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 PDF

Info

Publication number
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
Authority
CN
China
Prior art keywords
pressure vessel
reactor core
hanging basket
reactor
shielding construction
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
CN201210538783.XA
Other languages
Chinese (zh)
Other versions
CN103871492A (en
Inventor
谭怡
肖锋
李兰
闫新龙
杨舒琦
魏述平
应栋川
邓理邻
吕焕文
刘嘉嘉
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 CN201210538783.XA priority Critical patent/CN103871492B/en
Publication of CN103871492A publication Critical patent/CN103871492A/en
Application granted granted Critical
Publication of CN103871492B publication Critical patent/CN103871492B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • 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

  • 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

A kind of reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors
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.
CN201210538783.XA 2012-12-13 2012-12-13 A kind of reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors Active CN103871492B (en)

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

Family

ID=50909931

Family Applications (1)

Application Number Title Priority Date Filing Date
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

Country Status (1)

Country Link
CN (1) CN103871492B (en)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
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)

* Cited by examiner, † Cited by third party
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)

* Cited by examiner, † Cited by third party
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

Patent Citations (6)

* Cited by examiner, † Cited by third party
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

Also Published As

Publication number Publication date
CN103871492A (en) 2014-06-18

Similar Documents

Publication Publication Date Title
CN103871492B (en) A kind of reactor core shielding construction for 177 pressurized-water reactor nuclear power plant reactors
CN108511088B (en) Heavy water moderated molten salt reactor core and heavy water moderated molten salt reactor system
Sinha Advanced nuclear reactor systems–an Indian perspective
Csom et al. Thorium as an alternative fuel for SCWRs
CN103366836B (en) Fuel ball, method for making and nuclear reactor
CN205810388U (en) A kind of deep-wall type normal pressure supplying heat nuclear reactor
CN103578579B (en) A kind of fusion-fission subcritical energy reactor core of advanced person
CN103137221A (en) Subcritical wrapping layer of transmutation of pressure pipe type long-lived fission product
CN203026157U (en) Reactor core shielding structure applied to reactor of 177 pressurized water reactor nuclear power plant
CN107134298B (en) A kind of compact reactor core and power flattening method
CN103366835B (en) Fuel ball, method for making and nuclear reactor
JP6753760B2 (en) Fast reactor core
Zhou et al. Study on fission blanket fuel cycling of a fusion–fission hybrid energy generation system
KR20140096807A (en) Ultra-long Cycle Fast Reactor Using Spent Fuel
CN114496314B (en) Ultra-high flux reactor core with fast neutron thermal neutron concentric circle type partition
Xiao et al. Neutronic study of an innovative natural uranium–thorium based fusion–fission hybrid energy system
Villarino et al. Core Performance improvement using U3Si2-Al fuel in the RP-10 modernization
Hartanto et al. Conceptual study of a long-life prototype gen-IV sodium-cooled fast reactor (PGSFR)
Hartanto et al. An LEU-loaded long-life innovative sodium-cooled fast reactor (iSFR) with novel and passive safety devices
Suud Design study of small gas cooled fast nuclear power plant for synergetic energy system with renewable energy by employing pump storage
Trianti et al. Design study of thorium cycle based long life modular boiling water reactors
Kim et al. A pan-shape transuranic burner core with a low sodium void worth
Wang et al. Preliminary study on physical characteristics of single‐pass super‐critical water‐cooled reactor core
Kim et al. Systematic evaluation of uranium utilization in nuclear systems
Hartanto et al. A physics study on alternative reflectors in a compact sodium-cooled breed-and-burn fast reactor

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