RU2008108671A - METHOD FOR PRODUCING NUCLEAR REACTOR HEAT FUEL ELEMENTS - Google Patents
METHOD FOR PRODUCING NUCLEAR REACTOR HEAT FUEL ELEMENTS Download PDFInfo
- Publication number
- RU2008108671A RU2008108671A RU2008108671/02A RU2008108671A RU2008108671A RU 2008108671 A RU2008108671 A RU 2008108671A RU 2008108671/02 A RU2008108671/02 A RU 2008108671/02A RU 2008108671 A RU2008108671 A RU 2008108671A RU 2008108671 A RU2008108671 A RU 2008108671A
- Authority
- RU
- Russia
- Prior art keywords
- welding
- shell
- fuel element
- plug
- voltage values
- Prior art date
Links
Classifications
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- 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
- Butt Welding And Welding Of Specific Article (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
1. Способ изготовления тепловыделяющих элементов ядерного реактора, включающий фиксацию конца оболочки тепловыделяющего элемента, установленного с заглублением, в сварочной оснастке, приварку, по крайней мере, к одному из торцов оболочки тепловыделяющего элемента заглушки контактно-стыковой сваркой при задаваемом режиме сварки и одновременное перемещение заглушки вовнутрь оболочки на участке, прогретом сварочным током, и последующий контроль наружного грата по периметру сварного соединения, отличающийся тем, что торец установленного в сварочной оснастке конца заглушки фиксируют относительно торца сварочной оснастки в задаваемом положении, в процессе перемещения заглушки вовнутрь оболочки производят контроль величины напряжения на участке вторичного контура сварочной установки, образованного сварочной оснасткой с размещенным в ней концом оболочки тепловыделяющего элемента, и сравнивают полученные значения напряжения со значениями напряжения, характерными для условий оптимального разогрева свариваемых деталей при аналогичном расположении торца оболочки тепловыделяющего элемента в сварочной оснастке, а по разнице полученных значений судят о качестве сварки и стабильности процесса герметизации. ! 2. Способ по п.1, отличающийся тем, что разницу значений напряжений, полученных на участке вторичного контура сварочной установки, и значений напряжения, характерных для условий оптимального разогрева свариваемых деталей, определяют в моменты начала и конца процесса перемещения заглушки вовнутрь оболочки тепловыделяющего элемента. ! 3. Способ по п.1, отличающийся тем, что значения напряжений на участ1. A method of manufacturing fuel elements of a nuclear reactor, including fixing the end of the shell of the fuel element installed with burial in the welding equipment, welding, at least to one of the ends of the shell of the fuel element, the plug by butt-butt welding at the specified welding mode and simultaneously moving the plug inside the shell in the area heated by the welding current, and the subsequent control of the external burr along the perimeter of the welded joint, characterized in that the end of the end of the plug installed in the welding equipment is fixed relative to the end of the welding equipment in a given position, while moving the plug into the shell, the voltage value is monitored on the section of the secondary circuit of the welding installation formed by the welding equipment with the end of the shell of the fuel element placed in it, and the obtained voltage values are compared with the voltage values typical for the conditions of optimal heating for the parts to be welded with a similar location of the end face of the shell of the fuel element in the welding equipment, and the difference in the obtained values is used to judge the quality of welding and the stability of the sealing process. ! 2. The method according to claim 1, characterized in that the difference between the stress values obtained in the section of the secondary circuit of the welding unit and the voltage values characteristic of the conditions for optimal heating of the welded parts is determined at the moments of the beginning and end of the process of moving the plug into the shell of the fuel element. ! 3. The method according to claim 1, characterized in that the voltage values in the section
Claims (3)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
RU2008108671/02A RU2381881C2 (en) | 2008-03-05 | 2008-03-05 | Manufacturing method of nuclear fuel elements |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
RU2008108671/02A RU2381881C2 (en) | 2008-03-05 | 2008-03-05 | Manufacturing method of nuclear fuel elements |
Publications (2)
Publication Number | Publication Date |
---|---|
RU2008108671A true RU2008108671A (en) | 2009-09-10 |
RU2381881C2 RU2381881C2 (en) | 2010-02-20 |
Family
ID=41166179
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
RU2008108671/02A RU2381881C2 (en) | 2008-03-05 | 2008-03-05 | Manufacturing method of nuclear fuel elements |
Country Status (1)
Country | Link |
---|---|
RU (1) | RU2381881C2 (en) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU174885U1 (en) * | 2016-10-03 | 2017-11-09 | Общество С Ограниченной Ответственностью "Окб "Булат" | PLUG WELDING MACHINE WITH LONG PIPES |
EP4141890A4 (en) | 2021-05-31 | 2023-06-14 | Joint-Stock Company "TVEL" | Fuel element for a water-cooled water-moderated nuclear reactor |
-
2008
- 2008-03-05 RU RU2008108671/02A patent/RU2381881C2/en active
Also Published As
Publication number | Publication date |
---|---|
RU2381881C2 (en) | 2010-02-20 |
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