CN101685680A - Uniform inner heat source simulator of medical isotope production solution reactor - Google Patents
Uniform inner heat source simulator of medical isotope production solution reactor Download PDFInfo
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- CN101685680A CN101685680A CN200810166838A CN200810166838A CN101685680A CN 101685680 A CN101685680 A CN 101685680A CN 200810166838 A CN200810166838 A CN 200810166838A CN 200810166838 A CN200810166838 A CN 200810166838A CN 101685680 A CN101685680 A CN 101685680A
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Abstract
The invention relates to a reactor simulator, in particular to a uniform inner heat source simulator of a medical isotope production solution reactor, comprising a power simulation part and a fissiongas simulation part, wherein the power simulation part comprises a heating component and a heat exchange component, and the fission gas simulation part comprises a bubble generation device and simulation gas. The invention really reflects power distribution of fuel solution in the reactor, efficiently simulates power distribution of a prototype reactor, strictly controls occupied flow area of an electric heating element without causing great influence on natural convection heat exchange of the solution by the electric heating element, solves the problems of high simulation power and small cross section of the electric heating element in the prior art and satisfies the experimental requirements. In addition, nitrogen gas is used as the simulation gas so that the safety of an experiment is ensured.
Description
Technical field
The invention belongs to a kind of reactor simulator, be specifically related to a kind of uniform inner heat source simulator of medical isotope production solution reactor.
Background technology
At present, because
99Mo,
131I and
89Medical radionuclide such as Sr and pharmaceutical applications are worth huge, market outlook are wide, the many countries such as the U.S., Russia, Mexico etc. all produce solution reactor (Medical Isotope Production Reactor is called for short MIPR) technology at the active development medical-isotope.So far, the design power mostly MIPR below 50kW is built up, but does not still have the MIPR of design power up to 200kW.The whole exchange capability of heat of MIPR reactor core is the gordian technique of design-build MIPR, is the important content that nuclear safety is analyzed.For 200kW " homogeneous solution-type reactor " type MIPR, its fissionable material is not a solid, but homogeneous solution, the heat that fuel solution is fissioned and produced in core vessel, the main heat transfer free convection that relies between solution and heat exchange cooling coil outer wall, the hydrogen that irradiation decompose to produce, carrier of oxygen are assembled, are broken away from different rates, and disturbance solution influences the distribution and the share of cavity in the solution (hydrogen, oxygen, water vapour).
The heat release mode of fuel solution is distributing heating, and the heat transfer between the heat exchange cooling coil belongs to the heat transfer free convection with endogenous pyrogen, in addition irradiation institute constantly the hydrogen and oxygen of generation to the disturbing influence of reactor core heat exchange.Want this even distributing heating of complete real simulated and heat transfer free convection with the current experiments technology, difficulty is quite big.
Evenly the difficult point of endogenous pyrogen simulation mainly concentrate on following some:
(1) prior art is as adopting the simulation that experimentizes of type of heating such as infrared ray, magnetic induction heating, the homogeneity of fuel solution heating can effectively be guaranteed, but can't simulate the distribute power of fuel solution in the true reactor, certainly will cause to occur between experimental result and the prototype truth than large deviation;
(2) with the electrical heating elements of dispersed placement as heat source unit, be provided with according to the prototype distribute power; The superiority of this analog form is effectively to simulate the distribute power of prototype, but electrical heating elements will impact the heat transfer free convection between fuel solution and cooling coil after putting into core vessel; Therefore must strictly control the shared flow area of electrical heating elements; And have only all electrical heating elements sectional area sums to be lower than 3% o'clock of whole flow area, and electrical heating elements can not affect greatly the heat transfer free convection of solution, and the reliability of experimental result just is guaranteed, and prior art is difficult to realize this index;
(3) since the simulated power of this experiment up to 200kW, and the sectional area of electrical heating elements can not be difficult to meet the demands for the resistance wire diameter of electrical heating elements self, the technologies such as filling of insulating material magnesia powder in the prior art greater than 3% of whole flow area;
(4) in the simulation process of the hydrogen or oxygen gas that nuclear radiation produced to the disturbing influence of solution heat transfer free convection, if employing may be blasted with the hydrogen and the oxygen of prototype unanimity, this makes security of experiment to be protected; Need to seek appropriate gas, bubble is simulated, prior art is difficult to realize.
Summary of the invention
The objective of the invention is to solve the deficiencies in the prior art, provide a kind of and can accurately simulate the uniform inner heat source simulator of medical isotope production solution reactor that medical-isotope is produced the even endogenous pyrogen heat release of solution reactor mode.
The present invention is achieved in that
A kind of uniform inner heat source simulator of medical isotope production solution reactor, it comprises the power analog component that is made of heater and heat exchange component, and the fission gas analog component; The word a shape heating element that described heater comprises, word b shape heating element, circular-arc heating element and polyline shaped heating element, wherein, 5 word a linear element is distributed on the φ 100mm circumference, 6 word b linear element is distributed on the φ 217.55mm circumference, 2 circular-arc elements are distributed on the φ 284mm circumference, 20 polyline shaped elements are distributed in the heat transfer zone, and above-mentioned all heating sectional area summations account for 2.8% of whole device flow area; Described heat exchange component comprises 20 heat exchange cooling coils, they are along circumferentially uniform, each root heat exchange cooling coil radially is arranged in the annular region that diameter is φ 296~690mm, a heat exchange cooling coil is the spirally-wound tube of 13 circle ovalizes, its major axis is 400mm, and its minor axis length is with radially being fan-shaped increase; Described fission gas analog component comprises bubble generator and analog gas, and described bubble generator comprises spiracular plate, and spiracular plate is welded on the barrel of core vessel bottom, interlayer is arranged as reserving the headroom between it and the core vessel base plate.
The thickness of the interlayer between aforesaid spiracular plate and the core vessel floor is 15mm; Be furnished with the bubble generation hole of 166 φ 1mm according to solution reactor reactor core real power on spiracular plate, circumferentially evenly arranged 7 tracheaes on the core vessel base plate, described analog gas is a nitrogen.
The diameter of aforesaid all heating elements is φ 3.5mm, adopts the 220V alternating current, and power can reach 10~20W/cm
2
Remarkable advantage of the present invention is:
(1) truly reflected the distribute power of fuel solution in the reactor, avoided occurring between experimental result and the prototype truth than large deviation;
(2) with the electrical heating elements of dispersed placement as heat source unit, be provided with according to the prototype distribute power; Effectively simulated the distribute power of prototype, the shared flow area of electrical heating elements has been controlled in strictness, and electrical heating elements can not affect greatly the heat transfer free convection of solution, makes the reliability of experimental result be guaranteed;
(3) overcome the little technology difficult problem of sectional area of the simulated power height of this experiment, electrical heating elements in the prior art, satisfied requirement of experiment;
(4) use nitrogen as analog gas,, successfully simulated the disturbing influence of fission gas pair and reactor core heat exchange, make the security of testing to be protected by bubble generator.
Description of drawings
Fig. 1 produces the synoptic diagram of solution reactor for a kind of medical-isotope that the present invention mentioned;
Fig. 2 is the synoptic diagram of even endogenous pyrogen analogue means;
Fig. 3 is that the A of Fig. 2 is to view;
Fig. 4. be heating side stretch-out view;
Fig. 5 is word a shape heating vertical view for it;
Fig. 6 is word b shape heating vertical view for it;
Fig. 7 is a polyline shaped heating arrangenent diagram;
Fig. 8 is circular-arc heating arrangenent diagram;
Fig. 9 is the bubble generator structural drawing;
Figure 10 is the partial enlarged drawing of I among Fig. 8;
Figure 11 is the spiracular plate structural drawing;
1. airduct, 2. control rod guide tube, 3. top cover, 4. core vessel, 5. heat exchange cooling coil, 6. urceolus, word a shape heating 7., word b shape heating 8., 9. circular-arc heating, 10. polyline shaped heating, 12. spiracular plates, 13. core vessel base plates, the hole takes place in 14. bubbles.
Embodiment
Below in conjunction with accompanying drawing a kind of uniform inner heat source simulator of medical isotope production solution reactor specific embodiment of the present invention is introduced:
Shown in Fig. 1-11, a kind of uniform inner heat source simulator of medical isotope production solution reactor, it comprises the power analog component that is made of heater and heat exchange component, and the fission gas analog component; The word a shape heating element 7 that described heater comprises, word b shape heating element 8, circular-arc heating element 9 and polyline shaped heating element 10, wherein, 5 word a linear element 7 is distributed on the φ 100mm circumference, 6 word b linear element 8 is distributed on the φ 217.55mm circumference, 2 circular-arc elements 9 are distributed on the φ 284mm circumference, 20 polyline shaped elements 10 are distributed in the heat transfer zone, and above-mentioned all heating sectional area summations account for 2.8% of whole device flow area; Described heat exchange component comprises 20 heat exchange cooling coils 5, they are along circumferentially uniform, each root heat exchange cooling coil 5 radially is arranged in the annular region that diameter is φ 296~690mm, a heat exchange cooling coil 5 is the spirally-wound tube of 13 circle ovalizes, its major axis is 400mm, and its minor axis length is with radially being fan-shaped increase; Described fission gas analog component comprises bubble generator and analog gas, and described bubble generator comprises spiracular plate 12, and spiracular plate 12 is welded on the barrel of core vessel 4 bottoms, interlayer is arranged as reserving the headroom between it and the core vessel base plate 13.
The thickness of the interlayer between aforesaid spiracular plate 12 and the core vessel floor 13 is 15mm; Be furnished with the bubble generation hole 14 of 166 φ 1mm according to solution reactor reactor core real power on spiracular plate 12, circumferentially evenly arranged 7 tracheaes on core vessel base plate 13, described analog gas is a nitrogen.
Aforesaid all diameters that add heating are φ 3.5mm, adopt the 220V alternating current, and power can reach 10~20W/cm
2
It is the flange form pressure vessel that medical-isotope is produced solution reactor core vessel 4, and pressure-bearing 0.2MPa is placed on the support in the urceolus 6; Urceolus 6 is the back cover cylinder, is of a size of φ 1110 (external diameter) * 5 * 1400 (height) mm, and airduct 1 and top cover 3 are set at its top; Core vessel 4 is the back cover cylinder, is of a size of φ 710 (external diameter) * 5 * 1000 (height) mm; 6 run through control rod guide tube 2 and are welded on core vessel 4 bottoms, are distributed on the φ 217.55mm circumference; Control rod guide tube 2 is the thimble of φ 44 * 2 * 1400 (height) mm, in lower end 400mm place and the core vessel 4 inside and outside surface-welding of going to the bottom; Control rod guide tube 2 lower surfaces are that or not soft of load do not contact with the bottom surface of urceolus 6.
For reduce the simulation thermal source to the prototype influence on flow field as far as possible, all heatings should be thin more good more.But meticulous element can bring a series of problems such as the low and insulation of specified heating power, is difficult to realize the full power simulation.Comprehensive each side factor, adopting above-mentioned diameter is the heating of φ 3.5mm.
In this device, heat transfer zone is arranged in the belt zone of φ 296~690mm, and reactor core is divided into central heating zone and heat transfer zone, and promptly φ 296mm is central heating zone with interior zone, is heat transfer zone beyond the φ 296mm.Solution reactor reactor core real power calculates by following formula:
Wherein, q
iThe power of subregion, unit are kilowatt;
q
tGeneral power, unit is kilowatt
Fr is the distribute power factor radially, is a dimensionless numerical value;
V
iThe volume of subregion, unit are cubic meter.
Radially the distribute power factor can be provided by physical computing, and the result of calculation of this device Zhong Ge district power is as shown in table 1.Wherein, the heating zone general power is 75.7kW, and the heat transfer zone general power is 124.3kW.
Table 1. power radial distribution table
??r(mm) | ??50 | ??150 | ??200 | ??250 | ??300 | ??350 |
??Fr | ??2.4 | ??2.4 | ??1.36 | ??1 | ??0.8 | ??0.5 |
??q i(kW) | ??9.6 | ??66.1 | ??33.9 | ??33.0 | ??32.8 | ??24.6 |
Described all heating major parameters are as shown in table 2.
Table 2. electrical heating elements major parameter
Shape | Word a shape | Word b shape | Circular-arc | Polyline shaped |
Length, m | ??6 | ??6 | ??6 | ??6 |
Diameter, mm | ??3.5 | ??3.5 | ??3.5 | ??3.5 |
Quantity | ??5 | ??6 | ??2 | ??20 |
Power, kW | ??6 | ??6 | ??6 | ??6 |
Surface heat flux, kW/m 2 | ??90.94 | ??90.94 | ??90.94 | ??90.94 |
Claims (3)
1. uniform inner heat source simulator of medical isotope production solution reactor, it is characterized in that: it comprises the power analog component of being made up of heater and heat exchange component, and the fission gas analog component; The word a shape heating element (7) that described heater comprises, word b shape heating element (8), circular-arc heating element (9) and polyline shaped heating element (10), wherein, 5 word a linear element (7) is distributed on the φ 100mm circumference, 6 word b linear element (8) is distributed on the φ 217.55mm circumference, 2 circular-arc elements (9) are distributed on the φ 284mm circumference, 20 polyline shaped elements (10) are distributed in the heat transfer zone, and above-mentioned all heating sectional area summations account for 2.8% of whole device flow area; Described heat exchange component comprises 20 heat exchange cooling coils (5), they are along circumferentially uniform, each root heat exchange cooling coil (5) radially is arranged in the annular region that diameter is φ 296~690mm, a heat exchange cooling coil (5) is the spirally-wound tube of 13 circle ovalizes, its major axis is 400mm, and its minor axis length is with radially being fan-shaped increase; Described fission gas analog component comprises bubble generator and analog gas, described bubble generator comprises spiracular plate (12), spiracular plate (12) is welded on the barrel of core vessel (4) bottom, interlayer is arranged as reserving the headroom between it and the core vessel base plate (13).
2. uniform inner heat source simulator of medical isotope production solution reactor according to claim 1 is characterized in that: the thickness of the interlayer between described spiracular plate (12) and the core vessel base plate (13) is 15mm; Go up the bubble generation hole (14) that is furnished with 166 φ 1mm according to solution reactor reactor core real power at spiracular plate (12), circumferentially evenly arranged 7 tracheaes on core vessel base plate (13), described analog gas is a nitrogen.
3. uniform inner heat source simulator of medical isotope production solution reactor according to claim 1 and 2 is characterized in that: the diameter of described all heating elements is φ 3.5mm, adopts the 220V alternating current, and power can reach 10~20W/cm
2
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Cited By (6)
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CN104321827A (en) * | 2011-12-05 | 2015-01-28 | 威斯康星校友研究基金会 | Apparatus and method for generating medical isotopes |
CN104371762A (en) * | 2014-08-26 | 2015-02-25 | 王乾 | Device and method for fixedly connecting slag falling port and chilling ring and cooling chilling ring |
CN105788680A (en) * | 2016-03-30 | 2016-07-20 | 中国核动力研究设计院 | Heating simulation element for reactor core |
CN109935154A (en) * | 2019-03-12 | 2019-06-25 | 中国原子能科学研究院 | A kind of isotope heat source launching site fire smoldering test method |
CN109994242A (en) * | 2017-12-29 | 2019-07-09 | 中国核动力研究设计院 | A method of it is moved in solution reactor for simulating radiolysis bubble |
CN110596745A (en) * | 2019-09-09 | 2019-12-20 | 中国工程物理研究院核物理与化学研究所 | Electric heating simulated heat source of general isotope heat source |
Family Cites Families (5)
Publication number | Priority date | Publication date | Assignee | Title |
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US5596611A (en) * | 1992-12-08 | 1997-01-21 | The Babcock & Wilcox Company | Medical isotope production reactor |
US5910971A (en) * | 1998-02-23 | 1999-06-08 | Tci Incorporated | Method and apparatus for the production and extraction of molybdenum-99 |
GB2382453B (en) * | 2002-04-11 | 2004-05-19 | Amersham Plc | Radioisotope generator and method of construction thereof |
CN101154475A (en) * | 2006-09-26 | 2008-04-02 | 王黎 | Method for producing radionuclide |
JP4618732B2 (en) * | 2006-10-20 | 2011-01-26 | 独立行政法人 日本原子力研究開発機構 | Method and apparatus for manufacturing radioactive molybdenum |
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CN104321827A (en) * | 2011-12-05 | 2015-01-28 | 威斯康星校友研究基金会 | Apparatus and method for generating medical isotopes |
CN104321827B (en) * | 2011-12-05 | 2017-02-22 | 威斯康星校友研究基金会 | Apparatus and method for generating medical isotopes |
US10332646B2 (en) | 2011-12-05 | 2019-06-25 | Wisconsin Alumni Research Foundation | Apparatus and method for generating medical isotopes |
CN104371762A (en) * | 2014-08-26 | 2015-02-25 | 王乾 | Device and method for fixedly connecting slag falling port and chilling ring and cooling chilling ring |
CN105788680A (en) * | 2016-03-30 | 2016-07-20 | 中国核动力研究设计院 | Heating simulation element for reactor core |
CN109994242A (en) * | 2017-12-29 | 2019-07-09 | 中国核动力研究设计院 | A method of it is moved in solution reactor for simulating radiolysis bubble |
CN109994242B (en) * | 2017-12-29 | 2020-12-15 | 中国核动力研究设计院 | Method for simulating movement of radiolytic bubbles in solution pile |
CN109935154A (en) * | 2019-03-12 | 2019-06-25 | 中国原子能科学研究院 | A kind of isotope heat source launching site fire smoldering test method |
CN110596745A (en) * | 2019-09-09 | 2019-12-20 | 中国工程物理研究院核物理与化学研究所 | Electric heating simulated heat source of general isotope heat source |
CN110596745B (en) * | 2019-09-09 | 2022-05-10 | 中国工程物理研究院核物理与化学研究所 | Electric heating simulated heat source of general isotope heat source |
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