GB2018421A - A device for measuring local power in a nuclear reactor fuel assembly - Google Patents
A device for measuring local power in a nuclear reactor fuel assemblyInfo
- Publication number
- GB2018421A GB2018421A GB7909545A GB7909545A GB2018421A GB 2018421 A GB2018421 A GB 2018421A GB 7909545 A GB7909545 A GB 7909545A GB 7909545 A GB7909545 A GB 7909545A GB 2018421 A GB2018421 A GB 2018421A
- Authority
- GB
- United Kingdom
- Prior art keywords
- gamma
- rod
- nuclear reactor
- fuel assembly
- local power
- 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.)
- Granted
Links
- 239000003758 nuclear fuel Substances 0.000 title 1
- 230000005855 radiation Effects 0.000 abstract 2
- 239000000446 fuel Substances 0.000 abstract 1
- 239000011261 inert gas Substances 0.000 abstract 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/112—Measuring temperature
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Measurement Of Radiation (AREA)
- Measuring Temperature Or Quantity Of Heat (AREA)
Abstract
The measuring devices comprises a thermally and electrically conducting rod 7 having a number of regions 9 along its length, each forming a gamma- radiation thermometer. Each region comprises a thermal bridge 8 and a cold source 9 formed respectively by thick and thin sections of the rod 7; gamma- radiation absorbed in the rod causes the temperature of the thicker section to rise relative to that of the thinner one. A pair of thermocouple junctions 14, 15 produce signals representing the temperature difference of the two sections, from which the power produced by the fuel pencils 2 near each gamma- thermometer region is deduced. The area 10 bounded by the optional sheath 7a may be filled with an inert gas or evacuated. <IMAGE>
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US05/888,881 US4298430A (en) | 1977-03-23 | 1978-03-21 | Apparatus for determining the local power generation rate in a nuclear reactor fuel assembly |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| GB2018421A true GB2018421A (en) | 1979-10-17 |
| GB2018421B GB2018421B (en) | 1982-12-01 |
Family
ID=25394096
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| GB7909545A Expired GB2018421B (en) | 1978-03-21 | 1979-03-19 | Device for measuring local power in a nuclesr reactor fuelassembly |
Country Status (9)
| Country | Link |
|---|---|
| JP (1) | JPS54158591A (en) |
| BE (1) | BE874866A (en) |
| DE (1) | DE2910927C2 (en) |
| ES (1) | ES478846A1 (en) |
| FR (1) | FR2420827A1 (en) |
| GB (1) | GB2018421B (en) |
| IT (1) | IT1118443B (en) |
| NO (1) | NO148577C (en) |
| SE (2) | SE449040B (en) |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2470381A1 (en) * | 1979-11-23 | 1981-05-29 | Electricite De France | Determining local state of fluid in pressure vessel - using thermoelectric heat detector to measure heat exchange coefft. |
| FR2498765A1 (en) * | 1981-01-29 | 1982-07-30 | Electricite De France | IMPROVED GAMMA RAY THERMOMETER FOR HIGH PRESSURE ENVIRONMENT |
| FR2499253A1 (en) * | 1981-01-30 | 1982-08-06 | Electricite De France | APPARATUS AND METHOD FOR IN SITU CALIBRATION OF GAMMA RAY THERMOMETER IN SERVICE IN A NUCLEAR REACTOR |
| EP0064008A1 (en) * | 1981-04-24 | 1982-11-03 | Electricite De France | Device for locally measuring the power in a nuclear reactor |
| EP0064446A1 (en) * | 1981-04-24 | 1982-11-10 | Electricite De France | Device for measuring the local power production in a nuclear reactor, and method to calibrate the device |
| EP0066516A1 (en) * | 1981-05-27 | 1982-12-08 | Electricite De France | Device for checking the coolant condition in a nuclear reactor |
| EP0157132A1 (en) * | 1984-03-20 | 1985-10-09 | Westinghouse Electric Corporation | Reactor monitoring assembly |
| US9251920B2 (en) | 2012-04-11 | 2016-02-02 | Ge-Hitachi Nuclear Energy America Llc | In-situ and external nuclear reactor severe accident temperature and water level probes |
Families Citing this family (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4411859A (en) * | 1979-06-13 | 1983-10-25 | Scandpower, Inc. | Gamma sensor having combined thermal bridge and centering means |
| US4411858A (en) * | 1981-01-30 | 1983-10-25 | Scandpower, Inc. | Power performance monitoring system for nuclear reactor fuel core |
| JPS57146195A (en) * | 1981-03-06 | 1982-09-09 | Tokyo Shibaura Electric Co | Nuclear reactor power detecting device |
| US4425297A (en) | 1981-06-23 | 1984-01-10 | Scandpower, Inc. | Gamma ray thermometer for boiling water reactor |
| JPS57203996A (en) * | 1981-06-10 | 1982-12-14 | Tokyo Shibaura Electric Co | Device for monitoring inside of reactor |
| JPS5851299U (en) * | 1981-10-05 | 1983-04-07 | 株式会社東芝 | Furnace monitoring device |
| ES2016934B3 (en) * | 1986-02-03 | 1990-12-16 | Siemens Ag | GAMMA THERMOMETER |
| JP3462885B2 (en) * | 1993-03-11 | 2003-11-05 | 株式会社東芝 | Reactor power measurement apparatus and method of manufacturing the same |
| US20130272469A1 (en) * | 2012-04-11 | 2013-10-17 | Ge-Hitachi Nuclear Energy Americas Llc | Device and method for reactor and containment monitoring |
| EP3170185B1 (en) * | 2014-07-14 | 2019-02-27 | Westinghouse Electric Company Llc | Thermo-acoustic nuclear power distribution measurement assembly |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR1437184A (en) * | 1964-06-16 | 1966-04-29 | Licentia Gmbh | Apparatus intended for the measurement of a neutron flux |
| FR2385187A1 (en) * | 1977-03-23 | 1978-10-20 | Electricite De France | LOCAL POWER MEASUREMENT DEVICE IN A NUCLEAR REACTOR FUEL ASSEMBLY |
| US4149932A (en) * | 1977-03-25 | 1979-04-17 | Westinghouse Electric Corp. | Emergency disconnect means for the manipulator arm of a nuclear reactor vessel inspection apparatus |
-
1978
- 1978-05-22 NO NO781773A patent/NO148577C/en unknown
-
1979
- 1979-03-06 FR FR7905739A patent/FR2420827A1/en active Granted
- 1979-03-15 BE BE0/194039A patent/BE874866A/en not_active IP Right Cessation
- 1979-03-19 SE SE7902418A patent/SE449040B/en not_active IP Right Cessation
- 1979-03-19 GB GB7909545A patent/GB2018421B/en not_active Expired
- 1979-03-20 JP JP3313979A patent/JPS54158591A/en active Granted
- 1979-03-20 DE DE2910927A patent/DE2910927C2/en not_active Expired
- 1979-03-20 IT IT7967579A patent/IT1118443B/en active
- 1979-03-21 ES ES478846A patent/ES478846A1/en not_active Expired
-
1984
- 1984-04-04 SE SE8401872A patent/SE458405B/en not_active IP Right Cessation
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2470381A1 (en) * | 1979-11-23 | 1981-05-29 | Electricite De France | Determining local state of fluid in pressure vessel - using thermoelectric heat detector to measure heat exchange coefft. |
| FR2498765A1 (en) * | 1981-01-29 | 1982-07-30 | Electricite De France | IMPROVED GAMMA RAY THERMOMETER FOR HIGH PRESSURE ENVIRONMENT |
| FR2499253A1 (en) * | 1981-01-30 | 1982-08-06 | Electricite De France | APPARATUS AND METHOD FOR IN SITU CALIBRATION OF GAMMA RAY THERMOMETER IN SERVICE IN A NUCLEAR REACTOR |
| EP0064008A1 (en) * | 1981-04-24 | 1982-11-03 | Electricite De France | Device for locally measuring the power in a nuclear reactor |
| EP0064446A1 (en) * | 1981-04-24 | 1982-11-10 | Electricite De France | Device for measuring the local power production in a nuclear reactor, and method to calibrate the device |
| EP0066516A1 (en) * | 1981-05-27 | 1982-12-08 | Electricite De France | Device for checking the coolant condition in a nuclear reactor |
| EP0157132A1 (en) * | 1984-03-20 | 1985-10-09 | Westinghouse Electric Corporation | Reactor monitoring assembly |
| US4708844A (en) * | 1984-03-20 | 1987-11-24 | Westinghouse Electric Corp. | Reactor monitoring assembly |
| US9251920B2 (en) | 2012-04-11 | 2016-02-02 | Ge-Hitachi Nuclear Energy America Llc | In-situ and external nuclear reactor severe accident temperature and water level probes |
Also Published As
| Publication number | Publication date |
|---|---|
| JPS6161360B2 (en) | 1986-12-25 |
| NO781773L (en) | 1979-09-24 |
| FR2420827B1 (en) | 1984-12-07 |
| IT1118443B (en) | 1986-03-03 |
| SE8401872D0 (en) | 1984-04-04 |
| FR2420827A1 (en) | 1979-10-19 |
| JPS54158591A (en) | 1979-12-14 |
| SE449040B (en) | 1987-03-30 |
| DE2910927C2 (en) | 1986-05-07 |
| ES478846A1 (en) | 1979-12-16 |
| IT7967579A0 (en) | 1979-03-20 |
| GB2018421B (en) | 1982-12-01 |
| NO148577B (en) | 1983-07-25 |
| SE7902418L (en) | 1979-09-22 |
| SE458405B (en) | 1989-03-20 |
| DE2910927A1 (en) | 1979-10-11 |
| BE874866A (en) | 1979-07-02 |
| SE8401872L (en) | 1984-04-04 |
| NO148577C (en) | 1983-11-09 |
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Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PCNP | Patent ceased through non-payment of renewal fee |