JPS62188993A - Thermal shielding device for fast breeder reactor - Google Patents
Thermal shielding device for fast breeder reactorInfo
- Publication number
- JPS62188993A JPS62188993A JP61030132A JP3013286A JPS62188993A JP S62188993 A JPS62188993 A JP S62188993A JP 61030132 A JP61030132 A JP 61030132A JP 3013286 A JP3013286 A JP 3013286A JP S62188993 A JPS62188993 A JP S62188993A
- Authority
- JP
- Japan
- Prior art keywords
- heat
- reactor vessel
- cylindrical
- fast breeder
- shielding device
- 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 25
- 239000002826 coolant Substances 0.000 claims description 16
- 230000002265 prevention Effects 0.000 claims description 13
- 239000007788 liquid Substances 0.000 claims description 8
- 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 23
- 229910052708 sodium Inorganic materials 0.000 description 23
- 239000011734 sodium Substances 0.000 description 23
- 239000007789 gas Substances 0.000 description 18
- 229910001338 liquidmetal Inorganic materials 0.000 description 9
- 230000000694 effects Effects 0.000 description 7
- 238000005192 partition Methods 0.000 description 6
- 230000008646 thermal stress Effects 0.000 description 6
- 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
- 238000009413 insulation Methods 0.000 description 3
- 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
- PEDCQBHIVMGVHV-UHFFFAOYSA-N Glycerine Chemical compound OCC(O)CO PEDCQBHIVMGVHV-UHFFFAOYSA-N 0.000 description 1
- 240000002834 Paulownia tomentosa Species 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 235000013372 meat Nutrition 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- PVGBHEUCHKGFQP-UHFFFAOYSA-N sodium;n-[5-amino-2-(4-aminophenyl)sulfonylphenyl]sulfonylacetamide Chemical compound [Na+].CC(=O)NS(=O)(=O)C1=CC(N)=CC=C1S(=O)(=O)C1=CC=C(N)C=C1 PVGBHEUCHKGFQP-UHFFFAOYSA-N 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、冷却材に液体金属ナトリウムなどを使用する
高速増殖炉の熱遮蔽装置に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a heat shielding device for a fast breeder reactor that uses liquid metal sodium or the like as a coolant.
第８図はタンク型高速増殖炉の概略構成を示ずもので、
原子炉容器１０１内には、−次冷却材である液体金属ナ
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１
０１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１ｏ３の外周に設けられた仕切壁１０４により上
下に仕切られて、上方の高温ブレナム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ｕ１０
４に支持されたポンプ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。Figure 8 does not show the schematic configuration of a tank-type fast breeder reactor.
The reactor vessel 101 is filled with liquid metal sodium 102 as a secondary coolant, and a reactor core 103 loaded with a large number of fuel assemblies (not shown) is placed inside the reactor vessel 1.
It is placed immersed in sodium 102 so as to be located in the center of 01. 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 1o3, and divided into an upper high-temperature blemish 105 and a lower low-temperature blemish 106, and this partition u10
By driving a pump 107 supported by 4, 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機
１ｌＩ（図示せず）が取付けられており、前記仕切壁１
０４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１１０が
取付けられている。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
門にはアルゴン、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。Further, a secondary coolant supply machine 1lI (not shown) is attached to the upper part of the roof slab 108, and the partition wall 1
04 is attached with an intermediate heat exchanger 110 that receives a secondary coolant (liquid metal sodium) from this secondary coolant supply mechanism. Furthermore, a high-pressure blemish 111 is provided below the core 103. Note that the gate between the liquid surface 102a of the liquid metal sodium 102 and the roof slab 108 is filled with an inert gas G such as argon or helium as a cover gas. This inert gas G is used to absorb changes in the internal pressure of the reactor vessel 101 when the volume of sodium 102 expands due to temperature changes during reactor operation, and to prevent adverse effects on the reactor components. belongs to.
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、高温ブレナム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.
Sodium 102 heated to high temperature Blenheim 105
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下方の高圧ブレナム１１１内に圧送
される。It then flows down to the low-temperature blemish 106, is pressurized by the pump 107, and is pumped into the high-pressure blemish 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℃カラ約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
温度上昇する。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子炉容器１
０１の周壁部、炉心上部機構１０９、ポンプ１０７、中
間熱交換器１１０などの厚肉板には大きな熱応力が発生
し、特に原子炉容器１０１の周壁部ではその影響が大き
く、素材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 is about 500 to 600 degrees Celsius.
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 reactor vessel 1.
Large thermal stress occurs in thick plates such as the peripheral wall of the reactor vessel 101, the upper core mechanism 109, the pump 107, and the intermediate heat exchanger 110, and the effect is particularly large on the peripheral wall of the reactor vessel 101, which reduces the thickness of the material. There is a risk of accelerating fatigue of the meat plate.
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＠置が設けられている。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 shield is provided on the inner circumference of 01.
これは、第７図および第８図に示すように原子炉容器１
０１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］Ｏ１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内に輻
射熱をａ断するための複数の熱遮蔽板１１４を周方向お
よび径方向に配設してなるものである。This corresponds to the reactor vessel 1 as shown in Figures 7 and 8.
By installing a cylindrical wall 112 at a height including the free liquid level 102a of the sodium 102 over the entire inner circumference of the reactor vessel O1, a cylindrical space (gas dam) 113 is created in the inner circumference of the reactor vessel O1. A plurality of heat shielding plates 114 are arranged in the circumferential direction and the radial direction in this space 113 to cut off radiant heat.
上記熱遮蔽板１１４は熱膨張を見込んで周方向に一定の
間隙１１５をあけて配列され、径方向にも熱伝達防止の
ために一定の間隙１１６をあけて配列されている。上記
空間部１１３の下端開口は環状底板１１７によって閉塞
されており、この底板１１７と各熱遮蔽板１１４の下端
との間にも熱遮蔽板１１４の上下方向の熱膨張を見込ん
で間隙１１８をあけている。そしてこれらの熱遮蔽板１
１４は、筒状壁１１２と原子炉容器１０１の周壁との間
に径方向に固定されたボルト１１９によって支持される
とともに、上端は共通のカバー１２０を介して原子炉容
器１０１の内周面に固定されている。The heat shielding plates 114 are arranged with constant gaps 115 in the circumferential direction in anticipation of thermal expansion, and are also arranged with constant gaps 116 in the radial direction to prevent heat transfer. The lower end opening of the space 113 is closed by an annular bottom plate 117, and a gap 118 is also provided between this bottom plate 117 and the lower end of each heat shield plate 114 in anticipation of vertical thermal expansion of the heat shield plate 114. ing. And these heat shield plates 1
14 is supported by bolts 119 fixed in the radial direction between the cylindrical wall 112 and the peripheral wall of the reactor vessel 101, and its upper end is connected to the inner peripheral surface of the reactor vessel 101 via a common cover 120. Fixed.
なお、これらの熱遮蔽板１１４は第７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ＩＩ
！１１５が互に重なり合わないように配慮されている。As shown in FIG. 7, these heat shielding plates 114 are arranged so as to be shifted in the circumferential direction for each layer, with a distance II between the layers in the circumferential direction.
! 115 are taken into consideration 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により輻射によ
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.
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１１５および径方向間隙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７図および第８図に矢印で示すように、空間部１１３
内において、筒状壁１１２近傍の径方向間隙１１６内で
は高温プレナム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＠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と原子炉容器１０１の周壁との温度差
により径方向間隙１１５を通過する半径方向のガス流す
となる。However, in the above heat shielding device, gas flows in the circumferential direction, axial direction, and radial direction within the space 113 through the circumferential gap 115 and the radial gap 116 by natural convection, and heat is transferred in the direction of the circumferential wall of the reactor vessel 101. It cannot be expected to necessarily effectively block movement. That is,
As shown by arrows in FIGS. 7 and 8, the space 113
Inside, the radial gap 116 near the cylindrical wall 112 is affected by the axial temperature difference existing in the high temperature plenum 105, and 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 empty part 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 empty part 113. This results in a radial gas flow.
そして原子炉容器１０１の周壁に達したガス流しは、今
度は原子炉１０１の内周壁面に沿って軸方向下向きの下
降流Ｃとなり、さらに熱遮蔽板１１４の下方を内側へ回
りこんで筒状壁１１２に沿うガス上昇流となる。Then, the gas flow that has reached the peripheral wall of the reactor vessel 101 becomes a downward flow C in the axial direction along the inner peripheral wall surface of the reactor 101, and further goes around inside under the heat shielding plate 114 to form a cylindrical shape. This results in an upward flow of gas along the wall 112.
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が存在し、さらに熱遮蔽板１１４
の下方がおいているために、自然対流による循環ガス流
ａ、ｂ、ｃが生じて筒状壁１１２に接する液体金属ナト
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
ずしも満足すべきものとはいえなかった。In this way, a circumferential gap 115 and a radial gap 116 exist between each heat shield plate 114, and furthermore, the heat shield plate 114
Because the lower part of the reactor vessel 101 is located at the bottom, circulating gas flows a, b, and c occur due to natural convection, and the amount of heat transferred by the gas flow from the liquid metal sodium 102 in contact with the cylindrical wall 112 to the peripheral wall of the reactor vessel 101 is large. The heat insulation effect of the space 113 was not necessarily satisfactory.
さらに、原子炉容器１０１周型および筒状壁１１２の各
表面の軸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ｆｆ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 direction of each surface of the circumferential shape of the reactor vessel 101 and the cylindrical wall 112 becomes non-uniform, there is a risk of thermal stress generation and deformation due to this. It could not be said that it was sufficient to maintain sex.
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維持し
、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. Provides 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's about doing.
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、前記筒状空間のド端間口を閉塞する環状底板と
、前記筒状空間内に周方向および径方向に間隔をあけて
、かつそれぞれの下端と前記環状底板との間にも間隔を
あけて周方向および径方向に配列された複数の熱遮蔽板
と、これらの熱遮蔽板の径方向の各列ごとに対応して設
けられ前記環状底板の上面より立上がって上端部を前記
径方向の各列の熱遮蔽体の外周面または内周面下部に接
触させた複数の円筒状対流防止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 space and the inner peripheral surface of the reactor vessel; an annular bottom plate that closes the end opening of the cylindrical space; a plurality of heat shield plates arranged in the circumferential direction and the radial direction at intervals and also at intervals between each lower end and the annular bottom plate, and each row of these heat shield plates in the radial direction; a plurality of cylindrical convection prevention plates that are provided corresponding to the annular bottom plate and that stand up from the upper surface of the annular bottom plate and whose upper ends are in contact with the outer circumferential surface or the lower inner circumferential surface of each row of heat shields in the radial direction. It is composed of
従って、熱遮蔽異端下方を内方へ向って回り込むガス流
路は遮断されて自然対流を防止することができ、原子炉
容器の周壁を低温に維持することができる。Therefore, the gas flow path that goes inward under the heat shield is blocked, and natural convection can be prevented, and the peripheral wall of the reactor vessel can be maintained 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
＾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。また原子炉容器１の
内部空間は炉心３の外周に設番ノられた仕切壁４により
上下に仕切られて、上方の高温ブレナム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 (Fig. A reactor core 3 loaded with a reactor (not shown) is placed immersed in sodium 2 so as to be located in the center of the reactor vessel 1. Further, the internal space of the reactor vessel 1 is partitioned into an upper and lower part by a partition wall 4 numbered on the outer periphery of the reactor core 3, and divided into an upper high-temperature blemish 5 and a lower low-temperature blemish 6. By driving the pump 7 supported by the reactor 4, the sodium 2 flows from below to above the reactor core 3 and circulates 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により閉
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ｍ構９が垂設されてい
る。また、ルーフスラブ８の上部には二次冷却材供給１
１桐（図示せず）が取付けられており、前記仕切壁４に
はこの二次冷却月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
２ａ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
容器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 m structure 9 is vertically installed in the center of the roof slab 8, located directly above the reactor core 3. In addition, a secondary coolant supply 1 is provided at the top of the roof slab 8.
1 paulownia (not shown) is attached to the partition wall 4, and an intermediate heat exchanger 10 is attached to the partition wall 4, which receives a supply of secondary coolant (liquid metal sodium) from this secondary cooling moon supply mechanism. . Furthermore, below the core 3, there is a high-pressure blemish 11
is provided. Note that an inert gas G such as argon or helium is filled as a cover gas between the liquid surface 2a of the liquid metal sodium 2 and the roof slab 8. This inert gas G is sodium 2 during reactor operation.
This is to absorb changes in the internal pressure of the reactor vessel 1 when its volume expands due to temperature changes, and to prevent adverse effects on the reactor components.
原子炉容器１の内周面部には熱辿蔽装訪が設けられてい
る。これを第２図および第３図により説明すると、まず
図中１２は原子炉容器１の内周面全周にわたって、ナト
リウム２の自由液面２ａを含む高さ位置に取付けられた
筒状壁１２である。A heat tracing device is provided on the inner peripheral surface of the reactor vessel 1 . To explain this with reference to FIGS. 2 and 3, first, reference numeral 12 in the figure denotes a cylindrical wall 12 installed at a height position including the free liquid level 2a of sodium 2 over the entire inner peripheral surface of the reactor vessel 1. It is.
これは原子炉容器１の内周部に円筒状の空間部（ガスダ
ム）１３を形成して原子炉容器１の周壁を高温のナトリ
ウム２より隔離するためのもので、空間部１３内には輻
射熱を遮断するための複数の熱遮蔽板１４が、周方向お
よび径方向に配列されている。This is to form a cylindrical space (gas dam) 13 on the inner circumference of the reactor vessel 1 to isolate the peripheral wall of the reactor vessel 1 from the high-temperature sodium 2. A plurality of heat shielding plates 14 are arranged in the circumferential direction and the radial direction.
上記熱遮蔽板１４は熱膨張を見込んで周方向に一定のｌ
ｌ１ｌｌ！１５をあけて配列され、径方向にも熱伝達防
止のために一定の間隙１６をあけて配列されている。上
記空間部１３の下端開口は環状底板１７によって閉塞さ
れており、この底板１７と各熱遮蔽板１４の下端との間
にも熱遮蔽板１４の上下方向の熱膨張を見込んで間隙１
８をあけている。The heat shield plate 14 has a constant l in the circumferential direction in anticipation of thermal expansion.
l1ll! They are arranged with a certain gap 15 in between, and also in the radial direction with a certain gap 16 in order to prevent heat transfer. The lower end opening of the space 13 is closed by an annular bottom plate 17, and there is also a gap 1 between this bottom plate 17 and the lower end of each heat shield plate 14 in anticipation of vertical thermal expansion of the heat shield plate 14.
8 is open.
そしてこれらの熱遮蔽板１４は、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
って支持されるとともに、上端は共通のカバー２０を介
して原子炉容器１の内周面に固定されている。These heat shielding plates 14 are supported by bolts 19 fixed in the radial direction between the cylindrical wall 12 and the peripheral wall of the reactor vessel 1, and their upper ends are connected to the reactor vessel through a common cover 20. It is fixed to the inner peripheral surface of 1.
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、各層の周方向間隙１５
が互に重なり合わないように配慮されている。As shown in FIG. 2, these heat shielding plates 14 are arranged so as to be offset in the circumferential direction for each layer, and the circumferential gap 15 between each layer is
Care has been taken to ensure that they do not overlap each other.
前記各熱遮蔽板１４の表面は高度の反射率が得られるよ
うに鏡面加工が施され、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 mirror-finished so as to obtain a high degree of reflectance, and is designed to block radiant heat within the space 13.
また図中２１は前記熱遮蔽板１２の径方向の各列ごとに
対応して設けられた円筒状対流防止板である。これらは
環状底板１７の上面に設置された環状板２２より立上が
って各上端部２１ａを熱遮蔽板１２の外周面に接触させ
ている。Further, in the figure, reference numeral 21 denotes a cylindrical convection prevention plate provided corresponding to each row of the heat shield plate 12 in the radial direction. These are raised from an annular plate 22 installed on the upper surface of the annular bottom plate 17, and each upper end portion 21a is brought into contact with the outer circumferential surface of the heat shield plate 12.
以上のような構成では、空間部１３内において熱遮蔽板
１４の下方を回り込もうとするガス流が対流防止板２１
によって遮断され、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
器１周壁へ至る熱流束を効率よく遮断することができ、
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。また、複数の
対流防止板２１は共通の環状板２２に取付けて一体化さ
れているので、空間部１３内への組込みがきわめて容易
に行なえる。In the above configuration, the gas flow that tries to go around below the heat shielding plate 14 in the space 13 passes through the convection prevention plate 21.
Moreover, since the surface of each heat shield plate 14 is mirror-finished to obtain a high degree of reflectance, natural convection of the gas and radiant heat cause the high-temperature sodium 2 to be removed from the cylindrical wall 12 and the space. The heat flux reaching the atom and the peripheral wall of the reactor vessel 1 through the part 13 can be efficiently blocked,
The temperature of the peripheral wall of the reactor vessel 1 can be maintained at a low temperature to prevent excessive thermal stress and thermal deformation from occurring. Further, since the plurality of convection prevention plates 21 are attached to a common annular plate 22 and integrated, they can be incorporated into the space 13 very easily.
次に、第４図は本発明の第２の実施例を示すもので、図
中２３は円筒状対流防止板である。これらの対流防止板
２３は上端部２３ａを縦断面波形として、共通の環状板
２２より立ち上げである。Next, FIG. 4 shows a second embodiment of the present invention, in which reference numeral 23 is a cylindrical convection prevention plate. These convection prevention plates 23 have an upper end 23a having a corrugated longitudinal section and are upright from the common annular plate 22.
また第５図は本発明の第３の実施例を示すもので、図中
２４は円筒状対流防止板である。これらの対流防止板２
４は上端部２４ａを対応する熱遮蔽板１４に向けて屈曲
させており、共通の環状板２２より立ち上げである。Further, FIG. 5 shows a third embodiment of the present invention, in which numeral 24 is a cylindrical convection prevention plate. These convection prevention plates 2
4 has an upper end portion 24a bent toward the corresponding heat shield plate 14, and is raised from the common annular plate 22.
以上の第２．第３の実施例によっても第１の実施例と同
様の効果を得ることができる。The second above. The third embodiment can also provide the same effects as the first embodiment.
〔発明の効果）
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。[Effects of the Invention] As detailed above, according to the heat shielding device for a fast breeder reactor according to the present invention, the heat flux from the coolant to the reactor vessel peripheral wall can be significantly reduced, and the It also effectively prevents natural convection of the cover gas within the annular space formed on the inner periphery of the reactor vessel, greatly reducing thermal stress and thermal deformation on the peripheral wall of the reactor vessel, and improving the stability of the reactor vessel. It is possible to maintain soundness and improve its reliability.
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図は高速増殖炉の縦断面図、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ｉｔの一部を
拡大して示す縦断面図、第５図は第３の実施例における
熱遮蔽装置の一部を拡大して示す縦断面図、第６図ない
し第８図は従来例を示すもので、第６図は高速増殖炉の
縦断面図、第７図は熱遮蔽装置の一部を示す横断面図、
第８図は第６図の■−■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・
・・円筒状の空間部、１４・・・熱遮蔽板、１７・・・
環状底板、２１．２２．２４・・・円筒状対流防止板、
２２・・・環状板、２１ａ 、２３ａ ２４ａ・・・上
端部。
出願人代理人 弁理士 鈴江武彦
第１図
第４図
１ム
第５ 図
ｔ1 to 3 show a first embodiment of the present invention, in which FIG. 1 is a longitudinal cross-sectional view of a fast breeder reactor, FIG. 2 is a cross-sectional view showing a part of a heat shielding device, and FIG. 3 is a sectional view taken along the line ■-■ in FIG. 2, FIG. 4 is an enlarged vertical sectional view of a part of the heat shield IT in the second embodiment, and FIG. 5 is a cross-sectional view of the heat shield in the third embodiment. A vertical cross-sectional view showing an enlarged part of the device, Figures 6 to 8 show conventional examples, Figure 6 is a vertical cross-sectional view of a fast breeder reactor, and Figure 7 is a part of a heat shielding device. A cross-sectional view showing
FIG. 8 is a sectional view taken along the line ■-■ in FIG. 6. 1...Reactor vessel, 2...Liquid metal sodium (-
secondary coolant), 3... core, 12... cylindrical wall, 13...
...Cylindrical space, 14...Heat shielding plate, 17...
Annular bottom plate, 21.22.24... Cylindrical convection prevention plate,
22... Annular plate, 21a, 23a 24a... Upper end portion. Applicant's representative Patent attorney Takehiko Suzue Figure 1 Figure 4 Figure 1 Figure 5 T
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、前記筒状空間の下端開口を閉塞す
る環状底板と、前記筒状空間内に周方向および径方向に
間隔をあけて、かつそれぞれの下端と前記環状底板との
間にも間隔をあけて周方向および径方向に配列された複
数の熱遮蔽板と、これらの熱遮蔽板の径方向の各列ごと
に対応して設けられ前記環状底板の上面より立上がつて
上端部を前記径方向の各列の熱遮蔽体の外周面または内
周面下部に接触させた複数の円筒状対流防止板とを具備
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 cylindrical space; an annular bottom plate that closes a lower end opening of the cylindrical space; A plurality of heat shield plates are arranged in the circumferential direction and the radial direction with intervals between A heat shield for a fast breeder reactor, comprising a plurality of cylindrical convection prevention plates that rise and have upper ends in contact with the outer peripheral surface or the lower inner peripheral surface of each row of heat shields in the radial direction. Device.
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) The heat shielding device for a fast breeder reactor according to claim 1, wherein the surface of the heat shielding plate is mirror-finished.
設置された共通の環状板に下端が固着されていることを
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。(3) The heat of the fast breeder reactor according to claim 1, wherein the plurality of cylindrical convection prevention plates have lower ends fixed to a common annular plate installed on the annular bottom plate. Shielding device.
とした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。(4) The heat shielding device for a fast breeder reactor according to claim 1, wherein each of the cylindrical convection prevention plates has an upper end section cut to form a corrugated cross section.
に向けて屈曲させ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。(5) The heat shielding device for a fast breeder reactor according to claim 1, wherein each of the cylindrical convection prevention plates has an upper end bent toward the heat shielding plate.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP61030132A JPS62188993A (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 |
|---|---|---|---|
| JP61030132A JPS62188993A (en) | 1986-02-14 | 1986-02-14 | Thermal shielding device for fast breeder reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPS62188993A true JPS62188993A (en) | 1987-08-18 |
Family
ID=12295249
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP61030132A Pending JPS62188993A (en) | 1986-02-14 | 1986-02-14 | Thermal shielding device for fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS62188993A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8973731B2 (en) | 2010-12-17 | 2015-03-10 | Otis Elevator Company | Regenerative power control for passenger conveyors |
-
1986
- 1986-02-14 JP JP61030132A patent/JPS62188993A/en active Pending
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8973731B2 (en) | 2010-12-17 | 2015-03-10 | Otis Elevator Company | Regenerative power control for passenger conveyors |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US3962032A (en) | Fast nuclear reactor | |
| CN109147969B (en) | Nuclear reactor molten material core retention passive cooling system | |
| JP6395802B2 (en) | Reactor system and method | |
| US4055465A (en) | Device for thermal insulation of a vessel wall | |
| JPH0727050B2 (en) | Liquid metal cooled nuclear reactor with passive cooling system | |
| FI74830C (en) | Nuclear reactor, whose core is shielded with a construction of rods and transverse plates. | |
| JPH0326795B2 (en) | ||
| JPS62188993A (en) | Thermal shielding device for fast breeder reactor | |
| US4198271A (en) | Liquid metal cooled nuclear reactor constructions | |
| JP2008122248A (en) | Fast reactor | |
| JPS5952795B2 (en) | Reactor | |
| GB1314499A (en) | Nuclear reactior installation | |
| JPS62188995A (en) | Thermal shielding device for fast breeder reactor | |
| US4655996A (en) | East neutron reactor having a storage structure independent of the core structure | |
| JP2986348B2 (en) | Upper head reactor vessel | |
| JPS61180190A (en) | Heat shielding device for fast breeder reactor | |
| US20100172459A1 (en) | Fast reactor | |
| JPH0827368B2 (en) | Fast breeder reactor | |
| JP2837874B2 (en) | Liquid metal cooled fast neutron reactor | |
| JPS6157889A (en) | Upper shielding body of fast breeder reactor | |
| JPH0462037B2 (en) | ||
| JP2725804B2 (en) | Reactor vessel | |
| JPH02266296A (en) | Thermal shield device for nuclear reactor vessel | |
| JPS5939994A (en) | Circulating pump for fast breeder of tank type | |
| JPH0143671Y2 (en) |