CN107039090A - A kind of segment design sodium-cooled fast reactor control rod - Google Patents
A kind of segment design sodium-cooled fast reactor control rod Download PDFInfo
- Publication number
- CN107039090A CN107039090A CN201710324158.8A CN201710324158A CN107039090A CN 107039090 A CN107039090 A CN 107039090A CN 201710324158 A CN201710324158 A CN 201710324158A CN 107039090 A CN107039090 A CN 107039090A
- Authority
- CN
- China
- Prior art keywords
- control rod
- sodium
- cooled fast
- fast reactor
- enrichment
- 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.)
- Pending
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/24—Selection of substances for use as neutron-absorbing material
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a kind of segment design sodium-cooled fast reactor control rod, including drive mechanism, active region and with satellite composition, wherein control rod active region is segmentation structure, and segmentation structure includes absorber content from high to low from top to bottom.A kind of burnup of present invention offer is low, and caloric value is small, and surrounding fuel assembly power peak factor segmented sodium-cooled fast reactor control rod less than normal.
Description
Technical field
The invention belongs to reactor engineering field, more particularly to a kind of segment design sodium-cooled fast reactor control for sodium-cooled fast reactor
Rod processed.
Background technology
In sodium-cooled fast reactor, reactivity shimming and shutdown during reactor operation are mainly realized safely by control rod.When
In preceding sodium-cooled fast reactor design, safety rod group (SA), shim rod (SH) and regulating rod group (RE) are typically contained, some newest are set
Also contain passive rod group (PEP) in meter.Wherein, safety rod is mainly used in the emergency shut-down of reactor, and shim rod is mainly used in
The compensation of burnup reactivity and the safe shutdown of reactor, regulating rod are mainly used in automatically adjusting for reactivity.In existing control
In rod design processed, in shim rod10B enrichment is higher so that the burnup of shim rod is higher in the single loop cycle, and caloric value
It is larger, and cause around fuel assembly power peak factor it is bigger than normal.
The content of the invention
(1) goal of the invention
Instant invention overcomes the deficiencies in the prior art there is provided a kind of burnup is low, caloric value is small, and surrounding fuel assembly power
Peak factor segmented sodium-cooled fast reactor control rod less than normal.
(2) technical scheme
In order to solve the problems of prior art, the technical scheme that the present invention is provided is as follows：
A kind of segmented sodium-cooled fast reactor control rod, including drive mechanism, active region and with satellite composition, wherein control rod live
Property area be segmentation structure, segmentation structure includes absorber content from high to low from top to bottom.
Further, the segmentation structure is high enrichment boron area and low enrichment boron area two-part structure.
Further, the high enrichment boron area is10The high high enrichment boron carbide of B content, enrichment 60%-100%；Low richness
Ji Pengqu is use10The relatively low low enrichment boron carbide of B content, enrichment 10%-40%；
Further, the low enrichment boron area can use natural boron.
Further, the segmentation structure length is determined according to the reactive need of heap.
(3) beneficial effect
During reactor operation, the control rod in the present invention only has low enrichment region to be in the range of reactor core active region,
Therefore its control rod burnup is smaller, and more cycle periods can be used；Control rod heating is smaller, and circulation initial stage and end-of-cycle
Caloric value difference it is smaller, be conducive to lifting assembly outlet temperature；The power peak factor of surrounding fuel assembly is smaller, and in movement
When, the influence caused to peripheral components is smaller；Operationally, differential value is smaller, is conducive to power adjusting.Effectively raise
The economy of reactor.
It can be seen that from result of calculation, compared with traditional scheme, after the burnup by a circulation, the control of segmented
The burnup that the changes of reactivity aspect of rod value drops to B in 26/pcm, shim rod from 76/pcm is much smaller, when can be used longer
Between.Segmented sodium-cooled fast reactor control rod drops to 244/kw in terms of heat release from 369/kw, smaller than traditional scheme, causes the just end of term
Phase changed power is smaller, the influence reduction to outlet temperature, is conducive to improving reactor core mean outlet temperature.The control of segment design
The fuel assembly peak power peak factor near rod is substantially less than normal, and the full heap peak power peak factor is also less than normal, is conducive to reactor core
The flattening at power peak, improves full heap mean linear power density and average burn-up, improves the utilization rate of fuel.Compared with traditional scheme, point
There is certain difference in the control rod differential value of section design, be more beneficial for reactive regulation.
Brief description of the drawings
A kind of segmented sodium-cooled fast reactor control rod structural representations of Fig. 1
Fig. 2 traditional schemes fuel assembly fission power distribution nonuniformity coefficient
Fig. 3 uses the fuel assembly fission power distribution nonuniformity coefficient of segmented sodium-cooled fast reactor control rod
Fig. 4 traditional scheme shim rod group integral worth curves
Fig. 5 traditional scheme shim rod group differential worth curves
Fig. 6 segmented sodium-cooled fast reactor control rod group integral worth curves
Fig. 7 segmented sodium-cooled fast reactor control rod group differential worth curves
1st, drive mechanism 2, height are enriched with boron 3, low enrichment boron 4, with satellite
Embodiment
Below in conjunction with specification drawings and specific embodiments, the present invention is further elaborated.
A kind of segmented sodium-cooled fast reactor control rod for sodium-cooled fast reactor as shown in Figure 1, the control rod is by drive mechanism
1st, active region and constituted with satellite 4, active region is designed as segmentation structure, and segmentation structure includes absorber content from top to bottom
From high to low.Active region is designed as high enrichment boron 2 and the low enrichment two-part structure of boron 3 by the present embodiment, wherein high enrichment boron 2 area
Domain is10The high high enrichment boron carbide of B content, enrichment 60%-100%；Low enrichment boron 3 region is use10B content is relatively low
Low enrichment boron carbide, enrichment 10%-40%；Wherein low enrichment boron 3 region can also use natural boron.
In order that the value of control rod is consistent with the value of Traditional control rod as shown in Figure 1, in the design, activity is added
The length in area, i.e., under identical fuel activity area height, present invention activity section length is longer than traditional scheme.Simultaneously in shutdown
Control rod active region bottom is also different in the position of reactor core, in traditional scheme, during shutdown, and control rod bottom is lived with reactor core
Property area bottom it is concordant, and in the present invention, during shutdown, control rod bottom is less than reactor core active region bottom.This is mainly due in biography
In system scheme, if control rod continues to move down, control rod active section is caused away from reactor core, to cause reactive increase on the contrary,
It is thus impossible to move down again；And in the present invention, control rod active region lower surface moves down from reactor core active region bottom
When, low enrichment region is gradually distance from reactor core, and high enrichment region is gradually inserted reactor core, and full Reactivity still reduces, therefore, in this hair
In bright, control rod active region lower surface can be less than the design parameter of reactor core active region bottom, its pluggable numerical value and reactor core
It is related to the detail parameters of control rod.
The present embodiment is to typical sodium cooled fast reactor core using Traditional control rod design and the design of the present invention
Control rod worth, burnup, heat release and its influence to reactor core carried out comparative analysis, comparative analysis result is as follows.
1. calculate input
The C＆P systems parameter of structure design of table 1
| Parameter | Value |
| Absorber height/mm | 900 |
| Absorber core is block-shaped | Cylinder |
| Absorber pellet diameter (external diameter)/mm | 15.0 |
| Absorbent material | Boron carbide core |
The present invention is on the basis of Traditional control rod scheme, and it is 130cm that shim rod active section, which is lengthened, and is divided into 2 sections, its
Middle and upper part10B enrichments are 80%, and length 75cm, bottom is natural boron, length 55cm.The quantity of shim rod, other control rods
Parameter and reactor core display are identical with traditional scheme.
2. the present invention is contrasted with traditional scheme
2.1 control rod burnups
Table gives each group control rod in the burnup in single loop cycle, average burn-up and by control rod burnup is drawn
The changes of reactivity risen.
The each group control rod burnup unit of table 2：mm
*：Shim rod hypomere
**：Shim rod epimere
As can be seen from the table, compared with traditional scheme, the variable quantity of the shim rod value of segmentation scheme is smaller.
Compared with traditional scheme, B burnup is much smaller in shim rod, therefore, using segmented sodium-cooled fast reactor control rod
Life-span can be much higher than traditional scheme.
2.2 control rod heat releases
It is as shown in the table for each control rod average heat generation.
The control rod heat release of table 3/kW
As can be seen from the table, segmentation scheme is smaller than traditional scheme, causes latter stage at initial stage changed power smaller, to outlet temperature
The influence reduction of degree, is conducive to improving reactor core mean outlet temperature.
2.3 reactor cores fission power distribution nonuniformity coefficient
Fuel assembly peak power skewness coefficient, refer to current location module activity section fission maximum point power with
The ratio of full heap fuel assembly active section Average Fission power.Fig. 2 gives the maximum work of traditional scheme BOC reactor fuel components
Rate skewness coefficient.Fig. 3 gives the radial direction fission power distribution nonuniformity coefficient of segmentation scheme BOC reactor fuel components
And power distribution nonuniformity coefficient of axially fissioning.From Fig. 2 and Fig. 3 as can be seen that compared with traditional scheme, segmentation scheme compensation
The fuel assembly peak power peak factor near rod is substantially less than normal, and the full heap peak power peak factor is also less than normal.This is indicated that, is divided
Section scheme can increase the full heap mean linear power density peace of full heap in the case where not increasing full heap maximum linear heat generation rate and maximum fuel burnup
Equal burnup, so as to improve the economy of fuel.
2.4 shim rod worth curves
The integral worth curve and differential worth curve of traditional scheme shim rod group are as shown in Figure 4 and Figure 5.Segmented sodium is cold
The integral worth curve and differential worth curve of fast reactor control rod group are as shown in Figure 6 and Figure 7.As can be seen from Fig., segmented sodium
Cold fast reactor control rod worth curve is compared with traditional scheme, and the differential value ratio traditional scheme of segmentation scheme is small, and in back segment (work(
The actual rod position of rate operation phase) it is smaller, be conducive to the regulation of reactivity.
Claims (4)
1. a kind of segmented sodium-cooled fast reactor control rod, the control rod is constituted by drive mechanism, active region and with satellite, its feature exists
In active region is designed as segmentation structure, and segmentation structure includes absorber content from high to low from top to bottom.
2. a kind of segment design sodium-cooled fast reactor control rod according to claim 1, it is characterised in that the segmentation structure
For height enrichment boron area and low enrichment boron area two-part structure.
3. a kind of segment design sodium-cooled fast reactor control rod according to claim 2, it is characterised in that the high enrichment boron area
For10The high high enrichment boron carbide of B content, enrichment 60%-100%；Low enrichment boron area is use10The relatively low low richness of B content
Intensity boron carbide, enrichment 10%-40%.
4. a kind of segment design sodium-cooled fast reactor control rod according to claim 2, it is characterised in that the low enrichment boron area
For natural boron.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710324158.8A CN107039090A (en) | 2017-05-10 | 2017-05-10 | A kind of segment design sodium-cooled fast reactor control rod |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201710324158.8A CN107039090A (en) | 2017-05-10 | 2017-05-10 | A kind of segment design sodium-cooled fast reactor control rod |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN107039090A true CN107039090A (en) | 2017-08-11 |
Family
ID=59538039
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201710324158.8A Pending CN107039090A (en) | 2017-05-10 | 2017-05-10 | A kind of segment design sodium-cooled fast reactor control rod |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN107039090A (en) |
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108831569A (en) * | 2018-06-21 | 2018-11-16 | 西南科技大学 | A kind of novel reaction heap control rod and stick pair |
| CN111899899A (en) * | 2020-08-12 | 2020-11-06 | 中国核动力研究设计院 | Method for reducing HFETR reactor core nonuniformity |
| CN112133460A (en) * | 2020-08-26 | 2020-12-25 | 中国原子能科学研究院 | Fast reactor core on-line supervision method and system |
| CN112216410A (en) * | 2020-08-24 | 2021-01-12 | 中国原子能科学研究院 | Multifunctional safety rod for space nuclear reactor |
| CN112863716A (en) * | 2020-12-30 | 2021-05-28 | 中国原子能科学研究院 | A special structure of formula of pushing down reloading for changing control rod assembly moving body |
| CN114530266A (en) * | 2022-01-24 | 2022-05-24 | 中国原子能科学研究院 | Safety rod and space nuclear reactor |
| CN114530265A (en) * | 2022-01-11 | 2022-05-24 | 中国原子能科学研究院 | Safety rod for nuclear reactor and nuclear reactor |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3255092A (en) * | 1961-03-24 | 1966-06-07 | Gen Dynamics Corp | Control rods |
| CN86104957A (en) * | 1985-08-08 | 1987-04-01 | 西屋电气公司 | Consider zero reactivity redistribution factor and use the full length control rod of axial inhomogeneous absorbing material |
| CN103928061A (en) * | 2013-01-14 | 2014-07-16 | 上海核工程研究设计院 | Reverse pushing type reactor pressure vessel and reactor internals thereof |
| CN103985420A (en) * | 2014-06-05 | 2014-08-13 | 西南科技大学 | Control rod capable of flattening axial power distribution of reactor core and control rod assembly |
| CN105957561A (en) * | 2016-07-05 | 2016-09-21 | 上海核工程研究设计院 | Control rod mechanism |
-
2017
- 2017-05-10 CN CN201710324158.8A patent/CN107039090A/en active Pending
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3255092A (en) * | 1961-03-24 | 1966-06-07 | Gen Dynamics Corp | Control rods |
| CN86104957A (en) * | 1985-08-08 | 1987-04-01 | 西屋电气公司 | Consider zero reactivity redistribution factor and use the full length control rod of axial inhomogeneous absorbing material |
| CN103928061A (en) * | 2013-01-14 | 2014-07-16 | 上海核工程研究设计院 | Reverse pushing type reactor pressure vessel and reactor internals thereof |
| CN103985420A (en) * | 2014-06-05 | 2014-08-13 | 西南科技大学 | Control rod capable of flattening axial power distribution of reactor core and control rod assembly |
| CN105957561A (en) * | 2016-07-05 | 2016-09-21 | 上海核工程研究设计院 | Control rod mechanism |
Non-Patent Citations (1)
| Title |
|---|
| 阎昌琪等: "《核反应堆工程》", 31 January 2014, 哈尔滨工程大学出版社 * |
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108831569A (en) * | 2018-06-21 | 2018-11-16 | 西南科技大学 | A kind of novel reaction heap control rod and stick pair |
| CN111899899A (en) * | 2020-08-12 | 2020-11-06 | 中国核动力研究设计院 | Method for reducing HFETR reactor core nonuniformity |
| CN111899899B (en) * | 2020-08-12 | 2022-03-25 | 中国核动力研究设计院 | Method for reducing HFETR reactor core nonuniformity |
| CN112216410A (en) * | 2020-08-24 | 2021-01-12 | 中国原子能科学研究院 | Multifunctional safety rod for space nuclear reactor |
| CN112133460A (en) * | 2020-08-26 | 2020-12-25 | 中国原子能科学研究院 | Fast reactor core on-line supervision method and system |
| CN112133460B (en) * | 2020-08-26 | 2022-07-01 | 中国原子能科学研究院 | Fast reactor core online monitoring method and system |
| CN112863716A (en) * | 2020-12-30 | 2021-05-28 | 中国原子能科学研究院 | A special structure of formula of pushing down reloading for changing control rod assembly moving body |
| CN112863716B (en) * | 2020-12-30 | 2022-12-13 | 中国原子能科学研究院 | A special structure of formula of pushing down reloading for changing control rod assembly moving body |
| CN114530265A (en) * | 2022-01-11 | 2022-05-24 | 中国原子能科学研究院 | Safety rod for nuclear reactor and nuclear reactor |
| CN114530265B (en) * | 2022-01-11 | 2024-03-22 | 中国原子能科学研究院 | Safety rod for nuclear reactor and nuclear reactor |
| CN114530266A (en) * | 2022-01-24 | 2022-05-24 | 中国原子能科学研究院 | Safety rod and space nuclear reactor |
| CN114530266B (en) * | 2022-01-24 | 2024-05-14 | 中国原子能科学研究院 | Safety rod and space nuclear reactor |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN107039090A (en) | A kind of segment design sodium-cooled fast reactor control rod | |
| CN103985420B (en) | A kind of control rod that can flatten the distribution of reactor core axial power and C&P systems | |
| CN109036603B (en) | Long-circulation refueling and loading method for reactor core of ultra-large pressurized water reactor | |
| CN101128885B (en) | Fuel bundle for pressurized-water reactor and method of designing fuel bundle | |
| CN113012826B (en) | Small-sized lead-cooled fast reactor core | |
| CN207233400U (en) | A kind of segment design sodium-cooled fast reactor control rod | |
| CN113161021A (en) | Hollow uranium nitride fuel element of fast neutron reactor | |
| CN109473183A (en) | A kind of ultra-large type pressurized-water reactor nuclear power plant reactor core display | |
| JPH03108690A (en) | Fuel assembly | |
| Fareha et al. | Design Study of 600 MWt Long Life Modular Gas Cooled Fast Reactors | |
| Nguyen et al. | Optimization of centrally shielded burnable absorbers in soluble-boron-free SMR design | |
| JPH03179293A (en) | Fuel assembly | |
| CN118136289A (en) | Control method and system for power boost of high-temperature gas cooled reactor and electronic equipment | |
| Hong et al. | The KALIMER-600 Reactor Core Design Concept with Varying Fuel Cladding Thickness | |
| JP2003107183A (en) | Mox fuel assembly for thermal neutron reactor | |
| JP2024063575A (en) | How to control the reactor core | |
| KR102060778B1 (en) | Method of reducing nuclear fuel for heavy-water reactor | |
| Xiaoling et al. | Summary of the History of Improvement and Optimization of Fuel Management Strategies for Two 1000 MWe PWR Units | |
| Wang | Researches on the In-Core Reload Design for TianWan Nuclear Power Station | |
| JP3085715B2 (en) | Reactor operation method | |
| CN1783354A (en) | Method for inhibiting quadrantal power inclination of pressurized water reactor nuclear power station | |
| WO2022061689A1 (en) | Burnable poison rod and fuel assembly containing burnable poison rod | |
| Wu et al. | Performance of different absorber materials and move-in/out strategies for the control rod in small rod-controlled pressurized water reactor: A study based on KLT-40 model | |
| CN116525151A (en) | Efficient nuclear power station reactor core fuel loading transition arrangement method | |
| STATION | RESEARCHES ON THE IN-CORE RELOAD DESIGN FOR TIANWAN |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| RJ01 | Rejection of invention patent application after publication | ||
| RJ01 | Rejection of invention patent application after publication |
Application publication date: 20170811 |