CN108257695A - Axial quantity of power journey measuring device outside a kind of marine minitype reactor - Google Patents
Axial quantity of power journey measuring device outside a kind of marine minitype reactor Download PDFInfo
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- CN108257695A CN108257695A CN201711324223.3A CN201711324223A CN108257695A CN 108257695 A CN108257695 A CN 108257695A CN 201711324223 A CN201711324223 A CN 201711324223A CN 108257695 A CN108257695 A CN 108257695A
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- measuring device
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- 238000005259 measurement Methods 0.000 claims abstract description 19
- 230000003321 amplification Effects 0.000 claims abstract description 11
- 238000003199 nucleic acid amplification method Methods 0.000 claims abstract description 11
- 238000012545 processing Methods 0.000 claims description 11
- XKRFYHLGVUSROY-UHFFFAOYSA-N Argon Chemical compound [Ar] XKRFYHLGVUSROY-UHFFFAOYSA-N 0.000 claims description 6
- 238000013016 damping Methods 0.000 claims description 6
- 238000012544 monitoring process Methods 0.000 claims description 5
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 claims description 4
- 229910052796 boron Inorganic materials 0.000 claims description 4
- 238000004364 calculation method Methods 0.000 claims description 4
- 229910052786 argon Inorganic materials 0.000 claims description 3
- 239000007789 gas Substances 0.000 claims description 3
- 239000012212 insulator Substances 0.000 claims description 3
- 238000002955 isolation Methods 0.000 claims description 3
- 230000001105 regulatory effect Effects 0.000 claims description 3
- 238000007493 shaping process Methods 0.000 claims description 3
- 239000007787 solid Substances 0.000 claims description 3
- 230000007547 defect Effects 0.000 abstract description 3
- 238000013461 design Methods 0.000 abstract description 3
- 238000005516 engineering process Methods 0.000 description 3
- 230000008901 benefit Effects 0.000 description 2
- 238000007405 data analysis Methods 0.000 description 2
- 230000005611 electricity Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000004088 simulation Methods 0.000 description 2
- 238000004458 analytical method Methods 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000012423 maintenance Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 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
- G21C17/108—Measuring reactor flux
-
- 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
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- 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)
Abstract
The invention discloses quantity of power journey measuring devices axial outside a kind of marine minitype reactor, it is related to ship technical field of nuclear power, including at least three power range channels, there are at least four ionisation chambers in each power range channel, each ionisation chamber is circumferentially distributed outside reactor；Signal amplification unit, for the current signal of reception to be changed into voltage signal and amplifies output；Power measurement unit, including microprocessor, high voltage power supply and low-tension supply；Signal output unit, for microprocessor output analog signal to be converted to digital signal and is transmitted to display device.Axial quantity of power journey measuring device compensates for existing reactor outer core measuring device and the defects of scheme can not carry out power range neutron fluence rate axial direction distribution measuring outside the marine minitype reactor of the present invention, Axial power difference, power excursion, quadrant inclination angle etc. and the relevant Various types of data of reactor safety can be calculated, more feasibilities and design parameter are provided for reactor control.
Description
Technical field
The present invention relates to ship technical field of nuclear power, and in particular to axial quantity of power journey outside a kind of marine minitype reactor
Measuring device.
Background technology
It needs to measure the parameter that reactor core is run in real time during the operation and maintenance of offshore platform reactor, to monitor reaction
Stack operation state, the relevant issues that timely processing occurs.
The heap outer core measuring holes of offshore platform reactor use three-stage measurement scheme at present, i.e. source range measures, in
Between range measure, power range measures, the magnitudes of neutron fluence rate horizontal interval 1-1.5 of every two sections of measurements, three ranges it
Between measurement range it is overlapped, so that the seamless connection between measuring instrumentss and monitoring process do not have blind area.
Power range measuring device is as the main device for having the function of to measure pile neutron fluence rate, by anti-
The neutron fluence rate redundancy on reactor core top, lower part and mean power during heap Power operation is answered to measure, to reactor just
Reactor capability is monitored in real time under normal high-power operating condition.Usually using non-benefit in the large nuclear power station run at present
Chang Tu boron neutron ionization chamber (long ion chamber) is detected, and is surveyed to obtain accurate control parameter frequently with multistage ionisation chamber
Amount output, but this multistage ionisation chamber measures export structure and is had the following problems when applied to marine minitype reactor：
1st, since the technology of marine minitype reactor limits, it is difficult to reactor core measuring system is configured, it can not be to reactor core
Operating parameter measures, so current marine minitype reaction core measurement scheme is functionally short of；
2nd, general nuclear power plant's pile height 3.6m or so, marine minitype reactor is only 1.4m, traditional multistage ionisation chamber
It measures export structure and is respectively distributed to reactor core upper and lower part, take up space larger, original structure is difficult to anti-suitable for marine minitype
It answers in heap.
Invention content
For defect in the prior art, the purpose of the present invention is to provide a kind of marine minitype reactor outer shafts
To power range measuring device, reactor axial power can be distributed and measured.
To achieve the above objectives, the technical solution adopted by the present invention is that：
Axial quantity of power journey measuring device, is used to measure Small reactor axis peculiar to vessel outside a kind of marine minitype reactor
It is distributed and calculates with reactor safety related data and to reacting reactor surveillance and operating system feedback measuring signals, Xiang Gong to power
Rate regulating system provides maximum power and carries out reactor control, including：
At least three power range channels are both provided at least four ionisation chambers in each power range channel, each described
Ionisation chamber is circumferentially distributed outside reactor, and the ionisation chamber is set in the reactor, for neutron signal to be converted to
Pulse and current signal output；
Signal amplification unit, the signal amplification unit are connected with the power range channel output end, for that will receive
Weak current signal amplification and shaping output；
Power measurement unit, including microprocessor, high voltage power supply and low-tension supply, the microprocessor is put with the signal
Big unit output terminal is electrically connected, for will be converted to analog signal output, the high-voltage electricity after the current signal received processing
Source is electrically connected with all ionisation chambers, power supply supply when working for the ionisation chamber；
Signal output unit, the signal output unit are connect with the microprocessor signals in the power measurement unit,
Analog signal for the microprocessor to be exported, which is converted to digital signal and passes through bus interface, is transmitted to monitoring and operation
System.
Based on the above technical solution, the ionisation chamber is four, and one of ionisation chamber is set to reactor
Top, another ionisation chamber are set to reactor bottom, and each ionisation chamber is axially equidistantly distributed in marine minitype reactor.
Based on the above technical solution, the ionisation chamber includes high-field electrode, passive electrode, insulator and ionisation chamber
Sleeve, the ionisation chamber is interior full of argon gas, and the passive electrode surface is coated with solid boron film.
Based on the above technical solution, damping device is provided in the thimble ionization chamber, the damping device is set
At the top of the thimble ionization chamber, the gap of the thimble ionization chamber and the power range interchannel is filled up.
Based on the above technical solution, each ionisation chamber is arranged on the axial Along ent of marine minitype reactor
On.
Based on the above technical solution, each ionisation chamber is set to axis according to theoretical calculation or In-core Instrumentation demand
To specific position.
Based on the above technical solution, the ionisation chamber compensates long neutron ionization chamber for non-γ.
Based on the above technical solution, the electric signal of each ionisation chamber output independently of each other and with it is described peculiar to vessel
Small reactor out-pile axial power range measuring device internal circuit electrical isolation.
Based on the above technical solution, further include a signal processing unit, the signal processing unit respectively with institute
It states power measurement unit to connect with the signal output unit signal, for the simulation letter for exporting the power measurement unit
Number, acquisition logical signal is weighted, and export to the signal output unit by theoretical formula.
Based on the above technical solution, the signal output unit receives and exports the logical signal and simulation is believed
Number circuit it is mutual indepedent, the circuit for exporting the logical signal is connect with warning device；Export the circuit of the analog signal
It is connect with reactor control system, reactor protection system.
Compared with prior art, the advantage of the invention is that：
(1) axial quantity of power journey measuring device is visited by covering power range in list outside marine minitype reactor of the invention
It surveys placement location in device and designs four uncompensated ionization chamber according to the calculated value of axial reactor power, it can be to reactor
Axial power distribution measures, and realizes the multiple spot power output of marine minitype reactor, and shown with operating system for monitoring
And data analysis, reactor capability distributed controll is studied.
(2) axial quantity of power journey measuring device compensates for existing reactor outside marine minitype reactor of the invention
The defects of outer core measuring device and scheme can not be carried out in the measurement of power range neutron fluence rate and data analysis is reactor control
System and safety analysis, which calculate, provides more feasibilities and design parameter.
(3) axial quantity of power journey measuring device compatibility is used in existing system outside marine minitype reactor of the invention
Electronic circuit module ensure that the technological frame of original measuring device, have more preferably while meeting technology measurement request
Engineering reliability.
Description of the drawings
Fig. 1 is the structural representation of axial quantity of power journey measuring device outside marine minitype reactor in the embodiment of the present invention
Figure.
Specific embodiment
The present invention is described in further detail with reference to the accompanying drawings and embodiments.
Shown in Figure 1, the embodiment of the present invention provides axial quantity of power journey outside a kind of marine minitype reactor and measures dress
It puts, is used to measuring Small reactor axial power peculiar to vessel and is distributed and calculates with reactor safety related data and supervised to reactor
Depending on and operating system feedback measuring signals, to power regulating system provide maximum power carry out reactor control, including：
At least three power range channels are both provided at least four ionisation chambers in each power range channel, each described
Ionisation chamber is circumferentially distributed outside reactor, and the ionisation chamber is set in the reactor, for neutron signal to be converted to
Pulse and current signal output；
Signal amplification unit, the signal amplification unit are connected with the power range channel output end, for that will receive
Weak current signal amplification and shaping output；
Power measurement unit, including microprocessor, high voltage power supply and low-tension supply, the microprocessor is put with the signal
Big unit output terminal is electrically connected, for will be converted to analog signal output, the high-voltage electricity after the current signal received processing
Source is electrically connected with all ionisation chambers, power supply supply when working for the ionisation chamber；
Signal output unit, the signal output unit are connect with the microprocessor signals in the power measurement unit,
Analog signal for the microprocessor to be exported, which is converted to digital signal and passes through bus interface, is transmitted to monitoring and operation
System.
In one embodiment, can be four by ionisation chamber, one of ionisation chamber is set to PRV head package, another
Ionisation chamber is set to reactor bottom, and each ionisation chamber is axially equidistantly distributed in marine minitype reactor, to ensure reaction
The axially measured result of heap is convenient for theoretical calculation and compares, clearly to reflect that marine minitype reactor axial power is distributed.Ionisation chamber
It may include high-field electrode, passive electrode, insulator and thimble ionization chamber, and full of argon gas in ionisation chamber, in passive electrode table
Face is coated with solid boron film.
In one embodiment, damping device can be set in thimble ionization chamber, and damping device is set on thimble ionization chamber top
The gap of thimble ionization chamber and power range interchannel is filled up in portion.
The installation position of ionisation chamber can be determined according to actual demand, and such as in one embodiment, each ionisation chamber is arranged on
On the axial Along ent of marine minitype reactor；In another embodiment, each ionisation chamber is surveyed according to theoretical calculation or reactor core
Amount demand is set to axial specific position.
Preferably, the electric signal setting of each ionisation chamber output can be reacted independently of each other and with the marine minitype
Heap out-pile axial power range measuring device internal circuit electrical isolation, prevents measuring signal from mutually generating electromagnetic interference and expanding
Error.
Non- compensation Tu Pengchang neutron ionization chambers, in the power range stage, the pulse of γ generations are used in the embodiment of the present invention
Electric current can be ignored relative to the pulse current that α particles generate, therefore is not required to setting discriminator circuit or carries out γ compensation.
In one embodiment, a letter can be also set outside marine minitype reactor in axial quantity of power journey measuring device
Number processing unit, and signal processing unit is connect respectively with power measurement unit and signal output unit signal, signal processing
Unit is used for the analog signal for exporting power measurement unit, acquisition logical signal is weighted, and defeated by theoretical formula
Go out to signal output unit, and by signal output unit receive and export the logical signal and analog signal circuit it is mutually only
Vertical, the circuit for exporting the logical signal is connect with warning device；Export the circuit of the analog signal and reactor control system
System, reactor protection system connection.
The present invention is not limited to the above-described embodiments, for those skilled in the art, is not departing from
Under the premise of the principle of the invention, several improvements and modifications can also be made, these improvements and modifications are also considered as the protection of the present invention
Within the scope of.The content not being described in detail in this specification belongs to the prior art well known to professional and technical personnel in the field.
Claims (10)
1. axial quantity of power journey measuring device outside a kind of marine minitype reactor is used to measure Small reactor axial direction peculiar to vessel
Power is distributed and calculates with reactor safety related data and to reactor surveillance and operating system feedback measuring signals are reacted, to power
Regulating system provides maximum power and carries out reactor control, which is characterized in that including：
At least three power range channels are both provided at least four ionisation chambers, each ionization in each power range channel
Room is circumferentially distributed outside reactor, and the ionisation chamber is set in the reactor, for neutron signal to be converted to pulse
And current signal output；
Signal amplification unit, the signal amplification unit are connected with the power range channel output end, micro- for that will receive
The amplification of low current signal and shaping output；
Power measurement unit, including microprocessor, high voltage power supply and low-tension supply, the microprocessor and signal amplification are single
The electrical connection of first output terminal, for that will be converted to analog signal output after the current signal received processing, the high voltage power supply with
All ionisation chamber electrical connections, power supply supply when working for the ionisation chamber；
Signal output unit, the signal output unit connect with the microprocessor signals in the power measurement unit, are used for
The analog signal that the microprocessor exports is converted into digital signal and passes through bus interface and is transmitted to monitoring and operating system.
2. axial quantity of power journey measuring device outside marine minitype reactor as described in claim 1, it is characterised in that：It is described
Ionisation chamber is four, and one of ionisation chamber is set to PRV head package, another ionisation chamber is set to reactor bottom, each institute
Ionisation chamber is stated axially to equidistantly distribute in marine minitype reactor.
3. axial quantity of power journey measuring device outside marine minitype reactor as described in claim 1, it is characterised in that：It is described
Ionisation chamber includes high-field electrode, passive electrode, insulator and thimble ionization chamber, is full of argon gas, the collection in the ionisation chamber
Electrode surface is coated with solid boron film.
4. axial quantity of power journey measuring device outside marine minitype reactor as claimed in claim 3, it is characterised in that：It is described
Damping device is provided in thimble ionization chamber, the damping device is set at the top of the thimble ionization chamber, fills up the ionisation chamber
The gap of sleeve and the power range interchannel.
5. axial quantity of power journey measuring device outside marine minitype reactor as described in claim 1, it is characterised in that：Each institute
Ionisation chamber is stated to be arranged on the axial Along ent of marine minitype reactor.
6. axial quantity of power journey measuring device outside marine minitype reactor as claimed in claim 5, it is characterised in that：Each institute
It states ionisation chamber and axial specific position is set to according to theoretical calculation or In-core Instrumentation demand.
7. axial quantity of power journey measuring device outside marine minitype reactor as described in claim 1, it is characterised in that：It is described
Ionisation chamber compensates long neutron ionization chamber for non-γ.
8. axial quantity of power journey measuring device outside marine minitype reactor as described in claim 1, it is characterised in that：Each
The electric signal of ionisation chamber output independently of each other and with quantity of power journey measuring device axial outside the marine minitype reactor
Internal circuit electrical isolation.
9. axial quantity of power journey measuring device, special outside the marine minitype reactor as described in claim 1-8 any one
Sign is：Further include a signal processing unit, the signal processing unit respectively with the power measurement unit and the signal
Output unit signal connects, and for the analog signal for exporting the power measurement unit, is weighted by theoretical formula
Logical signal is obtained, and is exported to the signal output unit.
10. axial quantity of power journey measuring device outside marine minitype reactor as claimed in claim 9, it is characterised in that：Institute
It states signal output unit to receive and export the logical signal and the circuit of analog signal is mutual indepedent, exports the logical signal
Circuit connect with warning device；The circuit and reactor control system, reactor protection system for exporting the analog signal connect
It connects.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201711324223.3A CN108257695B (en) | 2017-12-13 | 2017-12-13 | Marine small-sized reactor outer axial power range measuring device |
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| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201711324223.3A CN108257695B (en) | 2017-12-13 | 2017-12-13 | Marine small-sized reactor outer axial power range measuring device |
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| CN108257695A true CN108257695A (en) | 2018-07-06 |
| CN108257695B CN108257695B (en) | 2024-03-26 |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109240245A (en) * | 2018-10-25 | 2019-01-18 | 中国船舶重工集团公司第七〇九研究所 | A kind of nuclear power unit complex control system Digitallized system framework |
Citations (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5440996A (en) * | 1977-09-06 | 1979-03-31 | Nippon Atom Ind Group Co Ltd | Power distribution deducing method |
| US4333797A (en) * | 1979-05-11 | 1982-06-08 | Hitachi, Ltd. | Reactor power control apparatus |
| US5490184A (en) * | 1994-07-21 | 1996-02-06 | Westinghouse Electric Corporation | Method and a system for accurately calculating PWR power from excore detector currents corrected for changes in 3-D power distribution and coolant density |
| US20020122522A1 (en) * | 1998-08-31 | 2002-09-05 | Yasushi Goto | Neutron flux measuring apparatus |
| US20020126790A1 (en) * | 2000-12-13 | 2002-09-12 | Hitachi, Ltd. | Reactor power output measurement device |
| JP2009085763A (en) * | 2007-09-28 | 2009-04-23 | Toshiba Corp | Average power measuring device and reactor output monitor using the same |
| CN201936627U (en) * | 2010-12-29 | 2011-08-17 | 中核(北京)核仪器厂 | Long neutron ionization chamber for detector for nuclear detection out of piles |
| CN202533587U (en) * | 2012-03-09 | 2012-11-14 | 中国船舶重工集团公司第七一九研究所 | Ionization chamber type detector used for measurement of strong gamma radiation field under accident conditions |
| CN202584750U (en) * | 2012-02-17 | 2012-12-05 | 中国原子能科学研究院 | Neutron fluence automatic measuring system for physical start of reactor |
| CN203787385U (en) * | 2014-02-20 | 2014-08-20 | 中国科学院高能物理研究所 | Multilayer high air pressure ionization chamber suitable for detecting high-dose-rate radiation fields |
| CN105448363A (en) * | 2015-11-12 | 2016-03-30 | 中广核工程有限公司 | Nuclear instrument system for nuclear power station and positioning method thereof |
| CN105513656A (en) * | 2015-11-30 | 2016-04-20 | 中广核工程有限公司 | System and method for monitoring reactor core parameters of nuclear power plant |
| WO2016091158A1 (en) * | 2014-12-08 | 2016-06-16 | 中广核工程有限公司 | Diversity drive method, device and system for nuclear power plant |
| CN206193255U (en) * | 2016-11-16 | 2017-05-24 | 北京华控宜境仪器有限公司 | Portable high atmospheric pressure ionization chamber |
| CN107146647A (en) * | 2017-04-20 | 2017-09-08 | 岭东核电有限公司 | A kind of portable neutron detection device |
| CN107195347A (en) * | 2017-06-23 | 2017-09-22 | 中国核动力研究设计院 | It is a kind of to calibrate the method that heap outer core surveys ionisation chamber |
-
2017
- 2017-12-13 CN CN201711324223.3A patent/CN108257695B/en active Active
Patent Citations (16)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS5440996A (en) * | 1977-09-06 | 1979-03-31 | Nippon Atom Ind Group Co Ltd | Power distribution deducing method |
| US4333797A (en) * | 1979-05-11 | 1982-06-08 | Hitachi, Ltd. | Reactor power control apparatus |
| US5490184A (en) * | 1994-07-21 | 1996-02-06 | Westinghouse Electric Corporation | Method and a system for accurately calculating PWR power from excore detector currents corrected for changes in 3-D power distribution and coolant density |
| US20020122522A1 (en) * | 1998-08-31 | 2002-09-05 | Yasushi Goto | Neutron flux measuring apparatus |
| US20020126790A1 (en) * | 2000-12-13 | 2002-09-12 | Hitachi, Ltd. | Reactor power output measurement device |
| JP2009085763A (en) * | 2007-09-28 | 2009-04-23 | Toshiba Corp | Average power measuring device and reactor output monitor using the same |
| CN201936627U (en) * | 2010-12-29 | 2011-08-17 | 中核(北京)核仪器厂 | Long neutron ionization chamber for detector for nuclear detection out of piles |
| CN202584750U (en) * | 2012-02-17 | 2012-12-05 | 中国原子能科学研究院 | Neutron fluence automatic measuring system for physical start of reactor |
| CN202533587U (en) * | 2012-03-09 | 2012-11-14 | 中国船舶重工集团公司第七一九研究所 | Ionization chamber type detector used for measurement of strong gamma radiation field under accident conditions |
| CN203787385U (en) * | 2014-02-20 | 2014-08-20 | 中国科学院高能物理研究所 | Multilayer high air pressure ionization chamber suitable for detecting high-dose-rate radiation fields |
| WO2016091158A1 (en) * | 2014-12-08 | 2016-06-16 | 中广核工程有限公司 | Diversity drive method, device and system for nuclear power plant |
| CN105448363A (en) * | 2015-11-12 | 2016-03-30 | 中广核工程有限公司 | Nuclear instrument system for nuclear power station and positioning method thereof |
| CN105513656A (en) * | 2015-11-30 | 2016-04-20 | 中广核工程有限公司 | System and method for monitoring reactor core parameters of nuclear power plant |
| CN206193255U (en) * | 2016-11-16 | 2017-05-24 | 北京华控宜境仪器有限公司 | Portable high atmospheric pressure ionization chamber |
| CN107146647A (en) * | 2017-04-20 | 2017-09-08 | 岭东核电有限公司 | A kind of portable neutron detection device |
| CN107195347A (en) * | 2017-06-23 | 2017-09-22 | 中国核动力研究设计院 | It is a kind of to calibrate the method that heap outer core surveys ionisation chamber |
Non-Patent Citations (2)
| Title |
|---|
| 夏虹等: "核工程检测仪表", 哈尔滨工程大学出版社, pages: 177 - 178 * |
| 石宗仁, 徐, 丁声耀, 王顺庆, 郭智荣, 左亮周: "NaI(Tl)对6.13MeV-γ射线的长管体源的探测效率的测量", 高能物理与核物理, no. 02, 21 February 2005 (2005-02-21), pages 124 - 129 * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109240245A (en) * | 2018-10-25 | 2019-01-18 | 中国船舶重工集团公司第七〇九研究所 | A kind of nuclear power unit complex control system Digitallized system framework |
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| Publication number | Publication date |
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| CN108257695B (en) | 2024-03-26 |
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