JPS61190898U - - Google Patents

Info

Publication number
JPS61190898U
JPS61190898U JP1985074220U JP7422085U JPS61190898U JP S61190898 U JPS61190898 U JP S61190898U JP 1985074220 U JP1985074220 U JP 1985074220U JP 7422085 U JP7422085 U JP 7422085U JP S61190898 U JPS61190898 U JP S61190898U
Authority
JP
Japan
Prior art keywords
reactor
pressure vessel
reinforcing plate
annular
boiling water
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
Application number
JP1985074220U
Other languages
Japanese (ja)
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed filed Critical
Priority to JP1985074220U priority Critical patent/JPS61190898U/ja
Publication of JPS61190898U publication Critical patent/JPS61190898U/ja
Pending legal-status Critical Current

Links

Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Description

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

第1図は本考案による沸騰水型原子炉の一実施
例を示す断面図、第2図は第1図―線に沿う
拡大断面図、第3図は第2図―線に沿う拡大
断面図である。 1……原子炉圧力容器、2……炉心、7……炉
心シユラウド、8……シユラウドサポートレグ、
9……環状炉水通路、10……環状炉水通路の底
仕切板、11……原子炉内循環ポンプ、11P…
…ポンプ部、11M……モータ部、12……補強
板、13……パツド、g……クリアランス。
Figure 1 is a sectional view showing an embodiment of the boiling water nuclear reactor according to the present invention, Figure 2 is an enlarged sectional view taken along the line of Figure 1, and Figure 3 is an enlarged sectional view taken along the line of Figure 2. It is. 1... Reactor pressure vessel, 2... Reactor core, 7... Core shroud, 8... Shroud support leg,
9...Annular reactor water passage, 10...Bottom partition plate of the annular reactor water passage, 11...Reactor circulation pump, 11P...
...Pump part, 11M...Motor part, 12...Reinforcement plate, 13...Pad, g...Clearance.

Claims (1)

【実用新案登録請求の範囲】 (1) 原子炉圧力容器内に炉心を支持する炉心シ
ユラウドを収容し、この炉心シユラウドと原子炉
圧力容器との間に底部が底仕切板で仕切られた環
状炉水通路を形成し、この環状炉水通路の底仕切
板に所要数台の原子炉内循環ポンプをそのポンプ
部が通路内にのぞむように設置したものにおいて
、前記環状炉水通路内を炉心シユラウドから放射
方向に突設した補強板によつて各原子炉内循環ポ
ンプのポンプ部毎に区切り、さらにその各々の補
強板の端面を原子炉の通常運転時は原子炉圧力容
器の内周壁および環状炉水通路の底仕切板に対し
て固定しないことを特徴とする沸騰水型原子炉。 (2) 各々の補強板の端部に対峙する原子炉圧力
容器の内周壁にパツドを設け、このパツドと補強
板の端部との間のクリアランスが補強板と原子炉
圧力容器とを構成する異種金属による熱膨張差に
よつて零になるよう構成したことを特徴とする実
用新案登録請求の範囲第1項記載の沸騰水型原子
炉。 (3) 補強板の上端の位置は炉心の有効燃料下端
の位置以下にしたことを特徴とする実用新案登録
請求の範囲第1項記載の沸騰水型原子炉。
[Scope of Claim for Utility Model Registration] (1) An annular reactor in which a reactor shroud that supports the reactor core is housed in a reactor pressure vessel, and a bottom partition plate is partitioned between the core shroud and the reactor pressure vessel. A water passage is formed, and a required number of reactor circulation pumps are installed on the bottom partition plate of this annular reactor water passage so that their pump parts look into the passage, and the inside of the annular reactor water passage is connected to the core shroud. The pump parts of each reactor circulation pump are separated by reinforcing plates protruding radially from the reactor, and the end faces of each reinforcing plate are connected to the inner circumferential wall of the reactor pressure vessel and the annular shape during normal operation of the reactor. A boiling water reactor characterized by not being fixed to the bottom partition plate of the reactor water passage. (2) A pad is provided on the inner peripheral wall of the reactor pressure vessel facing the end of each reinforcing plate, and the clearance between this pad and the end of the reinforcing plate constitutes the reinforcing plate and the reactor pressure vessel. A boiling water nuclear reactor according to claim 1, wherein the boiling water nuclear reactor is constructed such that the thermal expansion becomes zero due to a difference in thermal expansion between different metals. (3) The boiling water nuclear reactor according to claim 1, wherein the position of the upper end of the reinforcing plate is below the position of the lower end of the effective fuel in the reactor core.
JP1985074220U 1985-05-21 1985-05-21 Pending JPS61190898U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP1985074220U JPS61190898U (en) 1985-05-21 1985-05-21

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP1985074220U JPS61190898U (en) 1985-05-21 1985-05-21

Publications (1)

Publication Number Publication Date
JPS61190898U true JPS61190898U (en) 1986-11-27

Family

ID=30614313

Family Applications (1)

Application Number Title Priority Date Filing Date
JP1985074220U Pending JPS61190898U (en) 1985-05-21 1985-05-21

Country Status (1)

Country Link
JP (1) JPS61190898U (en)

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