JPH0434116B2 - - Google Patents
Info
- Publication number
- JPH0434116B2 JPH0434116B2 JP58033802A JP3380283A JPH0434116B2 JP H0434116 B2 JPH0434116 B2 JP H0434116B2 JP 58033802 A JP58033802 A JP 58033802A JP 3380283 A JP3380283 A JP 3380283A JP H0434116 B2 JPH0434116 B2 JP H0434116B2
- Authority
- JP
- Japan
- Prior art keywords
- nuclear fuel
- fuel rod
- cladding tube
- coolant
- nickel
- 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
- 239000003758 nuclear fuel Substances 0.000 claims description 30
- PXHVJJICTQNCMI-UHFFFAOYSA-N Nickel Chemical compound [Ni] PXHVJJICTQNCMI-UHFFFAOYSA-N 0.000 claims description 24
- 239000002826 coolant Substances 0.000 claims description 24
- 238000005253 cladding Methods 0.000 claims description 20
- 229910052759 nickel Inorganic materials 0.000 claims description 12
- 239000000446 fuel Substances 0.000 claims description 9
- 230000002285 radioactive effect Effects 0.000 claims description 9
- 239000008188 pellet Substances 0.000 claims description 6
- 238000007747 plating Methods 0.000 claims description 6
- 229910000990 Ni alloy Inorganic materials 0.000 claims description 5
- 239000010935 stainless steel Substances 0.000 claims description 5
- 229910001220 stainless steel Inorganic materials 0.000 claims description 5
- 230000002093 peripheral effect Effects 0.000 claims description 3
- 230000007797 corrosion Effects 0.000 description 5
- 238000005260 corrosion Methods 0.000 description 5
- 239000000463 material Substances 0.000 description 5
- 230000000694 effects Effects 0.000 description 4
- 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 2
- 238000010276 construction Methods 0.000 description 2
- 238000009792 diffusion process Methods 0.000 description 2
- 239000007788 liquid Substances 0.000 description 2
- 229910001338 liquidmetal Inorganic materials 0.000 description 2
- 238000012423 maintenance Methods 0.000 description 2
- 229910052708 sodium Inorganic materials 0.000 description 2
- 239000011734 sodium Substances 0.000 description 2
- GUTLYIVDDKVIGB-OUBTZVSYSA-N Cobalt-60 Chemical compound [60Co] GUTLYIVDDKVIGB-OUBTZVSYSA-N 0.000 description 1
- GUTLYIVDDKVIGB-BJUDXGSMSA-N cobalt-58 Chemical compound [58Co] GUTLYIVDDKVIGB-BJUDXGSMSA-N 0.000 description 1
- 239000000470 constituent Substances 0.000 description 1
- PWHULOQIROXLJO-BJUDXGSMSA-N manganese-54 Chemical compound [54Mn] PWHULOQIROXLJO-BJUDXGSMSA-N 0.000 description 1
- 239000007769 metal material Substances 0.000 description 1
- 230000002265 prevention Effects 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
Description
【発明の詳細な説明】
〔発明の属する技術分野〕
本発明は、冷却材中の放射性核種を炉心部に捕
獲滞留させておくことができるようにした核燃料
棒に関する。DETAILED DESCRIPTION OF THE INVENTION [Field of the Invention] The present invention relates to a nuclear fuel rod capable of capturing and retaining radionuclides in a coolant in a reactor core.
高速増殖炉においては、冷却材として、一般に
液体ナトリウムで代表されるアルカリ性の液体金
属が用いられている。そして、このような液体金
属冷却材は、原子炉容器内に設置された炉心で加
熱された後、容器外に設けられた中間熱交換器へ
と導かれ、再び原子炉容器内へと戻され、循環す
る。
In fast breeder reactors, alkaline liquid metal, typically liquid sodium, is generally used as a coolant. After being heated in the reactor core installed inside the reactor vessel, such liquid metal coolant is guided to an intermediate heat exchanger installed outside the vessel, and then returned to the reactor vessel. , circulate.
ところで、高速増殖炉にあつては、通常核燃料
棒の被覆管や炉心構造物を耐腐食性に富んだステ
ンレス鋼で構成するようにしている。しかし、ス
テンレス鋼も液体ナトリウムで腐食されることは
変りない。被覆管や炉心構造物の構成材料は放射
化されるので、上記のように腐食されると放射性
の腐食生成物が冷却材へ混入することになる。冷
却材へ混入した放射性腐食生成物は上記冷却材に
より前記中間熱交換器系へと運ばれ、上記中間熱
交換器系の配管壁面等に沈着する。このように、
中間熱交換器系の壁面等に沈着した放射性核種に
よる放射線はポンプ、熱交換器、パルプ、流量計
等の機器やこれ等の機器に接続された配管の保
守、補修作業に障害を与える。放射性核種のう
ち、特にマンガン−54、コバルト−60、コバルト
−58等は生成量も多く、半減期も長いためにその
影響が大きい。 By the way, in fast breeder reactors, the cladding tubes and core structures of nuclear fuel rods are usually made of stainless steel, which has high corrosion resistance. However, stainless steel can still be corroded by liquid sodium. Since the constituent materials of the cladding and core structure are radioactive, if they are corroded as described above, radioactive corrosion products will be mixed into the coolant. The radioactive corrosion products mixed into the coolant are carried by the coolant to the intermediate heat exchanger system, and are deposited on the pipe walls of the intermediate heat exchanger system. in this way,
Radiation from radionuclides deposited on the walls of intermediate heat exchanger systems can cause problems in maintenance and repair work of equipment such as pumps, heat exchangers, pulp, flowmeters, and piping connected to these equipment. Among radionuclides, manganese-54, cobalt-60, cobalt-58, etc. are produced in large quantities and have long half-lives, so their effects are large.
そこで、このような不具合を解消するために、
最近では、炉容器内に、ニツケル等の放射性核種
捕獲材を用いた放射性腐食生成物捕獲装置を設置
することが考えられている。この放射性腐食生成
物捕獲装置は、炉心の冷却材出口に対向させて、
つまり炉心上方に、前記捕獲材を収容した要素を
複数配置し、炉心から流出した冷却材に上記捕獲
材を直接接触させることによつて、放射性核種を
捕獲するようにしている。 Therefore, in order to eliminate such problems,
Recently, it has been considered to install a radioactive corrosion product capture device using a radionuclide capture material such as nickel inside the reactor vessel. This radioactive corrosion product capture device is placed opposite the coolant outlet of the reactor core.
That is, a plurality of elements containing the capture material are arranged above the reactor core, and radionuclides are captured by bringing the capture material into direct contact with the coolant flowing out from the core.
前記のような装置にあつて、効率よく放射性核
種を捕獲するには、捕獲材と冷却材との接触面積
をある程度以上にする必要があり、装置自体が大
型化する懸念がある。すなわち、実際に上記装置
を設置するには炉心の上方に高さ約30cmの空間が
必要である。したがつて、上記装置を設置するた
めには、炉心上部機構や原子炉容器を大型化しな
ければならず、原子炉プラントの建設費も増大化
する問題がある。 In order to efficiently capture radionuclides in such a device as described above, it is necessary to increase the contact area between the capture material and the coolant to a certain extent, and there is a concern that the device itself will become larger. That is, in order to actually install the above device, a space approximately 30 cm in height is required above the reactor core. Therefore, in order to install the above-mentioned device, it is necessary to increase the size of the upper core mechanism and the reactor vessel, which poses a problem of increasing the construction cost of the reactor plant.
本発明は、このような事情に鑑みてなされたも
ので、その目的とするところは核燃料棒自身に、
この核燃料棒の大型化を招くことなしに放射性核
種捕獲作用を行なわせることができ、もつて炉心
上部機構および炉容器の小型化および原子炉プラ
ントの建設費の減少化に寄与できる核燃料棒を提
供することにある。
The present invention was made in view of these circumstances, and its purpose is to provide nuclear fuel rods with
To provide a nuclear fuel rod that can perform a radionuclide capture action without increasing the size of the nuclear fuel rod, and that can contribute to downsizing of the upper core mechanism and reactor vessel and to reducing the construction cost of a nuclear reactor plant. It's about doing.
本発明は、燃料ペレツトを被覆管により被覆し
てなる核燃料棒において、前記核燃料棒の外周面
側を流れる冷却材の流れ方向を基準として、最下
流側に位置する前記被覆管の径を他の部分の前記
被覆管の径より大きくかつ内部を空洞に形成する
とともに、この径の大きい被覆管の部分をニツケ
ル、ニツケル合金、外表面にニツケルメツキが施
されたステンレス鋼、外表面にニツケルメツキが
施されたニツケル合金の中から選ばれる少なくと
も一種で形成して冷却材中に含まれる放射性核種
を捕獲するように構成したことを特徴とするもの
である。
The present invention provides a nuclear fuel rod in which fuel pellets are covered with a cladding tube, in which the diameter of the cladding tube located at the most downstream side is set to a different diameter with respect to the flow direction of a coolant flowing on the outer peripheral surface side of the nuclear fuel rod. The diameter of the cladding tube is larger than the diameter of the cladding tube, and the inside thereof is hollow, and the cladding tube portion having a large diameter is made of nickel, nickel alloy, stainless steel with nickel plating on the outer surface, or nickel plating on the outer surface. The coolant is made of at least one type of nickel alloy, and is configured to capture radionuclides contained in the coolant.
上述の構成であると、冷却材に混入した放射性
核種は冷却材が核燃料棒に沿つて流れる過程で上
記核燃料棒本体の最下流端に形成された放射性核
種捕獲器に捕獲されることになる。この場合、炉
心に装荷される核燃料棒本体は、周知のように１
集合体当り数十本から数百本といつた具合に多数
であり、これらの核燃料棒本体に捕獲器をつけた
場合、総表面積が非常に大きなものとなる。ま
た、核燃料棒本体は一般に数mm間隔に設けられる
ものであり、しかも捕獲器部分は他の燃料部と形
状が異なり流れが乱される。
With the above configuration, radionuclides mixed in the coolant are captured by the radionuclide trap formed at the downstream end of the nuclear fuel rod body as the coolant flows along the nuclear fuel rod. In this case, as is well known, the nuclear fuel rod body loaded into the reactor core is 1
There are a large number of nuclear fuel rods, ranging from tens to hundreds, per assembly, and when traps are attached to the bodies of these nuclear fuel rods, the total surface area becomes extremely large. In addition, the nuclear fuel rod bodies are generally arranged at intervals of several millimeters, and the shape of the catcher portion is different from that of other fuel portions, which disrupts the flow.
また、捕獲器部分は外径を太くし流路を狭める
ことにより流速が速くなつている。このため、上
記捕獲器部分で流れの乱された冷却材を広い表面
積を有する捕獲器に接触させることができまた、
流速が速くなつたため薄くなつた境界層を放射性
核種の拡散速度が上がりこの冷却材に混入してい
る放射性核種を確実に捕獲させることができる。
したがつて、放射性核種が中間熱交換器系まで流
れ出すのを防止できるので、この系の保守、補修
等の作業の容易化に寄与できる。 In addition, the flow velocity of the trap portion is increased by increasing the outer diameter and narrowing the flow path. Therefore, the coolant whose flow is disturbed in the trap portion can be brought into contact with the trap having a large surface area, and
The diffusion rate of radionuclides increases through the thinner boundary layer due to the faster flow rate, and the radionuclides mixed in this coolant can be reliably captured.
Therefore, it is possible to prevent radionuclides from flowing out to the intermediate heat exchanger system, which contributes to facilitating maintenance, repair, etc. of this system.
また、核燃料棒本体の前述した最下流端内に
は、一般的にガスプレナム部が形成されている。
本発明では、被覆管の径を太くしているので、こ
のガスプレナムの容積を大きくでき、燃料ペレツ
トから発生する放射性ガスを多量に溜めることが
でき、燃料棒本体の内圧上昇防止、被覆管の損傷
防止といつた効果も得られる。つまり、放射性核
種捕獲機能をもたせることによつて核燃料棒本体
が格別に大型化するようなこともない。したがつ
て、炉心上部機構や炉容器の大型化を招くことな
く放射性核種の捕獲作用を行なわせることがで
き、結局、原子炉プラントの高価格化防止に寄与
できる。 Further, a gas plenum portion is generally formed within the aforementioned most downstream end of the nuclear fuel rod body.
In the present invention, since the diameter of the cladding tube is increased, the volume of this gas plenum can be increased, and a large amount of radioactive gas generated from the fuel pellets can be stored, preventing an increase in the internal pressure of the fuel rod body and preventing damage to the cladding tube. It also has the effect of prevention. In other words, the nuclear fuel rod itself does not become particularly large by providing the radionuclide capture function. Therefore, it is possible to perform the trapping action of radionuclides without increasing the size of the upper core mechanism or the reactor vessel, which ultimately contributes to preventing the cost of nuclear reactor plants from increasing.
以下本発明の実施例を図面を参照しながら説明
する。
Embodiments of the present invention will be described below with reference to the drawings.
図は本発明の一実施例に係る核燃料棒の要部を
取り出して示す縦断面図であり、この核燃料棒１
は核燃料棒本体２と、この核燃料棒本体２の外周
面で、かつ上記核燃料棒本体２に接触する冷却材
ｐの流れ方向を基準にした最下流端部３に形成さ
れた放射性核種捕獲器４とで構成されている。 The figure is a vertical sectional view showing the main parts of a nuclear fuel rod according to an embodiment of the present invention.
is a nuclear fuel rod body 2 and a radionuclide trap 4 formed on the outer peripheral surface of this nuclear fuel rod body 2 and at the most downstream end 3 with reference to the flow direction of the coolant P that contacts the nuclear fuel rod body 2. It is made up of.
核燃料棒本体２は薄肉のステンレス鋼管で形成
された被覆管５と、この被覆管５の上部開口を閉
塞する上部端栓６および下部開口を閉塞する下部
端栓（図示せず）と、被覆管５内に収容された燃
料ペレツト７と、この燃料ペレツト７と前記上部
端栓６と燃料ペレツト７との間にガスプレナム９
を形成するスプリング１０と板体８で構成されて
いる。そして、上記被覆管５の前記ガスプレナム
９が設けられている部分に形成した放射性核種捕
獲器４の外径は他の部分の外径より大きくなつて
おり、表面にはたとえばニツケルメツキが施して
ある。そして、上記のように構成された核燃料棒
１は捕獲器４の側が核燃料棒本体２に接触しなが
ら流れる冷却材ｐの流れ方向を基準にして最下流
側に位置するように集合されて炉心に装荷され
る。 The nuclear fuel rod body 2 includes a cladding tube 5 formed of a thin-walled stainless steel tube, an upper end plug 6 for closing the upper opening of the cladding tube 5, a lower end plug (not shown) for closing the lower opening of the cladding tube 5, and a cladding tube. A gas plenum 9 is provided between the fuel pellets 7, the upper end plug 6, and the fuel pellets 7.
It is composed of a spring 10 and a plate body 8 which form a spring 10 and a plate body 8. The outer diameter of the radionuclide trap 4 formed in the portion of the cladding tube 5 where the gas plenum 9 is provided is larger than the outer diameter of other portions, and the surface is plated with, for example, nickel plating. The nuclear fuel rods 1 configured as described above are assembled into the reactor core such that the side of the trap 4 is located at the most downstream side with respect to the flow direction of the coolant p flowing while contacting the nuclear fuel rod body 2. loaded.
このような構成であると、原子炉運転時には、
冷却材ｐが図中矢印で示すように、核燃料棒１に
接触しながら流れるのであるが、この冷却材ｐに
は放射性核種捕獲器４の部分を通流するとき、捕
獲器部分の形状が他の部分と異なるために流れが
乱される。また捕獲器部分４の形径は他の燃料部
本体２の外径より太くなつており、流路が狭く流
速が速くなり、薄くなつた境界層を放射性核種が
速い速度で拡散することができる。このため冷却
材中に混入している放射性核種が確実に捕獲器４
の表面に接触することになる。捕獲器４は活性の
強いニツケルで例えば10μ以上メツキが施されて
いるので、接触した放射性核種は、この捕獲器に
捕獲され、メツキ層の内部へと拡散によつて侵透
し、結局前述した効果が得られることになる。 With this configuration, during reactor operation,
As shown by the arrow in the figure, the coolant p flows while contacting the nuclear fuel rods 1. When the coolant p flows through the radionuclide trap 4, the shape of the trap is different. The flow is disturbed because it is different from the part of the flow. In addition, the diameter of the trap section 4 is larger than the outer diameter of the other fuel section main body 2, so the flow path is narrow and the flow velocity is high, allowing radionuclides to diffuse through the thinned boundary layer at a high speed. . Therefore, the radionuclides mixed in the coolant are reliably removed from the trap 4.
will come into contact with the surface. Since the trap 4 is plated with highly active nickel of, for example, 10μ or more, the radioactive nuclides that come into contact with it are captured by this trap and penetrate into the plating layer by diffusion, as described above. The effect will be obtained.
本発明は上述した実施例に限定されるものでは
ない。実施例では、放射性捕獲器の表面にニツケ
ルメツキを施したが、捕獲器やガスプレナム部は
ニツケル材又はニツケル合金であつてもよく、さ
らに放射性核種を捕獲する機能を有する他の金属
材料であつてもよい。また捕獲器表面は形状を凹
凸にすることにより更に捕獲効率を高めることが
可能である。
The invention is not limited to the embodiments described above. In the example, the surface of the radioactive trap was plated with nickel, but the trap and the gas plenum may be made of nickel or a nickel alloy, or even other metal materials that have the function of capturing radionuclides. good. Further, by making the surface of the trap uneven, it is possible to further improve the trapping efficiency.
第１図は本発明の一実施例に係る核燃料棒の要
部を取り出して示す縦断面図である。
１……核燃料棒、２……核燃料棒本体、３……
ガスプレナム、４……放射性核種捕獲器、５……
被覆管、６……上部端栓、７……燃料ペレツト、
８……板体、１０……スプリング、ｐ……冷却
材。
FIG. 1 is a vertical cross-sectional view showing a main part of a nuclear fuel rod according to an embodiment of the present invention. 1... Nuclear fuel rod, 2... Nuclear fuel rod body, 3...
Gas plenum, 4... Radionuclide trap, 5...
Cladding tube, 6... Upper end plug, 7... Fuel pellets,
8... Plate, 10... Spring, p... Coolant.
Claims (1)
燃料棒において、 前記核燃料棒の外周面側を流れる冷却材の流れ
方向を基準として、最下流側に位置する前記被覆
管の径を他の部分の前記被覆管の径より大きくか
つ内部を空洞に形成するとともに、この径の大き
い被覆管の部分をニツケル、ニツケル合金、外表
面にニツケルメツキが施されたステンレス鋼、外
表面にニツケルメツキが施されたニツケル合金の
中から選ばれる少なくとも一種で形成して冷却材
中に含まれる放射性核種を捕獲するように構成し
たことを特徴とする核燃料棒。 ２ 前記径の太い被覆管の部分の外表面を凹凸形
状に形成したことを特徴とする特許請求の範囲第
１項記載の核燃料棒。[Scope of Claims] 1. In a nuclear fuel rod formed by covering fuel pellets with a cladding tube, the diameter of the cladding tube located at the most downstream side with respect to the flow direction of the coolant flowing on the outer peripheral surface of the nuclear fuel rod. The diameter of the cladding tube is larger than that of other parts and the inside thereof is hollow, and the part of the cladding tube with a large diameter is made of nickel, nickel alloy, stainless steel with nickel plating on the outer surface, or nickel plating on the outer surface. What is claimed is: 1. A nuclear fuel rod characterized in that it is formed of at least one type of nickel alloy that has been treated with nickel and is configured to capture radioactive nuclides contained in a coolant. 2. The nuclear fuel rod according to claim 1, wherein the outer surface of the portion of the cladding tube having a large diameter is formed into an uneven shape.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58033802A JPS59160794A (en) | 1983-03-03 | 1983-03-03 | Nuclear fuel rod |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP58033802A JPS59160794A (en) | 1983-03-03 | 1983-03-03 | Nuclear fuel rod |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS59160794A JPS59160794A (en) | 1984-09-11 |
| JPH0434116B2 true JPH0434116B2 (en) | 1992-06-04 |
Family
ID=12396602
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP58033802A Granted JPS59160794A (en) | 1983-03-03 | 1983-03-03 | Nuclear fuel rod |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS59160794A (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS6329798U (en) * | 1986-08-12 | 1988-02-26 | ||
| US5219519A (en) * | 1992-02-21 | 1993-06-15 | General Electric Company | Increased fuel column height for boiling water reactor fuel rods |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5390600A (en) * | 1977-01-18 | 1978-08-09 | Us Government | Method of controlling deposition of radioactive nuclide |
| JPS5673385A (en) * | 1979-11-20 | 1981-06-18 | Tokyo Shibaura Electric Co | Fast breeder |
-
1983
- 1983-03-03 JP JP58033802A patent/JPS59160794A/en active Granted
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5390600A (en) * | 1977-01-18 | 1978-08-09 | Us Government | Method of controlling deposition of radioactive nuclide |
| JPS5673385A (en) * | 1979-11-20 | 1981-06-18 | Tokyo Shibaura Electric Co | Fast breeder |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS59160794A (en) | 1984-09-11 |
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