CN106548023B - A kind of underground nuclear power station major accident airborne radioactivity source item accurate estimation method - Google Patents
A kind of underground nuclear power station major accident airborne radioactivity source item accurate estimation method Download PDFInfo
- Publication number
- CN106548023B CN106548023B CN201610955665.7A CN201610955665A CN106548023B CN 106548023 B CN106548023 B CN 106548023B CN 201610955665 A CN201610955665 A CN 201610955665A CN 106548023 B CN106548023 B CN 106548023B
- Authority
- CN
- China
- Prior art keywords
- activity
- burnup
- nuclear power
- power station
- discharged
- 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
Links
Classifications
-
- G—PHYSICS
- G16—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR SPECIFIC APPLICATION FIELDS
- G16Z—INFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR SPECIFIC APPLICATION FIELDS, NOT OTHERWISE PROVIDED FOR
- G16Z99/00—Subject matter not provided for in other main groups of this subclass
Landscapes
- Measurement Of Radiation (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a kind of underground nuclear power station major accident airborne radioactivity source item accurate estimation methods, comprising steps of 1) being directed to specific underground nuclear power station reactor, carry out the calculating of reactor core burnup；2) radioactive activity maximum fuel burnup point is determined according to underground nuclear power station burnup database；3) radioactive substance type and the activity being discharged into pressure vessel by fuel are calculated；4) it calculates and is discharged by pressure vessel to the radioactive substance activity of reactor building；5) it calculates and is changed with time by the radioactive substance activity that workshop is discharged to underground chamber；6) measure of evaluation of subterranean nuclear power station cavity engineering and natural barrier calculate the radioactive substance activity for entering atmosphere；7) the radioactive substance activity that finally can be discharged into environment is calculated.The characteristics of present invention combination underground nuclear power station, realizes the dispersal behavior of airborne radioactivity source item when major accident occurs for quantitative assessment underground nuclear power station by efficient, fine burnup computational theory and natural country rock SHIELDING CALCULATION model.
Description
Technical field
The present invention relates to nuclear power technologies, accurately comment in particular to a kind of underground nuclear power station major accident airborne radioactivity source item
Estimate method.
Background technique
Accident source term refers to nuclear power plant in the event of an accident, be released into the form of the radioactive substance of environment, quantity, component and
Discharge the release characteristic changed over time.Accident source term is the basis of nuclear power plant's Incident Management and contingency plan, is divided into design base
Quasi- accident source term and major accident.Severe accident source term is an important input of damage sequence evaluation, after Fukushima nuclear accident,
Severe accident source term assessment receives significant attention and payes attention to.Estimate major accident airborne radioactivity source item, calculate accident field in and
Over-the-counter radiation consequence is Incident Management and the key factor that contingency plan is formulated, is directly related to nuclear power station and nuclear power
The safety of surrounding of the standing public.
At present in the world nuclear power station assessment major accident when, using be most widely U.S.'s core pipe can in 1975
WASH-1400 reports the presurized water reactor and boiling-water reactor accident source term proposed in (RSS).Using similar approach, other countries are directed to it
His heap-type, it was also proposed that similar accident source term, such as the S3 source item of France.However these accident source terms are with a certain specific anti-
It answers and is calculated based on heap, belong to general source item, can not be accurately calculated for specific reactor.Fukushima, Japan nuclear accident
Afterwards, the largely research to severe accident source term has been carried out both at home and abroad, but has been not known and proposes and fine, efficient burnup calculation method
It combines.Meanwhile underground nuclear power station has one layer thicker of natural country rock shielded layer outside workshop, can effectively obstruct deflation placing and penetrate
Property substance migration, existing method cannot be used directly for underground nuclear power station major accident airborne radioactivity source item calculate, it is necessary to
In conjunction with country rock shielded layer Assessment theory, a set of new calculation method is proposed.
Summary of the invention
It is an object of the invention to overcome the shortcoming of above-mentioned existing background technique, in conjunction with the characteristics of underground nuclear power station,
A kind of underground nuclear power station major accident gas is proposed by efficient, fine burnup computational theory and natural country rock SHIELDING CALCULATION model
Radio nuclide source terms accurate estimation method is carried, with the expansion of airborne radioactivity source item when quantitative assessment underground nuclear power station generation major accident
The behavior of dissipating.
The purpose of the present invention is what is reached by following measure: underground nuclear power station major accident airborne radioactivity source item essence
True appraisal procedure, is characterized in that, includes the following steps:
1) it is directed to specific underground nuclear power station reactor, carries out the calculating of reactor core burnup, and establish underground nuclear power station burnup number
According to library；
2) radioactive activity maximum fuel burnup point is determined according to underground nuclear power station burnup database；
3) in the case of assessment accident, radioactive substance type and the activity being discharged into pressure vessel by fuel are calculated；
4) radioactive substance variation in pressure vessel is assessed, calculating is discharged by pressure vessel to the radioactivity of reactor building
Substance activity；
5) radioactive substance variation in reactor building is assessed, calculating is discharged by workshop to the radioactive substance of underground chamber
Activity changes with time；
6) measure of evaluation of subterranean nuclear power station cavity engineering and natural barrier calculate the radioactive substance activity for entering atmosphere；
7) the radioactive substance activity that finally can be discharged into environment is calculated.
Preferably, the specific steps of the step 1) include:
11) burnup step-length is formulated using burnup step length is estimated according to burn-up level；
12) reactor core burnup computational physics model is established, the nucleon density and activity of each burnup point are calculated；
13) underground nuclear power station burnup database is established according to reactor core parameter, the reactor core parameter includes type, power, combustion
Consume depth, nucleic type, nucleon density and activity.
Preferably, the specific steps in the step 2) include:
21) activity of all radioactive substances of each burnup point is summed, acquires that each burnup point of reactor core is total to be put
Penetrating property activity；
22) it is living to fit reactor core gross activity according to mathematical method for the radioactive activity total based on each burnup point of reactor core
Spend the smooth curve changed with burnup；
23) the maximum point of total radioactive activity is determined according to curve, the corresponding abscissa of point be radioactive activity most
Big burn up time point.
Preferably, the calculation method of the radioactive substance activity in pressure vessel is discharged into the step 3) by fuel
Are as follows:
Al=A0FbFl
Wherein, AlTo be discharged into the radioactive substance activity in pressure vessel, A by fuel0For the storage of core activity substance
Amount, FbFor damaged or fusing fuel element share, FlThe share of gross activity nucleic is accounted for for the radionuclide of release.
Preferably, it is discharged by pressure vessel to the calculating side of the radioactive substance activity of reactor building in the step 4)
Method are as follows:
A2=Al(1-P1)P2
Wherein A2For the activity for being discharged into each radionuclide in reactor building by pressure vessel, P1To be inhaled by coolant
The share of receipts, P2To reveal share from reactor pressure vessel.
Preferably, the specific steps of the step 5 include:
51) reactor building initial activity concentration C is calculated0
Wherein VaFor workshop volume, it is calculated by cavern's size；
52) airborne radioactivity substance C in workshop is established1(t) equilibrium equation changed over time are as follows:
Wherein t is to be discharged into the workshop time；λ is decay coefficient, P3For reactor building slip, ε1For due to reaction
Airborne radioactivity substance reduction speed, C caused by radioactive substance removing measure in heap workshop1(t) initial value is C0；
53) radionuclide specific activity of underground nuclear power station cavern A at any time is discharged into from reactor building3(t) change
It turns to:
Preferably, the specific steps of the step 6) include:
61) calculate underground chamber initial activity concentration C '0:
Wherein VbFor cavern's volume, it is calculated by cavern's size；
62) it establishes equilibrium equation, calculates radioactive substance activity in underground chamber and change with time Cf(t)。
Wherein t is the time for being discharged into cavern；λ is decay coefficient；P4For the total slip of underground chamber；ε2For due to hole
Airborne radioactivity substance reduction speed caused by indoor radioactive substance removing measure；
63) calculate airborne radioactivity substance pass through run through, divulge information, exhaust passage enters the activity C of atmosphere1,g,n(t):
Wherein, n indicates the number in channel, Sb,nIndicate the sectional area in n-th of channel, ScIndicate the inner surface of underground chamber
Product, P5,nIndicate the path leakage rate in n-th of channel；
64) calculating airborne radioactivity substance is transported by rock mass and dispersion effect enters the C of atmosphere2,g(t):
C2,g(t)=ke-ηNCf(t)
Wherein, η indicates that diffusion coefficient of the different airborne radiation radioactive substances in rock mass, N indicate that rock mass thickness, k are
Correction factor, e indicate the nature truth of a matter.
Preferably, the radioactive substance activity that finally can be discharged into environment in the step 7) changes with time Af(t)
Calculation method are as follows:
Preferably, the calculation method of the burnup step-length are as follows:
Wherein Δ t indicate burnup step-length, m indicate burnup number of steps number, τ be user-defined deviation, T be burnup
Duration, υ are burnup rate, and burnup rate υ estimates formula are as follows:
Wherein, AmIndicate that m-th of burnup walks initial total radioactive activity value.
Preferably, burnup initial stage, the value range of the burnup step-length are 500-1000MWd/tU, burnup latter stage, institute
The value range for stating burnup step-length is 2000-5000MWd/tU.
Beneficial effects of the present invention are as follows:
(1) it proposes radioactive substance and passes through natural rock mass barrier in the indoor equilibrium equation of Underground Tunnels and radioactive substance
Calculation formula, the assessment of underground nuclear power station major accident airborne radioactivity source item can be used for.
(2) overcome the shortcomings of traditional common accident source term, it, can be for specific in conjunction with efficient, fine burnup computational theory
Heap-type targetedly calculates high-precision severe accident source term, improves the accurate of major accident airborne radioactivity source item calculating
Property and reasonability.
(3) use estimates burnup step-length method and determines reasonable burnup step-length, combines computational accuracy and computational efficiency.
(4) curve graph that total source item changes with burnup is fitted according to limited burnup point, intuitive according to curve graph energy,
The maximum burn up time point of radioactive activity is accurately determined, so that it is more reasonable accurate to calculate accident source term.
(5) underground nuclear power station reactor core burnup database is established, for other similar underground nuclear power station, it is only necessary to according to
The information such as its type and power can extrapolate the nucleon density of specific burnup point according to database, can directly determine accident source
, a large amount of calculating costs are saved, calculating reliability is improved.
Detailed description of the invention
Fig. 1 is underground nuclear power station airborne radioactivity material transport schematic diagram.
Fig. 2 is the accurate estimation flow figure of underground nuclear power station major accident airborne radioactivity source item.
In figure: reactor core fuel 1, pressure vessel 2, reactor building 3, containment 4, underground nuclear power station cavern 5, day
Right rock mass shielded layer 6, exhaust outlet 7.
Specific embodiment
The present invention is described in further detail with reference to the accompanying drawings and embodiments, but the embodiment should not be construed as pair
Limitation of the invention.
In normal reactor operation, if major accident occurs, the process that airborne radioactivity substance is discharged from reactor core is as follows:
When major accident occurs, if damaged or fusing occurs for part fuel element in reactor core fuel 1, airborne radioactivity substance from
Reactor core fuel 1 discharge, in pressure vessel 2 after coolant absorbs, part airborne radioactivity substance through penetration piece into
Enter reactor building 3, airborne radioactivity substance is in reactor building 3 through safety after decaying and being absorbed due to safeguard procedures
Shell 4 is leaked to underground nuclear power station cavern 5, and airborne radioactivity substance is arranged through decay in underground nuclear power station cavern 5 and due to protection
It applies and discharges into the atmosphere after being absorbed by the exhaust outlet 7 of natural country rock shielded layer 6, make as initial source for subsequent calculating
With.
A kind of underground nuclear power station major accident airborne radioactivity source item accurate estimation method of the present invention, with a certain underground nuclear power
It is described in detail, includes the following steps: for standing
1) it is directed to specific underground nuclear power station reactor, carries out the calculating of reactor core burnup, and establish underground nuclear power station burnup number
According to library.
11) burnup step-length is formulated using burnup step length is estimated according to burn-up level.
According to practical heap-type by inquire Core Design handbook determine reactor core rated power, history run, fuel enrichment,
The known parameters such as component and core structure size；According to Core Design feature, taking maximum fuel burnup depth is 70000MWd/tU,
Consider following radionuclide: Kr-85m, Kr-85, Kr-87, Kr-88, Xe-133m, Xe-133, Xe-135, Xe-138, I-
131,I-132,I-133,I-134,I-135；Burnup step-length is estimated using following calculation formula:
Wherein Δ t indicates burnup step-length, and m indicates burnup number of steps number, and τ is user-defined deviation, and value is smaller
It is lower to calculate more accurate but efficiency, T is burnup duration, and υ is burnup rate, estimates formula are as follows:
Wherein, AmIndicate that m-th of burnup walks initial total radioactive activity value.
The formulation of burnup step-length follows following principle: lesser combustion is used when reactor core initial operating stage, i.e. burn-up level are smaller
Step-length is consumed, to accurately calculate vertiginous nucleon density at any time；Reactor core end-of-run, since nucleon density tends to substantially
Stablize, biggish burnup step-length can be used to improve computational efficiency.Burnup initial stage, burnup step-length range are 500-1000MWd/
TU, burnup latter stage, burnup step-length range are 2000-5000MWd/tU.
12) reactor core burnup computational physics model is established, the nucleon density and activity of each burnup point are calculated.It is fired using the world
Consumption program establishes AP1000 reactor core burnup computational physics model, and accurate burnup calculating is carried out on large server, is obtained each
The nucleon density of burnup point simultaneously calculates corresponding radioactive activity, and since reactor core size is larger, calculation amount is larger, using high-performance
Server carries out simulation calculating.
13) it is based on reactor core burnup calculated result, by type, power, burn-up level, nucleic type, nucleon density and activity
Etc. data integrated, underground nuclear power station reactor core burnup database is established using database management system software.
2) radioactive activity maximum fuel burnup point is determined according to underground nuclear power station burnup database.
21) activity of all radioactive substances of each burnup point is summed, acquires that each burnup point of reactor core is total to be put
Penetrating property activity.
22) it is living to fit reactor core gross activity according to mathematical method for the radioactive activity total based on each burnup point of reactor core
Spend the smooth curve changed with burnup.
23) the maximum point of total radioactive activity is determined according to curve, the corresponding abscissa of point be radioactive activity most
Big burn up time point.
The smooth curve that total radioactive activity changes with burnup is simulated using scientific mapping software ORIGIN, it is upper straight from figure
It sees and determines the highest point of ordinate, corresponding to abscissa is the maximum burn up time point T of total radioactive activity0, take the state
The start time point occurred as accident.
3) it in the case of assessment accident, is commented according to total radioactive activity maximum time point for a certain selected accident
In the case of estimating the time point, the accident, radioactive substance type and the activity being discharged into pressure vessel by fuel are calculated.
Accident leads to reactor fuel element rupture or fusing, to determine the conservative calculated, damaged or fusing fuel member
Part share Fb100% is taken, is analyzed according to existing nuclear reactor meltdown accident as a result, the radionuclide Zhan discharged is always put
The share F of penetrating property nucleiclValue is as follows: the release share of inert gas (except Kr-85) is 2%；Kr-85 discharges share
30%；The release share of iodine is 3%.Calculate the radioactive substance activity A being discharged into pressure vessel by fuell(Bq) are as follows:
Al=A0FbFl
4) radioactive substance variation in pressure vessel is assessed, based on the radioactive substance being discharged into pressure vessel by fuel
Activity Al, the radioactive substance equilibrium equation in pressure vessel is established, evaluation radioactive substance passes through vessel penetration
Slip；Calculated by equation calculation result and slip discharged by pressure vessel to the radioactive substance activity of reactor building and
Type.
Assuming that radioactive substance transit time in pressure vessel is shorter, the decay of radioactive substance is not considered, while not
Consider diffusion of the radioactive substance in pressure vessel wall.Radioactive substance only considers the suction due to coolant in pressure vessel
Radioactive substance caused by receiving is reduced, and the slip of vessel penetration is obtained by inquiring technology handbook, by pressure vessel
It is discharged into the activity A of each radioactive substance in reactor building2(Bq) are as follows:
A2=Al(1-P1)P2
Wherein P1For the share absorbed by coolant, 40% is taken for iodine, 0% is taken for other gases；P2For from reactor
Pressure vessel reveals share, takes 10%.
5) radioactive substance variation in reactor building is assessed, the radioactive substance balance side in reactor building is established
Journey calculates radioactive activity in workshop and changes with time；Evaluate the slip that radioactive substance passes through workshop penetration piece；By side
Journey calculated result and slip calculating are discharged by workshop to the radioactive substance activity and type of underground chamber, do not consider radioactivity
Diffusion of the substance in reactor building wall.
51) reactor building initial activity concentration C is calculated0:
Wherein VaFor workshop volume, it is calculated by cavern's size；
52) airborne radioactivity substance C in workshop is established1(t) equilibrium equation changed over time are as follows:
Wherein t is to be discharged into workshop time, unit h；λ is decay coefficient, unit h-1, different nucleic half-life period is different；
P3For reactor building slip, unit h-1, take 0.0004h-1；ε1For due in reactor building radioactive substance elimination arrange
Apply caused airborne radioactivity substance reduction speed, unit h-1, take 0.004h-1, C1(t) initial value is C0.The above parameter is equal
It can inquire to obtain by technical data or design manual.
53) radionuclide specific activity of underground nuclear power station cavern A at any time is discharged into from reactor building3(t) change
It turns to:
6) measure of evaluation of subterranean nuclear power station cavity engineering and natural barrier calculate the radioactive substance activity for entering atmosphere.
61) calculate underground chamber initial activity concentration C '0:
VbFor cavern's volume, unit m3, it is calculated by cavern's size
62) equilibrium equation is established using theory identical with reactor building, calculates the indoor gas in underground nuclear power station hole
Radioactive substance is carried to change with time as Cf(t)。
Wherein t is the time for being discharged into cavern, unit h；λ is decay coefficient, unit h-1；P4For the total leakage of underground chamber
Rate, unit h-1, ε2For airborne radioactivity substance reduction speed, unit due to caused by radioactive substance removing measure in cavern
h-1, take 0.008h-1。
63) calculate airborne radioactivity substance pass through run through, divulge information, exhaust passage enters the activity C of atmosphere1,g,n(t)。
Wherein, n indicates the number in channel, Sb,nIndicate the sectional area in n-th of channel, ScIndicate the inner surface of underground chamber
Product, P5,nIndicate the path leakage rate in n-th of channel.The above parameter can be inquired by underground nuclear power station design manual.
64) calculating airborne radioactivity substance is transported by rock mass and dispersion effect enters the C of atmosphere2,g(t):
C2,g(t)=ke-ηNCf(t)
Wherein, η indicates that diffusion coefficient of the different airborne radiation radioactive substances in rock mass, N indicate that rock mass thickness, k are
Correction factor, e indicate the nature truth of a matter.
The total slip P of underground chamber4, sum to obtain by the slip in each channel and rock mass.
7) the radioactive substance activity that finally can be discharged into environment is calculated.
It finally can be discharged into environment according to the measure of underground nuclear power station cavity engineering and the assessment result of natural barrier, calculating
Radioactive substance type and activity.
The radioactive activity that finally can be discharged into environment is calculated to change with time Af(t)
Calculate gained AfIt (t) is the final accident descended in the case of nuclear plant severe accident, can be discharged into environment as needed
Source item.
Other unspecified parts are the prior art.The present invention is not strictly limited to above-described embodiment.
Claims (3)
1. a kind of underground nuclear power station major accident airborne radioactivity source item accurate estimation method, which is characterized in that including walking as follows
It is rapid:
1) it is directed to specific underground nuclear power station reactor, carries out the calculating of reactor core burnup, and establish underground nuclear power station burnup database:
11) burnup step-length is formulated using burnup step length is estimated according to burn-up level；
12) reactor core burnup computational physics model is established, the nucleon density and activity of each burnup point are calculated；
13) underground nuclear power station burnup database is established according to reactor core parameter, the reactor core parameter includes type, power, burnup depth
Degree, nucleic type, nucleon density and activity；
2) radioactive activity maximum fuel burnup point is determined according to underground nuclear power station burnup database:
21) activity of all radioactive substances of each burnup point is summed, acquires the total radioactivity of each burnup point of reactor core
Activity；
22) radioactive activity total based on each burnup point of reactor core, according to mathematical method fit reactor core total radioactive activity with
The smooth curve of burnup variation；
23) the maximum point of total radioactive activity is determined according to curve, which is that radioactive activity is maximum
Burn up time point；
3) it in the case of assessment accident, calculates and radioactive substance type and activity in pressure vessel is discharged by fuel, by fuel
It is discharged into the calculation method of the radioactive substance activity in pressure vessel are as follows:
Al=A0FbFl
Wherein, AlTo be discharged into the radioactive substance activity in pressure vessel, A by fuel0For core activity substance storage capacity,
FbFor damaged or fusing fuel element share, FlThe share of gross activity nucleic is accounted for for the radionuclide of release；
4) radioactive substance variation in pressure vessel is assessed, calculating is discharged by pressure vessel to the radioactive substance of reactor building
Activity is discharged by pressure vessel to the calculation method of the radioactive substance activity of reactor building are as follows:
A2=Al(1-P1)P2
Wherein A2For the activity for being discharged into each radionuclide in reactor building by pressure vessel, P1It is absorbed by coolant
Share, P2To reveal share from reactor pressure vessel；
5) radioactive substance variation in reactor building is assessed, calculating is discharged by workshop to the radioactive substance activity of underground chamber
It changes with time:
51) reactor building initial activity concentration C is calculated0
Wherein VaFor workshop volume, it is calculated by cavern's size；
52) airborne radioactivity substance C in workshop is established1(t) equilibrium equation changed over time are as follows:
Wherein t is to be discharged into the workshop time；λ is decay coefficient, P3For reactor building slip, ε1For due to reactor factory
Airborne radioactivity substance reduction speed, C caused by radioactive substance removing measure in room1(t) initial value is C0；
53) radionuclide specific activity of underground nuclear power station cavern A at any time is discharged into from reactor building3(t) variation are as follows:
6) measure of evaluation of subterranean nuclear power station cavity engineering and natural barrier calculate the radioactive substance activity for entering atmosphere:
61) calculate underground chamber initial activity concentration C '0:
Wherein VbFor cavern's volume, it is calculated by cavern's size；
62) it establishes equilibrium equation, calculates radioactive substance activity in underground chamber and change with time Cf(t)；
Wherein t is the time for being discharged into cavern；λ is decay coefficient；P4For the total slip of underground chamber；ε2For due in cavern
Airborne radioactivity substance reduction speed caused by radioactive substance removing measure；
63) calculate airborne radioactivity substance pass through run through, divulge information, exhaust passage enters the activity C of atmosphere1,g,n(t):
Wherein, n indicates the number in channel, Sb,nIndicate the sectional area in n-th of channel, ScIndicate the internal surface area of underground chamber, P5,n
Indicate the path leakage rate in n-th of channel；
64) calculating airborne radioactivity substance is transported by rock mass and dispersion effect enters the C of atmosphere2,g(t):
C2,g(t)=ke-ηNCf(t)
Wherein, η indicates that diffusion coefficient of the different airborne radioactivity substances in rock mass, N indicate rock mass thickness, and k is correction factor,
E indicates the nature truth of a matter；
7) calculate the radioactive substance activity that finally can be discharged into environment, the radioactive substance activity that finally can be discharged into environment with
The variation A of timef(t) calculation method are as follows:
2. a kind of underground nuclear power station major accident airborne radioactivity source item accurate estimation method according to claim 1,
It is characterized in that: the calculation method of the burnup step-length are as follows:
Wherein Δ t indicates burnup step-length, and m indicates burnup number of steps number, and τ is user-defined deviation, and T is that burnup has continued
Time, υ be burnup rate, burnup rate υ estimate formula are as follows:
Wherein, AmIndicate that m-th of burnup walks initial total radioactive activity value.
3. a kind of underground nuclear power station major accident airborne radioactivity source item accurate estimation method according to claim 2,
Be characterized in that: burnup initial stage, the value range of the burnup step-length are 500-1000MWd/tU, burnup latter stage, the burnup
The value range of step-length is 2000-5000MWd/tU.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610955665.7A CN106548023B (en) | 2016-10-27 | 2016-10-27 | A kind of underground nuclear power station major accident airborne radioactivity source item accurate estimation method |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610955665.7A CN106548023B (en) | 2016-10-27 | 2016-10-27 | A kind of underground nuclear power station major accident airborne radioactivity source item accurate estimation method |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN106548023A CN106548023A (en) | 2017-03-29 |
| CN106548023B true CN106548023B (en) | 2019-06-07 |
Family
ID=58393496
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610955665.7A Active CN106548023B (en) | 2016-10-27 | 2016-10-27 | A kind of underground nuclear power station major accident airborne radioactivity source item accurate estimation method |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN106548023B (en) |
Families Citing this family (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108268694B (en) * | 2017-12-01 | 2021-03-26 | 广东核电合营有限公司 | Simulation method and device for nuclear accident radiation data, terminal equipment and storage medium |
| CN110390444B (en) * | 2018-04-16 | 2022-09-27 | 中国辐射防护研究院 | Nuclear fuel circulation facility UF 6 Accident leakage consequence evaluation and calculation method |
| CN109541664B (en) * | 2018-10-25 | 2023-12-15 | 中国辐射防护研究院 | Multi-stage dose estimation system for liquid state release of radionuclide in nuclear facility accident |
| CN110991809B (en) * | 2019-11-06 | 2022-11-15 | 中国辐射防护研究院 | Reactor core inventory real-time estimation method based on Hualong I |
| CN111540491B (en) * | 2020-05-14 | 2022-04-01 | 中国核动力研究设计院 | Rod-shaped fuel source item release characteristic research experimental device and using method thereof |
| CN112199851A (en) * | 2020-10-19 | 2021-01-08 | 中国核动力研究设计院 | Method, device and equipment for acquiring fuel consumption of fuel containing gadolinium based on Lagrange interpolation |
| CN112434405B (en) * | 2020-11-09 | 2024-01-23 | 中国核电工程有限公司 | Calculation method of environmental influence coefficient and determination method of radioactivity acceptance criterion |
| CN112786116B (en) * | 2020-12-23 | 2023-07-25 | 中国辐射防护研究院 | High-level waste liquid leakage accident emergency release source item estimation method based on break |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104517658A (en) * | 2014-12-24 | 2015-04-15 | 长江勘测规划设计研究有限责任公司 | Airborne radioactivity diffusion prevention method for underground nuclear power plant |
| CN104715141A (en) * | 2015-02-05 | 2015-06-17 | 中国核电工程有限公司 | Tritium discharge source item computing method of pressurized water reactor nuclear power plant |
-
2016
- 2016-10-27 CN CN201610955665.7A patent/CN106548023B/en active Active
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104517658A (en) * | 2014-12-24 | 2015-04-15 | 长江勘测规划设计研究有限责任公司 | Airborne radioactivity diffusion prevention method for underground nuclear power plant |
| CN104715141A (en) * | 2015-02-05 | 2015-06-17 | 中国核电工程有限公司 | Tritium discharge source item computing method of pressurized water reactor nuclear power plant |
Non-Patent Citations (3)
| Title |
|---|
| "Distribution of oceanic 137Cs from the Fukushima Dai-ichi Nuclear Power Plant simulated numerically by a regional ocean model";Daisuke Tsumune等;《Journal of environmental radioactivity》;20111108;第100-108页 |
| "压水堆核电厂事故后厂房内气载放射性源项计算";周静等;《核科学与工程》;20151231;第35卷(第4期);第682-687页 |
| "基于不同数据库的反应堆堆芯源项计算分析";陈海英等;《核科学与工程》;20141231;第34卷(第4期);第475-481、487页 |
Also Published As
| Publication number | Publication date |
|---|---|
| CN106548023A (en) | 2017-03-29 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN106548023B (en) | A kind of underground nuclear power station major accident airborne radioactivity source item accurate estimation method | |
| KR101752328B1 (en) | Educational and Training Simulation System for Emergency Response to Nuclear Accidents in Neighboring Countrie | |
| CN106528926A (en) | Underground nuclear power station smoke plume contingency planning zone division method | |
| Glaser et al. | Proliferation risks of magnetic fusion energy: clandestine production, covert production and breakout | |
| Birikorang et al. | Ground deposition assessment of radionuclides following a hypothetical release from Ghana Research Reactor-1 (GHARR-1) using atmospheric dispersion model | |
| Miller et al. | The passive neutron enrichment meter for uranium cylinder assay | |
| Mehboob et al. | Derivation of radiological source term of Korean design system-integrated modular advanced ReacTor (SMART) | |
| Wang et al. | Rapid accident source term estimation (RASTE) for nuclear emergency response in high temperature gas cooled reactor | |
| McEachern et al. | Performance of PyC, SiC, ZrC coatings in the geologic repository | |
| Christensen et al. | Antineutrino reactor safeguards-a case study | |
| Ibekwe et al. | Modeling the short-term and long-term behaviour of the Oklo natural nuclear reactor phenomenon | |
| Mao et al. | Preliminary analysis of polonium-210 contamination for China LEAd-based Research Reactor | |
| Guezzi et al. | The Fukushima Disaster: A Cold Analysis | |
| Rechard et al. | Bounding estimates for critical events when directly disposing highly enriched spent nuclear fuel in unsaturated tuff | |
| Pfingsten et al. | Radionuclide release and transport from nuclear underground tests performed at Mururoa and Fangataufa—predictions under uncertainty | |
| Ma et al. | Neutronic experiment and analyses of a hybrid tritium breeding blanket mockup for CFETR | |
| Collin | AGR-2 Irradiation Test Final As-Run Report (Revision 4) | |
| Dubenkov et al. | Radiation Safety Validation of a BREST-OD-300 Installation | |
| Madhusoothanan | Stochastic environmental modeling for nuclear waste management | |
| Tang et al. | Study on Radionuclide Migration Under Accident Conditions of Mobile Heat Pipe Small Module Reactor | |
| Jae Hyun et al. | An evaluation of the influence of impurity concentration and composition in concrete on activation and radiation dose in the reactor facility | |
| Reyes et al. | Safety assessment for inertial fusion energy power plants: Methodology and application to the analysis of the HYLIFE-II and SOMBRERO conceptual designs | |
| ZHAO et al. | A new generation of human radiation dose calculation technology based on deformable mesh-type phantom | |
| Bolshov et al. | Codes of New Generation Developed for Breakthrough Project | |
| Buck et al. | Neutron-induced background in the CONUS experiment |
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 | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |