CN103871492B - A kind of reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors - Google Patents
A kind of reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors Download PDFInfo
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- CN103871492B CN103871492B CN201210538783.XA CN201210538783A CN103871492B CN 103871492 B CN103871492 B CN 103871492B CN 201210538783 A CN201210538783 A CN 201210538783A CN 103871492 B CN103871492 B CN 103871492B
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- pressure vessel
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- hanging basket
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 21
- 238000010276 construction Methods 0.000 title claims abstract description 20
- 238000009413 insulation Methods 0.000 claims abstract description 4
- 230000004913 activation Effects 0.000 abstract description 4
- 239000002826 coolant Substances 0.000 abstract description 3
- 238000005516 engineering process Methods 0.000 abstract description 3
- 238000002955 isolation Methods 0.000 abstract 1
- 230000005855 radiation Effects 0.000 description 5
- 230000004907 flux Effects 0.000 description 3
- 238000005457 optimization Methods 0.000 description 3
- 230000000712 assembly Effects 0.000 description 2
- 238000000429 assembly Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000002349 favourable effect Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000002093 peripheral effect Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
Classifications
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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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- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The present invention relates to PWR nuclear power plant reactor core shield technology field, specifically disclose a kind of reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors.This reactor core shielding construction is included in outside reactor core the coaming plate and reflecting layer, hanging basket and pressure vessel installed, wherein, hanging basket and pressure vessel it is sequentially installed with outside coaming plate, and it is filled with reflecting layer in the coaming plate space with hanging basket, it is filled with water layer in the space between hanging basket and pressure vessel；Pressure vessel is externally provided with heat-insulation layer, and is positioned at normal concrete structural safety shell, utilizes air by the containment isolation of pressure vessel with normal concrete structure；Water layer thickness between hanging basket and pressure vessel is between 28cm～30cm.Reactor core shielding construction of the present invention, eliminate the traditional arrangement heat shield plate at core barrel outer wall, simplify reactor core shielding construction, alleviate core support load, reduce the activation of in-pile component, be conducive to improving the flow behavior of Main Coolant in pressure vessel.
Description
Technical field
The invention belongs to PWR nuclear power plant reactor core shield technology field, be specifically related to a kind of for 177
The reactor core shielding construction of pressurized-water reactor nuclear power plant reactor.
Background technology
In all of reactor plant, reactor core is the strongest radioactive radiation source, and run duration can produce greatly
The fission product of amount and secondary radiation source, discharge neutron and γ photon.Must basis in shielding theory design
The intensity of the various radiation source of reactor core and distribution, analytical reactions heap reactor core, in-pile component, pressure vessel, once
The irradiation situation of shielding concrete etc., determines a kind of reactor shielding structure for pressurized-water reactor nuclear power plant, full
Foot nuclear power plant radiation protection related request.
Current domestic in-service nuclear power plant, reactor core is typically made up of 121 or 157 fuel assemblies, and reactor core is peripheral
The structures such as coaming plate, reflecting layer, hanging basket, heat shielding are typically set, to weaken the neutron from reactor core and γ spoke
According to, the most secondary reactor pressure vessel inner surface fast neutron fluence adding M310 type (157 reactor core)
Rate peak value is typically 8 × 1010n/cm2About/s, primary shielding concrete inner surface Fast neutron flux peak value one
As 1 × 109n/cm2About/s.
Million kilowatt nuclear power factory reactor for 177 reactor cores carries out the optimization design of reactor core shielding construction,
This reactor core adds 20 fuel assemblies than 157 reactor cores, requires the projected life of pressure vessel to reach 60 years,
Reactor shielding design object is had higher requirement.Reactor pressure vessel inner surface should be reduced
Fast neutron fluence, flattens neutron fluence distribution, it is ensured that the pressure vessel life-span meets design requirement in 60 years, the most not
The increase reactor core shielding construction that energy is too much, strengthens the load of core support.Accordingly, it would be desirable to traditional setting-out
Heap reactor structure is optimized design, to meet corresponding requirements.
Summary of the invention
It is an object of the invention to provide a kind of reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors,
To flatten fast neutron fluence distribution, reduce pressure vessel neutron fluence rate peak value, it is ensured that the pressure vessel life-span is full
Foot design requirement in 60 years；Reduce the activation of in-pile component, make reactor shielding design result meet nuclear power plant's spoke
Penetrate protection related request.
Technical scheme is as follows: a kind of reactor core for 177 pressurized-water reactor nuclear power plant reactors shields knot
Structure, this reactor core shielding construction is included in outside reactor core the coaming plate and reflecting layer, hanging basket and pressure installed
Container, wherein, is sequentially installed with hanging basket and pressure vessel outside coaming plate, and in the coaming plate space with hanging basket
It is filled with reflecting layer, in the space between hanging basket and pressure vessel, is filled with water layer.
Described pressure vessel is externally provided with heat-insulation layer, and is positioned at normal concrete structure primary shielding.
Water layer thickness between described hanging basket and pressure vessel is between 28cm～30cm.
Described reactor core shielding construction eliminates the traditional arrangement heat shield plate at core barrel outer wall.
The remarkable result of the present invention is: one of the present invention is used for 177 pressurized-water reactor nuclear power plant reactors
Reactor core shielding construction, eliminate the traditional arrangement heat shield plate at core barrel outer wall, simplify reactor core screen
Shield structure, alleviate core support load, reduce the activation of in-pile component, be conducive to improving pressure vessel
The flow behavior of interior Main Coolant, meet the pressure vessel life-span and meet design requirement in 60 years, improve nuclear power plant
Economy.
Accompanying drawing explanation
Fig. 1 is that a kind of reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors of the present invention cuts open
Face schematic diagram；
In figure: 1, reactor core；2, coaming plate；3, reflecting layer；4, hanging basket；5, pressure vessel.
Detailed description of the invention
Below in conjunction with the accompanying drawings and the present invention is described in further detail by specific embodiment.
As it is shown in figure 1, a kind of reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors, including enclosing
Plate 2, reflecting layer 3, hanging basket 4 and pressure vessel 5, wherein, be provided with coaming plate outside reactor core 1
2, it is sequentially installed with hanging basket 4 and pressure vessel 5 outside coaming plate 2, and fills out in the space of hanging basket 4 at coaming plate 2
It is filled with reflecting layer 3, in the space between hanging basket 4 and pressure vessel 5, is filled with water layer, and the thickness of water layer
Between 28cm～30cm, such as water layer thickness can be 28cm, or 29cm, or 30cm；Pressure vessel
Heat-insulation layer is installed outside 5, and is positioned at normal concrete structure primary shielding.This reactor core shielding construction eliminates
Traditional arrangement, at the heat shield plate of core barrel outer wall, simplifies reactor core shielding construction, alleviates core support
Load, reduce the activation of in-pile component, be conducive to improving the flow behavior of Main Coolant in pressure vessel,
Meet the pressure vessel life-span meet 60 years design requirement, improve the economy of nuclear power plant.
Reactor shielding of the present invention optimizes structure, the Fast neutron flux peak value of pressure vessel inner surface
It is about 1.8 × 1010n/cm2/ s, substantially less than M310 type (8 × 1010n/cm2/ s), and distribution curve is more flat
Smooth, it is ensured that the pressure vessel life-span meets design requirement in 60 years, improves the economy of nuclear power plant.At reactor
In shielding optimization structure, primary shielding concrete inner surface Fast neutron flux peak value is about 3.1 ×
108n/cm2/ s, substantially less than M310 type (1 × 109n/cm2/ s), advantageously ensure that primary shielding concrete
The stability of structure and integrity, provide favourable guarantee for nuclear power plant's radiation protection optimization design.
Claims (2)
1. the reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors, it is characterised in that: this heap
Core shielding construction is included in coaming plate (2) and reflecting layer (3), the hanging basket that reactor core (1) is installed outward
(4) and pressure vessel (5), wherein, outside coaming plate (2), hanging basket (4) and pressure vessel it are sequentially installed with
(5), and be filled with reflecting layer (3) in the space of coaming plate (2) and hanging basket (4), at hanging basket (4) and
Being filled with water layer in space between pressure vessel (5), water layer thickness is between 28cm～30cm；Described
Reactor core shielding construction eliminate the traditional arrangement heat shield plate at core barrel (4) outer wall.
A kind of reactor core for 177 pressurized-water reactor nuclear power plant reactors the most according to claim 1 shields knot
Structure, it is characterised in that: described pressure vessel (5) is externally provided with heat-insulation layer, and is positioned at normal concrete structure
In primary shielding.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210538783.XA CN103871492B (en) | 2012-12-13 | 2012-12-13 | A kind of reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201210538783.XA CN103871492B (en) | 2012-12-13 | 2012-12-13 | A kind of reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN103871492A CN103871492A (en) | 2014-06-18 |
| CN103871492B true CN103871492B (en) | 2016-08-31 |
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| CN201210538783.XA Active CN103871492B (en) | 2012-12-13 | 2012-12-13 | A kind of reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors |
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Families Citing this family (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104658619B (en) * | 2015-02-11 | 2017-03-01 | 中国科学院合肥物质科学研究院 | Inherently safe guard method under a kind of fast neutron zero-power facility water logging major accident |
| CN104952493B (en) * | 2015-05-12 | 2018-05-25 | 中国核动力研究设计院 | A kind of control rod distributed architecture of 177 reactor core |
| CN112259275B (en) * | 2020-10-19 | 2022-02-11 | 中国核动力研究设计院 | Communication system and communication method under electromagnetic shielding environment |
| CN112792404A (en) * | 2021-01-14 | 2021-05-14 | 中广核工程有限公司 | Nuclear power station reactor core bounding wall cutting device |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN85109566A (en) * | 1984-10-31 | 1986-07-23 | 西屋电气公司 | The irradiation shielding of nuclear reactor high pressure vessel |
| US4731220A (en) * | 1985-08-14 | 1988-03-15 | Westinghouse Electric Corp. | Neutron reflector |
| US4751043A (en) * | 1984-02-03 | 1988-06-14 | Westinghouse Electric Corp. | Radial neutron reflector |
| CN1159062A (en) * | 1996-12-30 | 1997-09-10 | 常州飞机制造厂 | Metal insulating layer of nuclear reactor pressure vessel and pipeline |
| CN1193407A (en) * | 1995-07-13 | 1998-09-16 | 西屋电气公司 | Thermal insulating barrier and neutron shield providing integrated protection for a nuclear reactor vessel |
| CN203026157U (en) * | 2012-12-13 | 2013-06-26 | 中国核动力研究设计院 | Reactor core shielding structure applied to reactor of 177 pressurized water reactor nuclear power plant |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP3626844B2 (en) * | 1997-10-07 | 2005-03-09 | 三菱重工業株式会社 | Radial neutron reflector for nuclear reactors |
-
2012
- 2012-12-13 CN CN201210538783.XA patent/CN103871492B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4751043A (en) * | 1984-02-03 | 1988-06-14 | Westinghouse Electric Corp. | Radial neutron reflector |
| CN85109566A (en) * | 1984-10-31 | 1986-07-23 | 西屋电气公司 | The irradiation shielding of nuclear reactor high pressure vessel |
| US4731220A (en) * | 1985-08-14 | 1988-03-15 | Westinghouse Electric Corp. | Neutron reflector |
| CN1193407A (en) * | 1995-07-13 | 1998-09-16 | 西屋电气公司 | Thermal insulating barrier and neutron shield providing integrated protection for a nuclear reactor vessel |
| CN1159062A (en) * | 1996-12-30 | 1997-09-10 | 常州飞机制造厂 | Metal insulating layer of nuclear reactor pressure vessel and pipeline |
| CN203026157U (en) * | 2012-12-13 | 2013-06-26 | 中国核动力研究设计院 | Reactor core shielding structure applied to reactor of 177 pressurized water reactor nuclear power plant |
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| CN103871492A (en) | 2014-06-18 |
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