CN109801718A - A kind of inherently safe presurized water reactor of the removable separation of reactor core - Google Patents
A kind of inherently safe presurized water reactor of the removable separation of reactor core Download PDFInfo
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- CN109801718A CN109801718A CN201811490807.2A CN201811490807A CN109801718A CN 109801718 A CN109801718 A CN 109801718A CN 201811490807 A CN201811490807 A CN 201811490807A CN 109801718 A CN109801718 A CN 109801718A
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- reactor core
- reactor
- presurized water
- water reactor
- inherently safe
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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
Abstract
The invention discloses a kind of inherently safe presurized water reactors of the removable separation of reactor core, it is related to nuclear engineering field, if the inherently safe presurized water reactor forms cylindrical presurized water reactor entirety by isometric moveable stem portion, support system is separated by reactor core, described each section is separated under extreme accident conditions, reactor core is made to be in subcritical state, after the exclusion of extreme accident classification, described each section is closed up, keeps reactor core again critical.The inherently safe presurized water reactor can be avoided the reactor core under the extreme accident such as station blackout and superposition card rod, dilution system failure and criticality accident occur, and have a degree of inherent safety.
Description
Technical field
The present invention relates to nuclear engineering fields, and in particular to a kind of inherently safe presurized water reactor of the removable separation of reactor core.
Background technique
Presurized water reactor (pressurized water reactor), full name " pressurization water moderation cooled reactor ".With pressurization
, the reactor that the light-water not boiled (i.e. light water) is as moderator and coolant.It is (simultaneous by fuel assembly, moderator
Make coolant), C&P systems, burnable poison assembly, Neutron source assembly, the composition such as core barrel and pressure vessel.It is nuclear power station
Middle number of applications is most, the maximum heap-type of capacity.
Existing pressurized water reactor core adds water reflecting layer, is an entirety of approximate cylindrical shape, in case of nuclear power
Factory's station blackout accident, in the case where the extreme cases such as card rod, dilution system failure occur, existing presurized water reactor is possible to occur critical
Accident, cause presurized water reactor can not normal shutdown, thus can not accomplish waste heat export and radionuclide containing.
Summary of the invention
The purpose of the present invention is in view of the above shortcomings of the prior art, provide a kind of intrinsic peace of removable separation of reactor core
Total pressure water-water reactor overcomes existing presurized water reactor and the poles such as nuclear power plant's station blackout accident and superposition card rod, dilution system failure is occurring
End situation is possible to that this defect of criticality accident can occur.
The purpose of the present invention can be achieved through the following technical solutions:
A kind of inherently safe presurized water reactor of the removable separation of reactor core, the inherently safe presurized water reactor is by isometric moveable
If it is whole that stem portion forms cylindrical presurized water reactor, support system is separated by reactor core, to each portion under extreme accident conditions
It is separated, reactor core is made to be in subcritical state, after the exclusion of extreme accident classification, described each section closed up, is made
Reactor core can be again critical.
Further, described each section has an identical grid number, identical fuel rod number, control rod number and flammable
Poisonous substance in order to fuel management and reduces power peak factor.
Further, the reactor core separation support system can guarantee that under accidental conditions, reactor core each section occurs
It contacts and does not squeeze；Under extreme accident conditions, reactor core each section is separated, and reaches subcritical state；In extreme thing
Therefore after troubleshooting, reactor core each section contacts again, reaches critical state again.
Further, it is whole by isometric moveable four part form cylinder presurized water reactor for the inherently safe presurized water reactor
Body.
Compared with the prior art, the invention has the following advantages and beneficial effects:
The inherently safe presurized water reactor of the removable separation of reactor core provided by the invention, it is disconnected in full factory to avoid traditional presurized water reactor
The reactor core criticality accident that may occur under the extreme accident such as electricity and superposition card rod, dilution system failure, this inherently safe pressure water
Heap can divide several mobile parts by the way that reactor core to be divided into, so that in station blackout and superposition card rod, dilution system mistake
Reactor core each section can separate under the extreme accident such as effect, due to the increase of neutron leakage after separation, so that presurized water reactor is no longer critical,
It can be avoided the reactor core under the extreme accident such as station blackout and superposition card rod, dilution system failure and criticality accident occur, therefore make
There to be a degree of inherent safety with presurized water reactor proposed by the present invention.
Detailed description of the invention
Fig. 1 is existing presurized water reactor schematic diagram.
Fig. 2 is the inherently safe presurized water reactor schematic diagram of the removable separation of reactor core provided in an embodiment of the present invention.
Fig. 3 is inherently safe presurized water reactor provided in an embodiment of the present invention each section point in the case where reactor core separates support system control
From schematic diagram.
Fig. 4 is that inherently safe presurized water reactor provided in an embodiment of the present invention each section in the case where reactor core separates support system control is closed
The schematic diagram held together.
Specific embodiment
Present invention will now be described in further detail with reference to the embodiments and the accompanying drawings, but embodiments of the present invention are unlimited
In this.
Embodiment:
Present embodiments provide a kind of inherently safe presurized water reactor of the removable separation of reactor core, the inherently safe presurized water reactor by
If it is whole that isometric moveable stem portion forms cylindrical presurized water reactor, support system is separated by reactor core, in extreme accident work
Described each section is separated under condition, reactor core is made to be in subcritical state, after the exclusion of extreme accident classification, to each portion
Divide and closed up, keeps reactor core again critical.
When nuclear power plant's station blackout accident occurs, reactor core separation support system can to justify the inherently safe presurized water reactor
Cylinder reactor core splits into several parts, these parts then disengage, so that neutron leakage increases, so that reactor core
It is no longer critical, to fundamentally avoid the generation of criticality accident, therefore for existing presurized water reactor, the present embodiment is mentioned
Out be the presurized water reactor with innovative idea, the extreme shape such as the power-off of full heap and superposition card rod, dilution system failure can occur
Automatic shutdown under condition, thus there is better inherent safety.
Since the effective multiplication factor of presurized water reactor can be by shown in formula (1):
K=ε pf η x (1)
K in formula (1) indicates the effective multiplication factor of pressurized water reactor core, if k=1, reactor core is in critical state；Such as
Fruit k > 1, then reactor core is in a supercritical state；If k < 1, reactor core is in subcritical state.In accidental conditions, presurized water reactor
Reactor core is in critical state, i.e., corresponding effective multiplication factor k=1；ε in formula (1) indicates fast multiplication coefficient；Formula (1)
In p expression escape RESONANCE ABSORPTION probability；F in formula (1) indicates thermal neutron utilization factor；η in formula (1) indicates effectively fission
Neutron population；X in formula (1) indicates non-leakage probability.If initial state is critical, initial k=1, if this
When reactor core each section separate, then the Leakage probability of reactor core increases, that is, the non-leakage probability reduction of reactor core, that is, formula
(1) x in reduces, then the k on the equation left side can also reduce, so that k < 1, reactor core will be in subcritical state at this time.
Existing pressurized water reactor core adds water reflecting layer, is approximate cylindrical shape, as shown in Figure 1.It is solid in order to increase it
There is safety, the presurized water reactor that the present embodiment proposes then forms cylindrical shape by several parts, as shown in Figure 2.Each section is by heap
Core separation support system is controlled, and under accidental conditions, reactor core each section is in contact condition, as shown in figure 4, heap at this time
Core is just at critical state.However, when the extreme accident such as station blackout and superposition card rod, dilution system failure occurs, it can
Under the stretching of reactor core separation support system, rapidly each section is separated, as shown in Figure 3.Pass through observation reactor core separation support
The flexible length of system, that is, may know that the intermittent lengths of reactor core each section separation.Interval between each section is bigger, and neutron leakage is got over
More, neutron non-leakage probability is smaller, then corresponding effective multiplication factor is also smaller, therefore subcriticality is also deeper, and then keeps away
The generation of extreme accident lower critical accident is exempted from.
After extreme accident excludes, reactor core each section can be made to lean at leisure under the extruding that reactor core separates support system
Hold together, when each section is in contact, reactor core separation support system no longer squeezes reactor core each section, only plays fixed support and makees
With.Neutron leakage reduces at this time, and reactor core effective multiplication factor rises at leisure, so that reactor core is critical at leisure.
The above, only the invention patent preferred embodiment, but the scope of protection of the patent of the present invention is not limited to
This, anyone skilled in the art is in the range disclosed in the invention patent, according to the present invention the skill of patent
Art scheme and its patent of invention design are subject to equivalent substitution or change, belong to the scope of protection of the patent of the present invention.
Claims (4)
1. a kind of inherently safe presurized water reactor of the removable separation of reactor core, it is characterised in that: the inherently safe presurized water reactor is by waiting bodies
If it is whole that the moveable stem portion of product forms cylindrical presurized water reactor, support system is separated by reactor core, under extreme accident conditions
Described each section is separated, reactor core is made to be in subcritical state, extreme accident classification exclusion after, to described each section into
Row closes up, and keeps reactor core again critical.
2. a kind of inherently safe presurized water reactor of the removable separation of reactor core according to claim 1, it is characterised in that: described each
There are identical grid number, identical fuel rod number, control rod number and burnable poison, in order to fuel management and drop in part
The low-power peak factor.
3. a kind of inherently safe presurized water reactor of the removable separation of reactor core according to claim 1, it is characterised in that: the heap
Core separation support system can guarantee that under accidental conditions, reactor core each section is in contact and does not squeeze；Extreme
Under accident conditions, reactor core each section is separated, and reaches subcritical state；After the exclusion of extreme accident classification, reactor core each section
Again it contacts, reaches critical state again.
4. a kind of inherently safe presurized water reactor of the removable separation of reactor core according to claim 1, it is characterised in that: described solid
Cylindrical presurized water reactor entirety is formed by isometric moveable four part by safe presurized water reactor.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811490807.2A CN109801718B (en) | 2018-12-06 | 2018-12-06 | Intrinsic safety pressurized water reactor with movable and separable reactor core |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811490807.2A CN109801718B (en) | 2018-12-06 | 2018-12-06 | Intrinsic safety pressurized water reactor with movable and separable reactor core |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN109801718A true CN109801718A (en) | 2019-05-24 |
| CN109801718B CN109801718B (en) | 2020-12-22 |
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| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201811490807.2A Active CN109801718B (en) | 2018-12-06 | 2018-12-06 | Intrinsic safety pressurized water reactor with movable and separable reactor core |
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| US20030012328A1 (en) * | 2000-07-14 | 2003-01-16 | Kazuyoshi Kataoka | Supercritical-pressure water cooled reactor and power generation plant |
| CN1783352A (en) * | 2004-12-03 | 2006-06-07 | 大亚湾核电运营管理有限责任公司 | Reactor core loading method of pressurized water reactor nuclear power station reactor |
| CN1921027A (en) * | 2006-09-15 | 2007-02-28 | 中国核动力研究设计院 | Atomic reactor core for nuclear power station |
| CN103258576A (en) * | 2012-02-17 | 2013-08-21 | 中国原子能科学研究院 | Nuclear reactor for moon surface |
| CN103489488A (en) * | 2012-06-11 | 2014-01-01 | 中国核动力研究设计院 | Module type pressurized water reactor |
| CN104240772A (en) * | 2014-09-15 | 2014-12-24 | 中国工程物理研究院核物理与化学研究所 | Z-pinch driven fusion-fission hybrid energy reactor |
| CN204577112U (en) * | 2015-05-12 | 2015-08-19 | 中国核动力研究设计院 | The Class PWR Plants reactor core of a kind of employing 177 fuel assemblies |
| CN106128517A (en) * | 2016-06-24 | 2016-11-16 | 西安交通大学 | A kind of supercritical carbon dioxide cooling rickle using rod shape fuel assembly |
| US20170162278A1 (en) * | 2015-11-01 | 2017-06-08 | Daniel Laughman | Block-type movable reflector/moderator (RM) for nuclear reactor control |
-
2018
- 2018-12-06 CN CN201811490807.2A patent/CN109801718B/en active Active
Patent Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20030012328A1 (en) * | 2000-07-14 | 2003-01-16 | Kazuyoshi Kataoka | Supercritical-pressure water cooled reactor and power generation plant |
| CN1783352A (en) * | 2004-12-03 | 2006-06-07 | 大亚湾核电运营管理有限责任公司 | Reactor core loading method of pressurized water reactor nuclear power station reactor |
| CN1921027A (en) * | 2006-09-15 | 2007-02-28 | 中国核动力研究设计院 | Atomic reactor core for nuclear power station |
| CN103258576A (en) * | 2012-02-17 | 2013-08-21 | 中国原子能科学研究院 | Nuclear reactor for moon surface |
| CN103489488A (en) * | 2012-06-11 | 2014-01-01 | 中国核动力研究设计院 | Module type pressurized water reactor |
| CN104240772A (en) * | 2014-09-15 | 2014-12-24 | 中国工程物理研究院核物理与化学研究所 | Z-pinch driven fusion-fission hybrid energy reactor |
| CN204577112U (en) * | 2015-05-12 | 2015-08-19 | 中国核动力研究设计院 | The Class PWR Plants reactor core of a kind of employing 177 fuel assemblies |
| US20170162278A1 (en) * | 2015-11-01 | 2017-06-08 | Daniel Laughman | Block-type movable reflector/moderator (RM) for nuclear reactor control |
| CN106128517A (en) * | 2016-06-24 | 2016-11-16 | 西安交通大学 | A kind of supercritical carbon dioxide cooling rickle using rod shape fuel assembly |
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| Publication number | Publication date |
|---|---|
| CN109801718B (en) | 2020-12-22 |
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