JPH0193596U - - Google Patents
Info
- Publication number
- JPH0193596U JPH0193596U JP1987188781U JP18878187U JPH0193596U JP H0193596 U JPH0193596 U JP H0193596U JP 1987188781 U JP1987188781 U JP 1987188781U JP 18878187 U JP18878187 U JP 18878187U JP H0193596 U JPH0193596 U JP H0193596U
- Authority
- JP
- Japan
- Prior art keywords
- nuclear fuel
- cylindrical member
- heat generation
- neutron absorption
- generation device
- 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
- 239000003758 nuclear fuel Substances 0.000 claims description 9
- 238000010521 absorption reaction Methods 0.000 claims description 7
- 239000000463 material Substances 0.000 claims description 7
- 230000020169 heat generation Effects 0.000 claims description 6
- 238000010586 diagram Methods 0.000 description 2
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
- Particle Accelerators (AREA)
Description
第１Ａ図はこの考案の一実施例に係る核燃料発
熱可変装置のの要部を示した断面図、第１Ｂ図は
第１Ａ図のＢ―Ｂ断面図、第２図は装置全体の説
明図、第３Ａ図は円筒部材の断面図で、第３Ｂ図
は第３Ａ図のＢ―Ｂ断面図で、第４図は上記の装
置の動作説明図である。第５Ａ図は従来の装置の
断面図、第５Ｂ図は第５Ａ図のＢ―Ｂ断面図であ
る。
１：試験・研究用原子炉の炉心、２：反射体領
域、３：原子炉支持板、４：原子炉支持架台、５
：原子炉プール、６：遮蔽壁、７：核燃料試験容
器、８：核燃料、９：円筒部材、９―１：中性子
吸収の小さな材料、９―２：中性子吸収の大きな
材料、９―３：回転軸受、９―４：回転駆動の連
結部、１０：駆動連結管、１１：駆動連結管用回
転軸受、１２：回転駆動の連結部、１３：駆動軸
、１４：回転軸受、１５：駆動軸案内管、１６：
電動機、１７：電線、１８：電動機制御装置、１
９：連結棒、２０：ピストン。
FIG. 1A is a sectional view showing the main parts of a variable nuclear fuel heat generation device according to an embodiment of this invention, FIG. 1B is a sectional view taken along line BB in FIG. 1A, and FIG. 2 is an explanatory diagram of the entire device. FIG. 3A is a sectional view of the cylindrical member, FIG. 3B is a sectional view taken along the line BB in FIG. 3A, and FIG. 4 is an explanatory diagram of the operation of the above device. FIG. 5A is a sectional view of a conventional device, and FIG. 5B is a sectional view taken along line BB in FIG. 5A. 1: Core of test/research reactor, 2: Reflector area, 3: Reactor support plate, 4: Reactor support frame, 5
: Reactor pool, 6: Shielding wall, 7: Nuclear fuel test vessel, 8: Nuclear fuel, 9: Cylindrical member, 9-1: Material with low neutron absorption, 9-2: Material with high neutron absorption, 9-3: Rotation Bearing, 9-4: Rotation drive connection part, 10: Drive connection pipe, 11: Rotation bearing for drive connection pipe, 12: Rotation drive connection part, 13: Drive shaft, 14: Rotation bearing, 15: Drive shaft guide pipe , 16:
Electric motor, 17: Electric wire, 18: Motor control device, 1
9: connecting rod, 20: piston.
Claims (1)
み合わせて構成した円筒部材を有し、この円筒部
材内に核燃料を配置し、更にこの円筒部材を回転
又は揺動自在に支持したことを特徴とする核燃料
発熱可変装置。 (2) 中性子吸収の小さな材料で構成された円筒
部材に、中性子吸収の大きな材料を局部的に配し
た実用新案登録請求の範囲第１項記載の核燃料発
熱可変装置。 (3) 中性子吸収の大きな材料で構成された円筒
部材に、中性子吸収の小さな材料を局部的に配し
た実用新案登録請求の範囲第１項記載の核燃料発
熱可変装置。 (4) 円筒部材は回転若しくは揺動の速度又は移
動範囲が制御され、核燃料に任意の発熱変化を与
える機能を備えたものである実用新案登録請求の
範囲第１項記載の核燃料発熱可変装置。[Claims for Utility Model Registration] (1) It has a cylindrical member constructed by combining materials with different neutron absorption capacities in the circumferential direction, and nuclear fuel is arranged within this cylindrical member, and further this cylindrical member is rotated or oscillated. A variable nuclear fuel heat generation device characterized by being freely supported. (2) The variable nuclear fuel heat generation device according to claim 1, which is a utility model registration, in which a cylindrical member made of a material with low neutron absorption and a material with high neutron absorption locally arranged therein. (3) The variable nuclear fuel heat generation device according to claim 1, wherein a cylindrical member made of a material with high neutron absorption and a material with low neutron absorption locally arranged therein. (4) The variable nuclear fuel heat generation device according to claim 1, wherein the cylindrical member has a function of controlling the rotational or swinging speed or movement range and giving arbitrary heat generation changes to the nuclear fuel.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1987188781U JPH0193596U (en) | 1987-12-14 | 1987-12-14 |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP1987188781U JPH0193596U (en) | 1987-12-14 | 1987-12-14 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| JPH0193596U true JPH0193596U (en) | 1989-06-20 |
Family
ID=31479853
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP1987188781U Pending JPH0193596U (en) | 1987-12-14 | 1987-12-14 |
Country Status (1)
| Country | Link |
|---|---|
| JP (1) | JPH0193596U (en) |
-
1987
- 1987-12-14 JP JP1987188781U patent/JPH0193596U/ja active Pending
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