JPS59168389A - Thermal shield structure of reactor container wall - Google Patents

Thermal shield structure of reactor container wall

Info

Publication number
JPS59168389A
JPS59168389A JP58042302A JP4230283A JPS59168389A JP S59168389 A JPS59168389 A JP S59168389A JP 58042302 A JP58042302 A JP 58042302A JP 4230283 A JP4230283 A JP 4230283A JP S59168389 A JPS59168389 A JP S59168389A
Authority
JP
Japan
Prior art keywords
gas
layer
container wall
shield structure
reactor
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
JP58042302A
Other languages
Japanese (ja)
Inventor
魚谷 正樹
透 坂本
佐々田 泰宏
近藤 嶺一
山中 庸靖
大友 康正
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Central Research Institute of Electric Power Industry
Hitachi Ltd
Original Assignee
Central Research Institute of Electric Power Industry
Hitachi Ltd
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 by Central Research Institute of Electric Power Industry, Hitachi Ltd filed Critical Central Research Institute of Electric Power Industry
Priority to JP58042302A priority Critical patent/JPS59168389A/en
Publication of JPS59168389A publication Critical patent/JPS59168389A/en
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

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】 本発明は、断熱層@に係り、特に液体金属冷却高速増殖
炉等に使用するに好適な断熱構造に関する。
DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a heat insulating layer@, and particularly to a heat insulating structure suitable for use in liquid metal cooled fast breeder reactors and the like.

従来の断熱構造の一例として、第1図に示すようなもの
がある。
An example of a conventional heat insulating structure is shown in FIG.

第1図において、ホットプレナムlと炉容器壁4との間
に、冷却材が流れる冷却層3とガス断熱層2がある。冷
却材流量が十分とれる場合は、2の断熱効果と3の冷却
効果により、炉容器壁は、低い温度に維持できる。また
、冷却材a量がとれなくなった場合でも、2の断熱効果
と3内の冷却材の熱容量の効果によシ、炉容器壁の温度
上昇を緩慢なものにすることができる。ところでガス断
熱層は熱膨張吸収のため上部がカバーガス中に開口して
いる方が構造健全性の点で有利である。こうした断熱構
造において、ホットブレナム液面、又は壁冷却層液面の
変動等により、@2図のように冷却材がカス断熱層中へ
流入した場合、ガス層に、冷却材が満たされ、断熱機能
を失う。
In FIG. 1, between the hot plenum l and the reactor vessel wall 4 there is a cooling layer 3 through which a coolant flows and a gas insulation layer 2. If the coolant flow rate is sufficient, the temperature of the furnace vessel wall can be maintained at a low temperature due to the heat insulation effect (2) and the cooling effect (3). Further, even if the amount of coolant a cannot be obtained, the temperature rise in the wall of the furnace vessel can be made slow due to the heat insulation effect in 2 and the heat capacity effect of the coolant in 3. Incidentally, in order to absorb thermal expansion, it is advantageous for the gas heat insulating layer to have its upper part opened into the cover gas in terms of structural integrity. In such a heat insulating structure, when coolant flows into the scum heat insulating layer as shown in Figure 2 due to fluctuations in the hot blemish liquid level or the wall cooling layer liquid level, the gas layer is filled with coolant and the heat insulation layer is insulated. lose functionality.

したがって従来の断熱構造では、炉容器壁を低流に維持
することができなくなる欠点があった。
Therefore, the conventional heat insulating structure has the disadvantage that it is not possible to maintain a low flow through the wall of the furnace vessel.

本発明の目的は、前記の)ような従来のガス断熱層の欠
点を補ない、高速増殖炉の炉容器等に信頼性の高い、好
適な断熱構造を提供することにある。
An object of the present invention is to provide a highly reliable and suitable heat insulating structure for a reactor vessel of a fast breeder reactor, etc., which compensates for the drawbacks of the conventional gas heat insulating layer as described above.

本発明は第3図において、5の如く多層のエアポケット
を有するガス断熱層を有するものである。
The present invention has a gas insulation layer having multiple air pockets as shown in 5 in FIG.

このような構造とすることで第4図の如く、ガス断熱層
に冷却材が流入した場合でもエアポケットにガスが残留
し断熱機能を維持できる。さらに1つのエアポケットの
気密性が失われても他のエアポケットのガス層によシ断
熱機能は維持できる。
With such a structure, as shown in FIG. 4, even when coolant flows into the gas insulation layer, gas remains in the air pocket and the insulation function can be maintained. Furthermore, even if the airtightness of one air pocket is lost, the insulation function can be maintained by the gas layer of the other air pocket.

すなわち、本発明は、種々な事象にわたって、健全な断
熱機能を保証するガス断熱構造と言える。
That is, the present invention can be said to be a gas insulation structure that guarantees sound insulation function over various events.

本発明をタンク型高速増殖炉に実施した例を第5図に示
す。
FIG. 5 shows an example in which the present invention is implemented in a tank-type fast breeder reactor.

第5図において、炉心6で加熱され高温になったナトリ
ウムは、ホットプレナム1に入る。さらに、中間熱交換
器7に入り、2次側ナトリウムと熱交換して低温になシ
、コールドプレナム8に入る。ポンプ9で昇圧された後
、高圧プレナム10を経て再び、炉心6に入る。
In FIG. 5, sodium heated to a high temperature in the reactor core 6 enters the hot plenum 1. Furthermore, it enters the intermediate heat exchanger 7, exchanges heat with the secondary side sodium, becomes low temperature, and enters the cold plenum 8. After being pressurized by the pump 9, it passes through the high-pressure plenum 10 and enters the core 6 again.

上記のホットプレナム内のナトリウムの温度は5ooC
程度となっておシ、原子炉容器4の上半分は、特別な配
慮をしないとs ooc前後の高温となり、構造強度上
好ましくない。この為、ホットプレナム1と原子炉容器
4の壁を熱的に隔離するために、多層のエアポケットヲ
有するガス断熱層2′ft:設ける。ガス断熱層だけで
は、原子炉容器壁の温度を低温に保つ事ができない場合
には、バックアップとして冷却層3を設けてもよい。
The temperature of sodium in the hot plenum above is 5ooC
If special consideration is not taken, the upper half of the reactor vessel 4 will reach a high temperature of around SOOC, which is not desirable in terms of structural strength. For this reason, in order to thermally isolate the walls of the hot plenum 1 and the reactor vessel 4, a gas insulation layer 2'ft having multiple air pockets is provided. If the temperature of the reactor vessel wall cannot be kept low with only the gas insulation layer, a cooling layer 3 may be provided as a backup.

ところで、このような原子炉は、地震等の異常事象によ
り、ホットプレナムの液面が変動するととがある。上記
の如く、ガス断熱層に多層のエアポケット5を設けるこ
とにより、こうした液面変動等のためガス層にホットプ
レナムのナトリウムが流入することがあっても、ポケッ
ト内のガス圧により、ナトリウムは、ポケット中へ流入
することができない。乙たがって、ポケット内のガス層
によって、断熱機能は保護される。
Incidentally, in such a nuclear reactor, the liquid level in the hot plenum may fluctuate due to an abnormal event such as an earthquake. As mentioned above, by providing multi-layered air pockets 5 in the gas insulation layer, even if sodium from the hot plenum flows into the gas layer due to liquid level fluctuations, the gas pressure inside the pockets will keep the sodium from flowing. , cannot flow into the pocket. The insulation function is therefore protected by the gas layer inside the pocket.

また、このガスポケットを多重化することで、ある1つ
のエアポケットが破損した場合でも、残るガス層により
、断熱機能は保詐される。
Furthermore, by multiplexing these gas pockets, even if one air pocket is damaged, the remaining gas layer will maintain the insulation function.

さらに、本断熱構造の製造技術は、従来のマノメータシ
ールの製造技術に類似しておシ、大幅な製造コストの増
加なしに、信頼性の高い断熱構造を提供できる利点をも
もっている。
Furthermore, the manufacturing technology of the present heat-insulating structure is similar to the manufacturing technology of conventional manometer seals, and has the advantage of providing a highly reliable heat-insulating structure without significantly increasing manufacturing costs.

本発明によれば、冷却材が、ガス断熱層へ流入するとい
う異常事象等においても、なお、断熱機能を維持するこ
とができるので、原子炉等において、常に原子炉容器を
低温に保つという構造強度上の要求に対して、十分に応
えられる。
According to the present invention, even in an abnormal event such as when coolant flows into the gas insulation layer, the insulation function can be maintained, so in a nuclear reactor, etc., the reactor vessel is always kept at a low temperature. Can fully meet strength requirements.

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

第1図は従来のガス層を有する断熱構造の説明図、第2
図はガス層に冷却材が流入した場合の説明図、第3図は
本発明の一実施例の多層のエアポケットを設けたガス層
を有する断熱構造の説明図、第4図は同じくガス層た′
ナトリウムが流入した場合の説明図、第5図は本発明の
高速増殖炉への適用例を示す全体図である。 1・・・ホットプレナム、2・・・ガス断熱層、3・・
・冷却層、4・・・炉容器、5・・・エアポケット、6
・・・炉心、7・・・中間熱交換器、8・・・コールド
プレカム、9・・・峯1図 浩2図 第3図 千41¥1
Figure 1 is an explanatory diagram of a conventional heat insulating structure with a gas layer, Figure 2
The figure is an explanatory diagram when a coolant flows into the gas layer, FIG. 3 is an explanatory diagram of an insulating structure having a gas layer with multilayer air pockets according to an embodiment of the present invention, and FIG. 4 is an explanatory diagram of the gas layer as well. Ta'
FIG. 5, which is an explanatory diagram when sodium flows in, is an overall diagram showing an example of application of the present invention to a fast breeder reactor. 1...Hot plenum, 2...Gas insulation layer, 3...
・Cooling layer, 4...Furnace vessel, 5...Air pocket, 6
...Reactor core, 7...Intermediate heat exchanger, 8...Cold pre-cum, 9...Mine 1, Figure 2, Figure 3, 1,000,41 yen

Claims (1)

【特許請求の範囲】[Claims] 1、上部を炉容器カバーガス中に開口し、側部、及び、
底部を閉じたガス断熱層を有する炉壁断熱構造において
、該ガス断熱層に多層のエアポケットを設けたことを特
徴とする炉容器壁の断熱構造。
1. The upper part is opened into the furnace vessel cover gas, the side part, and
1. A furnace wall insulation structure having a gas insulation layer with a closed bottom, characterized in that the gas insulation layer is provided with multilayer air pockets.
JP58042302A 1983-03-16 1983-03-16 Thermal shield structure of reactor container wall Pending JPS59168389A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP58042302A JPS59168389A (en) 1983-03-16 1983-03-16 Thermal shield structure of reactor container wall

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP58042302A JPS59168389A (en) 1983-03-16 1983-03-16 Thermal shield structure of reactor container wall

Publications (1)

Publication Number Publication Date
JPS59168389A true JPS59168389A (en) 1984-09-22

Family

ID=12632223

Family Applications (1)

Application Number Title Priority Date Filing Date
JP58042302A Pending JPS59168389A (en) 1983-03-16 1983-03-16 Thermal shield structure of reactor container wall

Country Status (1)

Country Link
JP (1) JPS59168389A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4927597A (en) * 1986-10-09 1990-05-22 Novatome Device for cooling the main vessel of a fast neutron nuclear reactor cooled by a liquid metal

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4927597A (en) * 1986-10-09 1990-05-22 Novatome Device for cooling the main vessel of a fast neutron nuclear reactor cooled by a liquid metal

Similar Documents

Publication Publication Date Title
US11189384B2 (en) Systems and methods for enhancing isolation of high-temperature reactor containments
JP2659849B2 (en) Pressurized gasifier
JPS59168389A (en) Thermal shield structure of reactor container wall
US3106957A (en) Heat exchanger
US3844885A (en) Insulation and cooling system for a nuclear reactor condenser compartment
JPH0450552B2 (en)
CN108498979A (en) A kind of spiral plate type heat pipe spark arrester
JPS60158069A (en) Heat-resisting vessel
JPS59114487A (en) Fbr reactor vessel
JPS60205278A (en) Fast breeder reactor
JPS60259990A (en) Sodium fire inhibiting system
JPS6129789A (en) Tank type fast breeder reactor
JPH03207992A (en) Heat exchanger
JPS59108983A (en) Thermal shield layer structure
JPS5830699A (en) Leak sodium storing device
JPS59126292A (en) Coolant leakage preventive device for fast breeder
JPS61215994A (en) Protective device for reactor vessel of fast breeder reactor
JPS61181997A (en) Sodium cooling system arrangement system
JPS5899794A (en) Thermal shielding structure of reactor
JPS61120092A (en) Nuclear reactor structure
JPH0475362B2 (en)
JPS60198482A (en) Fast breeder reactor
JPS58223788A (en) Overflow and pump-up feedwater device of reactor coolant
JPS6350792A (en) Fast breeder reactor
JPS59212598A (en) Separation type low temperature tank