JPS6321592A - Loop type liquid metal cooling fast breeder reactor - Google Patents
Loop type liquid metal cooling fast breeder reactorInfo
- Publication number
- JPS6321592A JPS6321592A JP61166077A JP16607786A JPS6321592A JP S6321592 A JPS6321592 A JP S6321592A JP 61166077 A JP61166077 A JP 61166077A JP 16607786 A JP16607786 A JP 16607786A JP S6321592 A JPS6321592 A JP S6321592A
- Authority
- JP
- Japan
- Prior art keywords
- core
- reactor
- type liquid
- liquid metal
- fast breeder
- 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
- 229910001338 liquidmetal Inorganic materials 0.000 title claims description 11
- 238000001816 cooling Methods 0.000 title description 2
- 239000002826 coolant Substances 0.000 claims description 19
- 239000000463 material Substances 0.000 description 3
- 239000000446 fuel Substances 0.000 description 2
- 238000003466 welding Methods 0.000 description 2
- 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 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000003014 reinforcing effect Effects 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (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) [Abstract] This bulletin contains application data before electronic filing, so abstract data is not recorded.
Description
【発明の詳細な説明】
(イ)発明の目的
[産業上の利用分野]
この発明は、炉心を冷却材入口配管にJ:って懸垂支持
することにより原子炉容器径を縮小し、物ωを削減した
ループ型液体金属冷却高速増殖炉に関するものである。Detailed Description of the Invention (a) Purpose of the Invention [Field of Industrial Application] This invention reduces the diameter of the reactor vessel by suspending the reactor core from the coolant inlet piping. It concerns a loop-type liquid metal cooled fast breeder reactor that reduces the
[従来の技術]
従来、ループ型液体金属冷却高速増殖炉において、炉心
は第3図に示すように原子炉頂部のデツキ構造3より吊
り下げられた原子′炉容器2に固定され、かつ、原子炉
容器2の中心に向って張り出した炉心支持構造物5によ
って支持されていた。[Prior Art] Conventionally, in a loop-type liquid metal cooled fast breeder reactor, the reactor core is fixed to a reactor vessel 2 suspended from a deck structure 3 at the top of the reactor, as shown in FIG. It was supported by a core support structure 5 extending toward the center of the reactor vessel 2.
[発明が解決しようとする問題点]
しかるに、この炉心支持構造物5には、原子炉容器外か
ら導入され、炉心1の下部にある高圧ブレナム6に連通
ずる冷却材入口配管7、及び、燃料交換のための炉内中
継槽8が貫通する穴を設ける必要があり、また、地震時
にも炉心をしつかり支持する必要があるため高剛性の厚
肉鍛造材が使用され、更に、前記貫通部を補強するため
に図示していないが補強用リブを設ける等物伍増となる
問題があった。[Problems to be Solved by the Invention] However, the core support structure 5 includes a coolant inlet pipe 7 that is introduced from outside the reactor vessel and communicates with the high-pressure blenum 6 located at the lower part of the reactor core 1, and a fuel It is necessary to provide a hole through which the in-core relay tank 8 for replacement passes, and it is also necessary to firmly support the reactor core in the event of an earthquake, so a highly rigid, thick-walled forged material is used. Although not shown in the drawings, reinforcing ribs must be provided to reinforce the structure.
この発明は、上記の如き事情に鑑みてなされたものであ
って、従来の技術がもつ物涜増の問題を解消し、原子炉
容器径の縮小されたコストの低いループ型液体金属高速
増殖炉を提供することを目的とするものである。The present invention has been made in view of the above circumstances, and solves the problem of clutter in the conventional technology, and provides a low-cost loop-type liquid metal fast breeder reactor with a reduced reactor vessel diameter. The purpose is to provide the following.
(ロ)発明の構成
[問題を解決するための手段]
この目的に対応して、この発明のループ型液体金属冷却
高速増殖炉は、炉心を冷却材入口配管によって懸垂支持
したことを特徴としている。(B) Structure of the invention [Means for solving the problem] In response to this objective, the loop type liquid metal cooled fast breeder reactor of the present invention is characterized in that the core is suspended and supported by coolant inlet piping. .
以下、この発明の詳細を一実施例を示す図面について説
明する。Hereinafter, details of the present invention will be explained with reference to the drawings showing one embodiment.
第1図は本発明の一実施例に係わるループ型液体金属冷
却高速増殖炉の縦断面図、及び、第2図は炉心部の平面
図である。FIG. 1 is a longitudinal sectional view of a loop type liquid metal cooled fast breeder reactor according to an embodiment of the present invention, and FIG. 2 is a plan view of the reactor core.
第1図、第2図において符号2は原子炉容器である。原
子炉容器2は従来と同様デツキ構造3より吊り下げられ
ており、その外側にはガードベッセル4が設置されてい
る。符号1は炉心で、炉心1は多数の燃料集合体(図示
していない)によって構成されており、かつ、炉心槽1
0内において炉心支持板9上に支持されている。炉心支
持板9には冷却材(ナトリウム)を炉心に供給するため
の多数の冷却材流路孔aが穿たれている。炉心槽10は
底板13まで延びており、高圧ブレナム6に対応する部
分には複数の冷却材流路孔すが穿たれている。以上の構
成は第3図に示した従来例と全く同一である。なお、原
子炉容器2、デツキ構造3、ガードベッセル4、炉心支
持板9、炉心槽10、底板13の各々は板厚を有するも
のであるが、図を簡略とづるため単に線で示しである。In FIGS. 1 and 2, reference numeral 2 indicates a reactor vessel. The reactor vessel 2 is suspended from a deck structure 3 as in the past, and a guard vessel 4 is installed on the outside thereof. Reference numeral 1 indicates a reactor core, and the reactor core 1 is composed of a large number of fuel assemblies (not shown), and a core tank 1.
It is supported on a core support plate 9 within the core support plate 9. The core support plate 9 has a large number of coolant passage holes a for supplying coolant (sodium) to the core. The core barrel 10 extends to a bottom plate 13, and a plurality of coolant passage holes are bored in a portion corresponding to the high-pressure blemish 6. The above configuration is completely the same as the conventional example shown in FIG. Although each of the reactor vessel 2, deck structure 3, guard vessel 4, core support plate 9, core barrel 10, and bottom plate 13 has a thickness, they are simply shown by lines to simplify the diagram. .
冷却材入口配管7は複数設けられているが、これらは原
子炉容器2の外部より容器壁を貫通して原子炉容器2内
に導入されており、デツキ構造3の内部で方向を90°
変換し原子炉容器2の底に向って垂直に伸びている。ま
た、この冷却材入口配管7はデツキ構造3の下端面C部
においてデツキ構造にしっかりと接合されている。A plurality of coolant inlet pipes 7 are provided, and these are introduced into the reactor vessel 2 from the outside of the reactor vessel 2 through the vessel wall, and the direction is set at 90° inside the deck structure 3.
It extends vertically towards the bottom of the reactor vessel 2. Moreover, this coolant inlet pipe 7 is firmly joined to the deck structure at the lower end surface C portion of the deck structure 3.
この発明のループ型液体金属冷却高速増殖炉は、炉心槽
10の外側に外筒11を向応に備えており、その下端は
底板13に、上端は環状の上板12に溶接等の手段によ
り水密に接合されている。すなわち、炉心Fa10の外
側に外筒11、上板12及び底板13によって区画され
た高圧ブレナム6を形成している。複数の冷却材入口配
管7は前記環状の上板12に溶接により接合されており
、冷却材は図において矢印に示すように冷却材入口配管
7内を降下し、環状の高圧ブレナム部で十分に撹拌され
たのち炉心1の下方の高圧ブレナムに廻り込み、ここで
流れ方向を反転して炉心1に流入する。The loop type liquid metal cooled fast breeder reactor of the present invention is equipped with an outer cylinder 11 on the outside of a core tank 10, the lower end of which is attached to a bottom plate 13, and the upper end is attached to an annular upper plate 12 by means of welding or the like. Watertightly joined. That is, a high-pressure brenum 6 partitioned by an outer cylinder 11, an upper plate 12, and a bottom plate 13 is formed outside the core Fa10. A plurality of coolant inlet pipes 7 are joined to the annular upper plate 12 by welding, and the coolant descends within the coolant inlet pipes 7 as indicated by the arrows in the figure, and is sufficiently pumped in the annular high-pressure blennium section. After being stirred, it flows into the high-pressure blenum below the core 1, where the flow direction is reversed and flows into the core 1.
すなわち、炉心1を包含する炉心構造物の全体が冷却材
入口配管7によって懸垂支持されている。That is, the entire core structure including the core 1 is suspended and supported by the coolant inlet pipe 7.
符号15は振れ止めであり、振れ止め15は外筒11と
原子炉容器2との間に熱8Jt変位を吸収するための若
干の隙間を残すように、外筒11側若しくは原子炉容器
2側(図示の例)に固定される。Reference numeral 15 indicates a steady rest, and the steady rest 15 is attached to the outer cylinder 11 side or the reactor vessel 2 side so as to leave a slight gap between the outer cylinder 11 and the reactor vessel 2 to absorb the heat displacement of 8 Jt. (example shown).
符号16は、冷却材出口配管である。Reference numeral 16 is a coolant outlet pipe.
[作用]
例えば、100100O,4ループプラントでは、冷却
材入口配管は40B(1016mφ)程度のものが用い
られ、炉心全体を4本の冷却材人口配管によって懸垂支
持することになる。この場合、配管の肉厚を30II1
1とすると、自重十内圧による応力は3.5Kg/m2
であり、許容値であるBKgl履2(SUS304の5
25℃。[Function] For example, in a 100,100O, 4-loop plant, a coolant inlet pipe of approximately 40B (1016 mφ) is used, and the entire reactor core is suspended and supported by the four coolant artificial pipes. In this case, the wall thickness of the pipe is 30II1
1, the stress due to its own weight and internal pressure is 3.5Kg/m2
, and the allowable value is BKgl 2 (SUS304 5
25℃.
3×105hのS 値)内に納まる。また、鉛直S2地
震による荷重を1.5gとすると、これによる応力は2
.8に9/m である。水平S2地震に対しては、炉
心槽に対し軸長方向の上下に配置した撮れ止めで荷重を
受けることができるので、この時、配管側に発生する応
力は1.8Kg/aI2であり、自重+内圧+鉛直S2
地震+水平S2地雲による応力は8.1に9/m2とな
るが、この場合の許容fa11Kg/mlR2(SUS
304の525℃でのS、値)内に納まる。S value of 3×105h). Also, if the load due to the vertical S2 earthquake is 1.5g, the stress due to this is 2
.. 8 to 9/m. In the case of a horizontal S2 earthquake, the load can be received by the photo stops placed above and below the core barrel in the axial direction, so the stress generated on the piping side at this time is 1.8 Kg/aI2, and the self-weight +Internal pressure +Vertical S2
The stress due to the earthquake + horizontal S2 ground cloud is 8.1 to 9/m2, but the allowable fa11Kg/mlR2 (SUS
304 at 525°C).
また、100100O,3ルーブプラントテハ、配管口
径は46B (1168s*φ)程度の3本の冷却材入
口配管によって炉心は懸垂支持される。In addition, the core is suspended and supported by three coolant inlet pipes of 100,100 O, 3-lube plant technology, and a pipe diameter of about 46 B (1168 s*φ).
この場合も、配管の肉厚を305IIとすると、自毛(
8KS/l1III)、更に、自重+内圧+鉛直S2地
震+水平S2地震による応力は
9.3Kfl/m2<3 (11,0に9/m2)と
、■
いずれも許容値内に納まるので、冷却材入口配管によっ
て十分に炉心を懸垂支持することができ、しかも、従来
のように側部に炉心支持構造物を必要としないので原子
炉容器径の縮小が可能となる。In this case as well, if the wall thickness of the pipe is 305II, natural hair (
8KS/l1III), and the stress due to own weight + internal pressure + vertical S2 earthquake + horizontal S2 earthquake is 9.3 Kfl/m2 < 3 (9/m2 in 11,0), ■ All of which are within the allowable values, so cooling The reactor core can be sufficiently suspended and supported by the material inlet piping, and there is no need for a core support structure on the side as in the conventional method, making it possible to reduce the diameter of the reactor vessel.
(ハ)発明の効果
この発明によれば、冷却材入口配管を炉心支持手段とし
て兼用したので、従来の炉心側部の高剛性の炉心支持f
iG物を削除することができる。従って、原子炉容器径
の縮小が可能となり、物囚を削減したループ型液体金属
冷却高速増殖炉を得ることができ、プラントのコストダ
ウンに寄与する。(c) Effects of the invention According to this invention, the coolant inlet piping is also used as core support means, so the high rigidity core support f on the side of the core is
iG items can be deleted. Therefore, it is possible to reduce the diameter of the reactor vessel, and it is possible to obtain a loop-type liquid metal cooled fast breeder reactor with fewer trapped materials, contributing to a reduction in plant costs.
第1図は本発明の一実施例に係わるループ型液体金属冷
却高速増殖炉の縦断面図、第2図は同炉心部の平面図、
及び、第3図は従来のループ型液体金属冷却高速増殖炉
の縦断面図である。
1・・・炉心 2・・・原子炉容器 3・・・デツ
キ構造6・・・高圧ブレナム 7・・・冷却材入口配
管 9・・・炉心支持板 10・・・炉心槽 1
1・・・外筒12・・・上板 13・・・底板 1
5・・・撮れ止め第1図
第3図FIG. 1 is a longitudinal sectional view of a loop-type liquid metal cooled fast breeder reactor according to an embodiment of the present invention, and FIG. 2 is a plan view of the core of the same.
FIG. 3 is a longitudinal sectional view of a conventional loop type liquid metal cooled fast breeder reactor. 1... Reactor core 2... Reactor vessel 3... Deck structure 6... High pressure blennium 7... Coolant inlet piping 9... Core support plate 10... Core barrel 1
1...Outer cylinder 12...Top plate 13...Bottom plate 1
5...Photo stills Figure 1 Figure 3
Claims (1)
とするループ型液体金属冷却高速増殖炉A loop-type liquid metal cooled fast breeder reactor characterized by a core suspended and supported by coolant inlet piping.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61166077A JPS6321592A (en) | 1986-07-15 | 1986-07-15 | Loop type liquid metal cooling fast breeder reactor |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP61166077A JPS6321592A (en) | 1986-07-15 | 1986-07-15 | Loop type liquid metal cooling fast breeder reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
JPS6321592A true JPS6321592A (en) | 1988-01-29 |
Family
ID=15824552
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP61166077A Pending JPS6321592A (en) | 1986-07-15 | 1986-07-15 | Loop type liquid metal cooling fast breeder reactor |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS6321592A (en) |
-
1986
- 1986-07-15 JP JP61166077A patent/JPS6321592A/en active Pending
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