JPS6233558B2 - - Google Patents
Info
- Publication number
- JPS6233558B2 JPS6233558B2 JP54033715A JP3371579A JPS6233558B2 JP S6233558 B2 JPS6233558 B2 JP S6233558B2 JP 54033715 A JP54033715 A JP 54033715A JP 3371579 A JP3371579 A JP 3371579A JP S6233558 B2 JPS6233558 B2 JP S6233558B2
- Authority
- JP
- Japan
- Prior art keywords
- powder
- rod
- neutron
- capsule
- plug member
- 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
- 239000000843 powder Substances 0.000 claims description 25
- 239000002775 capsule Substances 0.000 claims description 14
- 238000010521 absorption reaction Methods 0.000 claims description 11
- 239000011358 absorbing material Substances 0.000 claims description 10
- 238000004891 communication Methods 0.000 claims description 3
- -1 B 4 C Substances 0.000 claims 1
- 230000002745 absorbent Effects 0.000 description 9
- 239000002250 absorbent Substances 0.000 description 9
- 229920000742 Cotton Polymers 0.000 description 4
- 239000000463 material Substances 0.000 description 4
- 239000001307 helium Substances 0.000 description 3
- 229910052734 helium Inorganic materials 0.000 description 3
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 238000004519 manufacturing process Methods 0.000 description 2
- 239000006096 absorbing agent Substances 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- 238000007796 conventional method Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 239000007789 gas Substances 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 238000012856 packing Methods 0.000 description 1
- 239000008188 pellet Substances 0.000 description 1
- 230000035699 permeability Effects 0.000 description 1
- 238000012545 processing Methods 0.000 description 1
- 125000006850 spacer group Chemical group 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Description
【発明の詳細な説明】
本発明は、原子炉制御棒の構成要素として備え
られる中性子吸収棒に係り、中性子吸収材として
充填されるB4C粉末を全長に亘つて均一な密度に
配分し、原子炉の制御をより正確に言ない得るよ
うにした中性子吸収棒に関する。DETAILED DESCRIPTION OF THE INVENTION The present invention relates to a neutron absorption rod provided as a component of a nuclear reactor control rod, in which B 4 C powder filled as a neutron absorption material is distributed at a uniform density over the entire length, This invention relates to a neutron absorption rod that enables more accurate control of nuclear reactors.
一般に、高速増殖炉(FBR)においては原子
炉制御棒の中性子吸収材としてB4Cを焼結しペレ
ツト状としたものが用いられ、一方、沸騰水型原
子炉(BWR)、加圧水型原子炉(PWR)等の軽
水炉においては粉末のB4Cが吸収材として用いら
れている。この差異は、主に経済的な理由に基づ
くものであり、吸収材としての粉末のB4Cを用い
る方が安価である。 Generally, in fast breeder reactors (FBRs), sintered B4C pellets are used as the neutron absorbing material for reactor control rods, while in boiling water reactors (BWRs), pressurized water reactors, In light water reactors such as (PWR), powdered B 4 C is used as an absorbent. This difference is mainly based on economic reasons, as it is cheaper to use powdered B4C as absorbent.
ところで、吸収材として粉末のB4Cを用いる従
来の中性子吸収棒においては、B4Cを粉末の状態
で直接充填したが、小径管状の中性子吸収棒に粉
末を詰める方法は容易でなく、全長に亘つて重点
密度が均一にならないので原子炉の正確な制御を
困難にする欠点があつた。さらに、長時間使用し
ているとB4C粉末は下方に偏り、上方に隙間がで
きることがあり、原子炉制御に支障をきたすこと
もある。この下方への偏りを防ぐためには、第1
図に示すように、B4C粉末と一しよに金属ボール
a,aをいくつか挿入し、これらを吸収棒bの外
側から凹成形したくぼみc,cによつて等間隔に
配置し、粉末の下方への移動を抑止するようにし
ているが、充分でなく、また製造方法が複雑にな
る新たな欠点を生ずるものであつた。 By the way, in conventional neutron absorption rods that use powdered B 4 C as an absorbing material, B 4 C is directly filled in the powder state, but it is not easy to pack powder into a small diameter tubular neutron absorption rod, and the entire length Since the focal density was not uniform over the period, it had the disadvantage of making accurate control of the reactor difficult. Furthermore, if used for a long time, the B 4 C powder may shift downward, creating a gap at the top, which may interfere with reactor control. In order to prevent this downward bias, the first step is to
As shown in the figure, several metal balls a, a are inserted together with the B 4 C powder, and these are arranged at equal intervals by recesses c, c formed from the outside of the absorption rod b. Although attempts have been made to prevent the powder from moving downward, this is not sufficient and also creates new drawbacks that complicate the manufacturing method.
本発明は以上の欠点を解消するもので、全長に
わたつてB4C等の中性子吸収材の粉末が均一密度
で充填され、使用中に上方に隙間ができず、また
くぼみなどの加工を要しない簡単な構造になる改
良された中性子吸収棒を提供することを目的とす
る。 The present invention solves the above-mentioned drawbacks, and the entire length is filled with powder of neutron absorbing material such as B 4 C at a uniform density, so that there is no upper gap during use, and processing such as recesses is required. The purpose of the present invention is to provide an improved neutron absorbing rod that has a simple structure.
以下添付図面を参照して本発明の一実施例につ
いて説明する。 An embodiment of the present invention will be described below with reference to the accompanying drawings.
第2図は本発明の基本的構成を示す図であつ
て、中性子吸収材としてのB4C粉末が充填された
複数個のカプセル2が、筒状の棒材3内に同軸的
に積重ねて挿入され、棒体内の空気をヘリウムガ
ス4に置換した後に密封されている。 FIG. 2 is a diagram showing the basic configuration of the present invention, in which a plurality of capsules 2 filled with B 4 C powder as a neutron absorbing material are coaxially stacked inside a cylindrical bar 3. The rod is inserted, and after replacing the air inside the rod with helium gas 4, it is sealed.
ところで、上記カプセル2は、第3図に示すよ
うに、比較的短尺な容器5と粉末が通過しない程
の連通孔を有する通気性のある端栓部材6によつ
て構成され、上記容器5内に前記中性子吸収材で
あるB4C粉末を充填した後、上記端栓部材6を装
着固定することによつて上記吸収材粉末が密封さ
れている。上記端栓部材6としては、第4図に示
すように、細い針状を綿状にした綿体8を使用し
てもよく、その綿体8を容器5の上部開口部に装
着固定して内部の吸収材粉末が流出しないように
することもできる。しかして、上記端栓部材の通
気性によつてカプセル内の空気をヘリウムに置き
変えることができる。 By the way, as shown in FIG. 3, the capsule 2 is composed of a relatively short container 5 and an air permeable end plug member 6 having a communication hole large enough to prevent powder from passing through. After filling the neutron absorbing material with B 4 C powder, the end plug member 6 is attached and fixed to seal the absorbing material powder. As the end plug member 6, as shown in FIG. 4, a cotton material 8 made of a thin needle-like cotton material may be used, and the cotton material 8 is attached and fixed to the upper opening of the container 5. It is also possible to prevent the absorbent powder inside from flowing out. Thus, the air permeability of the end plug member allows the air within the capsule to be replaced by helium.
上記端栓部材6の通気性付与部分は、筒状棒体
3内に積重ねられたとき、上のカプセル2に下底
面で閉塞されないように、浮かして、重ねられる
ようにする。例えばスペーサの使用やカプセル下
端部に脚部を延設すると有効である。 When the end plug member 6 is stacked in the cylindrical rod 3, the breathable portion of the end plug member 6 is floated and stacked so as not to be blocked by the lower bottom surface of the upper capsule 2. For example, it is effective to use a spacer or extend a leg portion to the lower end of the capsule.
本発明中性子吸収棒は以上のように、B4C等の
中性子吸収材の粉末を通気性のある複数個のカプ
セルに充填するとともに、この複数個のカプセル
を筒状の棒体内に同軸的に積重ねているので、中
性子吸収棒内の吸収粉末の充填密度をその軸線方
向にほぼ均一にすることができる。しかも、中性
子吸収材は複数のカプセルによつて縦方向に複数
に完全に分離されているので、吸収材粉末は充填
されているカプセル内においてのみ移動が許容さ
れ、その密度は中性子吸収棒の輸送時および原子
炉内での長時間使用によつても上下位置での変動
が少く、従来のもののように全体的な吸収材粉末
が下方へ沈み上部に隙間ができるような心配がな
い。しかも、本発明においては粉末が通過しない
程の連通路を有する通気性の端栓部材を容器に装
着固定してあるので、輸送時に吸収棒を横にした
ような場合ででも、吸収材粉末がカプセル外に流
出することが確実に防止され、中性子吸収棒内で
の粉末の移動を防止することができる。従つて従
来のにように吸収棒に周方向のくぼみを設ける等
の必要がなく、製造方法が簡単になつて生産性が
よくコスト上も有利である。そして長い間減速粉
末の均一な密度を保持し、原子炉を正確に制御す
ることができる等の効果を奏する。 As described above, the neutron absorbing rod of the present invention has a plurality of air-permeable capsules filled with powder of a neutron absorbing material such as B 4 C, and the plurality of capsules are coaxially arranged inside a cylindrical rod. Since they are stacked, the packing density of the absorbing powder inside the neutron absorbing rod can be made almost uniform in the axial direction. Moreover, since the neutron absorbing material is completely separated into multiple pieces in the longitudinal direction by multiple capsules, the absorbing material powder is only allowed to move within the filled capsules, and its density is determined by the transport of the neutron absorbing rod. There is little fluctuation in the vertical position even when the absorber is used for a long time or in a nuclear reactor, and there is no worry that the entire absorbent powder will sink downward and create a gap at the top, unlike conventional absorbent absorbent powder. Moreover, in the present invention, a breathable end plug member having a communication path that prevents the powder from passing through is attached and fixed to the container, so even if the absorbent rod is placed horizontally during transportation, the absorbent powder will still be absorbed. It is reliably prevented from flowing out of the capsule, and movement of the powder within the neutron absorption rod can be prevented. Therefore, there is no need to provide a circumferential recess in the absorbing rod as in the conventional method, and the manufacturing method is simplified, resulting in good productivity and cost advantages. Furthermore, the uniform density of the moderator powder can be maintained for a long time, and the nuclear reactor can be controlled accurately.
第1図は従来の中性子吸収棒の縦断面図、第2
図は本発明中性子吸収棒の一実施態様を示す一部
縦断正面図、第3図および第4図はそれぞれ本発
明中性子吸収棒に用いるカプセルの各実施態様を
示す図である。
1……B4C粉末(吸収材粉末)、2……カプセ
ル、3……中性子吸収棒、4……ヘリウム、5…
…容器、6……端栓部材、8……綿体。
Figure 1 is a vertical cross-sectional view of a conventional neutron absorption rod;
The figure is a partially longitudinal front view showing one embodiment of the neutron absorbing rod of the present invention, and FIGS. 3 and 4 are views showing respective embodiments of capsules used in the neutron absorbing rod of the present invention. 1... B 4 C powder (absorbent powder), 2... Capsule, 3... Neutron absorption rod, 4... Helium, 5...
... Container, 6 ... End plug member, 8 ... Cotton body.
Claims (1)
の粉末を充填し、その粉末が通過しない程の連通
路を有する通気性端栓部材を装着固定したカプセ
ルを、筒状棒体内に同軸的に複数個積重ねて挿入
密封したことを特徴とする中性子吸収棒。1 A relatively short container is filled with powder of a neutron absorbing material such as B 4 C, and a capsule is fitted and fixed with an air-permeable end plug member that has a communication path large enough to prevent the powder from passing through, and the capsule is placed inside a cylindrical rod body. A neutron absorption rod characterized by multiple coaxially stacked, inserted and sealed neutron absorption rods.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP3371579A JPS55125481A (en) | 1979-03-22 | 1979-03-22 | Neutron absorbing rod |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
JP3371579A JPS55125481A (en) | 1979-03-22 | 1979-03-22 | Neutron absorbing rod |
Publications (2)
Publication Number | Publication Date |
---|---|
JPS55125481A JPS55125481A (en) | 1980-09-27 |
JPS6233558B2 true JPS6233558B2 (en) | 1987-07-21 |
Family
ID=12394098
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP3371579A Granted JPS55125481A (en) | 1979-03-22 | 1979-03-22 | Neutron absorbing rod |
Country Status (1)
Country | Link |
---|---|
JP (1) | JPS55125481A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH01110145U (en) * | 1988-01-19 | 1989-07-25 |
Families Citing this family (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
NO891551L (en) * | 1988-04-19 | 1989-10-20 | Gen Electric | NUCLEAR REACTOR CONTROL BAR WITH COVERED, NOYTRON Absorbent. |
JP4898005B2 (en) * | 2001-01-15 | 2012-03-14 | 三菱重工業株式会社 | Reactor control rod |
JP4909951B2 (en) * | 2008-07-14 | 2012-04-04 | 株式会社東芝 | Neutron shield |
-
1979
- 1979-03-22 JP JP3371579A patent/JPS55125481A/en active Granted
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPH01110145U (en) * | 1988-01-19 | 1989-07-25 |
Also Published As
Publication number | Publication date |
---|---|
JPS55125481A (en) | 1980-09-27 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US4636352A (en) | Nuclear fuel rod with burnable plate and pellet-clad interaction fix | |
JPH02232591A (en) | Fuel rod for nuclear reactor fuel assembly | |
JPS6245510B2 (en) | ||
JP2580292B2 (en) | Transport container for core components | |
GB1130015A (en) | Improvements in or relating to fuel for nuclear reactors | |
JPS6290596A (en) | Control rod for different kind of neutron absorber of fuel aggregate | |
US6002735A (en) | Nuclear fuel pellet | |
JPS6233558B2 (en) | ||
GB1191806A (en) | Single Fluid Molten Salt Nuclear Breeder Reactor | |
KR20220076477A (en) | Modular radioisotope production capsules and related methods | |
US4696793A (en) | Burnable poison rod for use in a nuclear reactor | |
JPS62168092A (en) | Burnable thermal neutron absorption element | |
JPH0213888A (en) | Controller for nuclear reactor capsulated with neutron absorbing substance | |
JP2016080667A (en) | Fuel assembly for fast reactor and fast reactor core | |
US3252868A (en) | Fuel element for use in nuclear reactors | |
JPS6051071B2 (en) | Control rod for nuclear reactor | |
JP2565861B2 (en) | Fuel assembly for boiling water reactor | |
JPH1048375A (en) | Control material for nuclear system and control rod for reactor | |
US4762673A (en) | Burnable poison rod for use in a nuclear reactor | |
JP3825050B2 (en) | Actinide combustion fuel elements | |
JPS58113785A (en) | Nuclear fuel assembly | |
JPS5855886A (en) | Control rod of reactor | |
JPH041593A (en) | Fuel assembly | |
JPS54150582A (en) | Fuel assembly | |
JPH0422892A (en) | Fuel assembly |