JPH0155436B2 - - Google Patents
Info
- Publication number
- JPH0155436B2 JPH0155436B2 JP58174997A JP17499783A JPH0155436B2 JP H0155436 B2 JPH0155436 B2 JP H0155436B2 JP 58174997 A JP58174997 A JP 58174997A JP 17499783 A JP17499783 A JP 17499783A JP H0155436 B2 JPH0155436 B2 JP H0155436B2
- Authority
- JP
- Japan
- Prior art keywords
- shield
- heat exchanger
- reactor
- fast breeder
- core
- 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.)
- Expired
Links
- 239000002826 coolant Substances 0.000 claims description 15
- 229910001220 stainless steel Inorganic materials 0.000 claims description 13
- 239000010935 stainless steel Substances 0.000 claims description 13
- 229910000712 Boron steel Inorganic materials 0.000 claims description 4
- 238000001816 cooling Methods 0.000 claims description 2
- 239000000446 fuel Substances 0.000 claims 1
- 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 7
- 229910052708 sodium Inorganic materials 0.000 description 7
- 239000011734 sodium Substances 0.000 description 7
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 6
- 229910002804 graphite Inorganic materials 0.000 description 6
- 239000010439 graphite Substances 0.000 description 6
- 239000000463 material Substances 0.000 description 6
- 230000004913 activation Effects 0.000 description 5
- 230000000694 effects Effects 0.000 description 2
- 230000004992 fission Effects 0.000 description 2
- 238000007796 conventional method Methods 0.000 description 1
- 238000012217 deletion Methods 0.000 description 1
- 230000037430 deletion Effects 0.000 description 1
- 230000005251 gamma ray Effects 0.000 description 1
- 229910001338 liquidmetal Inorganic materials 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 230000005855 radiation Effects 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)
Description
【発明の詳細な説明】
［発明の技術分野］
本発明は高速増殖炉に係わり、特に原子炉容器
内に１次冷却材と２次冷却材との熱交換を行なう
熱交換器を備えた高速増殖炉に関する。[Detailed Description of the Invention] [Technical Field of the Invention] The present invention relates to a fast breeder reactor, and particularly to a fast breeder reactor equipped with a heat exchanger for exchanging heat between a primary coolant and a secondary coolant in a reactor vessel. Regarding breeder reactors.
［発明の技術的背景］
第１図は高速増殖炉の一実施例を示すもので、
図において符号１は中心に炉心２を有し１次冷却
材を収容する原子炉容器を示している。[Technical background of the invention] Figure 1 shows an example of a fast breeder reactor.
In the figure, reference numeral 1 indicates a reactor vessel having a reactor core 2 in the center and accommodating a primary coolant.
この原子炉容器１の上端開口部は図示しない遮
蔽プラグにより遮蔽されており、遮蔽プラグから
は１次冷却材と２次冷却材との熱交換を行なう複
数の熱交換器３が垂設されている。図示しない炉
心支持板により支持される炉心２を囲繞して着脱
自在とされる可動遮蔽体４が配設されており、こ
の可動遮蔽体４を囲繞して固定遮蔽体５が配設さ
れている。これらの遮蔽体４，５はステンレス鋼
材を多重に配設して構成されている。そして、さ
らに熱交換器３を囲繞して熱交換器遮蔽体６が配
設されている。 The upper end opening of the reactor vessel 1 is shielded by a shielding plug (not shown), and a plurality of heat exchangers 3 for exchanging heat between the primary coolant and the secondary coolant are vertically installed from the shielding plug. There is. A removable movable shield 4 is disposed surrounding the core 2 supported by a core support plate (not shown), and a fixed shield 5 is disposed surrounding the movable shield 4. . These shields 4 and 5 are constructed by arranging stainless steel materials in multiple layers. Further, a heat exchanger shield 6 is disposed to surround the heat exchanger 3.
以上のように構成された高速増殖炉では、炉心
２で発生した熱は例えば液体金属ナトリウムから
なる１次冷却材を介して熱交換器３内に移送さ
れ、この熱交換器３においてこのエネルギは２次
冷却材に伝達される。そして炉心２内の核分裂に
より発生した中性子は可動遮蔽体４、固定遮蔽体
５および熱交換器遮蔽体６により遮蔽される。そ
して、炉心２から熱交換器遮蔽体６に至る過程で
生み出され、ナトリウムの放射化に対する寄与の
大きい熱中性子は最終的に熱交換器遮蔽体６によ
り効果的に遮蔽される。 In the fast breeder reactor configured as described above, the heat generated in the core 2 is transferred into the heat exchanger 3 via a primary coolant made of, for example, liquid metal sodium, and in this heat exchanger 3, this energy is transferred. transferred to the secondary coolant. Neutrons generated by nuclear fission within the reactor core 2 are shielded by a movable shield 4, a fixed shield 5, and a heat exchanger shield 6. Thermal neutrons, which are generated in the process from the core 2 to the heat exchanger shield 6 and which greatly contribute to the activation of sodium, are finally effectively shielded by the heat exchanger shield 6.
すなわち、このような高速増殖炉では、２次冷
却材の循環する２次冷却系配管表面におけるγ線
線量率を許容線量率以下にすることが設計基準と
されており、可動遮蔽体４、固定遮蔽体５および
熱交換器遮蔽体６により熱交換器３内の２次冷却
材、例えばナトリウムの放射化率を許容レベル以
下にすることが行われている。 In other words, in such a fast breeder reactor, the design standard is to keep the gamma ray dose rate on the surface of the secondary cooling system piping where the secondary coolant circulates below the permissible dose rate. The shield 5 and the heat exchanger shield 6 are used to reduce the activation rate of the secondary coolant, such as sodium, in the heat exchanger 3 to below an acceptable level.
［背景技術の問題点］
しかしながら、このように炉心２を可動遮蔽体
４および固定遮蔽体５で遮蔽し、さらに熱交換器
３を一定の板厚を有する熱交換器遮蔽体６により
遮蔽する場合には、例えば熱出力2500MWクラス
のプール型高速増殖炉では、熱交換器３を６基配
設した場合、400〜700tの多大な量のステンレス
鋼が必要となり、経済的に望ましくなく、また原
子炉が大型化するという問題がある。[Problems with the Background Art] However, when the core 2 is shielded with the movable shield 4 and the fixed shield 5 in this way, and the heat exchanger 3 is further shielded with the heat exchanger shield 6 having a constant plate thickness, For example, in a pool-type fast breeder reactor with a thermal output of 2500 MW class, if six heat exchangers 3 are installed, a large amount of stainless steel of 400 to 700 tons is required, which is economically undesirable and There is a problem that the furnace becomes larger.
［発明の目的］
本発明はかかる従来の事情に対処してなされた
もので、遮蔽体の総重量を減少し経済的に安価
な、また原子炉の小型化を図ることのできる高速
増殖炉を提供しようとするものである。[Object of the Invention] The present invention has been made in response to such conventional circumstances, and provides a fast breeder reactor that is economically inexpensive by reducing the total weight of the shield, and that allows the reactor to be made smaller. This is what we are trying to provide.
［発明の概要］
すなわち本発明は、中心に炉心を有し１次冷却
材を収容する原子炉容器と、この原子炉容器内に
かつこの原子炉容器と前記炉心との間に配設され
前記１次冷却材と２次冷却材との熱交換を行なう
熱交換器とを備えた高速増殖炉において、前記熱
交換器は前記炉心側で厚くとられた熱交換器遮蔽
体により遮蔽されていることを特徴とする高速増
殖炉である。[Summary of the Invention] That is, the present invention provides a reactor vessel having a reactor core at the center and containing a primary coolant, and a nuclear reactor vessel disposed within the reactor vessel and between the reactor vessel and the reactor core, In a fast breeder reactor equipped with a heat exchanger for exchanging heat between a primary coolant and a secondary coolant, the heat exchanger is shielded by a thick heat exchanger shield on the reactor core side. This fast breeder reactor is characterized by:
［発明の実施例］
以下本発明の詳細を図面に示す一実施例につい
て説明する。[Embodiment of the Invention] The details of the present invention will be described below with reference to an embodiment shown in the drawings.
第２図は本発明の一実施例の高速増殖炉を示す
もので、図において符号３は熱交換器を示してい
る。この熱交換器３の炉心２側には中間熱交換器
遮蔽体７が配設されており、この熱交換器遮蔽体
７は異なる厚さを有する３層の遮蔽体７ａ，７
ｂ，７ｃから構成されている。最内層に位置する
遮蔽体７ａは熱交換器３の炉心側半面を遮蔽して
おり、また中間部に配設される遮蔽体７ｂは約
120゜の面を遮蔽し、さらに最外周に配設される遮
蔽体７ｃは約60゜の範囲を遮蔽している。 FIG. 2 shows a fast breeder reactor according to an embodiment of the present invention, and in the figure, reference numeral 3 indicates a heat exchanger. An intermediate heat exchanger shield 7 is disposed on the core 2 side of the heat exchanger 3, and this heat exchanger shield 7 includes three layers of shields 7a and 7 having different thicknesses.
It is composed of b and 7c. The shielding body 7a located in the innermost layer shields the half surface of the heat exchanger 3 on the core side, and the shielding body 7b disposed in the middle part covers approximately
The shield 7c, which is disposed at the outermost periphery, shields an area of about 60 degrees.
さらにこの実施例では、第１図で示した炉心２
を囲繞して配設される固定遮蔽体５が除去されて
いる。なお以上述べた部分を除いて第１図の高速
増殖炉と同様に構成されているので、第１図と同
一部分には同一符号を付し説明を省略する。 Furthermore, in this embodiment, the reactor core 2 shown in FIG.
The fixed shielding body 5 disposed to surround the is removed. Since the fast breeder reactor has the same structure as the fast breeder reactor shown in FIG. 1 except for the parts described above, the same parts as those in FIG.
以上のように構成された高速増殖炉では、炉心
内の核分裂により発生する中性子のうち、高速中
性子は可動遮蔽体４により遮蔽され、中速中性子
は１次冷却材であるナトリウム中で減速され、さ
らに２次ナトリウムの放射化に対する寄与の大き
い熱中性子は３層からなる熱交換器遮蔽体７によ
り完全に遮蔽される。 In the fast breeder reactor configured as described above, among the neutrons generated by nuclear fission in the reactor core, fast neutrons are shielded by the movable shield 4, medium-speed neutrons are decelerated in sodium, which is the primary coolant, Furthermore, thermal neutrons, which greatly contribute to the activation of secondary sodium, are completely shielded by the three-layer heat exchanger shield 7.
すなわち、熱交換器３内へ飛び込む中性子は、
炉心２中心と熱交換器３中心とを結ぶ直線ｌ上か
ら最も多く熱交換器３へ飛び込むため、この部分
の熱交換器遮蔽体７の厚みを最も大きくすること
により最も効率的な熱交換器遮蔽体７を得ること
ができる。 In other words, the neutrons that jump into the heat exchanger 3 are
Since most jumps into the heat exchanger 3 occur from the straight line l connecting the center of the core 2 and the center of the heat exchanger 3, the most efficient heat exchanger is created by making the thickness of the heat exchanger shield 7 in this part the largest. A shield 7 can be obtained.
この実施例によれば、前述した例えば熱出力
2500MWクラスのプール型高速増殖炉で、かつ熱
交換器３を６基配設した場合、遮蔽体であるステ
ンレス鋼の量を、例えば従来の400t〜700tから
210tまで低減することができる。さらに材料の放
射線損傷で特に問題となる高速中性子は、可動遮
蔽体４により十分遮蔽されているので固定遮蔽体
５を除去することができ、原子炉の小型化を図る
ことができる。 According to this embodiment, for example, the heat output
In the case of a 2500 MW class pool type fast breeder reactor with 6 heat exchangers 3 installed, the amount of stainless steel used as a shield can be reduced from, for example, the conventional 400 to 700 tons.
It can be reduced to 210t. Furthermore, since fast neutrons, which are particularly problematic for radiation damage to materials, are sufficiently shielded by the movable shield 4, the fixed shield 5 can be removed, and the reactor can be made smaller.
第３図は固定遮蔽体４の厚さとナトリウムの放
射化率を許容レベル以下にするという、遮蔽設計
基準を満たす為の遮蔽体総重量との関係を示すも
ので、図において曲線ａは、第１図に示した均等
厚ステンレス鋼製の熱交換器遮蔽体６と固定遮蔽
体４とを組合せた場合を、曲線ｂは第２図に示し
たステンレス鋼製３層の熱交換器遮蔽体７と固定
遮蔽体４とを組合せた場合を示している。 Figure 3 shows the relationship between the thickness of the fixed shield 4 and the total weight of the shield to satisfy the shield design standard of keeping the activation rate of sodium below the permissible level. Curve b represents the combination of the uniform thickness stainless steel heat exchanger shield 6 shown in Figure 1 and the fixed shield 4, and the curve b represents the combination of the stainless steel three-layer heat exchanger shield 7 shown in Figure 2. This shows a case in which the fixed shielding body 4 and the fixed shielding body 4 are combined.
この図から明らかなように以上述べた実施例の
高速増殖炉によれば、従来に比べ遮蔽体の総重量
を大幅に低減することができる。また、図中曲線
ｃ，ｄは熱交換器遮蔽体としてステンレス鋼の代
わりにステンレス鋼より中性子に対する遮蔽特性
の良いボロン鋼およびB4C遮蔽体を用いた場合に
ついて示す。これによれば、さらに大幅な遮蔽体
の総重量の低減が可能となる。 As is clear from this figure, according to the fast breeder reactor of the embodiment described above, the total weight of the shield can be significantly reduced compared to the conventional one. Curves c and d in the figure show the case where boron steel and B 4 C shielding material, which have better shielding properties against neutrons than stainless steel, are used instead of stainless steel as the heat exchanger shielding material. According to this, it becomes possible to further significantly reduce the total weight of the shield.
なお、固定遮蔽体４として黒鉛からなる遮蔽体
を用いる場合には、中高速中性子に対する黒鉛の
優れた減速効果と、黒鉛の密度が低いことから遮
蔽体総重量をステンレス鋼製の固定遮蔽体４を用
いる場合に比較してさらに減少することができ
る。そして、熱交換器遮蔽体としてボロン鋼や
B4Cを用いることにより、さらに遮蔽体総重量を
減少することができる。 Note that when using a shield made of graphite as the fixed shield 4, the total weight of the shield can be reduced by using the fixed shield 4 made of stainless steel due to graphite's excellent moderating effect on medium-fast neutrons and the low density of graphite. This can be further reduced compared to when using . Then, boron steel is used as a heat exchanger shield.
By using B 4 C, the total weight of the shield can be further reduced.
第４図は固定遮蔽体４として黒鉛からなる遮蔽
体を使用した場合の固定遮蔽体の厚さとナトリウ
ムの放射化率を許容レベル以下にするという、遮
蔽設計基準を満たす為の遮蔽体総重量との関係を
示すもので、図において曲線ｅは、第１図に示し
た均等厚ステンレス鋼製の熱交換器遮蔽体６と黒
鉛からなる固定遮蔽体とを組合せた場合を、曲線
ｆは第２図に示したステンレス鋼製３層の熱交換
器遮蔽体７と黒鉛からなる固定遮蔽体とを組合せ
た場合を示している。 Figure 4 shows the thickness of the fixed shield and the total weight of the shield to satisfy the shield design standard, which is to keep the activation rate of sodium below the permissible level when a shield made of graphite is used as the fixed shield 4. In the figure, curve e represents the case where the heat exchanger shield 6 made of uniform thickness stainless steel shown in FIG. This shows a case in which the three-layer heat exchanger shield 7 made of stainless steel shown in the figure is combined with a fixed shield made of graphite.
この図から明らかなように黒鉛からなる固定遮
蔽体を使用した高速増殖炉によれば、従来に比べ
遮蔽体の総重量を大幅に低減することができる。
また、図中曲線ｇ，ｈは熱交換器遮蔽体としてス
テンレス鋼の代わりにステンレス鋼より中性子に
対する遮蔽特性の良いボロン鋼およびB4C遮蔽体
を用いた場合について示す。これによれば、さら
に大幅な遮蔽体の総重量の低減が可能となる。 As is clear from this figure, according to a fast breeder reactor using a fixed shield made of graphite, the total weight of the shield can be significantly reduced compared to the conventional method.
Curves g and h in the figure show the case where boron steel and B 4 C shielding material, which have better shielding properties against neutrons than stainless steel, are used instead of stainless steel as the heat exchanger shielding material. According to this, it becomes possible to further significantly reduce the total weight of the shield.
［発明の効果］
以上述べたように本発明の高速増殖炉によれ
ば、中性子遮蔽体の総重量を従来に比較し大幅に
低減することができ、また、固定遮蔽体厚の減小
あるいはその削除を通じて原子炉の小型化を図る
ことができ、経済的に有利な原子炉を提供するこ
とができる。[Effects of the Invention] As described above, according to the fast breeder reactor of the present invention, the total weight of the neutron shield can be significantly reduced compared to the conventional one, and the thickness of the fixed shield can be reduced or Through deletion, it is possible to downsize the nuclear reactor and provide an economically advantageous nuclear reactor.
第１図は従来の高速増殖炉の一実施例の４半分
を示す横断面図、第２図は本発明の一実施例の高
速増殖炉の４半分を示す横断面図、第３図および
第４図は固定遮蔽体の厚さと遮蔽体総重量との関
係を示すグラフである。
１……原子炉容器、３……熱交換器、４……可
動遮蔽体、５……固定遮蔽体、７……熱交換器遮
蔽体。
FIG. 1 is a cross-sectional view showing a quarter half of an embodiment of a conventional fast breeder reactor, FIG. 2 is a cross-sectional view showing a quarter half of a fast breeder reactor according to an embodiment of the present invention, FIG. FIG. 4 is a graph showing the relationship between the thickness of the fixed shield and the total weight of the shield. 1... Reactor vessel, 3... Heat exchanger, 4... Movable shield, 5... Fixed shield, 7... Heat exchanger shield.
Claims (1)
炉容器と、この原子炉容器内にかつこの原子炉容
器と前記炉心との間に配設され前記１次冷却材と
２次冷却材との熱交換を行なう熱交換器とを備え
た高速増殖炉において、前記熱交換器は前記炉心
側で厚くとられた熱交換器遮蔽体により遮蔽され
ていることを特徴とする高速増殖炉。 ２ 熱交換器遮蔽体はステンレス鋼からなる特許
請求の範囲第１項記載の高速増殖炉。 ３ 熱交換器遮蔽体は、ボロン鋼からなる特許請
求の範囲第１項記載の高速増殖炉。 ４ 熱交換器遮蔽体は、B4C遮蔽体からなる特許
請求の範囲第１項記載の高速増殖炉。[Scope of Claims] 1. A reactor vessel having a core at the center and containing a primary coolant, and a reactor vessel disposed within the reactor vessel and between the reactor vessel and the reactor core, and the primary cooling A fast breeder reactor equipped with a heat exchanger for exchanging heat between a fuel and a secondary coolant, characterized in that the heat exchanger is shielded by a thick heat exchanger shield on the core side. fast breeder reactor. 2. The fast breeder reactor according to claim 1, wherein the heat exchanger shield is made of stainless steel. 3. The fast breeder reactor according to claim 1, wherein the heat exchanger shield is made of boron steel. 4. The fast breeder reactor according to claim 1, wherein the heat exchanger shield is a B 4 C shield.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58174997A JPS6066183A (en) | 1983-09-21 | 1983-09-21 | Fast breeder reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58174997A JPS6066183A (en) | 1983-09-21 | 1983-09-21 | Fast breeder reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6066183A JPS6066183A (en) | 1985-04-16 |
| JPH0155436B2 true JPH0155436B2 (en) | 1989-11-24 |
Family
ID=15988410
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58174997A Granted JPS6066183A (en) | 1983-09-21 | 1983-09-21 | Fast breeder reactor |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6066183A (en) |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110706830B (en) * | 2019-10-18 | 2022-04-08 | 中国科学院合肥物质科学研究院 | A shield with integrated shielding heat exchange function |
-
1983
- 1983-09-21 JP JP58174997A patent/JPS6066183A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6066183A (en) | 1985-04-16 |
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