JPH0476078B2 - - Google Patents
Info
- Publication number
- JPH0476078B2 JPH0476078B2 JP59205549A JP20554984A JPH0476078B2 JP H0476078 B2 JPH0476078 B2 JP H0476078B2 JP 59205549 A JP59205549 A JP 59205549A JP 20554984 A JP20554984 A JP 20554984A JP H0476078 B2 JPH0476078 B2 JP H0476078B2
- Authority
- JP
- Japan
- Prior art keywords
- neutron
- tube
- reinforcing member
- neutron shielding
- wrapper
- 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 - Lifetime
Links
- 238000005253 cladding Methods 0.000 claims description 20
- 239000000463 material Substances 0.000 claims description 18
- 125000006850 spacer group Chemical group 0.000 claims description 17
- 230000003014 reinforcing effect Effects 0.000 claims description 16
- 229910000831 Steel Inorganic materials 0.000 claims description 2
- 229910000963 austenitic stainless steel Inorganic materials 0.000 claims description 2
- 239000010959 steel Substances 0.000 claims description 2
- 229910000859 α-Fe Inorganic materials 0.000 claims description 2
- 229910000990 Ni alloy Inorganic materials 0.000 claims 1
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 7
- 229910002804 graphite Inorganic materials 0.000 description 7
- 239000010439 graphite Substances 0.000 description 7
- 239000002826 coolant Substances 0.000 description 6
- 230000000694 effects Effects 0.000 description 6
- 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 5
- 239000000446 fuel Substances 0.000 description 5
- 229910052708 sodium Inorganic materials 0.000 description 5
- 239000011734 sodium Substances 0.000 description 5
- 230000008961 swelling Effects 0.000 description 5
- 239000008358 core component Substances 0.000 description 3
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 description 2
- 238000007796 conventional method Methods 0.000 description 2
- 239000012634 fragment Substances 0.000 description 2
- 229910001338 liquidmetal Inorganic materials 0.000 description 2
- 229910001220 stainless steel Inorganic materials 0.000 description 2
- 239000010935 stainless steel Substances 0.000 description 2
- 230000002411 adverse Effects 0.000 description 1
- 229910045601 alloy Inorganic materials 0.000 description 1
- 239000000956 alloy Substances 0.000 description 1
- 229910052790 beryllium Inorganic materials 0.000 description 1
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 230000004907 flux Effects 0.000 description 1
- 230000001771 impaired effect Effects 0.000 description 1
- 229910000816 inconels 718 Inorganic materials 0.000 description 1
- 229910001090 inconels X-750 Inorganic materials 0.000 description 1
- 238000003780 insertion Methods 0.000 description 1
- 230000037431 insertion Effects 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 229910052759 nickel Inorganic materials 0.000 description 1
- NJPPVKZQTLUDBO-UHFFFAOYSA-N novaluron Chemical compound C1=C(Cl)C(OC(F)(F)C(OC(F)(F)F)F)=CC=C1NC(=O)NC(=O)C1=C(F)C=CC=C1F NJPPVKZQTLUDBO-UHFFFAOYSA-N 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 230000002787 reinforcement Effects 0.000 description 1
- 238000005482 strain hardening Methods 0.000 description 1
- 238000003466 welding Methods 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
Description
【発明の詳細な説明】
［発明の技術分野］
本発明は、例えば高速増殖炉において用いられ
る中性子遮蔽体に関する。DETAILED DESCRIPTION OF THE INVENTION [Technical Field of the Invention] The present invention relates to a neutron shield used, for example, in a fast breeder reactor.
［発明の技術的背景とその問題点］
第７図は液体金属冷却型高速増殖炉を示すもの
で、図において符号１１は原子炉容器を示してい
る。この原子炉容器１は原子炉建屋のペデスタル
２に固定されている。また、原子炉容器１の上端
開口部は遮蔽プラグ３により閉塞されている。[Technical background of the invention and its problems] FIG. 7 shows a liquid metal cooled fast breeder reactor, and in the figure, reference numeral 11 indicates a reactor vessel. This reactor vessel 1 is fixed to a pedestal 2 of a reactor building. Further, the upper end opening of the reactor vessel 1 is closed by a shielding plug 3.
そして原子炉容器１内には炉心部４が配置され
ている。この炉心部４は、炉心バレル５の内側に
第８図に示すように、中性子遮蔽体６、外側ブラ
ンケツト燃料集合体７、内側ブランケツト燃料集
合体８、炉心燃料集合体９を外側から順に装荷し
たものであり、これら各炉心構成要素は第９図に
示すように、炉心支持構造物１０によつて支持さ
れている。 A reactor core section 4 is arranged within the reactor vessel 1 . This reactor core 4 has a neutron shield 6, an outer blanket fuel assembly 7, an inner blanket fuel assembly 8, and a core fuel assembly 9 loaded in order from the outside as shown in FIG. 8 inside a core barrel 5. Each of these core components is supported by a core support structure 10, as shown in FIG.
前述した中性子遮蔽体６は、第１０図に示すよ
うに構成されている。 The neutron shield 6 described above is constructed as shown in FIG.
すなわち、図において符号１１は六角形状のラ
ツパ管であり、例えばステンレス鋼により形成さ
れている。このラツパ管１１の上端部には冷却材
流出孔１２が開口し、かつ燃料交換機等で取扱う
ためのハンドリングヘツド１３が形成されてい
る。 That is, in the figure, reference numeral 11 is a hexagonal wrapper tube, which is made of, for example, stainless steel. A coolant outflow hole 12 is opened at the upper end of the wrapper tube 11, and a handling head 13 for handling in a fuel exchanger or the like is formed.
また、ラツパ管１１の側面にはスペーサパツド
１４が軸線方向に離間して設けられている。これ
らスペーサパツド１４は互いに隣接し合う炉心構
成要素間に所定の間隔を確保する機能を持つ。 Furthermore, spacer pads 14 are provided on the side surface of the wrapper tube 11 to be spaced apart in the axial direction. These spacer pads 14 have the function of securing a predetermined distance between adjacent core components.
そしてラツパ管１１の下部にはエントランスノ
ズル１５ａが設けられている。このエントランス
ノズル１５ａは細長な形状をなし、炉心支持構造
物１０に形成された挿通孔に挿入支持可能とされ
ている。 An entrance nozzle 15a is provided at the bottom of the wrapper tube 11. This entrance nozzle 15a has an elongated shape and can be inserted and supported into an insertion hole formed in the core support structure 10.
また、エントランスノズル１５ａには冷却材取
入れ孔１６ａが形成されている。ラツパ管１１内
には密閉構造をした被覆管１５が収容されてお
り、この被覆管１５内には、例えばグラフアイト
ブロツクからなる中性子遮蔽材１６が収容されて
いる。また、被覆管１５とラツパ管１１の間には
液体金属ナトリウムを流通するアニラス部１６ａ
が形成されている。 Furthermore, a coolant intake hole 16a is formed in the entrance nozzle 15a. A cladding tube 15 having a sealed structure is housed within the wrapper tube 11, and a neutron shielding material 16 made of, for example, graphite block is housed within the cladding tube 15. Further, between the cladding tube 15 and the wrapper tube 11, there is an anneal section 16a through which liquid metal sodium flows.
is formed.
以上のように構成された中性子遮蔽体６は、炉
心において発生する中性子を有効に利用し、かつ
中性子の炉外への漏洩を防止する目的を有してい
る。 The neutron shield 6 configured as described above has the purpose of effectively utilizing neutrons generated in the reactor core and preventing leakage of neutrons to the outside of the reactor.
このため中性子遮蔽体６には、その寿命中所定
の位置に前述の目的を果すに必要な中性子遮蔽材
１６を内蔵していることが必要である。 For this reason, the neutron shield 6 needs to have a built-in neutron shield material 16 at a predetermined position during its lifetime, which is necessary to achieve the above-mentioned purpose.
一方、中性子遮蔽体６は炉心のすぐ外周に設置
されることから、高温、高中性子照射下に置かれ
ることになる。 On the other hand, since the neutron shield 6 is installed immediately on the outer periphery of the reactor core, it will be placed under high temperature and high neutron irradiation.
このような環境下において、中性子遮蔽体６は
それ自身の周方向に温度分布ができること、中性
子の照射により材料がスウエリングすること等に
より変形を起こす。また、外部からは他の炉心構
成要素が変形することによる荷重や、さらに地震
等によつて中性子遮蔽体６相互間の衝突や流体力
による荷重が、中性子遮蔽体６が横方向の移動を
相互に拘束しているスペーサパツド１４に作用す
ることになる。 Under such an environment, the neutron shield 6 is deformed due to temperature distribution in its own circumferential direction, swelling of the material due to neutron irradiation, etc. In addition, from the outside, loads due to deformation of other core components, collisions between the neutron shields 6 due to earthquakes, and loads due to fluid force can cause the neutron shields 6 to mutually move in the lateral direction. This will act on the spacer pad 14 which is restrained by the spacer pad 14.
ところで中性子遮蔽体６として、中性子遮蔽効
果の向上からグラフアイトが多用されている。こ
のグラフアイトは一般に充填率の向上のためブロ
ツクペレツト化され、また冷却材であるナトリウ
ムとの共存性を考慮し、ステンレス製の被覆管１
５内に収容した後、ラツパ管１１内に収容されて
いる。 Incidentally, graphite is often used as the neutron shield 6 because of its improved neutron shielding effect. This graphite is generally made into block pellets to improve the filling rate, and in consideration of coexistence with the coolant sodium, it is made into stainless steel cladding tubes.
After being housed in the tube 5, it is housed in the lapper tube 11.
一方、ラツパ管１１には隣接する炉心支持構造
物と接触するスペーサパツド１４が配設されてい
る。このスペーサパツド１４は地震時等に非常に
大きな荷重を受けることとなり、スペーサパツド
１４の受けた荷重による変形がラツパ管１１から
被覆管１５に作用し、さらに脆いグラフアイトブ
ロツクからなる中性子遮蔽材１６が圧縮荷重を受
け、破損するおそれがある。被覆管１５の損傷は
被覆管１５内に冷却材ナトリウムの侵入を許し、
破損したグラフアイトが冷却材ナトリウムイとと
もに被覆管１５外へ流出し、中性子遮蔽機能が損
われる。 On the other hand, the wrapper tube 11 is provided with a spacer pad 14 that comes into contact with an adjacent core support structure. This spacer pad 14 is subjected to a very large load during an earthquake, etc., and the deformation due to the load applied to the spacer pad 14 acts on the cladding tube 15 from the wrapper tube 11, and the neutron shielding material 16 made of brittle graphite blocks is compressed. There is a risk of damage due to the load. Damage to the cladding tube 15 allows coolant sodium to enter into the cladding tube 15,
The damaged graphite flows out of the cladding tube 15 together with the coolant sodium, and the neutron shielding function is impaired.
さらに流出した破片が他の機器へ悪影響を及ぼ
すおそれがあり、燃料にトラツプされると局所的
な流路閉塞事故にも繋がるという問題がある。 Furthermore, there is a risk that the spilled fragments may have an adverse effect on other equipment, and if they become trapped in the fuel, there is a problem that this may lead to local flow path blockage accidents.
［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、地震やスウエリング等の外部からの荷重
による。ラツパ管、被覆管および中性子遮蔽材の
破損を有効に防止することのできる中性子遮蔽体
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 is caused by external loads such as earthquakes and swelling. It is an object of the present invention to provide a neutron shielding body that can effectively prevent damage to a wrapper tube, a cladding tube, and a neutron shielding material.
［発明の概要］
すなわち本発明は筒状のラツパ管外壁にスペー
サパツドを設け、前記ラツパ管内部に中性子遮蔽
材を収容してなる中性子遮蔽体において、前記ラ
ツパ管のスペーサパツドの位置に他の位置よりも
高い強度を有する筒状の補強部材を配置したこと
を特徴とする中性子遮蔽体である。[Summary of the Invention] That is, the present invention provides a neutron shielding body in which a spacer pad is provided on the outer wall of a cylindrical wrapper tube, and a neutron shielding material is housed inside the wrapper tube, in which a spacer pad is provided at a position of the wrapper tube from another position. This is a neutron shield characterized by having a cylindrical reinforcing member having high strength arranged therein.
［発明の実施例］
以下本発明の詳細を図面に示す実施例について
説明する。[Embodiments of the Invention] Details of the present invention will be described below with reference to embodiments shown in the drawings.
第１図および第２図は本発明の中性子遮蔽体の
一実施例を示すもので、この実施例の中性子遮蔽
体では、ラツパ管１１のスペーサパツド１４の位
置に中性子遮蔽材１６を囲撓してリング状の補強
部材２０が配置されている。 1 and 2 show an embodiment of the neutron shield of the present invention, in which a neutron shield material 16 is bent around the spacer pad 14 of the wrapper tube 11. A ring-shaped reinforcing member 20 is arranged.
すなわち、補強部材２０は被覆管１５内に収容
されており、補強部材２０の中空部には中性子遮
蔽材１６が充填されている。なお、補強部材２０
は構造上強固であり、中性子遮蔽効果も備えてい
ることが要望されるため、この補強部材２０はフ
エライト鋼、オーステナイトステンレス鋼、ある
いはインコネル718、Ｘ−750のような高ニツケル
基合金が用いられる。さらに被覆管１５、ラツパ
管１１との照射スウエリングの膨張差による相互
作用を防止するため冷間加工等を施すのが望まし
い。 That is, the reinforcing member 20 is housed within the cladding tube 15, and the hollow portion of the reinforcing member 20 is filled with the neutron shielding material 16. In addition, the reinforcing member 20
Since the reinforcing member 20 is required to be structurally strong and have a neutron shielding effect, the reinforcing member 20 is made of ferrite steel, austenitic stainless steel, or a high nickel-based alloy such as Inconel 718 or X-750. . Further, in order to prevent interaction between the cladding tube 15 and the wrapper tube 11 due to expansion differences due to irradiation swelling, it is desirable to perform cold working or the like.
また、この実施例では、中性子遮蔽材１６とし
てグラフアイトブロツクが使用されている。 Further, in this embodiment, graphite block is used as the neutron shielding material 16.
以上のように構成された中性子遮蔽体では、地
震時あるいはスウエリング時等にスペーサパツド
１４に作用する多大な荷重がラツパ管１１、被覆
管１５を介して補強部材２０により支持されるた
め、ラツパ管１１、被覆管１５および中性子遮蔽
材１６の破損を効果的に防止することができる。 In the neutron shield constructed as described above, a large load acting on the spacer pad 14 during an earthquake or swelling is supported by the reinforcing member 20 via the wrapper tube 11 and the cladding tube 15. , damage to the cladding tube 15 and the neutron shielding material 16 can be effectively prevented.
この結果、被覆管１５が破損した場合に生ずる
と考えられる冷却材ナトリウムの被覆管１５内へ
の侵入と、これに伴う中性子遮蔽材１６破片の流
出を有効に防止することができ、原子炉の安全性
および信頼性を従来より大幅に向上することがで
きる。 As a result, it is possible to effectively prevent the coolant sodium from entering the cladding tube 15, which would occur if the cladding tube 15 is damaged, and the resulting leakage of neutron shielding material 16 fragments. Safety and reliability can be significantly improved compared to conventional methods.
第３図および第４図は本発明の中性子遮蔽体の
他の実施例を示すもので、この実施例では被覆管
１５に補強部材２１が溶接により接合され、補強
部材２１は被覆管１５に一体に形成されている。 3 and 4 show another embodiment of the neutron shield of the present invention. In this embodiment, a reinforcing member 21 is joined to the cladding tube 15 by welding, and the reinforcing member 21 is integrated with the cladding tube 15. is formed.
このように構成された中性子遮蔽体において
も、第１図および第２図に示す中性子遮蔽体と同
様の効果を得ることができる。 The neutron shield constructed in this manner can also provide the same effects as the neutron shield shown in FIGS. 1 and 2.
第５図および第６図は本発明の中性子遮蔽体の
さらに他の実施例を示すもので、この実施例の中
性子遮蔽体では補強部材２２の外形形状がラツパ
管１１の内形形状と同じ六角形状とされている。 5 and 6 show still another embodiment of the neutron shield of the present invention, in which the reinforcing member 22 has a hexagonal outer shape that is the same as the inner shape of the wrapper tube 11. It is said to be the shape.
このように構成された中性子遮蔽体では、スペ
ーサパツド１４に作用する荷重を前述した２つの
実施例に比べ、さらに有効に支持することができ
る。 The neutron shield constructed in this manner can support the load acting on the spacer pad 14 more effectively than the two embodiments described above.
なお、以上述べた実施例では、中性子遮蔽材１
６としてグラフアイトを用いた例について説明し
たが、本発明はかかる実施例に限定されるもので
はなく、例えばベリリウムのような材料を中性子
遮蔽材１６として用いた中性子遮蔽体にも適用で
きることは勿論である。 In addition, in the embodiment described above, the neutron shielding material 1
Although an example using graphite has been described as No. 6, the present invention is not limited to such an example, and can of course be applied to a neutron shielding material using a material such as beryllium as the neutron shielding material 16. It is.
［発明の効果］
以上述べたように本発明の中性子遮蔽体では、
ラツパ管のスペーサパツドの位置に筒状の補強部
材を配置したので、スウエリング時や地震時にス
ペーサパツドに作用する大荷重を補強部材により
有効に支持することができ、ラツパ管等の破損を
有効に防止することができる。[Effect of the invention] As described above, the neutron shield of the present invention has the following effects:
Since the cylindrical reinforcing member is placed at the position of the spacer pad of the Ratsupa pipe, the large load that acts on the spacer pad during swelling or earthquakes can be effectively supported by the reinforcing member, and damage to the Ratsupa pipe, etc. can be effectively prevented. be able to.
この結果、原子炉の安全性および信頼性を従来
より大幅に向上することができる。 As a result, the safety and reliability of the nuclear reactor can be significantly improved compared to conventional methods.
第１図は本発明の中性子遮蔽体の一実施例を示
す縦断面図、第２図は第１図の−線に沿う横
断面図、第３図は本発明の中性子遮蔽体の他の実
施例を示す縦断面図、第４図は第３図の−線
に沿う横断面図、第５図は本発明の中性子遮蔽体
のさらに他の実施例を示す縦断面図、第６図は第
５図の−線に沿う横断面図、第７図は高束増
殖炉を示す縦断面図、第８図は第７図に示す高速
増殖炉の炉心配置を示す説明図、第９図は炉心支
持構造物を示す縦断面図、第１０図は従来の中性
子遮蔽体を示す縦断面図である。
１……原子炉容器、６……中性子遮蔽体、１１
……ラツパ管、１４……スペーサパツド、１５…
…被覆管、１６……中性子遮蔽材、２０，２１，
２２……補強部材。
FIG. 1 is a longitudinal cross-sectional view showing one embodiment of the neutron shield of the present invention, FIG. 2 is a cross-sectional view taken along the line - in FIG. 1, and FIG. 3 is another embodiment of the neutron shield of the present invention. FIG. 4 is a longitudinal cross-sectional view showing an example, FIG. 4 is a cross-sectional view taken along the line - in FIG. 3, FIG. 5 is a cross-sectional view along the - line in Figure 7, Figure 7 is a vertical cross-sectional view showing a high flux breeder reactor, Figure 8 is an explanatory diagram showing the core arrangement of the fast breeder reactor shown in Figure 7, and Figure 9 is a core. FIG. 10 is a vertical cross-sectional view showing a support structure, and FIG. 10 is a vertical cross-sectional view showing a conventional neutron shield. 1... Reactor vessel, 6... Neutron shield, 11
...Ratsupa tube, 14...Spacer pad, 15...
...cladding tube, 16...neutron shielding material, 20, 21,
22...Reinforcement member.
Claims (1)
け、前記ラツパ管内部に被覆管により密封される
中性子遮蔽材を収容してなる中性子遮蔽体におい
て、前記ラツパ管内側のスペーサパツドの位置に
前記中性子遮蔽材を囲撓しラツパ管内に収容され
るリング状の補強部材を配置したことを特徴とす
る中性子遮蔽体。 ２ 補強部材は、オーステナイトステンレス鋼、
フエライト鋼または高ニツケル合金からなる特許
請求の範囲第１項記載の中性子遮蔽体。 ３ 補強部材は、被覆管と一体形成されている特
許請求の範囲第１項または第２項記載の中性子遮
蔽体。[Scope of Claims] 1. In a neutron shielding body comprising a spacer pad provided on the outer wall of a cylindrical wrapper tube and a neutron shielding material sealed by a cladding tube inside the wrapper tube, the position of the spacer pad inside the wrapper tube A neutron shielding body, further comprising a ring-shaped reinforcing member that surrounds the neutron shielding material and is housed in a wrapper tube. 2 The reinforcing member is austenitic stainless steel,
A neutron shield according to claim 1, which is made of ferrite steel or a high nickel alloy. 3. The neutron shield according to claim 1 or 2, wherein the reinforcing member is integrally formed with the cladding tube.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59205549A JPS6184593A (en) | 1984-10-02 | 1984-10-02 | Neutron shielding body |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP59205549A JPS6184593A (en) | 1984-10-02 | 1984-10-02 | Neutron shielding body |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6184593A JPS6184593A (en) | 1986-04-30 |
| JPH0476078B2 true JPH0476078B2 (en) | 1992-12-02 |
Family
ID=16508727
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP59205549A Granted JPS6184593A (en) | 1984-10-02 | 1984-10-02 | Neutron shielding body |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS6184593A (en) |
-
1984
- 1984-10-02 JP JP59205549A patent/JPS6184593A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6184593A (en) | 1986-04-30 |
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