JPS62159094A - Center rest mechanism of main vessel for fast breeder reactor - Google Patents
Center rest mechanism of main vessel for fast breeder reactorInfo
- Publication number
- JPS62159094A JPS62159094A JP61000807A JP80786A JPS62159094A JP S62159094 A JPS62159094 A JP S62159094A JP 61000807 A JP61000807 A JP 61000807A JP 80786 A JP80786 A JP 80786A JP S62159094 A JPS62159094 A JP S62159094A
- Authority
- JP
- Japan
- Prior art keywords
- vessel
- main
- fast breeder
- key structure
- melting point
- 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
- 238000002844 melting Methods 0.000 claims description 19
- 230000008018 melting Effects 0.000 claims description 19
- 229910045601 alloy Inorganic materials 0.000 claims description 14
- 239000000956 alloy Substances 0.000 claims description 14
- 229910001338 liquidmetal Inorganic materials 0.000 claims description 4
- 230000000284 resting effect Effects 0.000 claims 2
- 238000010438 heat treatment Methods 0.000 claims 1
- 239000002826 coolant Substances 0.000 description 9
- 230000000694 effects Effects 0.000 description 3
- 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
- HCHKCACWOHOZIP-UHFFFAOYSA-N Zinc Chemical compound [Zn] HCHKCACWOHOZIP-UHFFFAOYSA-N 0.000 description 1
- 238000010521 absorption reaction Methods 0.000 description 1
- 239000003795 chemical substances by application Substances 0.000 description 1
- 238000013016 damping Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000003384 imaging method Methods 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 150000002739 metals Chemical class 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 238000005192 partition Methods 0.000 description 1
- 230000000717 retained effect Effects 0.000 description 1
- 238000005096 rolling process Methods 0.000 description 1
- 229910052708 sodium Inorganic materials 0.000 description 1
- 239000011734 sodium Substances 0.000 description 1
- 239000004071 soot Substances 0.000 description 1
- 239000000725 suspension Substances 0.000 description 1
- 229910052725 zinc Inorganic materials 0.000 description 1
- 239000011701 zinc 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
- Blast Furnaces (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】
〔発明の技術分野〕
本発明は、地震時の主容器の横揺れを抑制する高速増殖
炉の主容器振れ止め機構に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a main vessel steadying mechanism for a fast breeder reactor that suppresses the lateral shaking of the main vessel during an earthquake.
（発明の技術的背景〕
液体金属を冷却材とする高速増殖炉は、例えば第５図に
示す如く構成されている。同図において符号１０１は内
部に炉心１０２を有、する主容器で、この主容器１０１
の外側には主容器１０１を保護するガードベッセル１０
３が設けられている。これらの主容器１０１及びガード
ベッセル１０３は、リングガータ１０４を介して原子炉
建屋１０５に据付けられており、主容器１０１の上部開
口はルーフスラブ１０６によって閉塞されている。(Technical Background of the Invention) A fast breeder reactor that uses liquid metal as a coolant is configured as shown in FIG. Main container 101
There is a guard vessel 10 on the outside that protects the main container 101.
3 is provided. The main vessel 101 and the guard vessel 103 are installed in the reactor building 105 via a ring gutter 104, and the upper opening of the main vessel 101 is closed by a roof slab 106.
このルーフスラブ１０６には中間熱交換器１０７と循環
ポンプ１０８が主容器１０１の周方向に複数台搭載され
ており、さらにルーフスラブ１０６の中央部には回転プ
ラグ１０９が回転自在に嵌装されている。A plurality of intermediate heat exchangers 107 and circulation pumps 108 are mounted on the roof slab 106 in the circumferential direction of the main container 101, and a rotary plug 109 is rotatably fitted in the center of the roof slab 106. There is.
この回転プラグ１０９の炉心上方位置には炉心上部機構
１１０が貫通しており、前記炉心１０２は炉心上部機構
１１０内に設けられた制御棒駆動機構（図示せず）によ
って炉心出力が制御されるようになっている。なお、炉
心１０２はルーフスラブ１０６から吊り下げられた円筒
状の吊り胴１１１によって支持されており、吊り胴１１
１の周面には複数のフローホール１１２が穿設されてい
る。A core upper mechanism 110 passes through the rotary plug 109 at a position above the core, and the reactor core 102 has a control rod drive mechanism (not shown) provided in the core upper mechanism 110 to control the core output. It has become. Note that the core 102 is supported by a cylindrical suspension shell 111 suspended from the roof slab 106.
A plurality of flow holes 112 are bored in the circumferential surface of 1.
また、前記主容！！！１０１内には液体ナトリウム等の
液体金属が冷却材１１３として貯溜されている。Also, the above subject! ! ! A liquid metal such as liquid sodium is stored in the coolant 113 as a coolant 113 .
この主容器１０１内の冷却材１１３は隔壁１１４によっ
て上下に仕切られており、主容器１０１内の上部をホッ
トブール１１５に、また主容器１０１内の下部をコール
ドプール１１６に形成している。The coolant 113 in the main container 101 is partitioned into upper and lower parts by a partition wall 114, with the upper part of the main container 101 forming a hot boule 115 and the lower part of the main container 101 forming a cold pool 116.
上記コールドプール１１Ｇ内の冷却材１１３は、原子炉
の定常運転時は約４００℃程度であり、循環ポンプ１０
８により炉心１０２の下方へ送り込まれる。The coolant 113 in the cold pool 11G is approximately 400°C during steady operation of the reactor, and the temperature of the coolant 113 in the cold pool 11G is approximately 400°C.
8 into the lower part of the core 102.
そして、炉心１０２内を下方から上方へと通流する間に
約５００ ’Ｃ程度まで昇温してホットブール１１５へ
流出し、ホットブール１１５に流出した冷却材１１３は
フローホール１１２を通過して中間熱交換器１０７に入
り、ここで約４００″Ｃ程度まで冷却された後、再びコ
ールドプール１１６へ戻るようになっている。The coolant 113 heats up to about 500'C while flowing from the bottom to the top in the core 102 and flows out into the hot boule 115. After entering the intermediate heat exchanger 107 and being cooled down to about 400''C, it returns to the cold pool 116 again.
ところで、このような高速増殖炉では地震時の主容器１
０１の横揺れを最少限に抑える必要がある。By the way, in such a fast breeder reactor, the main vessel 1 during an earthquake
It is necessary to minimize the rolling motion of 01.
そこで、従来では第５図に示すように、主容器１０１と
ガードベッセル１０３との間にメカニカル・キー構造２
０１を設け、主容器１０１に作用する水平地震力を上記
キー構造２０１を介してガードベッセル１０３へ伝達し
、さらにガードベッセル１０３から支持スカート１１１
を介して原子炉建屋１０５へ伝達することにより、主容
器１０１の横揺れを軽減する方法がとられている。Therefore, conventionally, as shown in FIG. 5, a mechanical key structure 2 is installed between the main container 101 and the guard vessel 103.
01 is provided to transmit the horizontal seismic force acting on the main vessel 101 to the guard vessel 103 via the key structure 201, and further from the guard vessel 103 to the support skirt 111.
A method has been adopted to reduce the lateral shaking of the main vessel 101 by transmitting it to the reactor building 105 via the reactor building 105.
このメカニカル・キー構造２０１は、第６図及び第７図
に示す如く主容器１０１の外壁に設けられたラジアルキ
ー２０２と、このラジアルキー２０２に対応してガード
ベッセル１０３の内壁に設けられたラジアルキー受け２
０３から構成され、上記ラジアルキー２０２とラジアル
キー受け２０３との間にはキー構造部でのかじり等を防
止するために熱膨張の吸収式としてギャップＱが設けら
れている。This mechanical key structure 201 includes a radial key 202 provided on the outer wall of the main container 101 and a radial key provided on the inner wall of the guard vessel 103 corresponding to the radial key 202, as shown in FIGS. 6 and 7. key holder 2
03, and a gap Q is provided between the radial key 202 and the radial key receiver 203 to absorb thermal expansion and prevent galling in the key structure.
ところが、このようなギャップＱを有する従来のキー構
造は、非線形振動（ガタ系の撮動）の様相を呈するため
有効な制振効果を期待することができず、また非常に難
しい非線形振動の評価を行なう必要があるなどの欠点が
あった。However, the conventional key structure with such a gap Q exhibits the appearance of nonlinear vibration (backlash-type shooting), so it is not possible to expect an effective vibration damping effect, and it is extremely difficult to evaluate nonlinear vibration. There were disadvantages such as the need to carry out
本発明は上記の問題点を解決するためになされたもので
、その目的とするところは地震時の主容器の横揺れを最
少限に抑制でき、かつ、耐震解析上も線形撮動で取扱う
ことのできる高速増殖炉の主容器振れ止め機構を提供す
ることにある。The present invention has been made to solve the above problems, and its purpose is to minimize the horizontal shaking of the main container during an earthquake, and to handle seismic analysis using linear imaging. An object of the present invention is to provide a main vessel steadying mechanism for a fast breeder reactor that is capable of providing a steady support mechanism for a fast breeder reactor.
本発明は上記の目的を達成づるために、主容器とガード
ベッセルとの間に低融点合金を保持したキー構造を設け
、主容器に作用する水平地震力を前記キー構造を介して
ガードベッセルへ伝達するようにしたことを特徴とする
ものである。In order to achieve the above object, the present invention provides a key structure holding a low melting point alloy between the main container and the guard vessel, and transfers the horizontal seismic force acting on the main container to the guard vessel through the key structure. It is characterized by being designed to communicate.
以下、第１図ないし第４図を参照して本発明の詳細な説
明する。なお、因中第５図ないし第７図と同一部分には
同一符号を付し、重複部分の説明は省略する。Hereinafter, the present invention will be explained in detail with reference to FIGS. 1 to 4. In addition, the same parts as in FIGS. 5 to 7 are given the same reference numerals, and the explanation of the overlapping parts will be omitted.
第１図及び第２図は本発明によるキー構造の一実施例を
示すもので、図中符号３０２はガードベッセル１０３の
内壁に取付けられた鉤形キー、３０３は上記鉤形キー３
０２に対応して主容器１０１の外壁に取付けられたキー
受けである。このキー受け３０３は第１図に示す如く断
面樋状に形成されており、その内部には低融点合金３０
４が保持されている。1 and 2 show an embodiment of the key structure according to the present invention, in which reference numeral 302 is a hook-shaped key attached to the inner wall of the guard vessel 103, and 303 is the hook-shaped key 3 attached to the inner wall of the guard vessel 103.
This is a key holder attached to the outer wall of the main container 101 corresponding to 02. The key receiver 303 has a gutter-like cross section as shown in FIG.
4 is retained.
この低融点合金３０４を保−持したキー構造３０１は、
主容器１０１内のコールドプール１１６と同レベルの位
置に設けられており、低融点合金３０４としては融点が
原子炉の定常運転時におけるコールドプール１１６の冷
却材温度（約４００℃程度）より若干高い金属（例えば
亜鉛、鉛、ビスマス−すす等）が使用されている。従っ
て、原子炉の定常運転時において低融点合金３０４は凝
固状態となっており、この凝固した低融点合金３０４の
中に前記鉤形キー３０２の端部が浸漬されている。なお
、図中３０５はヒータで、原子炉の起動時および停止時
に低融点合金３０４を溶融させるためのものである。The key structure 301 holding this low melting point alloy 304 is
It is provided at the same level as the cold pool 116 in the main vessel 101, and as a low melting point alloy 304, its melting point is slightly higher than the coolant temperature of the cold pool 116 (approximately 400°C) during steady operation of the reactor. Metals (eg zinc, lead, bismuth-soot, etc.) are used. Therefore, during steady operation of the nuclear reactor, the low melting point alloy 304 is in a solidified state, and the end of the hook-shaped key 302 is immersed in the solidified low melting point alloy 304. In addition, 305 in the figure is a heater for melting the low melting point alloy 304 at the time of starting and stopping the nuclear reactor.
このように主容器１０１とガードベッセル１０３との間
に低融点合金３０４を保持したキー構造３０１を設ける
ことにより、主容器１０１に作用する水平地震力は上記
キー構造３０１を介してガードベッセル１０３へ伝達さ
れ、さらにガードベッセル１０３から支持スカート１１
７を介して原子炉建屋１０５へ伝達されるので主容器１
０１の横揺れを最少限に抑制することができる。また、
従来のメカニカル・キー構造のように熱膨張の吸収式と
してギャップＱを必要としないので、耐震解析を評価の
容易な線形振動で取扱うことができる。さらに、原子炉
の起動時および停止時には凝固した低融点合金３０４を
ヒータ３０５で溶かすことにより、主容器１０１とガー
ドベッセル１０３間の熱膨張差による変位を吸収するこ
ともできる。By providing the key structure 301 holding the low melting point alloy 304 between the main container 101 and the guard vessel 103 in this way, the horizontal seismic force acting on the main container 101 is transferred to the guard vessel 103 via the key structure 301. further transmitted from the guard vessel 103 to the support skirt 11
7 to the reactor building 105, the main vessel 1
01 can be suppressed to a minimum. Also,
Unlike conventional mechanical key structures, a gap Q is not required as a thermal expansion absorption formula, so seismic analysis can be performed using linear vibration, which is easy to evaluate. Furthermore, by melting the solidified low melting point alloy 304 with the heater 305 when starting and stopping the nuclear reactor, it is also possible to absorb displacement due to the difference in thermal expansion between the main vessel 101 and the guard vessel 103.
なお、本発明は上記実施例に限定されるものではない。Note that the present invention is not limited to the above embodiments.
例えば、上記実施例では鉤形キー３０２をガードベッセ
ル１０３に、キー受け３０３を主容器１０１に取付けた
が、第３図に示す如く鉤形キー３０２を主容器１０１に
、キー受け３０３をガードベッセル１０３に設けてもよ
い。また、第４図に示す如く第１図及び第３図に示した
実施例を組み合せたキー構造３０１のもので同様の効果
が得られる。さらに、ヒータ３０５はキー構造３０１に
あらかじめ組み込んでおかなくてもよく、必要に応じて
局部的にヒータを近付けることにより低融点合金３０４
を溶かすようにしてもよい。For example, in the above embodiment, the hook-shaped key 302 was attached to the guard vessel 103 and the key receiver 303 was attached to the main container 101, but as shown in FIG. 103 may be provided. Further, as shown in FIG. 4, the same effect can be obtained by using a key structure 301 that is a combination of the embodiments shown in FIGS. 1 and 3. Furthermore, the heater 305 does not need to be incorporated into the key structure 301 in advance, and the low melting point alloy 305 can be heated locally by bringing the heater close to the key structure 301 as needed.
You may also try to dissolve it.
以上述べたように本発明によれば、液体金属が貯溜され
内部に炉心を有する有底円筒状の主容器と、この主容器
の上部開口をＭＭするルーフスラブと、上記主容器の外
側に設けられたガードベッセルとを具備した高速増殖炉
において、前記主容器とガードベッセルとの間に低融点
合金を保持したキー構造を設け、主容器に作用する水平
地震力を前記キー構造を介してガードベッセルへ伝達す
るようにしたので、高速増殖炉の耐震構造を大幅に向上
させることができる。As described above, according to the present invention, there is provided a bottomed cylindrical main container in which liquid metal is stored and has a reactor core therein, a roof slab that opens the upper opening of the main container MM, and a roof slab provided on the outside of the main container. In a fast breeder reactor equipped with a guard vessel, a key structure holding a low melting point alloy is provided between the main vessel and the guard vessel, and the horizontal seismic force acting on the main vessel is guarded through the key structure. Since the information is transmitted to the vessel, the seismic structure of the fast breeder reactor can be significantly improved.
第１図は本発明によるキー構造の一実施例を示す断面図
、第２図は第１図のｌｌ−１矢視断面図、第３図及び第
４図は本発明によるキー構造の変形例を示す断面図、第
５図は高速増殖炉の概略構成図、第６図及び第７図は従
来例を示し、第６図は第５図の■部分詳細図、第７図は
第６図の■−■矢視断面図である。
１０１・・・主容器、１０２・・・炉心、１０３・・・
ガードベッセル、１０６・・・ルーフスラブ、１１３・
・・冷却材、１１６・・・コールドプール、３０１・・
・キー構造、３０２・・・鉤形キー、３０３・・・キー
受け、３０４・・・低融点合金、３０５・・・ヒータ。
出願人代理人 弁理士 鈴江武彦
第１国
第２図
第３図
第４図
第５図FIG. 1 is a cross-sectional view showing an embodiment of the key structure according to the present invention, FIG. 2 is a cross-sectional view taken along arrow ll-1 in FIG. 1, and FIGS. 3 and 4 are modified examples of the key structure according to the present invention. FIG. 5 is a schematic configuration diagram of a fast breeder reactor, FIGS. 6 and 7 are conventional examples, FIG. 6 is a detailed partial view of FIG. 5, and FIG. It is a sectional view taken along the line ■-■. 101... Main vessel, 102... Core, 103...
Guard vessel, 106...Roof slab, 113...
...coolant, 116...cold pool, 301...
- Key structure, 302...Hook-shaped key, 303...Key receiver, 304...Low melting point alloy, 305...Heater. Applicant's agent Patent attorney Takehiko Suzue Country 1 Figure 2 Figure 3 Figure 4 Figure 5
Claims (4)
状の主容器と、この主容器の上部開口を閉塞するルーフ
スラブと、上記主容器の外側に設けられたガードベッセ
ルとを具備した高速増殖炉において、前記主容器とガー
ドベッセルとの間に低融点合金を保持したキー構造を設
け、主容器に作用する水平地震力を前記キー構造を介し
てガードベッセルへ伝達するようにしたことを特徴とす
る高速増殖炉の主容器振れ止め機構。(1) It is equipped with a bottomed cylindrical main container in which liquid metal is stored and has a reactor core inside, a roof slab that closes the upper opening of this main container, and a guard vessel provided on the outside of the main container. In a fast breeder reactor, a key structure holding a low melting point alloy is provided between the main vessel and the guard vessel, and horizontal seismic force acting on the main vessel is transmitted to the guard vessel via the key structure. A main vessel steadying mechanism for a fast breeder reactor featuring:
レベルの位置に設けられていることを特徴とする特許請
求の範囲第（１）項記載の高速増殖炉の主容器振れ止め
機構。(2) The main vessel resting mechanism for a fast breeder reactor according to claim (1), wherein the key structure is provided at the same level as the cold pool in the main vessel.
時におけるコールドプール温度より高いことを特徴とす
る特許請求の範囲第（２）項記載の高速増殖炉の主容器
振れ止め機構。(3) The main vessel resting mechanism for a fast breeder reactor according to claim (2), wherein the low melting point alloy has a melting point higher than the cold pool temperature during steady operation of the nuclear reactor.
前記低融点合金を溶融させるための加熱手段を備えてい
ることを特徴とする特許請求の範囲第（１）項記載の高
速増殖炉の主容器振れ止め機構。(4) The fast breeder reactor according to claim (1), wherein the key structure includes heating means for melting the low melting point alloy during startup and shutdown of the reactor. main container steady rest mechanism.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61000807A JPS62159094A (en) | 1986-01-08 | 1986-01-08 | Center rest mechanism of main vessel for fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61000807A JPS62159094A (en) | 1986-01-08 | 1986-01-08 | Center rest mechanism of main vessel for fast breeder reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS62159094A true JPS62159094A (en) | 1987-07-15 |
Family
ID=11483950
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61000807A Pending JPS62159094A (en) | 1986-01-08 | 1986-01-08 | Center rest mechanism of main vessel for fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS62159094A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR20160105411A (en) * | 2013-12-31 | 2016-09-06 | 뉴스케일 파워, 엘엘씨 | Seismic attenuation system for a nuclear reactor |
-
1986
- 1986-01-08 JP JP61000807A patent/JPS62159094A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR20160105411A (en) * | 2013-12-31 | 2016-09-06 | 뉴스케일 파워, 엘엘씨 | Seismic attenuation system for a nuclear reactor |
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