JPS6122800B2 - - Google Patents
Info
- Publication number
- JPS6122800B2 JPS6122800B2 JP52004025A JP402577A JPS6122800B2 JP S6122800 B2 JPS6122800 B2 JP S6122800B2 JP 52004025 A JP52004025 A JP 52004025A JP 402577 A JP402577 A JP 402577A JP S6122800 B2 JPS6122800 B2 JP S6122800B2
- Authority
- JP
- Japan
- Prior art keywords
- basket
- water
- cask
- hollow
- spent fuel
- 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
- 239000006096 absorbing agent Substances 0.000 claims description 13
- 239000002915 spent fuel radioactive waste Substances 0.000 claims description 8
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 8
- 238000010521 absorption reaction Methods 0.000 claims description 5
- 239000000463 material Substances 0.000 claims description 4
- 239000000498 cooling water Substances 0.000 claims description 2
- 239000008187 granular material Substances 0.000 claims description 2
- 239000000843 powder Substances 0.000 claims description 2
- 230000035939 shock Effects 0.000 claims description 2
- 230000002745 absorbent Effects 0.000 claims 3
- 239000002250 absorbent Substances 0.000 claims 3
- 239000000446 fuel Substances 0.000 description 19
- 230000002159 abnormal effect Effects 0.000 description 12
- 229910000831 Steel Inorganic materials 0.000 description 3
- 239000010959 steel Substances 0.000 description 3
- 230000005855 radiation Effects 0.000 description 2
- 235000006506 Brasenia schreberi Nutrition 0.000 description 1
- 244000267222 Brasenia schreberi Species 0.000 description 1
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 1
- 239000004327 boric acid Substances 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- -1 for example Substances 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 239000000155 melt Substances 0.000 description 1
- VPOLVWCUBVJURT-UHFFFAOYSA-N pentadecasodium;pentaborate Chemical compound [Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[Na+].[O-]B([O-])[O-].[O-]B([O-])[O-].[O-]B([O-])[O-].[O-]B([O-])[O-].[O-]B([O-])[O-] VPOLVWCUBVJURT-UHFFFAOYSA-N 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 239000000126 substance Substances 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
- Cooling, Air Intake And Gas Exhaust, And Fuel Tank Arrangements In Propulsion Units (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は、通常時及び異常事故時共に容器内を
未臨界に保つようにする使用済燃料輸送容器(以
下キヤスクと呼ぶ)に関するものである。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a spent fuel transport container (hereinafter referred to as a cask) that maintains the inside of the container at a subcritical state both in normal times and during abnormal accidents.
キヤスクは、原子炉で使用した燃料集合体を何
体かまとめて安全に輸送するものである。従つ
て、キヤスクの内部に入れた燃料集合体がどのよ
うなものでも、またどのように変化しようともキ
ヤスク内は常に未臨界になつていなければならな
い。 A cask is used to safely transport several fuel assemblies used in a nuclear reactor. Therefore, no matter what kind of fuel assembly is placed inside the cask or how it changes, the inside of the cask must always remain subcritical.
まず本発明の目的を明確にするため従来のキヤ
スクについて説明する。第1図において、キヤス
クは外側からシヨツクアブソーバー8,フイン
7,容器本体6と付属の容器脚9,冷却水5,中
空円筒4順でかこまれている。中空円筒4の内部
は燃料保持枠3と格子状になつたバスケツト1で
仕切られており、このバスケツト1内部には中空
角柱状のボトル2が設けられそのボトル2に燃料
集合体を入るようにしている。 First, in order to clarify the purpose of the present invention, a conventional cask will be explained. In FIG. 1, the cask is surrounded from the outside by a shock absorber 8, fins 7, a container body 6, an attached container leg 9, a cooling water 5, and a hollow cylinder 4. The interior of the hollow cylinder 4 is partitioned by a fuel holding frame 3 and a grid-like basket 1, and a hollow prismatic bottle 2 is provided inside the basket 1, into which the fuel assembly is placed. ing.
バスケツト1の材質としては鋼を、ボトル2の
材質としてはステンレスが一般によく用いられ
る。中空円筒4の内側のバスケツト1とボトル
2,燃料集合体以外の部分には水が入れられて燃
料集合体を冷却し、一方この水で燃料集合体より
出る放射線を遮蔽するようにしている。 Generally, the material of the basket 1 is steel, and the material of the bottle 2 is stainless steel. Water is placed inside the hollow cylinder 4 other than the basket 1, bottle 2, and fuel assembly to cool the fuel assembly, and on the other hand, this water shields radiation emitted from the fuel assembly.
使用済燃料が定められた位置におかれている通
常時のキヤスクでは、第5図の曲線61Aに示す
ように燃料のあらゆる燃焼度にわたつて中性子の
実効増倍率(keff)が十分1.0より小さく未臨界
である。 In a normal cask in which spent fuel is placed in a predetermined position, the effective multiplication factor (keff) of neutrons is sufficiently smaller than 1.0 over all fuel burnup levels, as shown by curve 61A in Figure 5. It is subcritical.
しかしながら、何らかの事故でバスケツト1ボ
トル2が粉砕され、燃料と水のみが一定の割合で
混合しキヤスクの一部にたまつて均質になつたよ
うな異常な場合(以下このケースを異常事故と呼
ぶ)は、第5図の曲線60Aに示すように、燃料
の燃焼度によつては臨界を越える場合があること
が考えられる。 However, in an abnormal case where the basket 1 bottle 2 is crushed due to some kind of accident, and only fuel and water are mixed at a certain ratio and collected in a part of the cask and become homogeneous (hereinafter this case is referred to as an abnormal accident). ) may exceed the critical value depending on the burnup of the fuel, as shown by the curve 60A in FIG.
実際のキヤスクのバスケツト1は、一般に鋼が
材質として用いられその厚さは約8mmもあるので
これがこわれることはあり得ない。仮にこわれた
としても上記異常事故になるにはかなりの条件す
なわち燃料と水の混合の割合および燃料のキヤス
ク内への広がり具合等が合致しなければ臨界を越
えることが実現することはないと考えられるが、
万一の場合の異常事故を想定しているものであ
る。 Since the actual cask basket 1 is generally made of steel and has a thickness of about 8 mm, it is unlikely that it will break. Even if it were to break, in order for the abnormal accident mentioned above to occur, it is thought that exceeding criticality would not be achieved unless the conditions such as the mixing ratio of fuel and water and the extent to which the fuel spreads within the cask were met. ,
This assumes an abnormal accident in the unlikely event of an accident.
本発明は以上の事情に鑑みてなされたもので、
キヤスクの安全性をさらに増すために起り得べき
現象を想定し、これらのいかなる現象が発生して
もこれに十分対応できるキヤスクを提供するもの
である。すなわち、第1の目的はバスケツトがこ
われるという異常事故が起きないようにバスケツ
トの強度を増したキヤスクを得ることにある。第
2の目的は、万一バスケツトがこわれて上記異常
事故が起きても、キヤスク内が十分未臨界に保て
るように、核的特性の点から配慮したキヤスクを
得ることにある。 The present invention was made in view of the above circumstances, and
In order to further increase the safety of the cask, we assume possible phenomena and provide a cask that can sufficiently cope with any of these phenomena. That is, the first objective is to obtain a cask with increased strength of the basket so that abnormal accidents such as the basket breaking do not occur. The second objective is to obtain a cask with consideration given to nuclear properties so that even if the basket is broken and the above-mentioned abnormal accident occurs, the inside of the cask can be maintained at a sufficiently subcritical state.
以下図面を参照して本発明の一実施例を説明す
る。第2図において、第1図と同じ番号に対して
は説明を省略する。キヤスクの中空円筒4の内部
は、燃料保持枠3と、内部を一部中空21にし、
その中空部に水溶性でかつ中性子吸収断面積の大
きい物質(以下中性子吸収剤と呼ぶ)を入れた格
子状のバスケツト20で仕切られていて、その中
に中空角柱状のボトル2があり、このボトル2の
中に燃料集合体が収納されるようになつている。
第3図において、格子状のバスケツト20の内部
を一部中空21にし、その中に中性子吸収剤を入
れている。格子状のバスケツト20の内にはボト
ル2があり、その中に燃料集合体10が収納され
る。バスケツト20の他の部分には水3Aが満た
され、燃料集合体10より出る放射線を遮蔽し、
一方燃料集合体10を冷却する。中空21に充填
されている中性子吸収剤は、粉末または果粒状に
なつている。これは異常事故時に、すみやかに中
性子吸収剤が水中に拡散さらには溶解し、キヤス
クを未臨界に保つようにするためである。中性子
吸収剤としては、例えば五ほう酸ナトリウム等の
ほう酸を用いる。 An embodiment of the present invention will be described below with reference to the drawings. In FIG. 2, explanations for the same numbers as in FIG. 1 will be omitted. The interior of the hollow cylinder 4 of the cask includes a fuel holding frame 3 and a partially hollow interior 21,
The hollow part is partitioned by a lattice-shaped basket 20 containing a water-soluble substance with a large neutron absorption cross section (hereinafter referred to as a neutron absorber), and a hollow prismatic bottle 2 is placed inside the basket 20. A fuel assembly is housed in the bottle 2.
In FIG. 3, a lattice-shaped basket 20 is partially hollow 21, into which a neutron absorber is placed. A bottle 2 is disposed within a lattice-shaped basket 20, and a fuel assembly 10 is housed therein. The other part of the basket 20 is filled with water 3A to shield radiation emitted from the fuel assembly 10,
Meanwhile, the fuel assembly 10 is cooled. The neutron absorber filled in the hollow 21 is in the form of powder or granules. This is to ensure that in the event of an abnormal accident, the neutron absorber will quickly diffuse into the water and even dissolve, keeping the cask in a subcritical state. As the neutron absorber, for example, boric acid such as sodium pentaborate is used.
第4図は他の実施例のキヤスクである。第4図
において、バスケツト30の内部全体を中空31
にし、その中に中性子吸収剤を充填しているもの
である。バスケツト30の内部には、ボトル2を
設け、その中に燃料集合体10を入れ、そのまわ
りを水3Aが満たしている。 FIG. 4 shows a cask of another embodiment. In FIG. 4, the entire inside of the basket 30 is made into a hollow 31.
A neutron absorber is filled inside the neutron absorber. A bottle 2 is provided inside the basket 30, into which the fuel assembly 10 is placed, and its surroundings are filled with water 3A.
次にキヤスク作用を説明する。キヤスクは、バ
スケツト20の内部を中空にしたことにより、単
に板状のものよりも、全体の鋼性(引張、圧縮、
ねじり等)が大となり、より強い力に対しても耐
えれるものである。 Next, the cask action will be explained. By making the inside of the basket 20 hollow, the cask has better overall steel properties (tensile, compressive,
(torsion, etc.) and can withstand even stronger forces.
万一、バスケツトがこわれた場合でも、バスケ
ツト20の中空21に収納されている中性子吸収
剤がすみやかに水中に拡散し、さらには溶けて燃
料集合体10より発生する中性子を吸収する。そ
のため第5図に示すように、異常事故時において
もキヤスク内の実効増倍率は1.0を越えずキヤス
ク内を未臨界に保つておくことができる。 Even if the basket is broken, the neutron absorber stored in the hollow 21 of the basket 20 quickly diffuses into the water and further melts to absorb the neutrons generated from the fuel assembly 10. Therefore, as shown in FIG. 5, even in the event of an abnormal accident, the effective multiplication factor inside the cask does not exceed 1.0 and the inside of the cask can be kept subcritical.
従つて、通常時においてもより完全にキヤスク
内を未臨界に保つておくことができ、きわめて安
全性の高いものである。 Therefore, even during normal times, the inside of the cask can be more completely kept subcritical, resulting in extremely high safety.
第4図においては前述の第3図の例と同じ効果
があり、強度的にも充分であり、さらに製作がよ
り容易である。 The example shown in FIG. 4 has the same effects as the example shown in FIG. 3, has sufficient strength, and is easier to manufacture.
斯して本発明のキヤスクは、通常時のキヤスク
の安全性を増し、さらに異常事故も事前に起らな
いようにすることができるとともに、万一異常事
故が起きる場合でも、キヤスク内を未臨界に保つ
ことができるきわめて安全性の高いものである。 In this way, the cask of the present invention can increase the safety of the cask during normal times, prevent abnormal accidents from occurring in advance, and even if an abnormal accident occurs, the inside of the cask can be kept subcritical. It is extremely safe and can be maintained at high temperatures.
第1図は従来のキヤスクの断面図、第2図は本
発明のキヤスクの一実施例の断面図、第3図は第
2図のキヤスクの一部を詳細に示した断面図、第
4図は本発明の他の実施例のキヤスクの一部を詳
細に示した断面図、第5図はキヤスクの通常時と
異常事故時の実効増倍率(keff)の比較図であ
る。
20,30,40……バスケツト、21……中
性子吸収剤を入れる中空部分、31……中性子吸
収剤を入れる中空部分。
Fig. 1 is a sectional view of a conventional cask, Fig. 2 is a sectional view of an embodiment of the cask of the present invention, Fig. 3 is a sectional view showing a part of the cask in Fig. 2 in detail, and Fig. 4. 5 is a cross-sectional view showing in detail a part of a cask according to another embodiment of the present invention, and FIG. 5 is a comparison diagram of the effective multiplication factor (keff) of the cask during normal times and during an abnormal accident. 20, 30, 40...Basket, 21...Hollow part into which the neutron absorber is placed, 31...Hollow part into which the neutron absorber is placed.
Claims (1)
内側にフイン、容器本体、冷却水部、中空円筒の
順に収容して成る使用済燃料輸送容器において、
前記中空円筒の内部に水溶性でかつ中性子吸収断
面積の大きい中性子吸収剤を収納した格子状のバ
スケツトを収容し、このバスケツトの内部に使用
済燃料集合体を収納固定するボトルを収納し、前
記中空円筒の内部を水で満たして成ることを特徴
とする使用済燃料輸送容器。 2 バスケツトは、その構造材の内部を一部中空
にし、この中空部に水溶性でかつ中性子吸収断面
積の大きい中性子吸収剤を充填していることを特
徴とする特許請求の範囲第1項記載の使用済燃料
輸送容器。 3 バスケツトは、その構造材の内部を全て中空
にし、この中空部に水溶性でかつ中性子吸収断面
積の大きい中性子吸収剤を充填していることを特
徴とする特許請求の範囲第1項記載の使用済燃料
輸送容器。 4 水溶性でかつ中性子吸収断面積の大きい中性
子吸収剤は、粉末または果粒状にて形成されてい
ることを特徴とする特許請求の範囲第1項記載の
使用済燃料輸送容器。[Scope of Claims] 1. A spent fuel transport container whose outermost periphery is surrounded by a shock absorber, and in which a fin, a container main body, a cooling water section, and a hollow cylinder are housed in this order,
A lattice-shaped basket containing a water-soluble neutron absorbent having a large neutron absorption cross section is housed inside the hollow cylinder, a bottle for storing and fixing the spent fuel assembly is housed inside this basket, and the A spent fuel transport container comprising a hollow cylinder filled with water. 2. According to claim 1, the basket is characterized in that the inside of its structural material is partially hollow, and this hollow part is filled with a neutron absorbent that is water-soluble and has a large neutron absorption cross section. spent fuel transport container. 3. The basket according to claim 1, wherein the inside of the structural material is entirely hollow, and the hollow part is filled with a neutron absorbent that is water-soluble and has a large neutron absorption cross section. Spent fuel transport container. 4. The spent fuel transport container according to claim 1, wherein the water-soluble neutron absorber having a large neutron absorption cross section is formed in the form of powder or granules.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP402577A JPS5390597A (en) | 1977-01-19 | 1977-01-19 | Transporting container of used fuel |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP402577A JPS5390597A (en) | 1977-01-19 | 1977-01-19 | Transporting container of used fuel |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS5390597A JPS5390597A (en) | 1978-08-09 |
| JPS6122800B2 true JPS6122800B2 (en) | 1986-06-03 |
Family
ID=11573412
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP402577A Granted JPS5390597A (en) | 1977-01-19 | 1977-01-19 | Transporting container of used fuel |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPS5390597A (en) |
Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| ES8602291A1 (en) * | 1983-11-25 | 1985-12-01 | Nuklear Service Gmbh Gns | Apparatus for the storage and transport of radioactive materials |
| US4780268A (en) * | 1984-06-13 | 1988-10-25 | Westinghouse Electric Corp. | Neutron absorber articles |
| JP2011247701A (en) | 2010-05-25 | 2011-12-08 | Mitsubishi Heavy Ind Ltd | Radioactive material containment |
| JP5787813B2 (en) * | 2012-03-29 | 2015-09-30 | 三菱重工業株式会社 | Radioactive material containment vessel |
-
1977
- 1977-01-19 JP JP402577A patent/JPS5390597A/en active Granted
Also Published As
| Publication number | Publication date |
|---|---|
| JPS5390597A (en) | 1978-08-09 |
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