JPS633292A - Fast breeder reactor - Google Patents
Fast breeder reactorInfo
- Publication number
- JPS633292A JPS633292A JP61147593A JP14759386A JPS633292A JP S633292 A JPS633292 A JP S633292A JP 61147593 A JP61147593 A JP 61147593A JP 14759386 A JP14759386 A JP 14759386A JP S633292 A JPS633292 A JP S633292A
- Authority
- JP
- Japan
- Prior art keywords
- primary
- coolant
- reactor
- heat exchanger
- 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.)
- Pending
Links
- 239000002826 coolant Substances 0.000 claims description 69
- 238000001816 cooling Methods 0.000 description 31
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 10
- 238000010276 construction Methods 0.000 description 8
- 239000000463 material Substances 0.000 description 7
- 229910001338 liquidmetal Inorganic materials 0.000 description 6
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical group [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 5
- 238000005192 partition Methods 0.000 description 5
- 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 3
- 238000001704 evaporation Methods 0.000 description 3
- 230000008020 evaporation Effects 0.000 description 3
- 230000005284 excitation Effects 0.000 description 3
- 229910052708 sodium Inorganic materials 0.000 description 3
- 239000011734 sodium Substances 0.000 description 3
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 239000003795 chemical substances by application Substances 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 230000007246 mechanism Effects 0.000 description 1
- 230000009257 reactivity Effects 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
- Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
Abstract
(57)【要約】本公報は電子出願前の出願データであるた
め要約のデータは記録されません。(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.
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の高速増殖炉に係り、特に、炉
心および一次冷却系と、二次冷ｎＩ系とをモジュール化
した高速増殖炉に関する。[Detailed Description of the Invention] [Object of the Invention] (Industrial Application Field) The present invention relates to a liquid metal cooled fast breeder reactor, and in particular, the present invention relates to a liquid metal cooled fast breeder reactor, and in particular, a reactor core, a primary cooling system, and a secondary cooling nI system are assembled into modules. Concerning fast breeder reactors that have become more advanced.
（従来の技術）
一般に、高速増殖炉では一次冷却材として液体金属ナト
リウム等の液体金属が使用されている。(Prior Art) Generally, a liquid metal such as liquid metal sodium is used as a primary coolant in a fast breeder reactor.
このような原子炉では炉心を通過する一次冷却材が強く
放射化される等の理由から、一次循環ポンプによって一
次冷却材を炉心および中間熱交換器を介して循環させ、
この中間熱交換器で二次冷却材と熱交換し、さらにこの
二次冷却材を二次循環ポンプにより蒸気発生器等を介し
て循環ざぜて高圧蒸気を４ｑるように構成されている。In such a nuclear reactor, the primary coolant passing through the core is strongly activated, so a primary circulation pump circulates the primary coolant through the core and intermediate heat exchanger.
This intermediate heat exchanger exchanges heat with the secondary coolant, and the secondary coolant is further circulated through a steam generator etc. by a secondary circulation pump to generate 4q of high-pressure steam.
このような高速増殖炉には大別して、いわゆるループ型
とタンク型の２種類がある。ループ型高速増殖炉の一例
としては第６図に示すものがあり、これは一次冷却系■
、二次冷却系■および蒸気系■を有し、原子炉容器１ｏ
１内に液体金属ナトリウム等の一次冷却材１０２および
炉心１０３を収容している。There are two types of fast breeder reactors: loop type and tank type. An example of a loop type fast breeder reactor is shown in Figure 6, which has a primary cooling system.
, has a secondary cooling system ■ and a steam system ■, and has a reactor vessel 1o.
1 contains a primary coolant 102 such as liquid metal sodium and a reactor core 103.
炉心１０３は図示しない複数の燃料集合体および制御棒
等から構成され、原子炉容器１０１の上部間口１０４は
ルーフスラブ１０５により閉塞されている。The reactor core 103 is composed of a plurality of fuel assemblies and control rods (not shown), and the upper opening 104 of the reactor vessel 101 is closed by a roof slab 105.
原子炉容器１０１は一次冷却配管１０６を介して中間熱
交換器１０７の一次側および一次循環ポンプ１０８を順
次、かつループ状に接続して、一次冷却材１０２を循環
させる閉ループの一次冷却系工を形成している。The reactor vessel 101 has a closed-loop primary cooling system in which the primary coolant 102 is circulated by connecting the primary side of the intermediate heat exchanger 107 and the primary circulation pump 108 sequentially and in a loop via primary cooling piping 106. is forming.
また、中間熱交換器１０７の一次側と熱交換を行なう二
次側には、二次冷却配管１０９を介して蒸気発生器１１
０の外１１内側とその伝熱管１１０Ａの外側との冷却流
路と、二次循環ポンプ１１１とを順次、かつループ状に
接続し、二次冷却材１１２を循環させる閉ループの二次
冷却系■を形成している。In addition, a steam generator 11 is connected to the secondary side that exchanges heat with the primary side of the intermediate heat exchanger 107 via a secondary cooling pipe 109.
A closed-loop secondary cooling system in which the cooling flow path between the inside of the outside 11 of the 0 and the outside of the heat transfer tube 110A and the secondary circulation pump 111 are connected sequentially and in a loop, and the secondary coolant 112 is circulated. is formed.
さらに、蒸気発生器１１０の伝熱管１１０Ａの蒸気出口
には蒸気管１１３を介して蒸気タービン１１４の蒸気入
口を連通し、タービン復水器１１５に給水ポンプ１１６
を介装した復水管１１７を介して蒸気発生器１１０の伝
熱管１１０Ａの給水入口を連通して蒸気系■を形成して
いる。Furthermore, the steam outlet of the heat transfer tube 110A of the steam generator 110 is connected to the steam inlet of a steam turbine 114 via a steam pipe 113, and a water supply pump 116 is connected to a turbine condenser 115.
The water supply inlet of the heat transfer tube 110A of the steam generator 110 is communicated with the water supply inlet of the heat transfer tube 110A of the steam generator 110 through a condensate pipe 117 interposed therein, thereby forming a steam system (2).
したがって、原子炉容器１０１内の炉心１０３で加熱さ
れて高温に昇温した一次冷却材１０２は中間熱交換器１
０７で二次冷却材１１２を加熱する一方で冷却され、原
子炉容器１０１内に再び還流される。Therefore, the primary coolant 102 heated in the core 103 in the reactor vessel 101 and heated to a high temperature is transferred to the intermediate heat exchanger 1.
At 07, the secondary coolant 112 is heated while being cooled, and is returned to the reactor vessel 101.
一方、中間熱交換器１０７で加熱された高温の二次冷却
材１１２は蒸気発生器１１０にて、その伝熱管１１０Ａ
に供給された給水を加熱して蒸気を発生させる一方で冷
却され、再び中間熱交換器１０７に戻される。゛
蒸気発生器１１０で発生した蒸気は蒸気タービン１１４
に送られて仕事をし、蒸気タービン１１４は発電機１１
８を駆動して発電させる。On the other hand, the high temperature secondary coolant 112 heated by the intermediate heat exchanger 107 is transferred to the steam generator 110 through its heat transfer tube 110A.
The feed water supplied to the intermediate heat exchanger 107 is heated to generate steam while being cooled and returned to the intermediate heat exchanger 107 again.゛The steam generated in the steam generator 110 is sent to the steam turbine 114.
The steam turbine 114 is sent to the generator 11 to do work.
8 to generate electricity.
蒸気タービン１１４で仕事をした蒸気はタービン復水器
１１５で冷却されて復水に凝縮し、この復水は復水管１
１７を通して給水として蒸気発生器１１０に給水される
。The steam that has done work in the steam turbine 114 is cooled in the turbine condenser 115 and condensed into condensate, and this condensate is passed through the condensate pipe 1.
Water is supplied to the steam generator 110 as feed water through 17.
第７図はタンク型高速増殖炉の構成の一例を示しており
、これは上述した従来例の一次冷却系■を原子炉容器２
０１内に収容している。Figure 7 shows an example of the configuration of a tank-type fast breeder reactor, in which the conventional primary cooling system
It is stored in 01.
すなわち、原子炉容器２０１内には一次冷却材２０２お
よび炉心２０３を収容し、炉心２０３を図示しない複数
の燃料集合体および制御棒等から構成して、炉心支持曙
橋２０４を介して前記原子炉容器２０１に支持されてい
る。That is, a reactor vessel 201 houses a primary coolant 202 and a reactor core 203, and the reactor core 203 is composed of a plurality of fuel assemblies and control rods (not shown), and is connected to the reactor vessel via a core support bridge 204. It is supported by 201.
原子炉容器２０１内は隔壁２０５により上下に２分され
、上部を上部プレナム２０６とし、下部を下部プレナム
２０７として、原子炉容器２０１の上部開口２０１Ａは
ルーフスラブ２０８により閉塞して、その内部の炉心２
０３の外周側には一次系■の中間熱交換器２０９および
一次循環ポンプ２１０の複数台が周方向に等間隔をおい
て交互に配置されている。The interior of the reactor vessel 201 is vertically divided into two parts by a partition wall 205, with the upper part serving as an upper plenum 206 and the lower part serving as a lower plenum 207. The upper opening 201A of the reactor vessel 201 is closed by a roof slab 208, and the core inside thereof is 2
On the outer circumferential side of 03, a plurality of primary system (2) intermediate heat exchangers 209 and primary circulation pumps 210 are alternately arranged at equal intervals in the circumferential direction.
なお、図中符号２１１は原子炉建屋、符号２１２は安全
容器を示し、また、二次冷却配管■と蒸気系■とは第６
図で示すループ型のものと同様に構成されているので、
第７図中、同一部分には同−Ｎ号を付して、その重複し
た説明は省略する。In addition, the reference numeral 211 in the figure indicates the reactor building, the reference numeral 212 indicates the safety container, and the secondary cooling pipe ■ and the steam system ■ are the sixth
It has the same structure as the loop type shown in the figure, so
In FIG. 7, the same parts are marked with the same numbers, and redundant explanations thereof will be omitted.
このような従来例によると一次冷却材２０２は炉心２０
３の核反応熱により加熱されて高温に昇温する。高温の
一次冷却材２０２は上部プレナム２０６内に流出してか
ら中間熱交換器２０９内に流入し、ここで、二次冷却材
１１２と熱交換して冷却される。冷却された一次冷却材
２０２は原子炉容器２０１内の下部プレナム２０７内に
流入し、さらに一次循環ポンプ２１０内に流入する。こ
の一次循環ポンプ２１０により加圧されて再度、炉心２
０３の下方に供給される。According to such a conventional example, the primary coolant 202 is
It is heated by the nuclear reaction heat of 3 and rises to a high temperature. The hot primary coolant 202 flows into the upper plenum 206 and then into the intermediate heat exchanger 209 where it exchanges heat with the secondary coolant 112 and is cooled. The cooled primary coolant 202 flows into the lower plenum 207 within the reactor vessel 201 and further into the primary circulation pump 210 . The core 2 is pressurized again by this primary circulation pump 210.
03 is supplied below.
しかしながら、このように構成された従来例には次のよ
うな問題がそれぞれあった。ループ型高速増殖炉の場合
は、一次冷却配管が１０６および二次冷却配管１０９が
原子炉容器１０１の外部に？！２雑に配設され、その結
果、装置としては大型化し、原子炉全体を収容する原子
炉建屋も大型化してしまうという問題があった。However, the conventional examples configured in this manner have the following problems. In the case of a loop type fast breeder reactor, the primary cooling pipe 106 and the secondary cooling pipe 109 are located outside the reactor vessel 101? ! As a result, the equipment becomes large in size, and the reactor building that houses the entire reactor also becomes large.
一方、タンク型高速増殖炉の場合には、中間熱交換器２
０９および一次循環ポンプ２１０を原子炉容器２０１内
に収容する構成であるために、原子炉容器２０１の外部
に一次冷却配管の配＠構成を省略することができる反面
で、二次冷却配管１０９を原子炉容器２０１外に配管す
る必要があるうえに、原子炉容器２０１が大型化してし
まうという問題があった。また、かかる原子炉容器２０
１の大型化により輸送上の事情から原子炉容器２０１は
複雑に分割されることとなるが、これら複数に分割され
たものを現場で組立てなければならず、その組立作業が
困難であった。On the other hand, in the case of a tank-type fast breeder reactor, the intermediate heat exchanger 2
09 and the primary circulation pump 210 are housed inside the reactor vessel 201, it is possible to omit the arrangement of the primary cooling piping outside the reactor vessel 201. There is a problem in that it is necessary to provide piping outside the reactor vessel 201, and the reactor vessel 201 becomes larger. In addition, such a reactor vessel 20
Due to the increase in the size of reactor vessel 201, the reactor vessel 201 has to be divided into complicated parts for transport reasons, but these divided parts have to be assembled on site, which is difficult.
さらに、上述したように原子炉容器２０１の内部には一
次循環ポンプ２１０Ｊ５よび中間熱交換器２０９収容が
されるために、原子炉容器２０１の内部には空間的余裕
がなく、保守・点検作業の作業性を悪化させていた。Furthermore, as described above, since the primary circulation pump 210J5 and the intermediate heat exchanger 209 are housed inside the reactor vessel 201, there is no space inside the reactor vessel 201, and maintenance and inspection work is difficult. This worsened workability.
このように従来の高速増殖炉はループ型およびタンク型
のいずれをとっても、装置の大型化・複雑化が問題とな
っている。これは一次冷却系■と蒸気系■との間に二次
冷却系■を介在させていることに起因するものである。As described above, conventional fast breeder reactors, both loop-type and tank-type, have the problem of becoming larger and more complex. This is due to the fact that the secondary cooling system (2) is interposed between the primary cooling system (2) and the steam system (2).
そこで、かかる事情に鑑みなされたものが時開Ｄｎ ６
０−５７２８９号公報に掲載された二重タンク型高速増
殖炉である。Therefore, in view of the circumstances, what was decided was Jikai Dn 6.
This is a double tank type fast breeder reactor published in Publication No. 0-57289.
これは第８図に示すように構成され、炉心３０１と、中
間熱交換器３０２と、一次循環ポンプ３０３とを一次冷
却材３０４と共に収容する原子炉容器（一次冷却系タン
ク）３０５の外側に二次冷却系タンク３０６を設置して
あり、これらの上面間口をルーフスラブ３０７により閉
塞している。This is constructed as shown in FIG. 8, and has two tanks located outside a reactor vessel (primary cooling system tank) 305 that houses a reactor core 301, an intermediate heat exchanger 302, and a primary circulation pump 303 together with a primary coolant 304. A secondary cooling system tank 306 is installed, and the upper surface opening of the tank 306 is closed by a roof slab 307.
そして、原子炉容器３０５と二次冷却系タンク３０６と
の間のアニユラス空間と二次循環ポンプ３０８と蒸気発
生器３０９とを配設し、その１ｆｆｌに二次冷却材３１
０である液体金属ナトリウムを満たしである。二次循環
ポンプ３０８と蒸気発生器３０９とは、一次系機器と同
様にルーフスラブ３０７より吊り下げてあり、二次冷却
材流路構成上、中間熱交換器３０２と同一の基数設けで
ある。Then, an annulus space between the reactor vessel 305 and the secondary cooling system tank 306, a secondary circulation pump 308, and a steam generator 309 are arranged, and a secondary coolant 31
Fill with liquid metal sodium which is 0. The secondary circulation pump 308 and the steam generator 309 are suspended from the roof slab 307 like the primary system equipment, and have the same number of bases as the intermediate heat exchanger 302 due to the secondary coolant flow path configuration.
なお、蒸気系■は第６図で示すループ型高速増殖炉と同
様に構成されているので、第８図に同一符号を付して、
その重複した説明は省略している。The steam system (■) has the same structure as the loop fast breeder reactor shown in Figure 6, so the same reference numerals are given in Figure 8.
The redundant explanation has been omitted.
このように構成された従来の二重タンク型高速増殖炉で
は、一次および二次冷却配管１０６，１０９（第６図参
照）を省略することができる反面、原子炉容器３０５の
大型化、複雑化が避けられず、。In the conventional double-tank fast breeder reactor configured in this way, the primary and secondary cooling pipes 106 and 109 (see Figure 6) can be omitted, but the reactor vessel 305 becomes larger and more complex. is unavoidable.
プラント建設における現地組立ての作業が困難となり、
作業性が悪化してｙＡ設工期が長期化するという問題が
あった。On-site assembly work during plant construction became difficult.
There was a problem that workability deteriorated and the construction period of yA became longer.
（発明が解決しようとする問題点）
上述したように従来の高速増殖炉には配管構成の複雑化
および大型化、または、原子炉容器２０１．３０５の大
型化等の問題があり、これらの問題がプラントぜ設にお
ける現地組立ての作業の困難性を高めて、作業性を悪化
さゼ、建設工期の長期化を（ａいている。(Problems to be Solved by the Invention) As mentioned above, conventional fast breeder reactors have problems such as the complicated and large piping configuration or the large size of the reactor vessels 201 and 305. This increases the difficulty of on-site assembly during plant construction, worsens work efficiency, and lengthens the construction period.
（問題点を解決するための手段）
本発明は一次冷却系と二次冷７４１系とをそれぞれモジ
ュール化したものであり、次のように構成される。(Means for Solving the Problems) The present invention is a system in which a primary cooling system and a secondary cooling 741 system are each modularized, and are configured as follows.
制御棒が挿ｌ１５２される炉心を一次冷却材に浸漬させ
て収容する！閉容器に、中間熱交換器と一次循環ポンプ
とを一体に組み込み、一次循環ポンプにより一次冷却材
を中間熱交換器を通して炉心に強制循環さける一次系モ
ジュールと、蒸気発生器と二次循環ポンプとを一体に組
み込み、二次循環ポンプにより二次冷却材を蒸気発生器
に流通させて蒸気発生器で蒸気を発生させる二次系モジ
ュールと、低温冷却材プレナムと高温冷却材プレナムと
に仕切られた内部に二次冷却材を充填する原子炉容器と
を有し、上記一次系モジュールおよび二次系モジュール
を上記原子炉容器内に配設し、これらの中間熱交換器お
よび蒸気発生器を通して原子炉容器の低温冷却材プレナ
ムと高温冷却材プレナムとを連通さセた。The core into which the control rods are inserted is immersed in the primary coolant and housed! A primary system module that integrates an intermediate heat exchanger and a primary circulation pump in a closed vessel, and uses the primary circulation pump to forcefully circulate the primary coolant through the intermediate heat exchanger into the reactor core, and a steam generator and a secondary circulation pump. It is divided into a secondary system module, which uses a secondary circulation pump to circulate secondary coolant to a steam generator and generates steam in the steam generator, a low-temperature coolant plenum, and a high-temperature coolant plenum. The reactor vessel has a reactor vessel in which a secondary coolant is filled, and the primary system module and secondary system module are arranged in the reactor vessel, and the reactor is supplied through the intermediate heat exchanger and steam generator. A low temperature coolant plenum and a high temperature coolant plenum of the vessel are connected.
（作用）
高速増殖炉が運転されると、一次系モジュールの炉心が
一次冷却材を加熱する。(Operation) When the fast breeder reactor is operated, the core of the primary system module heats the primary coolant.
これにより、高温に７７ ｇした一次冷ｆｊｌ材は一次
循環ポンプにより中間熱交換器を通して炉心に強′ａｉ
ｌｌ循環されるが、その間に中間熱交換器内で、原子炉
容き内の低温冷却材プレナムから導入した低温の二次冷
ｎＪ材と熱交換をして加熱する一方で冷却される。As a result, the primary cold FJL material heated to a high temperature of 77 g is transferred to the reactor core by the primary circulation pump through the intermediate heat exchanger.
During this period, it is heated and cooled by exchanging heat with the low-temperature secondary cold nJ material introduced from the low-temperature coolant plenum in the reactor vessel in the intermediate heat exchanger.
中間熱交換器で加熱された高温の二次冷却材は中間熱交
換器から原子炉容器の高温冷却材プレナムに流出してか
ら、二次系モジュールの蒸気発生器に導入される。The high temperature secondary coolant heated by the intermediate heat exchanger flows out from the intermediate heat exchanger into the high temperature coolant plenum of the reactor vessel and is then introduced into the steam generator of the secondary system module.
蒸気発生器では高温の二次冷却材が給水を加熱して蒸気
を発生させる一方で冷却され、この低温の二次冷却材が
二次循環ポンプにより原子炉容器の低温冷に１材プレナ
ムへ吐出される。In the steam generator, high-temperature secondary coolant heats the feed water to generate steam while being cooled, and this low-temperature secondary coolant is discharged by a secondary circulation pump to the 1-material plenum for low-temperature cooling of the reactor vessel. be done.
これ以後、原子炉容器内の二次冷却材は一次系モジュー
ルで加熱されて昇温し、二次系モジュールで蒸気を発生
させて再び１５Ｕし、低温冷却材プレナムとＲ’ｔ４冷
ｋＪ材プレナムとの間を循環する状態を繰り返ず。After this, the secondary coolant in the reactor vessel is heated and raised in temperature by the primary system module, and steam is generated in the secondary system module to 15U again, and the low temperature coolant plenum and R't4 cold kJ material plenum are heated. Do not repeat the cycle between.
二次系モジュールの蒸気発生器で発生した蒸気（ユ蒸気
タービン等に供給されて仕事をする。Steam generated in the steam generator of the secondary system module (supplied to a steam turbine, etc. to do work).
（実／１１］列 ）
以下、本発明の実滴例を第１図〜第５図に基づいて説明
する。(Real/11] column) Hereinafter, examples of actual drops of the present invention will be explained based on FIGS. 1 to 5.
第１図は本発明の一実施例の全体構成を示しており、原
子炉容器１内に一次系モジュール２と二次系モジュール
３とを吊設している。FIG. 1 shows the overall configuration of an embodiment of the present invention, in which a primary system module 2 and a secondary system module 3 are suspended within a reactor vessel 1.
原子炉容器１はその内部に二次冷却材４を収容して、上
端開口をルーフスラブ５により閉塞し、その内部を隔壁
６により高温冷却材プレナム７と低温冷却材プレナム８
とに上下方向に２分している。The reactor vessel 1 accommodates a secondary coolant 4 therein, has an upper end opening closed by a roof slab 5, and has a high-temperature coolant plenum 7 and a low-temperature coolant plenum 8 separated by partition walls 6.
It is divided into two vertically.
一次系モジュール２は第１図および第２図に示すように
構成され、密閉容器９内に炉心１０を一次冷却材１コに
浸漬させて収容している。The primary system module 2 is constructed as shown in FIGS. 1 and 2, and contains a reactor core 10 immersed in a single primary coolant in a closed container 9.
炉心１０はその内部に複数の制御棒１２が挿脱されて、
炉心反応度が制御されるようになっており、これらの制
御棒１２は密閉容器９の上端開口を閉塞する遮蔽プラグ
１３上に立設された複数の制御棒駆動機構１４によりそ
れぞれ駆動されるようになっている。A plurality of control rods 12 are inserted into and removed from the core 10, and
The reactor core reactivity is controlled, and these control rods 12 are each driven by a plurality of control rod drive mechanisms 14 erected on a shielding plug 13 that closes the upper end opening of the closed vessel 9. It has become.
密閉容器９内の炉心１０の外周には所要の間隔をおいて
中間熱交換器１５が配設されている。Intermediate heat exchangers 15 are arranged around the outer periphery of the core 10 within the closed vessel 9 at a required interval.
中間熱交換器１５は炉心１０の外周に所要の間隔をおい
て立設された伝熱管束１５ａを同心円状に配設し、この
伝熱管束１５ａの上端部を上部管板１５ｂで密閉容器９
の外周に固定し、その外周を伝熱管外胴１５ｃで被覆し
ている。伝熱管外胴１５ｃの外周にはシールスカート１
６が密着して外嵌され、このシールスカート１６の下端
は隔壁６に固着されている。The intermediate heat exchanger 15 has heat transfer tube bundles 15a arranged concentrically around the outer periphery of the reactor core 10 at predetermined intervals.
The heat exchanger tube outer shell 15c covers the outer circumference of the heat exchanger tube. A seal skirt 1 is provided on the outer periphery of the heat transfer tube outer body 15c.
6 is tightly fitted onto the outside, and the lower end of this seal skirt 16 is fixed to the partition wall 6.
伝熱管束１５ａは多数の伝熱管の内部を二次冷ｎｌ材４
の流路に設定する一方、これら伝熱管の相互間に所要の
間隙を一次冷却材１１の流路に設定しており、その流路
の上部に一次側入口１５ｄを、その下部に一次側出口１
５ｅを開口している。The heat exchanger tube bundle 15a has a large number of heat exchanger tubes with secondary cooling NL material 4 inside.
At the same time, a required gap is set between these heat transfer tubes in the flow path of the primary coolant 11, and the primary side inlet 15d is in the upper part of the flow path, and the primary side outlet is in the lower part. 1
5e is open.
また、伝熱管束１５ａの上部に二次側出口１５ｆを、下
部に二次側入口１５（Ｊをそれぞれ開口し、原子炉容器
１の高温冷ｌＪＩ材プレナム７と低温冷却材プレナム８
とを伝熱管束１５ａ内部を通して連通させている。In addition, a secondary side outlet 15f is opened at the upper part of the heat transfer tube bundle 15a, and a secondary side inlet 15 (J) is opened at the lower part of the heat exchanger tube bundle 15a.
and are communicated through the inside of the heat exchanger tube bundle 15a.
上記炉心１０の下方にはｍｌポンプよりなる一次循環ポ
ンプ１７を密閉容器９に設けており、この一次循環ポン
プ１７は中間熱交換器１５の一次側出口１５ｅを炉心１
０の下方空間に連通させるポンプケーシング１７ａを有
し、このポンプケーシング１７ａのアニユラス流路の内
周に、円筒状の鉄心１７ｂを設け、その鉄心１７ｂの外
周に磁場励…コイル１７Ｃを同軸状に設けて構成されて
いる。Below the core 10, a primary circulation pump 17 consisting of a ml pump is installed in the closed vessel 9, and this primary circulation pump 17 connects the primary side outlet 15e of the intermediate heat exchanger 15 to the core
A cylindrical iron core 17b is provided on the inner periphery of the annulus flow path of this pump casing 17a, and a magnetic field excitation coil 17C is coaxially arranged around the outer periphery of the iron core 17b. It is set up and configured.
一方、二次系モジュール３は第１図および第３図に示す
ように構成され、蒸気発生器１８は外胴１８ａ内に蒸発
管１８ｂを収容して、その上端開口をＭＥプラグ１９に
より密閉し、外胴１８ａの軸方向中間部には二次側人口
１８ｃを周方向に複数個開口させて、外胴１８ａ内に二
次冷却材４を導入するようになっている。On the other hand, the secondary system module 3 is configured as shown in FIGS. 1 and 3, and the steam generator 18 houses an evaporation tube 18b in an outer shell 18a, and its upper end opening is sealed with an ME plug 19. A plurality of secondary side openings 18c are opened in the circumferential direction in the axially intermediate portion of the outer shell 18a, and the secondary coolant 4 is introduced into the outer shell 18a.
蒸発管１８ｂは給水を供給する給水ヘッダ２０と然気出
口ヘッダ２１とに接続され、外１１］１８ａの底部に突
に２ ｔ、た吐出ノズル１８ｄのアニユラス流路の内周
に、電磁ポンプ２２の鉄心２２ａを設け、この鉄心２２
ａの外周に励磁コイル２２ｂを同心状に設け、外３１１
８ａ内の二次冷却材４を低温冷却材プレナム８に吐出す
るようになっている。The evaporation pipe 18b is connected to a water supply header 20 for supplying water and an air outlet header 21, and an electromagnetic pump 22 is connected to the inner circumference of the annulus flow path of the discharge nozzle 18d. An iron core 22a is provided, and this iron core 22
The excitation coil 22b is provided concentrically on the outer periphery of a, and the outer 311
The secondary coolant 4 in 8a is discharged into a low temperature coolant plenum 8.
外胴１８ａの軸方向中間部外周にはシールスカート２３
が嵌着され、その下端部を隔壁６に固着している。A seal skirt 23 is provided on the outer circumference of the axially intermediate portion of the outer body 18a.
is fitted, and its lower end is fixed to the partition wall 6.
なお、第１図〜第３図中白矢印は一次冷却材１１を、黒
矢印は二次冷却材４の流れ方向をそれぞれ示している。Note that in FIGS. 1 to 3, white arrows indicate the primary coolant 11, and black arrows indicate the flow direction of the secondary coolant 4.
次に、本実施例の作用について述べる。Next, the operation of this embodiment will be described.
高速増殖炉が運転されると、一次系モジュール２内の一
次冷却材１１が加熱されて高温に昇温し、白矢印に示す
ように中間熱交換器１５の一次側人口１５Ｃｊより伝熱
管束１５ａの外側へ流入して流下する。When the fast breeder reactor is operated, the primary coolant 11 in the primary system module 2 is heated to a high temperature, and as shown by the white arrow, the heat transfer tube bundle 15a is transferred from the primary side population 15Cj of the intermediate heat exchanger 15. flows outside and flows down.
このとき、伝熱管束１５ａの内部には低温冷却材プレナ
ム８から低温の二次冷却材４が二次側入口１５ｇより流
入しており、中間熱交換Ｚ１５で【よ高温の一次冷却材
１１と低温の二次冷却材４とが熱交換をして、一次冷却
材１１は低温に１！′ｌ温し、二次冷却材４は８温に昇
温する。At this time, the low-temperature secondary coolant 4 from the low-temperature coolant plenum 8 flows into the heat transfer tube bundle 15a from the secondary side inlet 15g, and is exchanged with the higher-temperature primary coolant 11 in the intermediate heat exchange Z15. The low temperature secondary coolant 4 exchanges heat, and the primary coolant 11 becomes low temperature 1! The temperature of the secondary coolant 4 increases to 8.
低温に降温した一次冷却材１１は中間熱交換器１５の一
次側出口１５ｅから一次循環ポンブ１７のポンプケーシ
ング１７ａ内に入り、ここで、移動磁場を発生している
励磁コイル１７Ｃと鉄心１７ｂとのアニユラス空間を流
れる際に加圧されて、炉心１０の下方に強制循環される
。The primary coolant 11, which has cooled to a low temperature, enters the pump casing 17a of the primary circulation pump 17 from the primary side outlet 15e of the intermediate heat exchanger 15, where it is connected to the excitation coil 17C, which generates a moving magnetic field, and the iron core 17b. As it flows through the annulus space, it is pressurized and forced to circulate below the core 10.
−方、一次系モジュール２の中間熱交換器１５で加熱さ
れた高温の二次冷却材４は、伝熱管束１５ａの二次側出
口１５ｆから原子炉容器１の高温冷却材プレナム７へ流
出してから、二次系モジュール３の蒸気発生器１８の二
次側人口１８ｃより、その外１ｊ１１８ａ内へ導入され
る。- On the other hand, the high-temperature secondary coolant 4 heated by the intermediate heat exchanger 15 of the primary system module 2 flows out from the secondary side outlet 15f of the heat transfer tube bundle 15a to the high-temperature coolant plenum 7 of the reactor vessel 1. Then, it is introduced into the outside 1j 118a from the secondary side population 18c of the steam generator 18 of the secondary system module 3.
この外＆１８ａ内では高温の二次冷ＩＪ材４が蒸発管１
８ｂ内に給水された給水を加熱して蒸気を発生させる一
方で、冷却されて降′温し、この低温の二次冷却材４は
二次循環ポンプ２２により加圧されて、吐出ノズル１８
ｄより低温冷却材プレナム８へ吐出される。Outside this & inside 18a, the high temperature secondary cooling IJ material 4 is in the evaporation tube 1.
The water supplied into the tank 8b is heated to generate steam, while being cooled down to a lower temperature. This low-temperature secondary coolant 4 is pressurized by the secondary circulation pump 22 and discharged from the discharge nozzle 18.
d is discharged to the low temperature coolant plenum 8.
一方、蒸発管１８ｂ内で発生した蒸気は蒸気出口ヘッダ
２１を介して図示しない蒸気系等に給気される。On the other hand, the steam generated in the evaporator tube 18b is supplied to a steam system (not shown) through the steam outlet header 21.
このように本実施例は構成されているので、一次冷却系
および二次冷却系の配管を削減することができる。Since this embodiment is configured in this manner, the number of piping for the primary cooling system and the secondary cooling system can be reduced.
しかも、炉心および一次冷却系と、二次冷却系別器とを
モジュール化したので、工場制作が可能となって、品質
の向上を図ることができると共に、プラント建設現場に
おける組み立て等の作業性を改善することができ、プラ
ント建設の工期を短縮することができる。Moreover, since the reactor core, primary cooling system, and secondary cooling system separate units are modularized, factory production is possible, improving quality and improving work efficiency such as assembly at the plant construction site. The plant construction period can be shortened.
第４図および第５図は本発明の他の実施例を示し、本実
施例は上記実施例の一次系モジュール２と二次系モジュ
ール３とを一対として、複数対を原子炉容器１内に吊設
したものである。4 and 5 show other embodiments of the present invention, in which a plurality of pairs of the primary system module 2 and secondary system module 3 of the above embodiment are installed in the reactor vessel 1. It is suspended.
この実施例によれば、一次系モジュール２と二次系モジ
ュール３との設置対数を適宜選択することにより、多様
なプラント容量の要求に容易に対応することができる。According to this embodiment, by appropriately selecting the installation logarithm of the primary system module 2 and the secondary system module 3, it is possible to easily meet various demands for plant capacity.
以上説明したように本発明は、炉心および一次冷却系と
、二次冷却系とをモジュール化したので、プラント建設
現場における組立作業等の作業性の向上を図ることがで
き、ブラント建設工期の短縮を図ることができる。As explained above, the present invention modularizes the core, the primary cooling system, and the secondary cooling system, so it is possible to improve workability such as assembly work at the plant construction site, and shorten the blunt construction period. can be achieved.
第１図は本発明の一実膿例の全体構成を示す正面図、第
２図は第１図で示す一次系モジュールを一部１断面で示
す正面図、第３図は第１図で示す二次系モジュールを一
部縦断面で示す正面図、第４図は本発明の他の実施例の
正面図、第５図は第４図の平面図、第６図は従来のルー
ブハ１高速増殖炉の系統構成図、第７図は従来のタンク
型高速贈殖炉の系統構成図、第８図は従来の二重タンク
型高速増殖炉の系統構成図である。
１・・・原子炉容器、２・・・一次系上ジュール、３・
・・二次系モジュール、４・・・二次冷却材、５・・・
ル−フスラプ、６・・・隔壁、７・・・高温冷却材プレ
ナム１，１
８・・・低温冷却材プレナム、９・・・密閉容器、１０
・・・−６−〜′
炉心、１１・−・一次冷却材、１２・・・あり御棒、１
５・・・中間熱交換器、１７・・・一次循環ポンプ、１
８・・・蒸気発生器、２２・・・二次循環ポンプ。
出願人代理人 波 多 野 久◆２次；令即材
第１図
第２図
第３ 図FIG. 1 is a front view showing the overall configuration of a one-dimensional example of the present invention, FIG. 2 is a front view showing a partial cross-section of the primary system module shown in FIG. 1, and FIG. 3 is shown in FIG. 1. FIG. 4 is a front view of another embodiment of the present invention, FIG. 5 is a plan view of FIG. 4, and FIG. 6 is a conventional Lubach 1 high-speed multiplication device. FIG. 7 is a system configuration diagram of a conventional tank type fast breeder reactor, and FIG. 8 is a system configuration diagram of a conventional double tank type fast breeder reactor. 1... Reactor vessel, 2... Joule on the primary system, 3.
...Secondary system module, 4...Secondary coolant, 5...
Roof lap, 6... Partition wall, 7... High temperature coolant plenum 1, 1 8... Low temperature coolant plenum, 9... Closed container, 10
...-6-~' Reactor core, 11...Primary coolant, 12...Archive rod, 1
5... Intermediate heat exchanger, 17... Primary circulation pump, 1
8...Steam generator, 22...Secondary circulation pump. Applicant's agent Hisashi Hatano ◆Second; Ready-to-read material Figure 1 Figure 2 Figure 3
Claims (1)
する密閉容器に、中間熱交換器と一次循環ポンプとを一
体に組み込み、一次循環ポンプにより一次冷却材を中間
熱交換器を通して炉心に強制循環させる一次系モジュー
ルと、蒸気発生器と二次循環ポンプとを一体に組み込み
、二次循環ポンプにより二次冷却材を蒸気発生器に流通
させて蒸気発生器で蒸気を発生させる二次系モジュール
と、低温冷却材プレナムと高温冷却材プレナムとに仕切
られた内部に二次冷却材を充填する原子炉容器とを有し
、上記一次系モジュールおよび二次系モジュールを上記
原子炉容器内に吊設し、これらの中間熱交換器および蒸
気発生器を通して原子炉容器の低温冷却材プレナムと高
温冷却材プレナムとを連通させたことを特徴とする高速
増殖炉。An intermediate heat exchanger and a primary circulation pump are integrated into a sealed container that houses the reactor core in which the control rods are inserted and removed by immersing it in the primary coolant, and the primary circulation pump supplies the primary coolant to the reactor core through the intermediate heat exchanger. A secondary system module that integrates a primary system module for forced circulation, a steam generator, and a secondary circulation pump, and uses the secondary circulation pump to circulate the secondary coolant to the steam generator to generate steam. system module, and a reactor vessel that is partitioned into a low-temperature coolant plenum and a high-temperature coolant plenum and is filled with a secondary coolant, and the primary system module and the secondary system module are installed in the reactor vessel. 1. A fast breeder reactor, characterized in that a low temperature coolant plenum and a high temperature coolant plenum of a reactor vessel are connected to each other through an intermediate heat exchanger and a steam generator.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61147593A JPS633292A (en) | 1986-06-24 | 1986-06-24 | Fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61147593A JPS633292A (en) | 1986-06-24 | 1986-06-24 | Fast breeder reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS633292A true JPS633292A (en) | 1988-01-08 |
Family
ID=15433858
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61147593A Pending JPS633292A (en) | 1986-06-24 | 1986-06-24 | Fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS633292A (en) |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH02128192A (en) * | 1988-11-08 | 1990-05-16 | Power Reactor & Nuclear Fuel Dev Corp | Decentralized nuclear reactor |
| JPH02151791A (en) * | 1988-12-05 | 1990-06-11 | Power Reactor & Nuclear Fuel Dev Corp | Steam generator of dispersion type fast breeder reactor |
| JP2012141304A (en) * | 2010-12-29 | 2012-07-26 | Westinghouse Electric Co Llc | Optimum configuration for fast reactors |
| JP2013520657A (en) * | 2010-02-22 | 2013-06-06 | アドバンスト・リアクター・コンセプツ・エルエルシー | Small fast neutron spectrum nuclear power plant with long refueling intervals |
| US10424415B2 (en) | 2014-04-14 | 2019-09-24 | Advanced Reactor Concepts LLC | Ceramic nuclear fuel dispersed in a metallic alloy matrix |
-
1986
- 1986-06-24 JP JP61147593A patent/JPS633292A/en active Pending
Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH02128192A (en) * | 1988-11-08 | 1990-05-16 | Power Reactor & Nuclear Fuel Dev Corp | Decentralized nuclear reactor |
| JPH02151791A (en) * | 1988-12-05 | 1990-06-11 | Power Reactor & Nuclear Fuel Dev Corp | Steam generator of dispersion type fast breeder reactor |
| US9640283B2 (en) | 2010-01-29 | 2017-05-02 | Advanced Reactor Concepts LLC | Small, fast neutron spectrum nuclear power plant with a long refueling interval |
| JP2013520657A (en) * | 2010-02-22 | 2013-06-06 | アドバンスト・リアクター・コンセプツ・エルエルシー | Small fast neutron spectrum nuclear power plant with long refueling intervals |
| JP2012141304A (en) * | 2010-12-29 | 2012-07-26 | Westinghouse Electric Co Llc | Optimum configuration for fast reactors |
| US10424415B2 (en) | 2014-04-14 | 2019-09-24 | Advanced Reactor Concepts LLC | Ceramic nuclear fuel dispersed in a metallic alloy matrix |
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