JPS6066183A - Fast breeder reactor - Google Patents
Fast breeder reactorInfo
- Publication number
- JPS6066183A JPS6066183A JP58174997A JP17499783A JPS6066183A JP S6066183 A JPS6066183 A JP S6066183A JP 58174997 A JP58174997 A JP 58174997A JP 17499783 A JP17499783 A JP 17499783A JP S6066183 A JPS6066183 A JP S6066183A
- 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.)
- Granted
Links
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)
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]
本発明は高速ハ′7り1炉に係わり、′1;jに原子炉
容器内に1重重1.0拐と2重重ム(1月どの熱交換を
行なう熱交換器を備えた高速増h゛1炉に関する、。Detailed Description of the Invention [Technical Field of the Invention] The present invention relates to a high-speed reactor. This invention relates to a high speed increaser 1 furnace equipped with a heat exchanger for heat exchange.
1発明の技術的背景」
第1図は高速増殖炉の一実施例を示づ゛もの一ζ、図に
おい(゛?〕号1は中心に炉心2をイjL1重重7JI
材を収容す゛る原子炉容器を示しCいる。1 Technical Background of the Invention Figure 1 shows an embodiment of a fast breeder reactor.
Figure C shows the reactor vessel containing the materials.
この原子炉容器1の上端器[1部は図示しない11ム蔽
プラグにより遮蔽されU J5す、遮蔽プラグから番は
1次冷却材と2次冷却材どの熱交換をtjなうN数の熱
交換器3が垂設されC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−<名IB2自在とされる
可動遮蔽体4が配設され−(d5つ、この可動遮蔽体4
を囲繞しC固定遮蔽体5jが配設されている。これらの
遮蔽体4.51Jステンレス3N月を多重に配設しC構
成されCいる。ぞしC1さらに熱交換器3を囲繞して熱
交換器3内(4V6か配設され石いる。The upper end of the reactor vessel 1 [1 part is shielded by an 11 shielding plug (not shown), and from the shielding plug the number of heat exchangers between the primary coolant and the secondary coolant is tj. An exchanger 3 is installed vertically. A reactor core 2 supported by a core support plate (not shown) is surrounded by movable shields 4 which are freely movable.
A C fixed shield 5j is disposed surrounding the C fixed shield 5j. These shields are constructed by arranging 4.51J stainless steel 3N shields in multiple layers. Next C1 further surrounds the heat exchanger 3, and inside the heat exchanger 3 (4V6 or the like is arranged).
以上のように構成された高速増タメ1炉(・は、炉心2
で発生した熱は例えば液体全屈すトリウムかうなる1次
冷却材を介し−(熱交換器3内に移送され、この熱交1
fA器3においてこのエネルギは2次冷油材に伝達され
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X蔽される。そしC1炉心2から熱交換器遮蔽体6に
至る過程で生み出され、ナトリウム中放射化に対する寄
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。The high-speed increaser 1 reactor (・ is the core 2
The heat generated in the
In the fA unit 3, this energy is transmitted to the secondary cold oil material. Neutrons generated by nuclear fission within the reactor core 2 are X-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 C1 core 2 to the heat exchanger shield 6 and contribute greatly to activation in sodium, are effectively shielded by the heat exchanger shield 6 in the end.
すなわら、このような高速増夕め炉では、2重重ノil
l祠の循環する2次冷却系配管表面にJjけるγ線線t
ii $をt′1容線口1率以下に“す〜ることが設η
1基11(とされてJ5す、可動遮蔽体4、固定遮蔽体
5 iJjよび熱交換器遮蔽体6にJζり熱交換器3内
の2重重却拐、例えばブトリウムの放射化率を許容レベ
ル以−トにすることが行われ”Cいる。In other words, in such a high-speed dusk reactor, double-layered fuel
γ-rays on the surface of the circulating secondary cooling system piping of the shrine
ii.
1 unit 11 (J5, movable shield 4, fixed shield 5 iJj and Jζ to the heat exchanger shield 6) double depletion in the heat exchanger 3, e.g. What is being done is "C".
[背景技術の問題点1
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
を右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250OMW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/、< n’tのステンレス鋼が必要どなり、経
済的に望ましくなく、また原子炉が大型化りるという問
題がある。[Problem in the Background Art 1 However, in this way, the core 2 is shielded by the movable shield 4 and the fixed shield 5, and the heat exchanger 3 is further shielded by the heat exchanger shield 6 having a constant plate thickness. For example, in a pool-type fast breeder reactor with a thermal output of 250 OMW class, when six heat exchangers 3 are installed, the total capacity is 400 to 700 tons.
This requires a large amount of stainless steel with <n't, which is economically undesirable, and there is a problem that the reactor becomes larger.
[発明の目的]
本発明はかかる従来の事情に対処しでなされたもので゛
、遮蔽体の総重但を減少し経済的に安1llll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
しようとするものぐある。[Object of the Invention] The present invention has been made in order to cope with the above-mentioned conventional circumstances. There are also efforts to provide breeder reactors.
[発明の11λ要〕
ずなわら本発明は、中心に炉心をイjL1重重力j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重重却祠と
2重重ljl拐どの熱交換を行なう熱交換器とを、備え
た高速増殖炉にL12いで、前記熱交換器は前記炉心側
C厚くとられた熱交換器遮蔽体により遮蔽されでいるこ
とを持i1′iどりる。!′31速」19殖炉0ある。[11λ Requirements of the Invention] The present invention has a reactor vessel in which a reactor core is housed in the center, and a reactor vessel that accommodates heavy gravity materials, and a reactor vessel that is disposed within this reactor vessel and between this reactor vessel and the reactor core. A fast breeder reactor is equipped with a heat exchanger for performing heat exchange such as the single-layer reactor and double-layer reactor, and the heat exchanger is provided with a thick heat exchanger shield on the core side C. i1'i is shielded by i1'i. ! '31 speed' There are 19 breeding furnaces and 0.
[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C1
図においC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は興なるI7さを右する3
層の遮蔽体7a、7b。Figure 2 shows a fast breeder reactor according to an embodiment of the present invention C1
In the figure, C symbol 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
Layer shields 7a, 7b.
7Gから414成され−C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CJ5す、ま
た中間部に配設される;席蔽体7bは約120’の面を
′m蔽し、さらに最外周に配設される遮蔽体7Gは約(
30°の範囲を遮蔽している。7G to 414-C. The shielding body 7a located in the innermost layer shields the half surface of the heat exchanger 3 on the core side, and is also arranged in the middle part; The shielding body 7G arranged on the outer periphery is approximately (
It covers a range of 30°.
さらにこの実施例では、第1図で示した炉心2を囲繞し
く Fli!設される固定遮蔽体5が除去され−Cいる
。なa5以上jホベた部分を除いて第1図の高速増殖炉
と同様に(14成されているので、第1図と同一部分に
は同一符号をf勺シ説明を省略する。Furthermore, in this embodiment, the reactor core 2 shown in FIG. 1 is surrounded by Fli! The installed fixed shield 5 is removed. The structure is the same as that of the fast breeder reactor shown in FIG. 1 except for the parts that have been moved over A5 and above, so the same parts as 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
裂により発生づる中性子のうち、高速中性子は可動鴻W
ik体4・にJ、り鴻i1’tliされ、中速中性子は
1重重却拐であるナトリウム中で減速され、さらに2次
す1〜リウムの放射化に対りる寄与の太きい熱中性子は
3層からなる熱交換器遮蔽体7にJ、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
The medium-velocity neutron is decelerated in sodium, which is a single-layer neutron, and the thermal neutron, which has a large contribution to the activation of secondary is completely shielded by a heat exchanger shield 7 consisting of three layers.
すなわち、熱交換器3内へ飛び込む中↑(1子は、炉心
2中心と熱交換器3中心とを結ぶ白線(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の厚みを最も人8くづ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, while jumping into heat exchanger 3 ↑ (the first child is the white line connecting the center of core 2 and the center of heat exchanger 3 (because it jumps into heat exchanger 3 most from above, By reducing the thickness of 7 to 8, the most efficient heat exchanger shield 7 can be obtained.
この実施例にJ:れば、前)ホした例えば熱出力250
0MWクラスのプール型高速増殖炉ぐ、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但を
、例えば従)!(の400t〜700tから210tま
で低減することか′Cきる。さらに材料の放JJ1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
十分鴻Nii[されているのぐ固定遮蔽体5を除去する
ことができ、原子炉の小型化を図ることがぐきる。In this example, J: If the previous) E is used, for example, the heat output is 250
0MW class pool type fast breeder reactor and heat exchanger 3
If six units are installed, the stainless steel shielding body (for example, sub-)! (It can be reduced from 400t to 700t to 210t.Furthermore, fast neutrons, which are a particular problem in radiation damage to materials, can be sufficiently suppressed by the movable shield 4, but not by the fixed shield 5. can be removed, making it possible to downsize nuclear reactors.
第3図は固定遮蔽体4の厚さとり−1−リウムの放射化
率を許容レベル以下にするという、遮蔽膜iI基準を満
たす為の遮蔽体総組b1との関係を示づもので、図にお
いC曲線aは、第1図に示した均等厚ステンレスuA製
の熱交換器遮蔽体6と同定遮蔽体4とを組合「だ場合を
、曲線すは第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どを組合けだ場合を示してい
る。Figure 3 shows the relationship between the thickness of the fixed shield 4 and the overall shield set b1 in order to satisfy the shielding film iI criteria, which is to keep the activation rate of -1-lium below the permissible level. The odor C curve a is obtained by combining the heat exchanger shield 6 made of uniform thickness stainless steel uA shown in FIG. A case is shown in which a layered heat exchanger shield 7 and a fixed shield 4 are combined.
この図から明らかなように以上述べl〔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
りることができる。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Jる遮蔽特性の良いボロン鋼およびB4G遮蔽
体を用いた場合につい−(示り。これにJ、れば、ざら
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. In addition, curves c and d in the figure are for the case where boron steel and B4G shielding material, which has better shielding properties against neutrons than stainless steel, are used instead of stainless steel as the heat exchanger shielding material. J, it becomes possible to significantly reduce the total weight of the shield.
なお、固定遮蔽体4としC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が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。In addition, when using a shield made of C graphite as the fixed shield 4, the total weight of the shield can be reduced by using a fixed shield 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 the case where 4 is used.
そしC1熱交換器遮蔽体としCボロン鋼や84G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。By using C boron steel or 84G for the C1 heat exchanger shield, 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′4蔽体を使
用した場合の固定遮蔽体の厚さとプ用・リウムの放射化
率を檜容レベル以下にするどいつ、遮蔽膜δ1基準を満
たず為の遮蔽体総重量との関係を示す−しのぐ、図にお
いて曲線Cは、第1図に示した均等厚ステンレス#A製
の熱交換器″&敵体6と黒鉛からなる固定遮蔽体どを組
合せた場合を、曲線[は第2図に示したステンレスm′
fA3層の熱交換器遮蔽体7と黒鉛からなる固定il!
!敞体どを組合【!た場合を示している。Figure 4 shows when a fixed shield 4 made of graphite is used, the thickness of the fixed shield 4 and the activation rate of phosphorium must be below the volume level to satisfy the shielding film δ1 criterion. Curve C in the figure shows the relationship between the total weight of the shield and the fixed shield made of uniform thickness stainless #A heat exchanger & enemy body 6 and graphite shown in Figure 1. The curve [is the stainless steel m' shown in Fig. 2]
fA3-layer heat exchanger shield 7 and fixed IL made of graphite!
! The union [! The case is shown below.
この図から明らかなように黒鉛から′/、j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
槽重、量を大幅に低減することがCきる。As is clear from this figure, a fast breeder reactor using a fixed shield made of graphite can significantly reduce the tank weight and amount of the shield compared to the conventional method.
また、図中曲線g 1t+は熱交換器遮蔽体としCステ
ンレス鋼の代わりにステンレス鋼より中性子に封する遮
蔽特性の良いボロン鋼ajよσ84C鴻敵体を用いた場
合についC示す。これによれは、ひらに大幅な遮蔽体の
組型■の低減が可能となる。In addition, the curve g1t+ in the figure shows the case where instead of C stainless steel, boron steel aj or σ84C, which has a better shielding property against neutrons than stainless steel, is used as a heat exchanger shield. This makes it possible to significantly reduce the assembly size of the shield.
[発明の効果」
以−[述l\たJ、うに本発明の111速増殖炉にJ、
れば、中性子4蔽体の組型1vを従来に比較し大幅に低
減りることがU″さ、また、P11定遮蔽体厚の減小あ
るいはぞの削除を通じて原子炉の小型化を図ることがで
・8、経流的に右利41原子炉を提供することがC′8
゛る。[Effects of the Invention] Hereinafter, the 111 fast breeder reactor of the present invention will be described.
If so, it is possible to significantly reduce the neutron 4 shield assembly type 1v compared to the conventional one, and also to reduce the size of the reactor by reducing the P11 constant shield thickness or eliminating the groove. 8, it is C'8 to provide 41 nuclear reactors in the right direction.
It's true.
911図は従来の高速増殖炉の一実施例の4半分を示1
J4M PJi而図面第2図はA(発明の一実施例の高
速増殖炉の4半分を示ブ(+4断面図、第3図およびa
(4図は固定連+l+1!体の斤8と遮蔽体総重量との
関係を示すグラフC゛ある。
1・・・・・・・・・・・・IGi子炉容器3・・・・
・・・・・・・・熱交換器
4・・・・・・・・・・・・11J動遮蔽体5・・・・
・・・・・・・・固定遮蔽体7・・・・・・・・・・・
・熱交挽器連i1i!i体代理人弁理f 須 山 佐
−
莞3図
固定速11圭っ厚さくC町Figure 911 shows four halves of an embodiment of a conventional fast breeder reactor.
J4M PJi Figure 2 shows four halves of a fast breeder reactor according to an embodiment of the invention (+4 sectional view, Figure 3 and a
(Figure 4 is a graph C showing the relationship between the fixed station + l + 1! body weight 8 and the total weight of the shield. 1... IGi child reactor vessel 3...
......Heat exchanger 4...11J moving shield 5...
・・・・・・Fixed shield 7・・・・・・・・・・・・
・Heat exchanger ren i1i! I-Entity Attorney Patent Attorney Sa Suyama
- Guan 3 fixed speed 11 Kei thick C town
Claims (4)
子炉容器と、この原子炉容器内にかつこの原子炉容器と
前記メツ」心どの間に配設され前記1次冷却材と2次冷
却4Aどの熱交換を行なう熱交換器どを備えた高速増9
〆1メ)コにおいC1前記熱交換器は前記炉心側?l″
即くとられた熱交換器遮蔽体により遮蔽されCいること
を特徴とする高速増殖炉。(1) A reactor vessel which has a reactor core in the center and which accommodates the primary reactor, and the primary coolant which is disposed within this reactor vessel and between this reactor vessel and the above-mentioned core. A high-speed increaser 9 equipped with a heat exchanger etc. for heat exchange such as secondary cooling 4A etc.
〆1Me) Smell C1 Is the heat exchanger on the core side? l″
A fast breeder reactor, characterized in that it is shielded by a heat exchanger shield that is removed immediately.
る1Ji晶21品求の範囲第1項記載の高速i!Il殖
炉。(2) Force () exchange l! /I device tracking body is made of stainless steel and is made of stainless steel. Il Breeder.
′[請求の範囲第1項記載の高速増殖炉。(3) The heat exchanger shaking shield A4- is a special 5-piece made of 1" bone steel.
' [Fast breeder reactor according to claim 1.
からなる特晶′l請求の範囲411項記載の高速増殖力
」(4) λ() The alternator shield 11iA i is a special crystal consisting of a BnC 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 true JPS6066183A (en) | 1985-04-16 |
| JPH0155436B2 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) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110706830A (en) * | 2019-10-18 | 2020-01-17 | 中国科学院合肥物质科学研究院 | A shield with integrated heat exchange function |
-
1983
- 1983-09-21 JP JP58174997A patent/JPS6066183A/en active Granted
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110706830A (en) * | 2019-10-18 | 2020-01-17 | 中国科学院合肥物质科学研究院 | A shield with integrated heat exchange function |
Also Published As
| Publication number | Publication date |
|---|---|
| JPH0155436B2 (en) | 1989-11-24 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US2832733A (en) | Heavy water moderated neutronic reactor | |
| US3042598A (en) | Shielded thorium fuel element | |
| US2810689A (en) | Fluid moderated reactor | |
| US2992982A (en) | Coupled fast-thermal power breeder reactor | |
| US3640844A (en) | Power-flattened seed-blanket reactor core | |
| US3175955A (en) | Gradient fuel plates | |
| US2921007A (en) | Thermal neutronic reactor | |
| US3098024A (en) | Composite fuel elements for nuclear reactors | |
| US3255083A (en) | Method of flux separation in nuclear reactors and structure therefor | |
| US3211626A (en) | Neutronic reactor fuel element and member therefor | |
| US2836554A (en) | Air cooled neutronic reactor | |
| JPH11352272A (en) | Reactor core, fuel assembly and fuel element used for the core | |
| US3974028A (en) | Reactor and method of operation | |
| US2872399A (en) | Self-reactivating neutron source for a neutronic reactor | |
| JPH0155436B2 (en) | ||
| US2990357A (en) | Method and apparatus for controlling neutron density | |
| JPS622189A (en) | High-temperature gas furnace | |
| Tarby et al. | Fuel handling workshop at the Creys-Malville plant | |
| JPS5853757B2 (en) | Reactor | |
| JPS61240192A (en) | nuclear reactor fuel assembly | |
| JPS5819590A (en) | Fast breeder | |
| KR100237136B1 (en) | Candu fuel bundle with a low void coefficient | |
| Mishima | Improvements in MOX fuel utilization in Japan and technological developments for an economical FBR fuel cycle | |
| Wasinger | Conceptual study on the interim underwater storage of KNK-II fuel elements | |
| Mitsutsuka et al. | Fission product measurements in the inpile fission product loop |