JPS62188995A - Thermal shielding device for fast breeder reactor - Google Patents
Thermal shielding device for fast breeder reactorInfo
- Publication number
- JPS62188995A JPS62188995A JP61030141A JP3014186A JPS62188995A JP S62188995 A JPS62188995 A JP S62188995A JP 61030141 A JP61030141 A JP 61030141A JP 3014186 A JP3014186 A JP 3014186A JP S62188995 A JPS62188995 A JP S62188995A
- Authority
- JP
- Japan
- Prior art keywords
- reactor vessel
- heat
- heat shielding
- reactor
- heat shield
- 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
- 230000002093 peripheral effect Effects 0.000 claims description 27
- 239000002826 coolant Substances 0.000 claims description 16
- 239000007788 liquid Substances 0.000 claims description 11
- 238000009413 insulation Methods 0.000 claims description 4
- 239000007789 gas Substances 0.000 description 21
- 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 20
- 229910052708 sodium Inorganic materials 0.000 description 20
- 239000011734 sodium Substances 0.000 description 20
- 230000000694 effects Effects 0.000 description 8
- 229910001338 liquidmetal Inorganic materials 0.000 description 6
- 230000008646 thermal stress Effects 0.000 description 6
- 238000005192 partition Methods 0.000 description 5
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 description 4
- 239000000446 fuel Substances 0.000 description 4
- 239000011261 inert gas Substances 0.000 description 4
- 230000000712 assembly Effects 0.000 description 3
- 238000000429 assembly Methods 0.000 description 3
- 230000004907 flux Effects 0.000 description 3
- FAPWRFPIFSIZLT-UHFFFAOYSA-M Sodium chloride Chemical compound [Na+].[Cl-] FAPWRFPIFSIZLT-UHFFFAOYSA-M 0.000 description 2
- 230000002411 adverse Effects 0.000 description 2
- 229910052786 argon Inorganic materials 0.000 description 2
- 239000001307 helium Substances 0.000 description 2
- 229910052734 helium Inorganic materials 0.000 description 2
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 2
- 238000005452 bending Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- CRHGSCXKJPJNAB-UHFFFAOYSA-M fomesafen-sodium Chemical compound [Na+].C1=C([N+]([O-])=O)C(C(/[O-])=N/S(=O)(=O)C)=CC(OC=2C(=CC(=CC=2)C(F)(F)F)Cl)=C1 CRHGSCXKJPJNAB-UHFFFAOYSA-M 0.000 description 1
- 239000011810 insulating material Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000011780 sodium chloride 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)
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、冷却材に液体全屈す１−リウムなどを使用す
る高速増殖炉の熱遮蔽装置に関ザる。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a thermal shielding device for a fast breeder reactor that uses a liquid 1-lium or the like as a coolant.
〔発明の技術的背Ｗ４）
第８図はタンク型高速増殖炉の概略構成を示す゛もので
、原子炉容器１０１内には、−次冷ＩＡ祠である液体金
属ナトリウム１０２が充填されており、多数本の燃料集
合体く図示せず）を装荷してなる炉心１０３が原子炉容
器１０１の中央部に位置するようにナトリウム１０２内
に浸漬配置されている。また原子炉炉容器１０１の内部
空間は炉心１０３の外周に設けられた仕切壁１０４によ
り上下に仕切られて、上方の８温ブレナム１０５と下方
の低温ブレナム１０６とに区画されており、この仕切壁
１０４に支すされたポンプ１０７を駆動することにより
、ナトリウム１０２が炉心１０３の下方から上方へ流通
して原子炉容器１０１内を循環するようになっている。[Technical Background of the Invention W4] Figure 8 shows a schematic configuration of a tank-type fast breeder reactor, in which a reactor vessel 101 is filled with liquid metal sodium 102, which is a sub-cooled IA shrine. A reactor core 103 loaded with a large number of fuel assemblies (not shown) is immersed in sodium 102 so as to be located in the center of the reactor vessel 101. Further, the internal space of the reactor vessel 101 is divided into an upper and lower part by a partition wall 104 provided on the outer periphery of the reactor core 103, and divided into an upper 8-temperature blennium 105 and a lower low-temperature blennium 106, and this partition wall By driving the pump 107 supported by the reactor 104, the sodium 102 flows from below to above the reactor core 103 and circulates within the reactor vessel 101.
前記原子炉容器１０１の上部開口はルーフスラブ１０８
により閉塞されており、このルーフスラブ１０８の中心
部には前記炉心１０３の真上に位置させて炉心上部機構
１０９が垂設されている。The upper opening of the reactor vessel 101 is a roof slab 108.
A core upper mechanism 109 is vertically installed in the center of the roof slab 108, located directly above the core 103.
また、ルーフスラブ１０８の上部には二次冷却材供給１
４ｍ（図示せず）が取付けられており、前記仕切壁１０
４にはこの二次冷却材供給機構より二次冷却材（液体全
屈ナトリウム）の供給を受ける中間熱交換器１１０が取
イリけられている。さらに炉心１０３の下方には、高圧
ブレナム１１１が設けられている。なお、液体金属ナト
リウム１０２の液面１０２ａとルーフスラブ１０８との
間にはアルゴン、ヘリウム等の不活性ガスＧがカバーガ
スとして充填されている。この不活性ガスＧは、原子炉
運転時におけるすトリウム１０２の温度変化に伴ってそ
の体積が膨張した場合の、原子炉容器１０１の内圧変化
を豊収し、原子炉構成機器に及ぼす悪影響を防止するた
めのものである。Additionally, a secondary coolant supply 1 is provided at the top of the roof slab 108.
4m (not shown) is installed, and the partition wall 10
4 is provided with an intermediate heat exchanger 110 that receives a supply of secondary coolant (liquid total flex sodium) from this secondary coolant supply mechanism. Furthermore, a high-pressure blemish 111 is provided below the core 103. Note that an inert gas G such as argon or helium is filled as a cover gas between the liquid surface 102a of the liquid metal sodium 102 and the roof slab 108. This inert gas G absorbs changes in the internal pressure of the reactor vessel 101 when the volume of storium 102 expands due to temperature changes during reactor operation, and prevents adverse effects on the reactor components. It is for the purpose of
以上の構成において、炉心１０３で約５００〜６００℃
に加熱されたナトリウム１０２は、高温プレナム１０５
から中間熱交換器１１０に導入され、ここで二次冷却材
としての二次ナトリウムと熱交換して約３００〜４００
℃まで冷却される。In the above configuration, the temperature in the core 103 is approximately 500 to 600°C.
The sodium 102 heated to
is introduced into the intermediate heat exchanger 110, where it exchanges heat with secondary sodium as a secondary coolant to generate approximately 300 to 400
Cooled to ℃.
そして低温ブレナム１０６へ流下し、ポンプ１０７で加
圧されて炉心１０３下方の高圧プレナム１１１内に圧送
される。Then, it flows down to the low-temperature blenum 106, is pressurized by the pump 107, and is pumped into the high-pressure plenum 111 below the reactor core 103.
ところで、炉心１０３内の燃料集合体の交換等を行なう
場合、原子炉運転を停止することによりナトリウム１０
２の温度は急激に低下し、燃料交換後の再運転時には急
激に上昇する。この温度変動は液面１０２ａ近傍で特に
著しく、運転停止時には約５００〜６００℃から約３０
０〜４００℃まで急激に温度降下し、再運転時には逆に
約３００〜４００℃から約５００〜６００℃まで急激に
温度上Ｒする。この急激な温度変動により、ナトリウム
１０２の液面１０２ａが直接接触している原１ｉ’８Ｚ
１０１ Ｌ［部、炉心上部ＩａｌｌＩＢ１０９、ポン
プ１０７、中間熱交換器１１０などの厚肉板には人さな
熱応力が発生し、特に原子炉容器１０１の周壁部ではそ
の影響が大きく、累月となる厚肉板の疲労を速めるおそ
れがある。By the way, when replacing the fuel assemblies in the reactor core 103, sodium 10
The temperature of No. 2 drops rapidly, and then rises rapidly when restarting operation after a fuel change. This temperature fluctuation is particularly remarkable near the liquid level 102a, and when the operation is stopped, it changes from about 500 to 600°C to about 30°C.
The temperature suddenly drops from 0 to 400°C, and when restarted, the temperature rises rapidly from about 300 to 400°C to about 500 to 600°C. Due to this rapid temperature fluctuation, the liquid surface 102a of the sodium 102 is in direct contact with the base 1i'8Z.
101 L [section, upper core IallIB 109, pump 107, intermediate heat exchanger 110, and other thick plates generate severe thermal stress, and the effect is particularly large on the peripheral wall of the reactor vessel 101, causing This may accelerate the fatigue of thick-walled plates.
そこで、原子炉容器１０１周壁部の温度変動を小さくし
、この部分の熱応力を減少させるために、原子炉容器１
０１の内周部には熱遮蔽装置が股（プられている。Therefore, in order to reduce the temperature fluctuation in the peripheral wall of the reactor vessel 101 and reduce the thermal stress in this part, the reactor vessel 101
A heat shielding device is installed on the inner periphery of 01.
これは、第９図および第１０図に示すように原子炉容器
１０１の内周面全周にわたって、ナトリウム１０２の自
由液面１０２ａを含む高さ位置に筒状壁１１２を取付け
ることにより原子炉容器１０１の内周部に円筒状の空間
部（ガスダム）１１３を形成し、この空間部１１３内に
複数の熱遮蔽板１１４を周方向および径方向に配設して
なるものである。As shown in FIGS. 9 and 10, a cylindrical wall 112 is installed over the entire inner peripheral surface of the reactor vessel 101 at a height that includes the free liquid level 102a of the sodium 102. A cylindrical space (gas dam) 113 is formed in the inner circumference of the gas dam 101, and a plurality of heat shield plates 114 are arranged in the space 113 in the circumferential direction and the radial direction.
上記熱遮蔽板１１４は周方向に一定の間隙１１５をあけ
て設けられ、径方向にも複数層たとえば３￥Ｊにわたり
一定の間隙１１６をあけて設（）られている。そしてこ
れらの熱遮蔽板１１４は、筒状壁１１２と原子炉容器１
０１の周壁との間に径方向に固定されたボルト１１７に
よって支持されている。The heat shielding plate 114 is provided with a constant gap 115 in the circumferential direction, and is also provided with a constant gap 116 in the radial direction over a plurality of layers, for example, 3J. These heat shield plates 114 are connected to the cylindrical wall 112 and the reactor vessel 1.
It is supported by bolts 117 fixed in the radial direction between it and the peripheral wall of 01.
なお、これらの熱遮蔽板１１４は第９図の如く各層ごと
に互に周方向へずらして配置され、各層の周方向間隙１
１５が互に重なり合わないように配ｂ′Ｂ、されている
。As shown in FIG. 9, these heat shielding plates 114 are arranged so as to be shifted in the circumferential direction for each layer, and the circumferential gap 1 between each layer is
15 are arranged so that they do not overlap each other.
以上の構成では、原子炉容器１０１の内側に形成された
空間部１１３がガス断熱層となって、ナトリウム１０２
から原子炉容器１０１の周壁方向への熱移動が抑制され
、また空間部１１３内の熱遮蔽板１１４により放射によ
る熱移動も抑制される。In the above configuration, the space 113 formed inside the reactor vessel 101 serves as a gas insulation layer, and the sodium 102
Heat transfer from the reactor vessel 101 toward the peripheral wall of the reactor vessel 101 is suppressed, and heat transfer due to radiation is also suppressed by the heat shield plate 114 in the space 113.
〔背景波４＋ｉの問題点〕
しかしながら、上記熱遮蔽装置では、空間部１１３内に
おいて周方向間隙１１５ｊ３よび径方向間隙１１６を通
して周方向、軸方向および径方向にガスが自然対流によ
り流通し、原子炉容器１０１の周壁方向への熱移動を必
ずしも効果的に遮蔽することは期待できない。すなわち
、第９図および第１０図に矢印で示すように、空間部１
１３内において、筒状壁１１２近傍の径方向間隙１１６
内では高温ブレナム１０５に存在する軸方向温度差の影
響を受け、筒状壁１１２に沿って軸方向上向きのガス上
昇流ａが発生する。このガス上昇流ａは空間部１１３の
上部で流れの方向を変え、空間部１１３の断熱効果によ
り生じた筒状壁１１２ど原子炉容器１０１の周壁との温
度差により径方向間隙１１５を通過する平径方向のガス
流すとなる。[Problem with background wave 4+i] However, in the above heat shielding device, gas flows in the circumferential direction, axial direction, and radial direction through the circumferential gap 115j3 and the radial gap 116 in the space 113 by natural convection, and the reactor It cannot be expected that heat transfer toward the peripheral wall of the container 101 will necessarily be effectively blocked. That is, as shown by arrows in FIGS. 9 and 10, the space 1
13, a radial gap 116 near the cylindrical wall 112
Under the influence of the axial temperature difference existing in the high temperature blemish 105, an upward axial gas flow a is generated along the cylindrical wall 112. This upward gas flow a changes its flow direction at the upper part of the space 113 and passes through the radial gap 115 due to the temperature difference between the cylindrical wall 112 and the peripheral wall of the reactor vessel 101 caused by the insulation effect of the space 113. Gas flows in the diameter direction.
そして原子炉容器１０１の周壁に達したガス流すは、今
度は原子炉１０１の内周壁面に治って軸方向下向きの下
降流Ｃとなる。The gas that has reached the peripheral wall of the reactor vessel 101 then flows down the inner peripheral wall surface of the reactor 101 and becomes a downward flow C in the axial direction.
このように、各熱遮蔽板１１４間に周方向間隙１１５お
よび径方向間隙１１６が存在するために、自然対流によ
るガス流ａ、ｂ、ｃが生じ、さらに、周方向のガス流も
生じて筒状壁１１２に接する液体台底ナトリウム１０２
から原子炉容器１０１の周壁へ至るガス流による伝達熱
量が大きく、空間部１１３の断熱効果は必ずしも満足寸
べきこしのどはいえなかった。In this way, since the circumferential gap 115 and the radial gap 116 exist between each heat shield plate 114, gas flows a, b, and c occur due to natural convection, and furthermore, a circumferential gas flow also occurs, and the cylinder Liquid platform sodium 102 in contact with shaped wall 112
The amount of heat transferred by the gas flow from the reactor vessel 101 to the peripheral wall of the reactor vessel 101 was large, and the heat insulation effect of the space 113 was not necessarily satisfactory.
さらに、原子炉容器１０１周壁および筒状壁１１２の各
表面の軸方向および周方向の温度分布が不均一となるた
め、熱応力発生およびこれに伴う変形発生のおそれもあ
り、原子炉容器１０１の健全性を充分維持するものとは
いえなかった。Furthermore, since the temperature distribution in the axial and circumferential directions on each surface of the peripheral wall of the reactor vessel 101 and the cylindrical wall 112 becomes non-uniform, there is a risk that thermal stress and accompanying deformation will occur. It could not be said that the soundness was sufficiently maintained.
本発明はこのような事情にもとづいてなされたもので、
その目的は、冷却材から原子炉容器周壁部への熱流束を
大幅に減少させることができ、さらに原子炉容器の内周
部に形成される環状空間部内でのカバーガスの自然対流
をも有効に防止して、原子炉容器の周壁部の熱応力およ
び熱変形を大幅に軽減し、原子炉容器の健全性を雑持し
、その信頼性の向上を図り得る高速増殖炉の熱遮蔽装置
を提供することにある。The present invention was made based on these circumstances, and
The purpose is to significantly reduce the heat flux from the coolant to the reactor vessel peripheral wall, and also to improve the natural convection of the cover gas within the annular space formed at the inner circumference of the reactor vessel. A thermal shielding device for a fast breeder reactor that can significantly reduce thermal stress and thermal deformation of the peripheral wall of the reactor vessel, maintain the integrity of the reactor vessel, and improve its reliability. It is about providing.
以上の目的達成のため、本発明の熱遮蔽装置は、冷却材
を収容した原子炉容器内に、その原子炉容器内周の全周
にわたって前記冷却材の自由液面を含む高さ位置に設け
られ原子炉容器内周面との間に筒状空間部を形成する筒
状壁と、前記筒状空間を周方向および径方向に複数分割
してそれぞれを独立空間とする、表面に鏡面加工を施さ
れた熱遮蔽板とを具備して構成される。In order to achieve the above object, the heat shielding device of the present invention is installed in a reactor vessel containing a coolant at a height including the free liquid level of the coolant over the entire inner circumference of the reactor vessel. A cylindrical wall that forms a cylindrical space between the cylindrical wall and the inner circumferential surface of the reactor vessel, and a surface that is mirror-finished by dividing the cylindrical space into a plurality of spaces in the circumferential direction and radial direction, each of which is an independent space. and a heat shield plate.
従って、空間部内に形成された複数の独立空間により周
方向および径方向のガス流路は遮断されて自然対流を防
止することができる。また、熱遮蔽板の表面に鏡面加工
を施したことによりその表面が熱反射面となって、放射
熱を遮断し、原子炉容器の周壁を低温に維持することが
できる。Therefore, the circumferential and radial gas flow paths are blocked by the plurality of independent spaces formed within the space, thereby preventing natural convection. Further, by mirror-finishing the surface of the heat shield plate, the surface becomes a heat reflecting surface, which blocks radiant heat and maintains the peripheral wall of the reactor vessel at a low temperature.
以下、本発明の第１の実施例を示す。第１図はタンク型
高速増殖炉の概略構成を示すもので、原子炉容器１内に
は、−次冷却材である液体金属ナトリウム２が充填され
ており、多数本の燃料集合体（図示せず）を装荷してな
る炉心３が原子炉容器１の中央部に位置するようにナト
リウム２内に浸漬配置されている。また原子炉炉容器１
の内部空間は炉心３の外周に設けられた仕切壁４により
上下に仕切られて、上方の高温ブレナＬ、 ５と下方の
低温ブレナム６とに区画されており、この仕切壁４に支
持されたポンプ７を駆動することにより、ナトリウム２
が炉心３の下方から上方へ流通して原子炉容器１内を循
環するようになっている。A first embodiment of the present invention will be described below. Figure 1 shows the schematic configuration of a tank-type fast breeder reactor, in which a reactor vessel 1 is filled with liquid metal sodium 2, which is a secondary coolant, and a large number of fuel assemblies (not shown in the figure) are filled. A reactor core 3 loaded with sodium chloride is immersed in sodium 2 so as to be located in the center of the reactor vessel 1. Also, reactor vessel 1
The internal space of the reactor core 3 is divided into upper and lower parts by a partition wall 4 provided on the outer periphery of the reactor core 3, and divided into an upper high-temperature brenum L, 5 and a lower low-temperature brenum 6. By driving pump 7, sodium 2
is arranged to flow from the bottom to the top of the reactor core 3 and circulate within the reactor vessel 1.
前記原子炉容器１の上部開口はルーフスラブ８ににり閉
塞されており、このルーフスラブ８の中心部には前記炉
心３の真上に位置させて炉心上部機構９が重設されてい
る。また、ルーフスラブ８の上部には二次冷却材供給機
構く図示せず）が取付けられており、前記仕切壁４には
この二次冷却材供給機構より二次冷却材（液体金属ナト
リウム）の供給を受ける中間熱交換器１０が取付けられ
ている。さらに炉心３の下方には、高圧ブレナム１１が
設けられている。なお、液体金属ナトリウム２の液面２
ａとルーフスラブ８との間にはアルゴン、ヘリウム等の
不活性ガスＧがカバーガスとして充填されている。この
不活性ガスＧは、原子炉運転時におけるナトリウム２の
温度変化に伴ってその体積が膨張した場合の、原子炉Ｕ
器１の内圧変化を吸収し、原子炉構成機器に及ぼす悪影
響を防止するためのものである。The upper opening of the reactor vessel 1 is closed by a roof slab 8, and a core upper mechanism 9 is superimposed in the center of the roof slab 8, located directly above the reactor core 3. A secondary coolant supply mechanism (not shown) is attached to the upper part of the roof slab 8, and a secondary coolant (liquid metal sodium) is supplied to the partition wall 4 from this secondary coolant supply mechanism. A fed intermediate heat exchanger 10 is installed. Furthermore, a high-pressure blemish 11 is provided below the core 3. In addition, the liquid level 2 of the liquid metal sodium 2
A and the roof slab 8 are filled with an inert gas G such as argon or helium as a cover gas. This inert gas G is used in the reactor U when its volume expands with the temperature change of sodium 2 during reactor operation.
This is to absorb changes in the internal pressure of the reactor 1 and prevent adverse effects on the reactor components.
原子−容器１の内周面部には熱遮蔽装置が設けられてい
る。これは、第２図および第３図に示すように原子炉容
器１の内周面全周にわたって、ナトリウム２の自由液面
２ａを含む高さ位置に筒状壁１２を取付けることにより
原子炉容器１の内周部に円筒状の空間部（ガスダム）１
３を形成し、この空間部１３内に複数の熱遮蔽板１４を
周方向および径方向に配設してなるものである。A heat shielding device is provided on the inner peripheral surface of the atom-container 1. As shown in FIGS. 2 and 3, a cylindrical wall 12 is installed over the entire inner peripheral surface of the reactor vessel 1 at a height that includes the free liquid level 2a of the sodium 2. A cylindrical space (gas dam) 1 on the inner circumference of 1
3, and a plurality of heat shielding plates 14 are arranged in the circumferential direction and the radial direction within this space 13.
上記熱遮蔽板１４は、原子炉容器１周壁の曲面に沿うよ
うに曲成された中央遮蔽部１５の両側を原子炉容器１の
中心に向けてほぼ直角に折曲して側方遮蔽部１６ａ、１
６ｂとし、両側方遮蔽部１６ａ、１６ｂの終端縁を筒状
壁１２外面、または内側に位置する熱遮蔽板１４の中央
遮蔽部１５外面に密接させているものである。そして各
熱遮蔽板１４は周方向に一定の間隙１７をあけて取イ」
けられ、この間隙１７により熱遮蔽板１４の熱膨張を吸
収するようにしている。また、各熱遮蔽板１４間には径
方向にも側方遮蔽部１６ａ、１６ｂの幅寸法に相当する
間隙１８が形成される。The heat shielding plate 14 is formed by bending both sides of the central shielding part 15, which is curved along the curved surface of the peripheral wall of the reactor vessel 1, at a substantially right angle toward the center of the reactor vessel 1, and forming side shielding parts 16a. ,1
6b, and the terminal edges of both side shielding parts 16a and 16b are brought into close contact with the outer surface of the cylindrical wall 12 or the outer surface of the central shielding part 15 of the heat shielding plate 14 located inside. Each heat shield plate 14 is placed with a certain gap 17 in the circumferential direction.
This gap 17 absorbs thermal expansion of the heat shield plate 14. Further, a gap 18 corresponding to the width dimension of the side shielding portions 16a, 16b is also formed in the radial direction between each of the heat shielding plates 14.
なお、これらの熱遮蔽板１４は第２図の如く各層ごとに
互に周方向へずらして配置され、筒状壁１２と原子炉容
器１の周壁との間に径方向に固定されたボルト１９によ
って支持されている。なお熱遮蔽板１４の支持手段とし
ては、ルーフスラブ８より垂下支持するようにしてもよ
い。モして各熱遮蔽板１４ごとに多数の独立空間を形成
して、独立空間から他の独立空間へのガスの流路を遮断
し、周方向および径方向のガス流路をいずれも遮断して
、自然対流の発生を防止するようにしている。As shown in FIG. 2, these heat shielding plates 14 are arranged so as to be shifted in the circumferential direction in each layer, and bolts 19 are fixed in the radial direction between the cylindrical wall 12 and the peripheral wall of the reactor vessel 1. Supported by Note that the heat shielding plate 14 may be supported by hanging from the roof slab 8 as a supporting means. A large number of independent spaces are formed in each heat shield plate 14 to block gas flow paths from one independent space to another independent space, and to block both circumferential and radial gas flow paths. This prevents the occurrence of natural convection.
前記各熱遮蔽板１４の表面は高度の反射率が得られるよ
うにａ面加工が施され、空間部１３内の放射熱を遮断す
るようにしている。The surface of each of the heat shielding plates 14 is subjected to a-plane processing so as to obtain a high degree of reflectance, and is designed to block radiant heat within the space 13.
以上のような構成では、原子炉容器１の内側に形成され
た円筒状の空間部１３内においては、多数の熱遮蔽板１
４が周方向および径方向に配設されて熱遮蔽板１４ごと
に独立空間を形成し、しかも各熱遮蔽板１４の表面は高
度の反射率が得られるように鏡面加工が施されているの
で、ガスの自然対流および放射熱により高温のナトリウ
ム２から筒状壁１２および空間部１３を介して原子炉容
Ｎ１周壁へ至る熱流束を効率よく遮断し、原子炉容器１
周壁の温度を低温に維持して過大な熱応力、熱変形の発
生を防止することができる。In the above configuration, in the cylindrical space 13 formed inside the reactor vessel 1, a large number of heat shield plates 1
4 are arranged in the circumferential direction and the radial direction to form an independent space for each heat shield plate 14, and the surface of each heat shield plate 14 is mirror-finished to obtain a high degree of reflectance. , the heat flux from the high-temperature sodium 2 to the reactor volume N1 circumferential wall via the cylindrical wall 12 and the space 13 is efficiently blocked by gas natural convection and radiant heat, and the reactor vessel 1
By maintaining the temperature of the peripheral wall at a low temperature, excessive thermal stress and thermal deformation can be prevented from occurring.
次に、第４図は本発明の第２の実施例を示すもので、こ
の実施例は周方向に連続し、かつ横断面が波形形状をな
す熱遮蔽板２１を使用したものである。すなわち熱遮蔽
板２１には、上下方向に連続する横断面山形の突条２２
が周方向等間隔に、かつ外方または内方へ突出するよう
に形成され、これら突条２２の頂部を原子炉容器１内周
面、筒状１１２または隣接する他の熱遮蔽板２１に＊接
させて、これら熱遮蔽板２１同志の間、熱遮蔽板２１と
原子炉容器１周壁面との間、または熱″ＸＸ根板１と筒
状壁１２との間にそれぞれ独立した間隙２３が形成され
るように構成されている。そして各熱遮蔽板２１の表面
は高度の熱反射率が得られるように鏡面加工が施されて
いる。Next, FIG. 4 shows a second embodiment of the present invention, which uses a heat shield plate 21 that is continuous in the circumferential direction and has a wave-shaped cross section. That is, the heat shielding plate 21 has a protrusion 22 having a chevron-shaped cross section that continues in the vertical direction.
are formed to protrude outward or inward at equal intervals in the circumferential direction, and the tops of these protrusions 22 are attached to the inner peripheral surface of the reactor vessel 1, the cylindrical shape 112, or other adjacent heat shielding plate 21. In contact with each other, there are independent gaps 23 between these heat shield plates 21, between the heat shield plates 21 and the peripheral wall surface of the reactor vessel 1, or between the heat "XX root plate 1 and the cylindrical wall 12. The surface of each heat shield plate 21 is mirror-finished to obtain a high degree of heat reflectance.
以上の構成によっても第１の実施例と同様の効果を得る
ことができる。The above configuration also provides the same effects as the first embodiment.
次に第５図および第６図は第３の実ｍ例を示すもので、
この実施例では第１の実施例にお【プる熱遮蔽板１４の
中央遮蔽部１５と側方熱遮蔽板１６ａ、１６ｂとを別部
材として構成しているものである。すなわち熱遮蔽板３
１が第１の実施例の中央遮蔽部１５に相当し、角柱状パ
ッド３２が第１の実施例の側方熱遮蔽板１６ａ、１６ｂ
に相当する。Next, FIGS. 5 and 6 show a third actual example,
In this embodiment, the central shielding portion 15 of the heat shielding plate 14 and the side heat shielding plates 16a, 16b, which are similar to the first embodiment, are constructed as separate members. That is, the heat shield plate 3
1 corresponds to the central shielding part 15 of the first embodiment, and the prismatic pads 32 correspond to the side heat shielding plates 16a, 16b of the first embodiment.
corresponds to
モして各熱遮蔽板３１の表面は８度の熱反射率が得られ
るように鏡面加工が施されている。また側方熱遮蔽板３
２は断熱材により形成されている。Furthermore, the surface of each heat shield plate 31 is mirror-finished so as to obtain a heat reflectance of 8 degrees. Also, the side heat shield plate 3
2 is made of a heat insulating material.
以上の構成によっても第１．第２の実施例と同様の効果
を得ることができる。With the above configuration, the first. The same effects as in the second embodiment can be obtained.
次に第７図は第４の実施例を示すもので、筒状壁１２と
原子炉容器１の内周面との間に形成された筒状空間１３
内に多数の熱遮蔽板４１が、周方向に一定の間隙４２を
あけ、径方向にも一定の間隙４３をあけて複数層たとえ
ば３層にわたり配列されている。そしてこれらの熱遮蔽
板４１は各層ごとに互いに周方向へずらして配置され、
筒状壁１２と熱遮蔽板４１との間、および周方向に隣接
する熱遮蔽板４１同志の間に、断面コ字形をなす支持体
４２を介挿してなるものである。なお、上記支持体４２
はボルト４３により熱遮蔽板４１に固定され、これらの
支持体４２により熱遮蔽板４１間の周方向間隙を保持す
るとともに、周方向および半径方向のガス流銘を遮断し
、自然対流による熱移動を防止するものである。Next, FIG. 7 shows a fourth embodiment, in which a cylindrical space 13 is formed between the cylindrical wall 12 and the inner peripheral surface of the reactor vessel 1.
A large number of heat shielding plates 41 are arranged in multiple layers, for example, three layers, with constant gaps 42 in the circumferential direction and constant gaps 43 in the radial direction. These heat shielding plates 41 are arranged so as to be offset from each other in the circumferential direction for each layer,
A support body 42 having a U-shaped cross section is inserted between the cylindrical wall 12 and the heat shield plate 41 and between the heat shield plates 41 adjacent to each other in the circumferential direction. Note that the support body 42
are fixed to the heat shield plate 41 by bolts 43, and these supports 42 maintain the circumferential gap between the heat shield plates 41, block gas flow in the circumferential direction and radial direction, and prevent heat transfer by natural convection. This is to prevent
以上詳述したように、本発明に係る高速増殖炉の熱遮蔽
装置によれば、冷却材から原子炉容器周壁部への熱流束
を大幅に減少させることができ、さらに原子炉容器の内
周部に形成される環状空間部内でのカバーガスの自然対
流をも有効に防止して、原子炉容器の周壁部の熱応力お
よび熱変形を大幅に軽減し、原子炉容器の健全性を維持
し、その信頼性の向上を図ることができる。As described in detail above, according to the heat shielding device for a fast breeder reactor according to the present invention, it is possible to significantly reduce the heat flux from the coolant to the peripheral wall of the reactor vessel, and It also effectively prevents natural convection of the cover gas within the annular space formed in the reactor vessel, significantly reducing thermal stress and thermal deformation on the peripheral wall of the reactor vessel, and maintaining the integrity of the reactor vessel. , its reliability can be improved.
第１図ないし第３図は本発明の第１の実施例を示すもの
で、第１図は高速増殖炉の１Ｉ１７ｉ面図、第２図は熱
遮蔽装置の一部を示す横断面図、第３図は第２図の■−
■断面図、第４図は第２の実施例における熱遮蔽装置の
一部を示す横断面図、第５図および第６図は第３の実施
例を示すもので、第５図は熱遮蔽装置の一部を示す横断
面図、第６図は第５図のＶｌ −ＶＩＸ断面図第７図は
第４の実施例における熱遮蔽装置の一部を示す横断面図
、第８図ないし第１０図は従来例を示すもので、第８図
は高速増殖炉の縦断面図、第９図は熱遮蔽装置の一部を
示す横断面図、第１０図は第９図のＸ−Ｘ断面図である
。
１・・・原子炉容器、２・・・液体金属ナトリウム（−
次冷却材）、３・・・炉心、１２・・・筒状壁、１３・
・・円筒状の空＠部、１４．２１・・・熱遮蔽板。
出顕人代理人 弁理士 鈴江武彦
第１図
第２図
第３図
第４図
第５図
第６図
第７図
第８図
第９図
第１０図1 to 3 show a first embodiment of the present invention, in which FIG. 1 is a 1I17i side view of a fast breeder reactor, FIG. 2 is a cross-sectional view showing a part of a heat shielding device, and FIG. Figure 3 shows ■− in Figure 2.
■Cross-sectional view, Figure 4 is a cross-sectional view showing a part of the heat shielding device in the second embodiment, Figures 5 and 6 show the third embodiment, and Figure 5 is a cross-sectional view showing a part of the heat shielding device in the second embodiment. FIG. 6 is a cross-sectional view showing a part of the device, FIG. 6 is a cross-sectional view taken along Vl-VIX in FIG. Figure 10 shows a conventional example, Figure 8 is a longitudinal cross-sectional view of a fast breeder reactor, Figure 9 is a cross-sectional view showing a part of the heat shielding device, and Figure 10 is a cross-section taken along line XX in Figure 9. It is a diagram. 1...Reactor vessel, 2...Liquid metal sodium (-
secondary coolant), 3... core, 12... cylindrical wall, 13...
...Cylindrical empty @ part, 14.21...Heat shielding plate. Representative Patent Attorney Takehiko Suzue Figure 1 Figure 2 Figure 3 Figure 4 Figure 5 Figure 6 Figure 7 Figure 8 Figure 9 Figure 10
Claims (5)
器内周の全周にわたって前記冷却材の自由液面を含む高
さ位置に設けられ原子炉容器内周面との間に筒状空間部
を形成する筒状壁と、前記筒状空間を周方向および径方
向に複数分割してそれぞれを独立空間とする、表面に鏡
面加工を施された熱遮蔽板とを具備したことを特徴とす
る高速増殖炉の熱遮蔽装置。(1) A cylinder installed in the reactor vessel containing the coolant at a height including the free liquid level of the coolant over the entire inner circumference of the reactor vessel and between the reactor vessel inner circumferential surface. A cylindrical wall forming a shaped space, and a heat shielding plate having a mirror-finished surface that divides the cylindrical space into a plurality of spaces in a circumferential direction and a radial direction, each of which is an independent space. Features of fast breeder reactor heat shielding equipment.
に複数枚ずつ配設され、各熱遮蔽板は原子炉容器周壁の
曲面に沿うように曲成された中央遮蔽部の両側を原子炉
容器の中心に向けてほぼ直角に折曲して側方遮蔽部とす
るもので、両側方遮蔽部の終端縁を筒状壁外面、または
内側に位置する熱遮蔽板の中央遮蔽部外面に密接させて
おり、各熱遮蔽板は周方向に一定の間隙をあけて取付け
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
の高速増殖炉の熱遮蔽装置。(2) A plurality of the heat shield plates are arranged in the circumferential direction and the radial direction of the reactor vessel, and each heat shield plate covers both sides of the central shield part that is curved along the curved surface of the reactor vessel peripheral wall. The side shields are bent almost at right angles toward the center of the reactor vessel, and the terminal edges of both side shields are attached to the outer surface of the cylindrical wall, or the outer surface of the central shield of the heat shield located inside. 2. A heat shielding device for a fast breeder reactor according to claim 1, wherein the heat shielding plates are mounted in close contact with each other, and each heat shielding plate is attached with a constant gap in the circumferential direction.
突条を周方向等間隔に、かつ外方または内方へ突出する
ように形成され、これら突条の頂部を原子炉容器内周面
、筒状壁または隣接する他の熱遮蔽板に当接させて、こ
れら熱遮蔽板同志の間、熱遮蔽板と原子炉容器内周面と
の間、または熱遮蔽板と筒状壁との間にそれぞれ独立し
た間隙２３が形成されるようにした特許請求の範囲第１
項記載の高速増殖炉の熱遮蔽装置。(3) The heat shield plate is formed with protrusions having a mountain-shaped cross section that are continuous in the vertical direction and are formed at equal intervals in the circumferential direction and protrude outward or inward, and the tops of these protrusions are connected to the reactor vessel. In contact with the inner peripheral surface, cylindrical wall, or other adjacent heat shielding plate, between these heat shielding plates, between the heat shielding plate and the inner peripheral surface of the reactor vessel, or between the heat shielding plate and the cylindrical Claim 1 wherein independent gaps 23 are formed between the wall and the wall.
A heat shielding device for a fast breeder reactor as described in .
に複数枚ずつそれぞれの間に間隔をあけて配設され、径
方向に隣接する熱遮蔽板間に角柱状の断熱材製パッドを
介挿してなる特許請求の範囲第１項記載の高速増殖炉の
熱遮蔽装置。(4) A plurality of the heat shield plates are arranged at intervals in the circumferential direction and the radial direction of the reactor vessel, and a prismatic insulation pad is formed between the radially adjacent heat shield plates. A heat shielding device for a fast breeder reactor according to claim 1, which comprises:
に複数枚ずつそれぞれの間に間隔をあけて配設され、径
方向に隣接する熱遮蔽板間に断面コ字形の支持体を介挿
してなる特許請求の範囲第１項記載の高速増殖炉の熱遮
蔽装置。(5) A plurality of the heat shield plates are arranged at intervals in the circumferential direction and radial direction of the reactor vessel, and a support body having a U-shaped cross section is provided between the heat shield plates adjacent in the radial direction. A heat shielding device for a fast breeder reactor according to claim 1, which is inserted therein.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61030141A JPS62188995A (en) | 1986-02-14 | 1986-02-14 | Thermal shielding device for fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61030141A JPS62188995A (en) | 1986-02-14 | 1986-02-14 | Thermal shielding device for fast breeder reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS62188995A true JPS62188995A (en) | 1987-08-18 |
Family
ID=12295488
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61030141A Pending JPS62188995A (en) | 1986-02-14 | 1986-02-14 | Thermal shielding device for fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS62188995A (en) |
-
1986
- 1986-02-14 JP JP61030141A patent/JPS62188995A/en active Pending
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