JPH0348800U - - Google Patents
Info
- Publication number
- JPH0348800U JPH0348800U JP1989109665U JP10966589U JPH0348800U JP H0348800 U JPH0348800 U JP H0348800U JP 1989109665 U JP1989109665 U JP 1989109665U JP 10966589 U JP10966589 U JP 10966589U JP H0348800 U JPH0348800 U JP H0348800U
- Authority
- JP
- Japan
- Prior art keywords
- cladding tube
- coil spring
- end plug
- control rod
- neutron absorber
- 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.)
- Pending
Links
- 238000005253 cladding Methods 0.000 claims description 9
- 239000006096 absorbing agent Substances 0.000 claims description 7
- 230000006835 compression Effects 0.000 claims 1
- 238000007906 compression Methods 0.000 claims 1
- 230000001788 irregular Effects 0.000 claims 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 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
第１図は第１の考案に従つた制御棒の縦断面図
、第２図は第１図の制御棒に用いられているスリ
ーブを示す一部切欠き側面図、第３図は第２の考
案に従つた制御棒の縦断面図、第４図は第３図の
−線に沿つての断面図、第５図は加圧水型原
子炉用の代表的な制御棒組立体の側面図、第６図
は従来の制御棒の縦断面図、第７図は第６図の
−線に沿つての断面図である。図中、
１……制御棒組立体、５……被覆管、６……中
性子吸収体、７……下部端栓、８……上部端栓、
９，２１……コイルスプリング、１０，２０……
制御棒、１１……スリーブ。
Fig. 1 is a longitudinal cross-sectional view of the control rod according to the first invention, Fig. 2 is a partially cutaway side view showing the sleeve used in the control rod of Fig. 1, and Fig. 3 is a longitudinal sectional view of the control rod according to the first invention. FIG. 4 is a cross-sectional view taken along line - in FIG. 3; FIG. 5 is a side view of a typical control rod assembly for a pressurized water reactor; FIG. 6 is a longitudinal sectional view of a conventional control rod, and FIG. 7 is a sectional view taken along the line - in FIG. In the figure, 1... control rod assembly, 5... cladding tube, 6... neutron absorber, 7... lower end plug, 8... upper end plug,
9,21...Coil spring, 10,20...
Control rod, 11...sleeve.
Claims (1)
収体と、前記被覆管の上端及び下端をそれぞれ閉
じる上部端栓及び下部端栓と、前記上部端栓及び
前記中性子吸収体の間に配置されたコイルスプリ
ングとを備えている原子炉用の制御棒において、
外径が前記中性子吸収体の外径とほぼ同一であり
且つ全長がプラント運転中における前記コイルス
プリングの最大圧縮時の全長とほぼ同一である円
筒形のスリーブを、前記被覆管と前記コイルスプ
リングとの間に配設したことを特徴とする原子炉
用の制御棒。 ２ 被覆管と、該被覆管内に収容された中性子吸
収体と、前記被覆管の上端及び下端をそれぞれ閉
じる上部端栓及び下部端栓と、前記上部端栓及び
前記中性子吸収体の間に配置されたコイルスプリ
ングとを備えている原子炉用の制御棒において、
前記被覆管と前記コイルスプリングとが接触した
場合に、当該接触が面接触となるように、前記コ
イルスプリングの断面を異形断面としたことを特
徴とする原子炉用の制御棒。[Claims for Utility Model Registration] 1. A cladding tube, a neutron absorber housed in the cladding tube, an upper end plug and a lower end plug that close the upper and lower ends of the cladding tube, respectively, and the upper end plug and the A control rod for a nuclear reactor comprising a coil spring disposed between neutron absorbers,
A cylindrical sleeve having an outer diameter that is approximately the same as the outer diameter of the neutron absorber and a total length that is approximately the same as the total length of the coil spring at maximum compression during plant operation is attached to the cladding tube and the coil spring. A control rod for a nuclear reactor, characterized in that the control rod is disposed between the control rods. 2. A cladding tube, a neutron absorber housed in the cladding tube, an upper end plug and a lower end plug that close the upper and lower ends of the cladding tube, respectively, and a neutron absorber disposed between the upper end plug and the neutron absorber. In a control rod for a nuclear reactor equipped with a coil spring,
A control rod for a nuclear reactor, characterized in that the coil spring has an irregular cross section so that when the cladding tube and the coil spring come into contact, the contact becomes surface contact.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1989109665U JPH0348800U (en) | 1989-09-21 | 1989-09-21 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1989109665U JPH0348800U (en) | 1989-09-21 | 1989-09-21 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0348800U true JPH0348800U (en) | 1991-05-10 |
Family
ID=31658241
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1989109665U Pending JPH0348800U (en) | 1989-09-21 | 1989-09-21 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0348800U (en) |
-
1989
- 1989-09-21 JP JP1989109665U patent/JPH0348800U/ja active Pending