CN1384507A - Determining method and device for reactor core of spherical-bed high-temperature gas-cooled reactor - Google Patents
Determining method and device for reactor core of spherical-bed high-temperature gas-cooled reactor Download PDFInfo
- Publication number
- CN1384507A CN1384507A CN02121435A CN02121435A CN1384507A CN 1384507 A CN1384507 A CN 1384507A CN 02121435 A CN02121435 A CN 02121435A CN 02121435 A CN02121435 A CN 02121435A CN 1384507 A CN1384507 A CN 1384507A
- Authority
- CN
- China
- Prior art keywords
- core
- reactor
- bead
- irradiation
- pipe
- 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
Images
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
Abstract
In pneumatic conveying mode, one string of detecting pellets is blown to above double spherical-bed reactor core, activated through irradiation by neutron inside the reactor core and conveyed by pressure difference to outside the reactor core. The radioactivity of the activated pellets are measured one by one with gramma ray, and thus the radial neutron flux distribution in the double reactor region is measured and the radius of interface in the double reactor region is determined. The advantages of the present invention includes capacity of maintaining stable double reactor region geometrical layout via the irradiation measurement, simple structure, easy operation and irradiation detection under power.
Description
Technical field
The invention belongs to nuclear reactor field, relate in particular to the mensuration of spherical-bed high temperature gas cooled reactor two-zoned-core interface radius.
Background technology
In order to improve the power output of pebble bed reactor, pebble bed core is designed to the layout of two-region, and the center is not for containing the spherical graphite element sphere bed of fuel, and the periphery is the spheric fuel element ball bed of annular, surrounds for fixing graphite reflector all around.Graphite component is packed into by the dress ball hole at graphite nodule bed top, and fuel element is packed into by equally distributed dress ball hole on the circumference in annular fuel ball bed top, forms the two-region pebble bed core of stablizing streamline on whole vertical height.Graphite component and fuel element draw off by the ball hole of unloading of bottom centre.Distinguished through the burnup measurement measurement device by unloading graphite component and the fuel element that the ball hole draws off, more respectively by the dress ball hole at top pack into the graphite nodule bed of center and the fuel sphere bed of annular.
The size of boundary radius is subjected to the influence of top, two districts dress ball speed between graphite nodule bed and the annular fuel ball bed, if the dress ball excessive velocities of center graphite nodule, its boundary radius is just big, otherwise the dress ball speed of center slows down, and its boundary radius just dwindles.Because the friction factor of graphite is temperature variant, than much bigger under air atmosphere, even under the constant condition of two-region dress ball speed, the different atmosphere condition also can be change with boundary radius different operating conditions under under helium atmosphere.Therefore, need in the reactor operation process, be measured,, be kept the radius at stable interface, two-region and stable operating condition to regulate the dress ball speed at top, two districts to two-zoned-core boundary radius.
The notion of spherical-bed high temperature gas cooled reactor two-zoned-core with the carrying out of South Africa ball bed modular reactor plant project, just entered the research of engineering in recent years, did not see article or patent that relevant two-zoned-core interface radius is measured so far as yet.
Summary of the invention
The purpose of this invention is to provide a kind of method and device of measuring reactor core of spherical-bed high-temperature gas-cooled reactor.
The matrix material of graphite nodule and fuel sphere is graphite, and diameter is all 6cm, can not be distinguished with the way of machinery.Therefore, measuring the neutron flux distribution at the reactor core upper surface along the two-zoned-core radial direction is a kind of feasible solution of measuring two-zoned-core boundary radius.Because the high temperature gas cooled reactor reactor core is in very high running temperature, the inlet helium temperature is 250-500 ℃, and the outlet helium temperature is 700-950 ℃, and general neutron detector is difficult to bear so high work.
Method of the present invention is: the mode of utilizing strength to carry, a string detection bead is blown into the top of two-region pebble bed core from the pipe of losing, in reactor core, after the irradiation of neutron certain hour, be activated, utilize air-flow differential will survey bead again and be transported to out-pile, with the gamma-ray measurement device radioactivity of surveying the bead activation is measured one by one, measure two-zoned-core neutron flux radially with this and distribute, determine the radius of two-zoned-core interface.
Advantage of the present invention is:
1. can carry out irradiation to the Flux Distribution of two-zoned-core at any time and measure, determine the interface radius of two-region, the adjusting by two-region dress ball speed keeps the stable geometric arrangement in two-region.
2. simple in structure, maintenance operation is convenient.
3. can carry out irradiation under power surveys.
Description of drawings
Fig. 1 is a measurement mechanism structural representation of the present invention
Embodiment
Measurement mechanism (see figure 1) of the present invention is made up of a string detection bead 1, irradiation section 2, delivery pipe 3, measuring section 4, mistake ball isolation valve 5, draft tube 9, air-flow isolation valve 10, high-pressure air source 11, low-pressure gas source 12, Displacement Measurement mechanism 7, measurement collimation passage 6, measurement mechanism 8 and bell housing 13 etc.
The pipe 3 of losing is a pipe (see figure 1), left end passed through ball isolation valve 5 and linked to each other with irradiation section 2 pipes, right-hand member links to each other with measuring section 4 pipes, measuring section 4 circular tube external walls have ring shielding cover 13, bell housing 13 lower ends are provided with collimation passage 6, and the right-hand member of collimation passage 6 is settled γ measurement mechanism 8, and the bottom of collimation passage 6 is provided with Displacement Measurement device 7 around the outer wall of measuring section 4 pipes, the lower end of measuring section 4 pipes is by air-flow isolation valve 10 and high-pressure air source 11, and low-pressure gas source 12 links to each other.
Measuring process is as follows:
Open high-pressure air source, will survey bead and be blown in the heap, and utilize pressure differential will survey the left end that bead is pressed against irradiation section 2, the location during with assurance irradiation.Open low-pressure gas source behind the irradiation certain hour, to survey bead output out-pile, drop in the Displacement Measurement mechanism 7, survey bead this moment over against measuring collimation passage 6, sniffer 8 can record this radioactive activity intensity of surveying bead, and after measurement finished, traverse measurement displacement mechanism 7 made another bead collimate passage to locating tab assembly, can be measured one by one surveying bead, and the location when guaranteeing to measure.Activity intensity according to a string detection bead of measuring distributes, and in addition the correction of fall time can calculate two-zoned-core neutron flux radially to distribute, and determines the radius at two-zoned-core interface.
Surveying bead is matrix material with graphite or aluminium oxide, and wherein having mixed to be the material of neutron activation, and diameter is 10-50mm.
Above two-zoned-core, irradiation section 2 is horizontally disposed with along diametric(al), is the metal tube of high temperature resistant (allow working temperature 〉=500 ℃).Its medial extremity surpasses interface, two-region 25-50cm at least to the center extension, and medial extremity is welded with a termination, and the center, termination has a through hole, as carrying the gas channel of surveying bead.The pipe 3 of losing passes outside the reactor vessel, be connected with two and cross ball isolation valve 5, survey bead enter in the heap and the process of discharge out-pile in, crossing the ball isolation valve opens, can allow it pass through, close otherwise cross the ball isolation valve, play the effect of first, second road safety isolating valve on a circuit pressure border.Cross the ball isolation valve pipe of losing afterwards, connect a vertical pipe of losing after upwards promoting certain height, the height of this lifting is used for the kinetic energy of absorbing detection bead at course of conveying, speed when the detection bead is peaked approaches zero, the impact when falling into detecting location to reduce the detection bead.
Survey bead in vertical tube from the top platform of the Displacement Measurement mechanism 7 that drops into bottom measuring section 4, top platform is provided with snubber assembly, surveys the impact that bead falls to reduce.Tail end at the pipe of losing is connected with draft tube 9 and gas isolation valve 10, the air-flow control that is used to survey the bead input and discharges.
Be input to the reactor core top in order to survey bead, open the isolation valve of high pressure draught, by means of the pressure differential between the pressure in the pressure of high pressure draught and a loop, air-flow is entered by high-pressure air source, the detection bead that the pressure differential that its air-flow forms will leave in the measuring section is input in the irradiation section 2 on reactor core top, and air-flow is discharged from the air-flow through hole of the pipe reactor core end of losing, and keeps certain airshed, make detection bead string be pressed in the top, termination, in the irradiation process, keep stable location.
After irradiation is intact, close the high pressure draught isolation valve, open the low-pressure air current isolation valve, the pressure of low-pressure air current is lower than a circuit pressure, with the pressure reduction between a loop and the low-pressure air current, detection bead string after the irradiation is blown out out-pile, fall into and be deposited in the measuring section 4, be the screen layer encirclement around the measuring section 4, the gamma-rays of the detection bead that activates behind the irradiation is shielded, reduce the background level of surveying, be provided with a collimating aperture road 6 at the intermediate altitude place.The gamma-rays that activation detection bead produces enters the γ measurement mechanism of tail end after the collimation duct.
Displacement mechanism is in the upper end when initial, makes the center of surveying bead in the measuring section bottom just in time aim at the center in collimation duct.After treating that a radioactivation strength level measurement of surveying bead is finished, the control bit moving mechanism moves down a height of surveying little bulb diameter, allow second centrally aligned of surveying bead collimate the duct, go down according to this, measure whole detection beads always.
The selection of activating substance is mainly considered: (1) neutron-absorption cross-section is big, more than (2) a few minutes half life period, is unlikely to the too fast decay of activation radioactivity in detection process.In table 1, list selectable main activating substance.
The alternative activating substance of table 1.
Nucleic thermal cross section (crust) resonance absorption cross section (crust) half life period
I
n 115 202 2640 54min
E
u 153 390 950 16yr
T
u 181 21 590 115d
R
e 185 112 1160 90.14hr
R
e 187 74 305 17hr
A
u 197 99 1558 2.7d
Claims (2)
1. the assay method of a reactor core of spherical-bed high-temperature gas-cooled reactor, it is characterized in that utilizing the mode of strength conveying, a string detection bead is blown into the top of two-region pebble bed core from the pipe of losing, in reactor core, after the irradiation of neutron certain hour, be activated, utilize air-flow differential will survey bead again and be transported to out-pile, with the gamma-ray measurement device radioactivity of surveying the bead activation is measured one by one, measure two-zoned-core neutron flux radially with this and distribute, determine the radius of two-zoned-core interface.
2. the determinator of a reactor core of spherical-bed high-temperature gas-cooled reactor, it is characterized in that this device is by a string detection bead, the irradiation section, delivery pipe, measuring section, cross the ball isolation valve, draft tube, the air-flow isolation valve, high-pressure air source, low-pressure gas source, Displacement Measurement mechanism, measure the collimation passage, composition such as measurement mechanism and bell housing, the Guan Weiyi pipe of losing, left end passed through the ball isolation valve and linked to each other with irradiation section pipe, right-hand member links to each other with the measuring section pipe, the measuring section circular tube external wall has the ring shielding cover, the bell housing lower end is provided with the collimation passage, the right-hand member of collimation passage is settled the γ measurement mechanism, the bottom of collimation passage is provided with the Displacement Measurement device around the outer wall of measuring section pipe, the lower end of measuring section pipe is by air-flow isolation valve and high-pressure air source, and low-pressure gas source links to each other.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNB021214352A CN1159726C (en) | 2002-06-21 | 2002-06-21 | Determining method and device for reactor core of spherical-bed high-temperature gas-cooled reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CNB021214352A CN1159726C (en) | 2002-06-21 | 2002-06-21 | Determining method and device for reactor core of spherical-bed high-temperature gas-cooled reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN1384507A true CN1384507A (en) | 2002-12-11 |
| CN1159726C CN1159726C (en) | 2004-07-28 |
Family
ID=4744968
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CNB021214352A Expired - Fee Related CN1159726C (en) | 2002-06-21 | 2002-06-21 | Determining method and device for reactor core of spherical-bed high-temperature gas-cooled reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN1159726C (en) |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1296939C (en) * | 2005-08-26 | 2007-01-24 | 田嘉夫 | Regular bed modular high temperature gas cooled reactor and its fuel sphere disposal method |
| CN102496394A (en) * | 2011-11-30 | 2012-06-13 | 清华大学 | Spherical component identifier |
| CN106128539A (en) * | 2016-08-30 | 2016-11-16 | 中广核研究院有限公司 | A kind of system utilizing pressurized-water reactor nuclear power plant to produce medical short-lived phase radioactive source |
| CN104813411B (en) * | 2012-09-18 | 2018-01-19 | 阿海珐有限公司 | For applying the device of lubricant in pipeline |
| CN113892152A (en) * | 2019-05-23 | 2022-01-04 | 法玛通股份有限公司 | Systems and methods for removing irradiation targets from nuclear reactors and radionuclide generation systems |
| CN114373560A (en) * | 2021-12-16 | 2022-04-19 | 华能核能技术研究院有限公司 | Modular high-temperature gas cooled reactor internal power detection model |
| CN113892152B (en) * | 2019-05-23 | 2024-05-03 | 法玛通股份有限公司 | System and method for removing irradiation targets from nuclear reactor and radionuclide generation systems |
-
2002
- 2002-06-21 CN CNB021214352A patent/CN1159726C/en not_active Expired - Fee Related
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1296939C (en) * | 2005-08-26 | 2007-01-24 | 田嘉夫 | Regular bed modular high temperature gas cooled reactor and its fuel sphere disposal method |
| CN102496394A (en) * | 2011-11-30 | 2012-06-13 | 清华大学 | Spherical component identifier |
| CN102496394B (en) * | 2011-11-30 | 2014-09-03 | 清华大学 | Spherical component identifier |
| CN104813411B (en) * | 2012-09-18 | 2018-01-19 | 阿海珐有限公司 | For applying the device of lubricant in pipeline |
| CN106128539A (en) * | 2016-08-30 | 2016-11-16 | 中广核研究院有限公司 | A kind of system utilizing pressurized-water reactor nuclear power plant to produce medical short-lived phase radioactive source |
| CN113892152A (en) * | 2019-05-23 | 2022-01-04 | 法玛通股份有限公司 | Systems and methods for removing irradiation targets from nuclear reactors and radionuclide generation systems |
| CN113892152B (en) * | 2019-05-23 | 2024-05-03 | 法玛通股份有限公司 | System and method for removing irradiation targets from nuclear reactor and radionuclide generation systems |
| CN114373560A (en) * | 2021-12-16 | 2022-04-19 | 华能核能技术研究院有限公司 | Modular high-temperature gas cooled reactor internal power detection model |
Also Published As
| Publication number | Publication date |
|---|---|
| CN1159726C (en) | 2004-07-28 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN109616235B (en) | Temporary discharging storage device | |
| CA2792593C (en) | Systems and methods for processing irradiation targets through a nuclear reactor | |
| CN112789689B (en) | Target irradiation system for producing radioisotope | |
| US4208247A (en) | Neutron source | |
| CN107710333A (en) | Radioisotopic method is produced using heavy water type nuclear power station | |
| CN1159726C (en) | Determining method and device for reactor core of spherical-bed high-temperature gas-cooled reactor | |
| CN101740147A (en) | Dry vertical shaft storage system for spent fuel of nuclear power station and storage method thereof | |
| CN215574486U (en) | Device for researching graphite dust deposition source item of flow ball pipeline | |
| CN1447342A (en) | Second shutdown system of absorption ball applicable to gas-cooled reactor | |
| US4076584A (en) | Rodded shutdown system for a nuclear reactor | |
| CN101777397B (en) | Reactor core ball feeding device of high temperature gas cooled reactor | |
| Wu et al. | Design, experiment, and commissioning of the spent fuel conveying and loading system of HTR-PM | |
| JP2003222693A (en) | Reactor facility, reactor core, and reactor operation method | |
| Ozaki et al. | Refurbishment of KamLAND outer detector | |
| JP2004502143A5 (en) | ||
| CN104011801A (en) | Earthquake-resistant reinforcement assembly | |
| US4411860A (en) | Pebble bed reactor with feeding device for absorber material and method for its operation | |
| CN100541188C (en) | A kind of X-ray detection apparatus X and method of detection thereof | |
| CN107591215B (en) | The reinspection method and device of thermometric graphite nodule in a kind of high temperature gas cooled reactor | |
| US3393125A (en) | Testing for fuel element sheathing failures in nuclear reactors | |
| JPH02263188A (en) | Crushing body radioactivity discrimination processing system and very low level radioactivity measuring instrument | |
| CN109817359A (en) | A kind of circumferential trolley for Fusion-fission covering refuelling system | |
| CN109448882A (en) | Nuclear Power Station's Exhausted Fuels Dry storage concrete silo | |
| RU2787139C1 (en) | Method for controlling the thermal neutron flux density and a device for its implementation | |
| CN216596967U (en) | High temperature gas cooled reactor fuel ball integrity detection device based on X-ray tomography |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| C19 | Lapse of patent right due to non-payment of the annual fee | ||
| CF01 | Termination of patent right due to non-payment of annual fee |