CN109994227A - A kind of tungsten material heat shield plate - Google Patents

A kind of tungsten material heat shield plate Download PDF

Info

Publication number
CN109994227A
CN109994227A CN201711468527.7A CN201711468527A CN109994227A CN 109994227 A CN109994227 A CN 109994227A CN 201711468527 A CN201711468527 A CN 201711468527A CN 109994227 A CN109994227 A CN 109994227A
Authority
CN
China
Prior art keywords
tungsten
heat shield
shield plate
pressure vessel
tungsten material
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
Application number
CN201711468527.7A
Other languages
Chinese (zh)
Inventor
唐松乾
吕焕文
肖锋
谭怡
景福庭
应栋川
邓理邻
李兰
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 CN201711468527.7A priority Critical patent/CN109994227A/en
Publication of CN109994227A publication Critical patent/CN109994227A/en
Pending legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C11/00Shielding structurally associated with the reactor
    • G21C11/08Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
    • G21C11/083Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation consisting of one or more metallic layers
    • G21C11/085Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation consisting of one or more metallic layers consisting exclusively of several metallic layers
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Biomedical Technology (AREA)
  • General Health & Medical Sciences (AREA)
  • Molecular Biology (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Powder Metallurgy (AREA)

Abstract

The invention belongs to nuclear reactor designs technical fields, and in particular to a kind of tungsten material heat shield plate.The tungsten material heat shield plate can be nested in inside the hollow involucrum of stainless steel by tungsten plate and be formed, ferro element can be added in tungsten base or nickel element forms tungsten alloy material and formed, the materials packing materials such as lead, boracic carbon steel can be nested in inside the hollow involucrum of tungsten material and be formed, can also formed using tungsten material merely.The present invention has excellent neutron shield effect, can significantly reduce the fast neutron fluence peak value of pressure vessel, reduce the radiation embrittlement of pressure vessel, increase the service life of pressure vessel.

Description

A kind of tungsten material heat shield plate
Technical field
The invention belongs to nuclear reactor designs technical fields, and in particular to a kind of tungsten material heat shield plate.
Background technique
Reactor pressure vessel is the key equipment for determining nuclear power station service life, during normal reactor operation, heap The neutron that core fission generates can persistently bombard pressure vessel material, increase it without brittle transition temperature, influence pressure The use of container.Since the spacing between component each in reactor and pressure vessel is had nothing in common with each other, the fission power of each component It is not quite similar, therefore the distribution of neutron fluence suffered by pressure vessel and uneven.The overall performance of pressure vessel depends on it most Generally there is the position meeting of peak value for pressure vessel neutron fluence in hanging basket outer surface in reactor design in weak position Heat shield plate is set, to reduce neutron fluence suffered by pressure vessel, while flattening the distribution of neutron fluence suffered by pressure vessel.
The design of traditional reactor heat shield plate generally uses stainless steel material, shield effectiveness one of the material for neutron As, the peak value of neutron fluence suffered by pressure vessel can only be reduced to a certain extent, effect is not obvious enough, can not eliminate it is in place The neutron fluence peak set.Design uses the better heat shield plate of shield effectiveness thus, and providing preferably irradiation for pressure vessel makes With environment very it is necessary to.
Summary of the invention
The technical problem to be solved in the invention are as follows: stainless steel hot barricade neutron shield effect in the prior art is difficult to Meet technical requirements, neutron fluence peak value suffered by pressure vessel can not be significantly reduced.
It is described that technical scheme is as follows:
A kind of tungsten material heat shield plate, including the hollow involucrum of stainless steel and tungsten plate, tungsten plate are nested in the hollow involucrum of stainless steel It is internal.
A kind of tungsten material heat shield plate, material be tungsten material or tungsten alloy material, the tungsten alloy material be Alloy material of the tungsten base added with ferro element or nickel element.
A kind of tungsten material heat shield plate, including the hollow involucrum of tungsten material and packing material, packing material are nested in tungsten material Inside hollow involucrum.As a preferred solution: the packing material is lead material or boracic carbon steel material.
The invention has the benefit that
(1) a kind of tungsten material heat shield plate of the invention, can significantly reduce the peak value of neutron fluence suffered by pressure vessel, Improve pressure vessel radiation environment, make it possible increase pressure vessel service life;
(2) a kind of tungsten material heat shield plate of the invention, using tungsten material, tungsten material atom ordinal number density is all higher, removes Outside with preferable gamma ray shielding ability, also there is good shield effectiveness to fast neutron, uses tungsten material as heat shielding The material of plate can be significantly reduced the neutron fluence peak value of pressure vessel;
(3) a kind of tungsten material heat shield plate of the invention, tungsten material have the characteristics such as nontoxic, high temperature resistant, corrosion-resistant can Meet working environment harsh in reactor, for tungsten material after by neutron activation, the radioactivity of activation products is smaller, in subsequent The maintenance and replacement of sub- barricade are provided convenience;
(4) a kind of tungsten material heat shield plate of the invention, can make the neutron fluence peak value of pressure vessel inner surface significant Decline: by taking typical 157 reactor core nuclear power stations as an example, pressure vessel fast neutron fluence peak value is generally present near 0 ° of position, if single Former stainless steel hot barricade solely is replaced using the heat shield plate of tungsten material, then the peak value of pressure vessel fast neutron fluence E > 1.0MeV About 30%, E > 0.1MeV peak value, which can be declined, can decline about 40%, design compared to the former heat shield plate using stainless steel, The distribution of pressure vessel fast neutron fluence can also be significantly improved.If replacing stainless steel using tungsten-bast alloy or stainless Increase the interlayer of tungsten sill in Steel material, shield effectiveness, which can be weaker than, is used alone tungsten material, but still enables to pressure The fast neutron fluence of container is decreased significantly, while making heat shield plate itself mechanical performance and significant changes do not occur.Pressure is held The case where decline of device fast neutron fluence peak value can improve pressure vessel material radiation embrittlement, thus lengthening the life for pressure vessel Equal offers support.When because of irradiation behaviour obvious deteriorate occurs for reactor pressure vessel material, it can also be used as one kind and remedy hand Section has potential engineering value and economic value.
Detailed description of the invention
Fig. 1 is the tungsten material heat shield plate in embodiment 1.
In figure, the hollow involucrum of 1- stainless steel, 2- tungsten plate.
Specific embodiment
A kind of tungsten material heat shield plate of the invention is described in detail with reference to the accompanying drawings and examples.
Tungsten material heat shield plate in the present embodiment is manufactured in advance by modes such as castings, heat shield plate as needed The specific design requirement of cradle cylinder body be fabricated to respective shapes.According to the neutron fluence distribution situation of pressure vessel, determination is hung Basket cylinder needs the region using heat shield plate, and heat shield plate is installed on cradle cylinder body surface by fixed forms such as bolts.
Embodiment 1
As shown in Figure 1, the tungsten material heat shield plate in the present embodiment, including the hollow involucrum of stainless steel and tungsten plate, tungsten plate are embedding It is placed on inside the hollow involucrum of stainless steel, forms novel heat shield structure, improving heat shield plate to the same of fast neutron screening ability When, do not change the performance of heat shield plate itself.
Embodiment 2
Tungsten material heat shield plate in the present embodiment, material are tungsten material or tungsten alloy material.
The tungsten alloy material is the tungsten alloy material added with elements such as iron, nickel, and reducing, pressure vessel is fast It provides while neutron fluence peak value compared with the better mechanical performance of tungsten material itself.
Embodiment 3
Tungsten material heat shield plate in the present embodiment, including the hollow involucrum of tungsten material and packing material, packing material are nested Inside the hollow involucrum of tungsten material, hierarchical design can realize the shielding to fast neutron to the maximum extent, reach shielding design Optimum target.
The packing material is the materials such as lead, boracic carbon steel.
Embodiment 4
Tungsten material heat shield plate in the present embodiment can be manufactured in advance by modes such as castings, according to design requirement system It is made designated shape;Manufactured heat shield plate can be used for replacement original and transported in addition to can apply to the out-of-pile newly run The stainless steel hot barricade of row reactor needs to unload former heat shield plate by specific purpose tool first, and using bolted New heat shield plate is mounted on hanging basket by mode.

Claims (4)

1. a kind of tungsten material heat shield plate, including the hollow involucrum of stainless steel and tungsten plate, it is characterised in that: tungsten plate is nested in stainless steel Inside hollow involucrum.
2. a kind of tungsten material heat shield plate, material is tungsten material or tungsten alloy material, it is characterised in that: straight using tungsten material Production heat shield plate is connect, or makes heat shield plate using containing the tungsten-bast alloy of ferro element or nickel element.
3. a kind of tungsten material heat shield plate, including the hollow involucrum of tungsten material and packing material, it is characterised in that: packing material is nested Inside the hollow involucrum of tungsten material.
4. tungsten material heat shield plate according to claim 3, it is characterised in that: the packing material is lead material or boracic Carbon steel material.
CN201711468527.7A 2017-12-29 2017-12-29 A kind of tungsten material heat shield plate Pending CN109994227A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201711468527.7A CN109994227A (en) 2017-12-29 2017-12-29 A kind of tungsten material heat shield plate

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201711468527.7A CN109994227A (en) 2017-12-29 2017-12-29 A kind of tungsten material heat shield plate

Publications (1)

Publication Number Publication Date
CN109994227A true CN109994227A (en) 2019-07-09

Family

ID=67108541

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201711468527.7A Pending CN109994227A (en) 2017-12-29 2017-12-29 A kind of tungsten material heat shield plate

Country Status (1)

Country Link
CN (1) CN109994227A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114962862A (en) * 2022-05-13 2022-08-30 安徽工业大学 Single-layer heat insulation shielding device for high-temperature pipeline of nuclear power station

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4743423A (en) * 1984-09-28 1988-05-10 Westinghouse Electric Corp. Neutron shield panel arrangement for a nuclear reactor pressure vessel
EP0483555A1 (en) * 1990-10-24 1992-05-06 ANSALDO S.p.A. An intrinsic arrangement for power stabilization in a thermal nuclear reactor
US20070194256A1 (en) * 2005-05-10 2007-08-23 Space Micro, Inc. Multifunctional radiation shield for space and aerospace applications
CN101504872A (en) * 2008-02-08 2009-08-12 西屋电气有限责任公司 Advanced gray rod control assembly

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4743423A (en) * 1984-09-28 1988-05-10 Westinghouse Electric Corp. Neutron shield panel arrangement for a nuclear reactor pressure vessel
EP0483555A1 (en) * 1990-10-24 1992-05-06 ANSALDO S.p.A. An intrinsic arrangement for power stabilization in a thermal nuclear reactor
US20070194256A1 (en) * 2005-05-10 2007-08-23 Space Micro, Inc. Multifunctional radiation shield for space and aerospace applications
CN101504872A (en) * 2008-02-08 2009-08-12 西屋电气有限责任公司 Advanced gray rod control assembly

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
《电离辐射防护基础与实践》: "《电离辐射防护基础与实践》", 31 December 2011, pages: 164 *
R.F.博格斯等: "《中子发生器运行中的辐射安全问题》", 28 February 1981, pages: 18 *

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114962862A (en) * 2022-05-13 2022-08-30 安徽工业大学 Single-layer heat insulation shielding device for high-temperature pipeline of nuclear power station

Similar Documents

Publication Publication Date Title
EP2956944B1 (en) Nuclear reactor target assemblies and methods for producing isotopes, modifying materials within target material, and/or characterizing material within a target material
CN103174912A (en) Nuclear power plant device and composite type insulating layer used for pipeline
CN103106938B (en) A kind of spent fuel transport container with damping, protecting against shock spring assembly
CN102498541B (en) There is electronics and the target assembly of photon window
CN109994227A (en) A kind of tungsten material heat shield plate
CN108648844B (en) Novel spent fuel transportation equipment
RU2686399C1 (en) Device and method for coating long products
CN203026182U (en) Spent fuel transporting container with damping and impact-preventing spring device
CN105427997A (en) Electromagnetic coil framework for reactor as well as inner framework and outer casing on electromagnetic coil framework
CN108648842B (en) Material product cup of nuclear fuel post-processing factory
CN104651857A (en) Carburizing and quenching deformation control method for gears of large-sized heavy-load locomotive
CN102794612B (en) Preparation method of W/Cu composite component
CN107805777A (en) A kind of tungsten boron stratified material with ray and neutron comprehensive shielding effect
CN102606823A (en) Constant-stress constant-displacement-line sealing component
US3016462A (en) Multi-layer vessel having a gamma ray flux absorbing layer
CN203131329U (en) Composite type thermal insulation layer for nuclear plant equipment and pipeline
CN109296869A (en) A kind of nuclear leve equipment and pipeline disperse filled composite insulating layer
CN109785987A (en) A kind of tungsten alloy particle spallation target material
US2894889A (en) Jacketed uranium slugs and method
ZA202208023B (en) Layered neutron shielding
CN104681116A (en) Cobalt regulating rod and cobalt rod cluster component used for producing medical cobalt source with high specific activity
CN203026157U (en) Reactor core shielding structure applied to reactor of 177 pressurized water reactor nuclear power plant
CN109616227B (en) Dispersion filling composite function metal heat preservation
CN208991455U (en) A kind of roll of heat-resistant anti-fatigue quick distachable composite construction rolling copper bar
CN102955165A (en) Method for compensating X and gamma energy response of ionization chamber by aluminum material

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

Application publication date: 20190709

RJ01 Rejection of invention patent application after publication