CN104183278A - Reactor core of beryllium-water moderated high-flux engineering test reactor - Google Patents
Reactor core of beryllium-water moderated high-flux engineering test reactor Download PDFInfo
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- CN104183278A CN104183278A CN201310201613.7A CN201310201613A CN104183278A CN 104183278 A CN104183278 A CN 104183278A CN 201310201613 A CN201310201613 A CN 201310201613A CN 104183278 A CN104183278 A CN 104183278A
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- beryllium
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- 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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Abstract
The invention belongs to the reactor design technical field, and particularly relates to a reactor core of a beryllium-water moderated high-flux engineering test reactor. The reactor core is composed of a central fuel assembly, side reflective layers, upper reflective layers, lower reflective layers, isotopic target members and control rods; each side reflective layer comprises water gate elements, beryllium assemblies and the isotopic target members; the central fuel assembly comprises fuel assemblies; the central fuel assembly also comprises fuel assemblies each having the center with a target and a beryllium rod, and fuel assemblies each having the center with a beryllium rod; the center of each of the fuel assemblies is the beryllium rod, the upper reflective layer and the lower reflective layer of each of the fuel assemblies are each composed of aluminum, water and beryllium from outside to inside, namely the upper end part and the lower end part are each filled with a target member (C); the center of each of the fuel assemblies is composed of the beryllium rod and the external target member, the upper reflective layer and the lower reflective layer of each of the fuel assemblies are each composed of aluminum, water, target and beryllium from outside to inside, namely the upper end part and the lower end part are each filled with a target member (D). The reactor core has the isotope yield increased by 49% compared with a CETR adopted reactor core.
Description
Technical field
The invention belongs to reactor design field, be specifically related to a kind of beryllium water slowing down high flux ETR Engineering Test Reactor reactor core.
Background technology
China's ETR Engineering Test Reactor (CETR) design initial stage is main with reference to French JHR heap.
In France's JHR heap pressure-bearing shell, only have 37 lattice cells, referred to as little pneumatic shell scheme: 37 lattice cells insert 34 of fuel assemblies, have 3 lattice cells can putting material duct, other materials target can be placed on fuel assembly center pit, and reactor core is arranged underaction; This heap is mainly born material test, there is no central hot trap, and therefore thermal neutron fluence rate is lower, does not more consider Isotope production; 27 groups of control rods are arranged in fuel assembly center pit, change dumb.
CETR design also adopts little pneumatic shell scheme at the initial stage, after decide the large pneumatic shell scheme that adopts.Large pneumatic shell is that reactor core outer reflective layer is wrapped in pressure shell.Position, the outer duct of reactor core is subject to the restriction of pressure shell upper cover fairlead, and underaction is arranged in duct.But fuel assembly is furnished with to quite flexible.CETR is not also placed on critical positions Isotope production.According to China's national situation, more should emphasize comprehensive utilization.Isotope production to be placed on to critical positions.The fuel assembly of CETR forms by seven layers, although can improve fast flux, has lost excess reactivity.
China high flux ETR Engineering Test Reactor (HFETR) is undermoderated reactor core.The fission fast neutron that when stack operation, reactor core produces, can not get abundant slowing down at reactor core, enters reactor core beryllium reflector slowing down around, and quite a few turns back to reactor core the thermal neutron after slowing down.But beryllium cannot be enclosed in reactor core upper and lower end face, causes neutron leakage.Water is the good moderator of fast neutron, but the thermal neutron absorption cross section of water is larger, and it is few that thermal neutron turns back to reactor core probability.How to reduce reactor core upper and lower end face neutron leakage?
Summary of the invention
The object of the present invention is to provide a kind of beryllium water slowing down high flux ETR Engineering Test Reactor reactor core that can improve Isotope production ability.
For solving the problems of the technologies described above, the technical solution used in the present invention is:
A kind of beryllium water slowing down high flux ETR Engineering Test Reactor reactor core, this reactor core is made up of center fuel assembly, lateral reflection layer, upper and lower reflection horizon, isotopic target part and control rod; Lateral reflection layer comprises boom unit, beryllium assembly, isotopic target part; Center fuel assembly comprises fuel assembly; Center fuel assembly also comprises that center is that fuel assembly, the center of target+beryllium rod is the fuel assembly of beryllium rod; The center of described fuel assembly is beryllium rod, and the reflection horizon up and down of fuel assembly forms by aluminium+water+beryllium from outside to inside, and upper and lower end parts is filled out; The center of fuel assembly is made up of beryllium rod and outside target part thereof, and the reflection horizon up and down of fuel assembly forms by aluminium+water+target+beryllium from outside to inside, and upper and lower end parts is filled out.
The height of the described target part being made up of aluminium+water+target+beryllium is from outside to inside 10～15cm.
The height of the described target part being made up of aluminium+water+beryllium is from outside to inside 10～15cm.
The two ends up and down of described isotopic target part all exceed 10～15cm than fuel assembly.
Absorber in described control rod 9 adopts isotopic target, and its upper and lower two ends all exceed 10～15cm than fuel assembly.
The obtained beneficial effect of the present invention is:
Beryllium water slowing down high flux ETR Engineering Test Reactor reactor core of the present invention is according to the reactor core index of design, and available fuel assembly E, fuel assembly F part or replacing whole fuel assembly, to improve isotope output.Calculate through reactor core, the reactor core that reactor core of the present invention adopts than CETR, isotope output improves 49%.
The height of target part D, target part C is 10～15cm, and reactor core upper and lower end face can increase moderating power like this, reduces the absorption of water; When upper and lower end parts is stretched out 15cm, isotope improves output also can be high.
The two ends up and down of isotopic target part all exceed 10～15cm than fuel assembly, and the neutron leaking like this will be absorbed by isotopic target part.
Absorber in control rod adopts isotopic target, and its upper and lower two ends all exceed 10～15cm than fuel assembly, can reduce the invalid absorption of reactor core as far as possible, has both played the effect of control rod absorber simultaneously, produces again isotope.
Brief description of the drawings
Fig. 1 is the schematic diagram that CETR adopts reactor core.
Fig. 2 is the schematic diagram of reflection horizon up and down of beryllium water slowing down high flux ETR Engineering Test Reactor reactor core of the present invention;
Fig. 3 is that beryllium water slowing down high flux ETR Engineering Test Reactor reactor core of the present invention is arranged schematic diagram.
In figure: 1, boom unit; 2, beryllium assembly; 5, fuel assembly; 7, isotopic target part; 9, control rod; D, the target part that formed by aluminium+water+target+beryllium from outside to inside; E, center are the fuel assembly of target part+beryllium rod; F, center are the fuel assembly of beryllium rod.
Embodiment
Below in conjunction with drawings and Examples, the present invention is further detailed explanation.
As shown in Figure 2 and Figure 3, beryllium water slowing down high flux ETR Engineering Test Reactor reactor core of the present invention is made up of center fuel assembly, lateral reflection layer, upper and lower reflection horizon, isotopic target part 7 and control rod 9; Wherein center fuel assembly comprises that fuel assembly 5, center are the fuel assembly E of target+beryllium rod, the fuel assembly F that center is beryllium rod; Lateral reflection layer comprises boom unit 1, beryllium assembly 2, isotopic target part 7; Wherein boom unit 1, beryllium assembly 2, fuel assembly 5, control rod 9 are identical with existing CETR.
The center of described fuel assembly F is beryllium rod, and the reflection horizon up and down of fuel assembly F forms by aluminium+water+beryllium from outside to inside, and upper and lower end parts is filled out C; The center of fuel assembly E is made up of beryllium rod and outside target part thereof, and the reflection horizon up and down of fuel assembly E forms by aluminium+water+target+beryllium from outside to inside, and upper and lower end parts is filled out D; According to the reactor core index of design, available fuel assembly E, fuel assembly F part or replacing whole fuel assembly 5, to improve isotope output.
The target part D that is made up of aluminium+water+target+beryllium from outside to inside, the height of the target part C that is made up of aluminium+water+beryllium is 10～15cm from outside to inside, and reactor core upper and lower end face can increase moderating power like this, reduces the absorption of water.When upper and lower end parts is stretched out 15cm, isotope improves output also can be high.The two ends up and down of isotopic target part 7 all exceed 10～15cm than fuel assembly 5, and the neutron leaking like this will be absorbed by isotopic target part 7.Absorber in control rod 9 adopts isotopic target, and its upper and lower two ends all exceed 10～15cm than fuel assembly 5, can reduce the invalid absorption of reactor core as far as possible, has both played the effect of control rod absorber simultaneously, produces again isotope.
Calculate existing CETR and these two kinds of reactor cores of the present invention below.
CETR adopts reactor core:
Reactor core adopts hexangle type fuel assembly 5, its opposite side distance 70mm, seven layers of cartridge, center is the aluminium bar of diameter 14mm, outermost layer is outer-hexagonal inner circle special-shaped aluminium tubes, and totally 42 boxes, 18 account for the control rod 9, three circle isotopic target parts 7 of lattice cell, are that two circle beryllium assemblies 2, outermost two circles are boom unit 1 outward again.
Heap power 90MW operation 21 effective full power skies
Reactor core of the present invention:
Reactor core adopts hexangle type fuel assembly, its opposite side distance 70mm, and outermost layer is outer-hexagonal inner circle special-shaped aluminium tubes.The center of fuel assembly F is diameter 35mm beryllium rod, and the reflection horizon up and down of fuel assembly F forms by aluminium+water+beryllium from outside to inside, and upper and lower end parts is filled out C; The center of fuel assembly E is made up of diameter 35mm beryllium rod and outside target part thereof, and the reflection horizon up and down of fuel assembly E forms by aluminium+water+target+beryllium from outside to inside, and upper and lower end parts is filled out D; The target part D that is made up of aluminium+water+target+beryllium from outside to inside, the height of the target part C that is made up of aluminium+water+beryllium is 10cm from outside to inside.Totally 48 box F+6 box E, are that two circle beryllium assemblies 2, outermost two circles are boom unit 1 more outward at 18 control rods 9 that account for lattice cell, isotopic target part 7.
Heap power 90MW operation 21 effective full power skies
Reactor core result of calculation is as follows:
The reactor core visible, reactor core of the present invention adopts than CETR, isotope output improves 49%.
Claims (5)
1. a beryllium water slowing down high flux ETR Engineering Test Reactor reactor core, this reactor core is made up of center fuel assembly, lateral reflection layer, upper and lower reflection horizon, isotopic target part (7) and control rod (9); Lateral reflection layer comprises boom unit (1), beryllium assembly (2), isotopic target part (7); Center fuel assembly comprises fuel assembly (5); It is characterized in that: center fuel assembly also comprises that center is the fuel assembly (E) of target+beryllium rod, the fuel assembly (F) that center is beryllium rod; The center of described fuel assembly (F) is beryllium rod, and the reflection horizon up and down of fuel assembly (F) forms by aluminium+water+beryllium from outside to inside, and upper and lower end parts is filled out (C); The center of fuel assembly (E) is made up of beryllium rod and outside target part thereof, and the reflection horizon up and down of fuel assembly (E) forms by aluminium+water+target+beryllium from outside to inside, and upper and lower end parts is filled out (D).
2. beryllium water slowing down high flux ETR Engineering Test Reactor reactor core according to claim 1, is characterised in that: the height of the described target part (D) being made up of aluminium+water+target+beryllium is from outside to inside 10～15cm.
3. beryllium water slowing down high flux ETR Engineering Test Reactor reactor core according to claim 1, is characterized in that: the height of the described target part (C) being made up of aluminium+water+beryllium is from outside to inside 10～15cm.
4. beryllium water slowing down high flux ETR Engineering Test Reactor reactor core according to claim 1, is characterized in that: the two ends up and down of described isotopic target part (7) all exceed 10～15cm than fuel assembly (5).
5. beryllium water slowing down high flux ETR Engineering Test Reactor reactor core according to claim 1, is characterized in that: the absorber in described control rod (9) adopts isotopic target, and its upper and lower two ends all exceed 10～15cm than fuel assembly (5).
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| CN201310201613.7A CN104183278A (en) | 2013-05-28 | 2013-05-28 | Reactor core of beryllium-water moderated high-flux engineering test reactor |
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Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN109192333A (en) * | 2018-09-13 | 2019-01-11 | 中国核动力研究设计院 | Hexagon thimble tube fuel assembly nuclear design certificate authenticity reactor core and verification method |
| CN109192331A (en) * | 2018-09-13 | 2019-01-11 | 中国核动力研究设计院 | Hexagon thimble tube fuel assembly nuclear design certificate authenticity reactor core and method of adjustment |
| CN109273108A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | Hexagon thimble tube fuel assembly core bore road nuclear design examines reactor core and test method |
| CN109273107A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | Hexagon thimble tube fuel beryllium component nuclear design certificate authenticity reactor core and method |
| CN109712724A (en) * | 2018-12-29 | 2019-05-03 | 中国原子能科学研究院 | A kind of double reactor core zero-power facilities |
| CN110211710A (en) * | 2019-06-12 | 2019-09-06 | 中国核动力研究设计院 | A kind of more illuminated target material irradiations test core structure and arrangement and operation method |
| CN112366013A (en) * | 2020-11-10 | 2021-02-12 | 中国核动力研究设计院 | Nuclear test method suitable for heat pipe reactor |
| CN113192657A (en) * | 2021-04-29 | 2021-07-30 | 西南科技大学 | Non-uniform control rod with reflecting layer |
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Cited By (15)
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| CN109273107B (en) * | 2018-09-13 | 2020-01-14 | 中国核动力研究设计院 | Hexagonal casing type fuel beryllium component nuclear design reliability inspection reactor core and method |
| CN109192333A (en) * | 2018-09-13 | 2019-01-11 | 中国核动力研究设计院 | Hexagon thimble tube fuel assembly nuclear design certificate authenticity reactor core and verification method |
| CN109273108A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | Hexagon thimble tube fuel assembly core bore road nuclear design examines reactor core and test method |
| CN109273107A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | Hexagon thimble tube fuel beryllium component nuclear design certificate authenticity reactor core and method |
| CN109192331B (en) * | 2018-09-13 | 2020-06-23 | 中国核动力研究设计院 | Hexagonal casing type fuel assembly nuclear design reliability inspection reactor core and adjusting method |
| CN109273108B (en) * | 2018-09-13 | 2020-06-23 | 中国核动力研究设计院 | Hexagonal casing type fuel reactor core pore channel nuclear design inspection reactor core and test method |
| CN109192331A (en) * | 2018-09-13 | 2019-01-11 | 中国核动力研究设计院 | Hexagon thimble tube fuel assembly nuclear design certificate authenticity reactor core and method of adjustment |
| CN109192333B (en) * | 2018-09-13 | 2020-06-23 | 中国核动力研究设计院 | Hexagonal casing type fuel assembly nuclear design reliability inspection reactor core and verification method |
| CN109712724A (en) * | 2018-12-29 | 2019-05-03 | 中国原子能科学研究院 | A kind of double reactor core zero-power facilities |
| CN110211710A (en) * | 2019-06-12 | 2019-09-06 | 中国核动力研究设计院 | A kind of more illuminated target material irradiations test core structure and arrangement and operation method |
| CN110211710B (en) * | 2019-06-12 | 2022-03-25 | 中国核动力研究设计院 | Multi-irradiation target material irradiation inspection reactor core structure and arrangement and operation method |
| CN112366013A (en) * | 2020-11-10 | 2021-02-12 | 中国核动力研究设计院 | Nuclear test method suitable for heat pipe reactor |
| CN112366013B (en) * | 2020-11-10 | 2022-04-15 | 中国核动力研究设计院 | Nuclear test method suitable for heat pipe reactor |
| CN113192657A (en) * | 2021-04-29 | 2021-07-30 | 西南科技大学 | Non-uniform control rod with reflecting layer |
| CN113192657B (en) * | 2021-04-29 | 2022-11-04 | 西南科技大学 | Non-uniform control rod with reflecting layer |
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Application publication date: 20141203 |