DE2910927C2 - Device for measuring the local power in a fuel assembly of a nuclear reactor - Google Patents
Device for measuring the local power in a fuel assembly of a nuclear reactorInfo
- Publication number
- DE2910927C2 DE2910927C2 DE2910927A DE2910927A DE2910927C2 DE 2910927 C2 DE2910927 C2 DE 2910927C2 DE 2910927 A DE2910927 A DE 2910927A DE 2910927 A DE2910927 A DE 2910927A DE 2910927 C2 DE2910927 C2 DE 2910927C2
- Authority
- DE
- Germany
- Prior art keywords
- rod
- zones
- protective tube
- constriction
- expansion
- 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
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
Description
sehen, wobei die Warm-Verbindungsstellen der Thermoelemente in der Mitte der Verengungszone und die Kalt-Verbindungsstellen der Thermoelemente in dersee the warm junctions of the thermocouples in the middle of the constriction zone and the cold junctions of the thermocouples in the
Ein Problem besteht bei einer derartigen Vorrichtung darin, daß sich das aufgenommene Meßsignal im Laufe der Zeit verändert, ohne daß Änderungen der zu ermittelnden Leistung vorliegen.One problem with such a device is that the recorded measurement signal changes in the course of the process changes over time without any changes in the performance to be determined.
Die Aufgabe der Erfindung besteht daher darin, eine Vorrichtung zur Messung der örtlichen Leistung in einer Brennstoffanordnung eines Kernreaktors anzuge-The object of the invention is therefore to provide a device for measuring the local power in a Fuel assembly of a nuclear reactor
bekannt sind.are known.
In der voranstehenden Gleichung bedeuten L die Hälfte der Länge der Verengungszonen 9 und K die Wärmeleitfähigkeit des Stabes 7.In the above equation, L denotes half the length of the narrowing zones 9 and K denotes the thermal conductivity of the rod 7.
Es wurde festgestellt, daß bei der Schaffung eines Hochvakuums in den Isolierkammern 10 und bei Ausführung des Schutzrohres 50 aus austenitischem Stahl oder aus Nickel-Chrom-Legierungen im Laufe der Zeit Änderungen des aufgenommenen Signals auch dann festzustellen sind, wenn keine Änderungen der zu ermittelnden Leistung auftreten. Es ist herausgefunden worden, daß diese anomalen Schwankungen des Meßsignals auf die Tatsache zurückgehen, daß die genannten Materialien für Wasserstoffmoleküle sehr gut durchlässig sind und daß darüber hinaus diese Materialien bei Vorhandensein von Hochvakuum Wasserstoffmoleküle durch einen Entgasungsprozeß abgeben.It was found that in creating a High vacuum in the insulating chambers 10 and when the protective tube 50 is made of austenitic steel or from nickel-chromium alloys, changes in the recorded signal over time also occur must be determined if there are no changes in the performance to be determined. It has been found out that these anomalous fluctuations in the measurement signal are due to the fact that the materials mentioned are very permeable to hydrogen molecules and that these materials are also present if they are present release hydrogen molecules from high vacuum through a degassing process.
Bei einer Vorrichtung, bei der das Schutzrohr 50 aus austenitischem Stahl besteht und bei der die Isofierkammern 10 ein Hochvakuum von 10~6 bar aufweisen, zeigt sich am Ende einer Betriebsdauer von einigen Stunden in einem Druckwasserreaktor eine Änderung des Meßsignals, die einer Abnahme von 400C auf 19° C entspricht. Der Druck nimmt dabei auf 10~5 oder sogar auf \Q-' bar infolge der Durchlässigkeit des Schuizrohres 50 und aufgrund der Entgasungserscheinungen ab. Um derartige Phänomene zu verhindern wird das Schutzrohr 50 nunmehr so ausgebildet, daß die Vorrichtung so dicht ist, daß ein Hochvakuum in der Größenordnung von 10~6 bar in den Isolierkammern 10 aufrechterhalten wird. Dazu weist das Schutzrohr 50 zwei Schichten, d. h. eine äußere Schicht 50a aus rostfreiem Stahl, die einen mechanischen Widerstand bewirkt bzw. äußere mechanische Spannungen absorbiert, und eine innere Schicht 50b auf, die eine Wasserstoffbarriere bildet und aus einer Zirkonlegierung besteht, um das Hochvakuum auf- w rechtzuerhalten. Zirkonlegierungen werden in Kernreaktoren häufig verwendet. Das Oxid der Zirkonlegierungen ist in hohem Maße wasserstoffundurchlässig. Das Material selbst absorbiert die Wasserstoffmoleküle bei hoher Temperatur unter Bildung von Zirkonhydrid.In a device in which the protective tube 50 is made of austenitic steel and in which the insulating chambers 10 have a high vacuum of 10 ~ 6 bar, at the end of an operating period of a few hours in a pressurized water reactor there is a change in the measurement signal that corresponds to a decrease of 40 0 C to 19 ° C. The pressure takes up to 10 ~ 5, or even on \ Q 'bar due to the permeability of the Schuizrohres 50 and due to the Entgasungserscheinungen from. In order to prevent such phenomena, the protective tube 50 is now designed in such a way that the device is so tight that a high vacuum of the order of magnitude of 10 ~ 6 bar is maintained in the insulating chambers 10. For this purpose, the protective tube 50 has two layers, ie an outer layer 50a made of stainless steel, which creates a mechanical resistance or absorbs external mechanical stresses, and an inner layer 50b , which forms a hydrogen barrier and consists of a zirconium alloy, in order to maintain the high vacuum - w right. Zirconium alloys are widely used in nuclear reactors. The oxide of the zirconium alloys is highly impermeable to hydrogen. The material itself absorbs the hydrogen molecules at high temperature to form zirconium hydride.
Da ein thermischer Kontakt zwischen den Erweiterungszonen 8 des Stabes 7 und dem Schutzrohr 50 besteht, haben die Erweiterungszonen auch einen guten thermischen Kontakt zu dsm Kühlfluid des Reaktors.Since there is thermal contact between the expansion zones 8 of the rod 7 and the protective tube 50, the expansion zones also have good thermal contact with the cooling fluid of the reactor.
5050
Hierzu 1 Blatt Zeichnungen1 sheet of drawings
6060
Claims (1)
eine Vorrichtung zur Messung der örtlichen Leistung io
einer Brennstoffanordnung eines Kernreaktors beschrieben, bei der die Meßeinrichtung einen langge- ^ In the older patent application DE-OS 28 01 253 is
a device for measuring the local power io
a fuel assembly of a nuclear reactor described, in which the measuring device has a long ^
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 |
---|---|
DE2910927A1 DE2910927A1 (en) | 1979-10-11 |
DE2910927C2 true DE2910927C2 (en) | 1986-05-07 |
Family
ID=25394096
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
DE2910927A Expired DE2910927C2 (en) | 1978-03-21 | 1979-03-20 | Device for measuring the local power in a fuel assembly of a nuclear reactor |
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) |
Families Citing this family (17)
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 |
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. |
US4459045A (en) * | 1981-01-29 | 1984-07-10 | Scandpower, Inc. | Gamma thermometer with zircaloy barrier |
US4440716A (en) * | 1981-01-30 | 1984-04-03 | Scandpower, Inc. | In-situ calibration of local power measuring devices for nuclear reactors |
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 |
US4439396A (en) * | 1981-04-24 | 1984-03-27 | Scandpower, Inc. | Multijunction difference thermocouples for gamma sensors |
DE3271335D1 (en) * | 1981-04-24 | 1986-07-03 | Electricite De France | Device for measuring the local power production in a nuclear reactor, and method to calibrate the device |
US4418035A (en) * | 1981-05-27 | 1983-11-29 | Scandpower, Inc. | Coolant condition monitor for nuclear power 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 |
US4708844A (en) * | 1984-03-20 | 1987-11-24 | Westinghouse Electric Corp. | Reactor monitoring assembly |
DE3764525D1 (en) * | 1986-02-03 | 1990-10-04 | Siemens Ag | Gammathermometer. |
JP3462885B2 (en) * | 1993-03-11 | 2003-11-05 | 株式会社東芝 | Reactor power measurement apparatus and method of manufacturing the same |
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 |
US20130272469A1 (en) * | 2012-04-11 | 2013-10-17 | Ge-Hitachi Nuclear Energy Americas Llc | Device and method for reactor and containment monitoring |
CN106471583B (en) * | 2014-07-14 | 2018-03-09 | 西屋电气有限责任公司 | Thermoacoustic formula core 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 GB GB7909545A patent/GB2018421B/en not_active Expired
- 1979-03-19 SE SE7902418A patent/SE449040B/en not_active IP Right Cessation
- 1979-03-20 DE DE2910927A patent/DE2910927C2/en not_active Expired
- 1979-03-20 JP JP3313979A patent/JPS54158591A/en active Granted
- 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
Also Published As
Publication number | Publication date |
---|---|
DE2910927A1 (en) | 1979-10-11 |
SE7902418L (en) | 1979-09-22 |
NO781773L (en) | 1979-09-24 |
SE8401872L (en) | 1984-04-04 |
BE874866A (en) | 1979-07-02 |
JPS54158591A (en) | 1979-12-14 |
SE449040B (en) | 1987-03-30 |
IT1118443B (en) | 1986-03-03 |
JPS6161360B2 (en) | 1986-12-25 |
SE458405B (en) | 1989-03-20 |
NO148577C (en) | 1983-11-09 |
GB2018421B (en) | 1982-12-01 |
SE8401872D0 (en) | 1984-04-04 |
IT7967579A0 (en) | 1979-03-20 |
GB2018421A (en) | 1979-10-17 |
ES478846A1 (en) | 1979-12-16 |
FR2420827B1 (en) | 1984-12-07 |
NO148577B (en) | 1983-07-25 |
FR2420827A1 (en) | 1979-10-19 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
OAP | Request for examination filed | ||
OD | Request for examination | ||
D2 | Grant after examination | ||
8364 | No opposition during term of opposition | ||
8339 | Ceased/non-payment of the annual fee |