CN102831946B - Medical isotope production reactor capable of reducing reactor core uranium inventory - Google Patents

Medical isotope production reactor capable of reducing reactor core uranium inventory Download PDF

Info

Publication number
CN102831946B
CN102831946B CN201110160629.9A CN201110160629A CN102831946B CN 102831946 B CN102831946 B CN 102831946B CN 201110160629 A CN201110160629 A CN 201110160629A CN 102831946 B CN102831946 B CN 102831946B
Authority
CN
China
Prior art keywords
reactor
reactor core
water
core
heap
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.)
Active
Application number
CN201110160629.9A
Other languages
Chinese (zh)
Other versions
CN102831946A (en
Inventor
吴英华
李大图
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Nuclear Power Institute of China
Original Assignee
Nuclear Power Institute of China
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Nuclear Power Institute of China filed Critical Nuclear Power Institute of China
Priority to CN201110160629.9A priority Critical patent/CN102831946B/en
Publication of CN102831946A publication Critical patent/CN102831946A/en
Application granted granted Critical
Publication of CN102831946B publication Critical patent/CN102831946B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Landscapes

  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

The invention discloses a medical isotope production reactor capable of reducing reactor core uranium inventory. A fuel solution of the medical isotope production reactor is a water solution formed by mixing 24 to 34g U/L of uranium nitrate in concentration with 50 to 70% of heavy water and 30 to 50% of light water in volume. A reactor core reflecting layer is made of graphite. A reactor core is not provided with a control rod guide tube. A reactor core cooling tube in a reactor container is centralized outwards and annularly arranged between 0cm and 15cm of the inner wall of the reactor container approximately. The medical isotope production reactor reduces the uranium inventory and solves the problem of negative reactivity caused by water-adding dilution or evaporation-caused dehydration concentration of the reactor core.

Description

The Medical isotope production reactor of reactor core uranium loading amount can be reduced
Technical field
The present invention relates to a kind of nuclear reactor, be specifically related to the Core optimization of Medical isotope production reactor.
Background technology
Medical isotope production reactor is a kind of solution-type nuclear reactor.The heap power of the solution reactor run in the world is at present 20 ~ 50 kW, peak power is 50kW, heap liquor capacity less (<20L), under this power, solution reactor has inherent safety, and namely reactor core water inlet dilution or evaporation water loss concentrate and all introduce negative reactivity.Power cut-off outside, under control rod tripping, raise by solution temperature and introduce negative reactivity, make heap fall power and natural heat dissipation power balances each other, now fuel solution does not seethe with excitement.
At present, the fuel solution that Medical isotope production reactor adopts is the aqueous solution of uranyl nitrtate+light-water mixing, the defect of this fuel solution is: due to very capable to moderation of neutrons of light-water, reactor core is very little, just reaches required excess reactivity, if power is higher, then reactor core can not stable operation, if increasing reactor core, then need to increase uranium loading amount, also need to increase absorber to suppress excess reactivity; If change uranyl nitrtate+heavy water into, then because the energy force rate light-water of heavy water to moderation of neutrons is poor, thus need to fill a large amount of heavy water, cause heap core volume too large, when extracting isotope, because concentration is low, adsorptive power is poor, and thus isotope yields poorly.
In order to improve the output of medical-isotope, must improve the heap power of solution reactor, if improve heap power, liquor capacity will become large.From heap cooling, heap power stability runs and in heap solution, unit volume bubble generation can not be excessive, in order to avoid cause the angle that heap liquor capacity expands to consider, heap Solution Unit volumetric specific power should at 2.0 ~ 2.5kw/L.If the U-235 concentration of solution is constant, the excess reactivity of heap must be made too large; If reduce the U-235 concentration of solution, just can not meet the requirement that negative reactivity is all introduced in the water inlet of heap solution or dehydration.
Through calculating discovery in a large number, pancaked core (ratio of height to diameter 0.3 ~ 0.7) can meet the water inlet of heap solution or the requirement of negative reactivity is all introduced in dehydration, but, current reactor core adopts light-water to do reflection horizon, have control rod guide tube and Core cooling pipe, Core cooling pipe has two kinds of arrangements: be 1. evenly arranged (cooling tube ring-type is evenly arranged between reactor core and heap container); 2. radiation is arranged (cooling tube is outside from reactor core, and inner close outer thin ring-type radiation is arranged), and control rod guide tube and cooling tube are neutron absorber, arrange from reactor core more close to, the neutron of absorption is more, and loss of reactivity is larger, and the dress uranium amount of needs is larger.The heap of 200kW requires that liquor capacity is about 100L, when having a large amount of cooling tube and control rod guide tube, heap liquor capacity could close to or reach 100L, make heap solution fill uranium amount comparatively greatly (3.6 ~ 4.0 kilograms), very uneconomical.
At present, also do not have the solution reactor of 200 more than kW to run in the world, therefore, provide one both can reduce U-235 loading amount, can meet again the requirement of heap liquor capacity, and the Medical isotope production reactor all can introducing negative reactivity when piling solution water inlet or dehydration is necessary.
Summary of the invention
The object of the invention is to: the reactor core of Medical isotope production reactor is optimized, a kind of Medical isotope production reactor reducing reactor core uranium loading amount is provided.
Technical scheme of the present invention is as follows:
A kind of Medical isotope production reactor reducing reactor core uranium loading amount, comprise be arranged in heap container content have fuel solution and there is the reactor core of Core cooling pipe, be arranged in heap container outside core reflector, it is characterized in that: be contained in the fuel solution in heap container, for the aqueous solution that uranyl nitrtate mixes with heavy water and light-water, in this fuel solution, the volume of heavy water is 50 ~ 70%, the volume of light-water is 30 ~ 50%, and the concentration of added uranyl nitrtate is 24 ~ 34g U/L; Described core reflector adopts graphite linings; Described Core cooling pipe is outwards concentrated and is arranged in the form of a ring near heap container inner wall; Reactor core is without control rod guide tube.
Its supplementary features are:
The described Core cooling pipe be arranged in heap container, outwards concentrates and is arranged in the form of a ring between 0 ~ 15cm of heap container inner wall.
Effect of the present invention is: because fuel solution adopts the mixed liquor of uranyl nitrtate and heavy water and light-water, decrease the mistake moderating power of light-water, has both increased the volume and highly of reactor core solution, but can not excessive increase U-235 loading amount; The outside centralized arrangement of Core cooling pipe, reduces reactive loss, reduces reactor core uranium loading amount; Change reactor core light-water reflection horizon into graphite reflector and excellent conduit of removing controls, decrease U-235 loading amount; Due to the minimizing of high-enriched uranium consumption, decrease the hydrolysis of nitrogen content in feed liquid and radiolysis uranyl, be conducive to extracting medical-isotope 99mo.
Embodiment
The Medical isotope production reactor reducing reactor core uranium loading amount of the present invention, adopts the reactor core of following measure to the Medical isotope production reactor run at present to be optimized:
1. fuel solution adopts the mixed liquor of uranyl nitrtate and heavy water and light-water: if adopt uranyl nitrtate+light-water, heap container diameter is larger, and reactor core liquor capacity and highly less, unfavorable to cooling, thus the mixed liquor of uranyl nitrtate and heavy water and light-water is adopted, to reduce the mistake moderating power of light-water, increase reactor core liquor capacity and height;
2. change reactor core light-water reflection horizon into graphite reflector: because graphite is fewer than light-water absorption neutron, increases excess reactivity, reactor core uranium loading amount can be reduced;
3. Core cooling pipe adopts outside centralized arrangement (cooling tube, away from reactor core, is outwards concentrated near heap container inner wall annular configuration), reduces reactive loss, reduces reactor core uranium loading amount;
4. to remove controls excellent conduit: because the unlatching of heap and shutdown can control with the liquid level of reactor core liquor capacity, so can not arrange control rod guide tube, reactor core, without control rod guide tube, can reduce reactor core uranium loading amount further.
below in conjunction with embodiment, the invention will be further described:
A kind of Medical isotope production reactor, heap power 200kW.Heap inside diameter of vessel 700mm, heap container wall thickness 10mm, reactor core display in heap container, without control rod guide tube.Reactor core is equipped with fuel solution, and fuel solution is the aqueous solution that uranyl nitrtate mixes with heavy water and light-water, and uranyl nitrtate concentration is 24 ~ 34g U/L, and heavy water volume is 50 ~ 70%, and light-water volume is 30 ~ 50%; Core reflector is graphite reflector, is arranged in outside heap container; Core cooling pipe is outwards concentrated and is arranged in the form of a ring between 0 ~ 15cm of heap container inner wall.
Through assessing calculation, when fuel solution be the uranyl nitrtate of concentration 24 ~ 34g U/L, heavy water volume is 50 ~ 70%, light-water volume is 30 ~ 50% time, reactor core all can meet water inlet and to dilute or evaporation water loss concentrates the requirement of introducing negative reactivity.
Core result of calculation is as shown in table one, table two, table three.For reducing the effect of reactor core uranium loading amount as shown in Table 4 after Core optimization.
Table one (70%D 2o+30%H 2o)
Table two (60% D 2o+40%H 2o)
Table three (50% D 2o+50%H 2o)
Find out from table one to table three: compared with background technology, after reactor core is optimized, decrease U-235 loading amount.Above reactor core display scheme had both decreased uranium loading amount, met again reactor core water inlet dilution or evaporation water loss and concentrated and introduce the requirement of negative reactivity.
Table four (reducing reactor core uranium loading amount effectiveness comparison)
As can be seen from Table IV:
Fuel solution is uranyl nitrtate+heavy water: uranium loading amount is greater than 10 kilograms, heap core volume is greater than 200L, there is control rod guide tube, no matter adopt light-water or graphite does reflection horizon, no matter Core cooling pipe is evenly arranged, radiation arranges or outside centralized arrangement, reactor core excess reactivity (Keff) is all less than 1, can not reach critical, can not meet reactive requirement.
Fuel solution is uranyl nitrtate+light-water: when light-water does reflection horizon, has control rod guide tube, cooling tube is evenly arranged, U-235 loading amount is maximum; When light-water does reflection horizon, has control rod guide tube, cooling tube radiation is arranged, little to saving U-235 loading amount effect; Light-water does reflection horizon, has control rod guide tube, cooling tube outside centralized arrangement time, reduce U-235 loading amount; When graphite does reflection horizon, has control rod guide tube, cooling tube is evenly arranged or radiation is arranged, all do reflector saving U-235 loading amount than light-water; During centralized arrangement outside without control rod guide tube, cooling tube, better to saving U-235 loading amount effect.
Fuel solution is uranyl nitrtate+heavy water+light-water: heap core volume is greater than 100L, uranium loading amount about 2.4 kilograms, graphite does reflection horizon, reactor core without control rod guide tube, during the outside centralized arrangement of cooling tube, compared with uranyl nitrtate+heavy water or uranyl nitrtate+light-water, substantially reduce reactor core uranium loading amount, best to saving U-235 loading amount effect.

Claims (1)

1. can reduce a Medical isotope production reactor for reactor core uranium loading amount, there is power 200kW, include and be arranged in splendid attire in heap container 86.83 ~ 140.5Lfuel solution also has the reactor core of Core cooling pipe, the core reflector be arranged in outside heap container, and Core cooling pipe is outwards concentrated the inwall near heap container and arranged in the form of a ring, and without control rod guide tube, it is characterized in that:the fuel solution be contained in heap container is the mixed fuel solution of uranyl nitrtate+heavy water+light-water, and wherein uranyl nitrtate concentration is 24 ~ 30g U/L, dress uranium amount is 2.302 ~ 2.980kg, heavy water volume is 50 ~ 70%, and light-water volume is 30 ~ 50%.
CN201110160629.9A 2011-06-15 2011-06-15 Medical isotope production reactor capable of reducing reactor core uranium inventory Active CN102831946B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201110160629.9A CN102831946B (en) 2011-06-15 2011-06-15 Medical isotope production reactor capable of reducing reactor core uranium inventory

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201110160629.9A CN102831946B (en) 2011-06-15 2011-06-15 Medical isotope production reactor capable of reducing reactor core uranium inventory

Publications (2)

Publication Number Publication Date
CN102831946A CN102831946A (en) 2012-12-19
CN102831946B true CN102831946B (en) 2015-03-11

Family

ID=47335038

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201110160629.9A Active CN102831946B (en) 2011-06-15 2011-06-15 Medical isotope production reactor capable of reducing reactor core uranium inventory

Country Status (1)

Country Link
CN (1) CN102831946B (en)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN104376889A (en) * 2013-08-12 2015-02-25 中国核动力研究设计院 Reactor core of medical isotope production reactor
CN106384615B (en) * 2016-10-18 2018-03-13 中国核动力研究设计院 Save the Medical isotope production reactor of uranium fuel
CN106384616B (en) * 2016-10-18 2018-07-24 中国核动力研究设计院 The Medical isotope production reactor of uncompensated stick
CN108053910B (en) * 2017-12-07 2019-12-24 中国核动力研究设计院 Clean heap of solution heap
CN116386925B (en) * 2023-03-06 2024-03-19 中子高新技术产业发展(重庆)有限公司 Liquid subcritical isotope production system driven by accelerator

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA2098560A1 (en) * 1992-12-08 1994-02-19 Russell M. Ball Medical isotope production reactor
US5596611A (en) * 1992-12-08 1997-01-21 The Babcock & Wilcox Company Medical isotope production reactor
CN1234290A (en) * 1999-05-25 1999-11-10 中国核动力研究设计院 Extraction and purification process for production of molybdenum-99 using medical isotope production reactor
CN1992094A (en) * 2005-12-29 2007-07-04 中国核动力研究设计院 Air circuit of high power water boiler solution nuclear reactor
CN101325092A (en) * 2008-07-31 2008-12-17 中国核动力研究设计院 Solution stack for burning plutonium and transmutation of neptunium-237 or americium-241

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA2098560A1 (en) * 1992-12-08 1994-02-19 Russell M. Ball Medical isotope production reactor
US5596611A (en) * 1992-12-08 1997-01-21 The Babcock & Wilcox Company Medical isotope production reactor
CN1234290A (en) * 1999-05-25 1999-11-10 中国核动力研究设计院 Extraction and purification process for production of molybdenum-99 using medical isotope production reactor
CN1992094A (en) * 2005-12-29 2007-07-04 中国核动力研究设计院 Air circuit of high power water boiler solution nuclear reactor
CN101325092A (en) * 2008-07-31 2008-12-17 中国核动力研究设计院 Solution stack for burning plutonium and transmutation of neptunium-237 or americium-241

Non-Patent Citations (3)

* Cited by examiner, † Cited by third party
Title
溶液堆的蒙特卡罗方法物理计算模型及特性研究;汪量子;《中国博士学位论文全文数据库》;20110531;章节7.3 *
生产Mo-99、I-131和Sr-89医用同位素的水溶液堆;罗强 刘思维;《广东微量元素科学》;20061215;第13卷(第12期);章节1-2,4 *
竖直和水平圆管换热器在内热源液池内的两相换热特性;李隆键 等;《核动力工程》;20090815;第30卷(第4期);章节1-2、图1,3 *

Also Published As

Publication number Publication date
CN102831946A (en) 2012-12-19

Similar Documents

Publication Publication Date Title
CN102831946B (en) Medical isotope production reactor capable of reducing reactor core uranium inventory
CN102610284B (en) Hybrid reactor cladding for realizing long-term energy amplification by using fast-thermal coupling mixed energy spectrum
CN100578681C (en) Water boiler solution nuclear reactor having inherent security
US9014324B2 (en) Coolant with dispersed neutron poison micro-particles, used in SCWR emergency core cooling system
EP3453023A1 (en) Molten fuel nuclear reactor with neutron reflecting coolant
CN103093838B (en) Sleeve type rod-shaped fuel assembly and supercritical water-cooling nuclear reactor utilizing same
CA2999894A1 (en) Neutron reflector assembly for dynamic spectrum shifting
CN108511088B (en) Heavy water moderated molten salt reactor core and heavy water moderated molten salt reactor system
CN108172318B (en) Molten salt reactor core, molten salt reactor system, fuel circulation system and fuel circulation method
CA2723272A1 (en) Molten salt nuclear reactor
EP2421005B1 (en) Nuclear reactor
CN112992389B (en) Molten salt fast reactor
CN109545412A (en) The online removing means of PWR fuel assembly fission gas
CN104376889A (en) Reactor core of medical isotope production reactor
CN103137221A (en) Subcritical wrapping layer of transmutation of pressure pipe type long-lived fission product
CN106981320A (en) A kind of natural circulation cooling liquid heavy metal reactor
CN103871492B (en) A kind of reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors
Cao et al. Preliminary study on nuclear fuel cycle scenarios of China before 2050
CN208385016U (en) Deuterium oxide moderated molten salt reactor reactor core and deuterium oxide moderated fused salt shut-down system
JP2018071997A (en) Fast reactor core
GB1084255A (en)
CN101656112A (en) Follower component driven by driving mechanism in pressure shell and water reactor adopting same
CN104376879B (en) A kind of deficient moderated reactor reactor core
CN113241200A (en) Fuel salt loop system and operation method
CN106448753A (en) Method for solving water boiler solution nuclear reactor power fluctuation under high power

Legal Events

Date Code Title Description
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