このルー
プスラブ上に搭載され上記隔壁を貫通して炉心の周囲に
配設された複数台の冷却材循環ポンプおよび中間熱交換
器とを有する高速増殖炉において、前記冷却材循環ポン
プまたは前記中間熱交換器の隔壁貫通部に端部を有する
補修装置走行用レールを前記炉心支持構造物の外周に沿
って敷設したことを特徴とする高速増殖炉。A reactor vessel containing a coolant, a reactor core installed in the reactor vessel via a core support structure, a partition wall that adiabatically separates the interior of the reactor vessel into a high temperature region and a low temperature region, and the reactor In a fast breeder reactor that has a loop slab that closes the upper part of the vessel, and a plurality of coolant circulation pumps and intermediate heat exchangers that are mounted on the loop slab and are arranged around the reactor core passing through the partition wall. A fast breeder reactor, characterized in that a repair device running rail having an end at a partition wall penetration portion of the coolant circulation pump or the intermediate heat exchanger is laid along the outer periphery of the core support structure.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1211409A JPH0375594A (en) | 1989-08-18 | 1989-08-18 | Fast breeder reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP1211409A JPH0375594A (en) | 1989-08-18 | 1989-08-18 | Fast breeder reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
JPH0375594A true JPH0375594A (en) | 1991-03-29 |
Family
ID=16605479
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP1211409A Pending JPH0375594A (en) | 1989-08-18 | 1989-08-18 | Fast breeder reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPH0375594A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2007000312A (en) * | 2005-06-23 | 2007-01-11 | Mitsuhiro Kurashige | End seating position auxiliary legless chair |
-
1989
- 1989-08-18 JP JP1211409A patent/JPH0375594A/en active Pending
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JP2007000312A (en) * | 2005-06-23 | 2007-01-11 | Mitsuhiro Kurashige | End seating position auxiliary legless chair |
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