CN106297920B - A kind of subcriticality inverse kinematics measuring method of no three-dimensional effect - Google Patents
A kind of subcriticality inverse kinematics measuring method of no three-dimensional effect Download PDFInfo
- Publication number
- CN106297920B CN106297920B CN201610708257.1A CN201610708257A CN106297920B CN 106297920 B CN106297920 B CN 106297920B CN 201610708257 A CN201610708257 A CN 201610708257A CN 106297920 B CN106297920 B CN 106297920B
- Authority
- CN
- China
- Prior art keywords
- mrow
- netron
- flux density
- subcriticality
- msub
- 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.)
- Expired - Fee Related
Links
- 238000000034 method Methods 0.000 title claims abstract description 75
- 230000000694 effects Effects 0.000 title claims abstract description 19
- 230000008859 change Effects 0.000 claims abstract description 28
- 230000003111 delayed effect Effects 0.000 claims abstract description 23
- 238000005259 measurement Methods 0.000 claims abstract description 20
- 230000036461 convulsion Effects 0.000 claims abstract description 11
- 230000004907 flux Effects 0.000 claims abstract description 8
- 239000002243 precursor Substances 0.000 claims description 12
- 238000013461 design Methods 0.000 claims description 7
- 230000004044 response Effects 0.000 claims description 6
- 230000008901 benefit Effects 0.000 abstract description 4
- 238000005070 sampling Methods 0.000 abstract description 2
- 238000010606 normalization Methods 0.000 abstract 1
- 230000009257 reactivity Effects 0.000 description 13
- 230000008569 process Effects 0.000 description 6
- 230000001052 transient effect Effects 0.000 description 6
- 230000004992 fission Effects 0.000 description 4
- 238000007716 flux method Methods 0.000 description 4
- 238000012544 monitoring process Methods 0.000 description 4
- 230000003068 static effect Effects 0.000 description 4
- 238000004364 calculation method Methods 0.000 description 3
- 238000005516 engineering process Methods 0.000 description 3
- 239000000523 sample Substances 0.000 description 3
- 239000002699 waste material Substances 0.000 description 3
- 238000004458 analytical method Methods 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 2
- 238000012790 confirmation Methods 0.000 description 2
- 238000002474 experimental method Methods 0.000 description 2
- 239000000446 fuel Substances 0.000 description 2
- 230000010354 integration Effects 0.000 description 2
- 239000002245 particle Substances 0.000 description 2
- 238000004088 simulation Methods 0.000 description 2
- 230000009897 systematic effect Effects 0.000 description 2
- 208000000058 Anaplasia Diseases 0.000 description 1
- 238000012935 Averaging Methods 0.000 description 1
- 229910001152 Bi alloy Inorganic materials 0.000 description 1
- 210000001367 artery Anatomy 0.000 description 1
- 238000010523 cascade reaction Methods 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 235000013399 edible fruits Nutrition 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 210000004209 hair Anatomy 0.000 description 1
- 229910001385 heavy metal Inorganic materials 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 229910052745 lead Inorganic materials 0.000 description 1
- 239000007788 liquid Substances 0.000 description 1
- 238000000691 measurement method Methods 0.000 description 1
- 238000012552 review Methods 0.000 description 1
- 210000003462 vein Anatomy 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/104—Measuring reactivity
-
- 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
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The present invention provides a kind of subcriticality inverse kinematics measuring method of no three-dimensional effect.Compared with other method, the method is characterized in that, realize the subcriticality on-line measurement not influenceed by three-dimensional effect：Selection stationary source mode computation obtains netron-flux density normalization shape function does not change after reactor state change locus to arrange detector；Netron-flux density in the case of stable external source with reference to subcriticality and is had according to pulsed neutron source method or source jerk method measure sub-critical reactor, utilizes subcritical Inverse kinetic formula scale outside interruption item；According to the time series data read at detector position in line computation subcriticality.The invention has the advantages that：Avoid being influenceed by neutron flux shape space redistribution when measuring subcriticality；The delay effect of delayed neutron can be responded；Either accomplish the On-line sampling system of subcriticality under low-power or high power.
Description
Technical field
The present invention relates to time of the field of measuring technique of subcritical system subcriticality, more particularly to a kind of no three-dimensional effect
Critical Degree inverse kinematics measuring method.
Background technology
Nuclear waste it is minimized be nuclear fission energy sustainable development key issue.Accelerator-driven sub-critical system
(ADS) it is a kind of efficient nuke rubbish transmuting device, is the key technology for solving nuclear waste.ADS by it is middle can high current proton precessional magnetometer,
Outer source neutron produces target and subcritical reactor is formed, and is a kind of efficient nuclear waste transmuting device (or incinerator).ADS is by accelerating
Proton beam bombardment is located at the heavy metal target piece (such as liquid Pb or Pb-Bi alloys) in sub-critical reactor caused by device, causes spallation
Reaction, then by the way that cascade reaction produces neutron driving sub-critical reactor and run in core, outside core.The subcriticality of reactor is ADS
One of key parameter of core design, review and operation control.Future ADS operation and safety central issue be online
Subcriticality is monitored, makes reactor operation in the range of the subcriticality of design must assure that and all avoids in any condition
Critical or delayed criticality.
The method of conventional reactivity measurement has at present：Source multiplication method (ASM), asymptotic period technique, source jerk method, rod drop method,
Pulsed neutron source method, succusion, inverse kinematics method, noise analysis method, Averaging Energy Method, and it is anti-for ADS sub-critical reactors recently
The stream of answering property measurement is strong-flux method (Current to Flux method) and improved source multiplication method (MSM), for subcritical
On-line measurement requirement required for monitoring, these methods respectively have advantage and disadvantage and usable condition：Most typical reactivity measuring method-
Asymptotic period technique is small due to by short all duration value security restrictions, being only used for, the measurement of step positive reactivity, and negative reactivity
Measurement is influenceed by delayed-neutron precursor half-life period, is generally not used for measuring negative reactivity, and time of measuring is grown, and can not do
To real-time；Rod drop method cannot be used for not containing the ADS subcriticalities measurement of control rod；Source jerk method is surveyed available for ADS subcriticalities
Amount, but needs external source step disturbance, and needs to stablize source strength that (long-time burnup behavior needs external source small size during ADS normal operations
Change is with subcriticality monitoring range when maintaining that power is constant to be not belonging to transient state), jump source necessarily causes power swing, and behind jump source
Counting statistics error is larger, can not accomplish continuous on-line real time monitoring analysis；Pulsed neutron source can be used for ADS cold start or low
Power subcriticality measures, and outside interruption not operates in pulse condition and can not used in high power power reactor；Average energy
Method establishes the one-to-one relationship of subcriticality and reactor core average neutron energy, needs further experiment confirmation；Source multiplication method is used
Extrapolated in the critical level of reactor start-up process fuel loading, studied trial at present and be used for improved source multiplication method
ADS subcriticalities measure, and also have in the world in the recent period for the stream of ADS subcriticalities monitoring it is strong-flux method, but these methods
Static measurement method is belonged to, when subcriticality is shallower, delayed neutron influences increase, and this method can not consider delayed neutron
Response, stream is strong-and flux method needs continual periodically to carry out scale using other method and increase the complexity that method uses.
In theory, inverse kinematics method can accomplish reactive online survey in real time for (positive and negative) type that introduces of any reactivity
Amount, can respond effect of delayed neutron, relatively other reactivity measuring methods, it make use of most complete kinetic model to ask
Solution, can measure the instantaneous reactivity ρ (t) in change procedure, can so find the reactivity surprisingly added in time, so as to
Take measures rapidly, ensure the safe operation of reactor；And different from adding reactivity disturbance in examining system, also different from
The measuring method of extra neutron source is added, inverse kinematics method only solves dynamics by the change of neutron-flux density meter number in heap
Equation, interference will not be produced to heap normal operation.Inverse kinematics method is used for the more ripe of critical reactor, has produced various heaps and has used
Reactivity meter, the subcritical reactor subcriticality measurement of the special Accelerator driven of subcritical system of strong external source driving is inverse
Dynamic application needs solve 2 problems：(1) validity of subcritical point-reactor kinetic equation；(2) scale after being exogenously introduced
Problem is measured with reference to subcriticality；
First problem can consider in turn：The assumed condition that subcritical point-reactor kinetic equation should effectively meet is such as
Fruit can be met in some locus of reactor core, you can prove that the equation can effectively be applied to subcriticality measurement, root
Derived according to sub-critical point heap dynamics formula as can be seen that as long as active netron-flux density shape function is distributed not anaplasia at any time
Change, then sub-critical point heap kinetic model is effective, and subcritical inverse kinematics method can be applied.
Sub-critical point heap dynamics exports and the satisfaction of assumed condition：
Represent as follows with the operator of the related instantaneous neutron-pioneer's core coupled wave equation of outside interruption：
(1-1a)：
(1-1b)：
Wherein Φ is Φ (r, E, Ω, t), and F is fission neutron generation rate operator, and M is absorbs, neutron caused by leakage loses
Rate operator, SdFor delayed neutron source item operator, the time correlation item of delayed neutron, F are representeddFor delayed neutron static state source item operator,
S is outside interruption item, ξkFor kth group delayed-neutron precursor concentration, υ is neutron speed.
Select original state λ pattern adjoint fluxsMake weighting function (to consider different-energy, diverse location, different angles
Spend the contribution of netron-flux density) (1-1a) formula is multiplied by, and to space, energy integral (being represented with []), obtain：
(1-2)：
Netron-flux density function factor is decomposed such as (1-3), increases one degree of freedom newly, but it is not approximate, and p (t) is width
Spend function,For shape function：
(1-3)：
The typically change of netron-flux density shape function is little, (has one using some form of normalizing condition (1-4)
Fixed arbitrariness), free degree constraint is carried out to (1-3) formula, K is constant：
(1-4)：
(1-3), (1-4) two formula are substituted into instantaneous neutron transport equation (1-1a), by equation both sides divided byMerger integration is carried out to continuous item, obtains the Accurate Points dynamics neutron side available for subcritical reactor
Journey：
(1-5)：
The dynamical equation of delayed-neutron precursor satisfaction can similarly be exported：
(1-6)：
(1-5), (1-6) are Accurate Points kinetics equations.
Kinetic parameter is accordingly：
(1-7):
(1-8):
(1-9):
Wherein, t is the time, and p (t) is netron-flux density, Ck(t) it is kth group delayed-neutron precursor concentration, s (t) is
Outside interruption item, λkFor kth group delayed-neutron precursor decay coefficient, ρ (t) is subcriticality, and β (t) is total effective under t
Delayed neutron fraction (βk(t) it is kth group effective delayed neutron fraction under t), Λ is neutron generation time.
The numerical solution of accurate point-reactor kinetic equation is identical with the precision of direct numerical solution in time step very little, i.e.,
Accurate Points heap dynamics may be considered in the absence of approximate, kinetic parameter with the time also in change, therefore for numerical value
Solve, can meet to require using Accurate Points heap dynamics.
Experimentally, do not consider that kinetic parameter changes with time, this hypothesis is rational, because actually it becomes
Change minimum.But in the subcritical reactor of Accelerator driven, point heap dynamics approximation also lacks effective proof at present, neutron
Flux density shape function is likely to vary greatly in reactor state change (such as transient process), for numerical computations using normal
Rule point heap dynamics is inaccurate, but calculates reactivity for experimentally inverse process, only need to be special at some by detector arrangement
Fixed locus, meet the assumed condition that the export of sub-critical point heap dynamics formula uses over these locations, you can be based on
The inverse process of the model：Subcritical Inverse kinetic formula inverse goes out subcriticality.The description export of particular spatial location is as follows：
For equation (1-4) formula, i.e.,K is constant, has certain arbitrariness, not strictly speaking
It is bright, if it is possible to a sensing point is found, the pointUnrelated with the time, then (1-4) formula obviously meets, and causes a system next
Row export is reasonable.And make following simplify：
A:Initial value is Fλ(0) replace, the value be an equation both sides jointly by except the factor, because
Here do not carry out approximate；
B：Delayed neutron fission operator is approximate with initial value operator, i.e.,：Fd≈Fd0, this for delayed neutron it is static into
Point, because simplification here is rational.
Based on (1-4) and 2 points of A, B so that subcritical point-reactor kinetic equation is effective, and kinetic parameter change turns to not
The parameter changed over time.Following sub-critical point heap dynamics formula is obtained according to above method：
(1-10)
(1-11)
Wherein, t is the time, and p (t) is netron-flux density, Ck(t) it is kth group delayed-neutron precursor concentration, s (t) is
Outside interruption item, λkFor kth group delayed-neutron precursor decay coefficient, ρ (t) is subcriticality, and β is total effectively delayed neutron part
Volume (βkFor kth group effective delayed neutron fraction), Λ is neutron generation time.
By classical theory, point heap dynamics is only in KeffIt is just effective when near about 1, for subcritical system such as ADS, instead
Heap is answered to be operated in subcritical state, the applicability of point reactor model is limited by very large.But measured for experiment, especially instead
The measurement of answering property, as long as can be calculated from some detector position extraction data for meeting subcritical point reactor model assumed condition
The reactivity of whole reactor is still feasible.
Second Problem needs to carry out scale to external source, is transformed to use certain deep subcriticality measuring method, such as arteries and veins
Neutron source method or source jerk method accurate measurement are rushed to referring to subcriticality ρ$, this is then based on reference to subcriticality and the reactor core containing steady
Detector position goes out netron-flux density data p (0) scale and gone out source item size under state external source：S=-p (0) β ρ$。
Therefore detector position is determined by calculating, you can according to the netron-flux density transient information obtained from the position
And the subcriticality of reactor is extrapolated based on subcritical Inverse kinetic formula.In implementation, using PARTICLE TRANSPORT FROM program as surpassed
Level Monte Carlo, which is assessed, calculates the model that simulation software SuperMC establishes ADS subcritical reactors, calculates outer source size and utilizes
Identical stationary source mode computation reactor core netron-flux density information, and netron-flux density shape letter it is normalized to obtain
Counting, after transient changing, the point that netron-flux density shape function does not change can turn into the sensing point without three-dimensional effect, from
The time change that neutron density is extracted at this is to complete to calculate the online of subcriticality in real time.
The content of the invention
The present invention provides a kind of subcriticality inverse kinematics measuring method of no three-dimensional effect, for based on inverse kinematics method application
2 problems solving are needed to be to the measurement of sub-critical reactor subcriticality：(A) validity of subcritical point-reactor kinetic equation；(B)
Scale and reference reaction measurement problem after being exogenously introduced.
The technical solution adopted by the present invention is：A kind of subcriticality inverse kinematics measuring method of no three-dimensional effect, Neng Goushi
The on-line measurement of occurrence critical system subcriticality, realizes that step is as follows：
Step (1), according to subcritical Core Design, calculate differential responses heap state i, different spaces position under fixed source module
Place netron-flux density j is put, the netron-flux density under same state is normalized as netron-flux density shape functionI.e.Netron-flux density shape function value after selection reactor state changesConstant position
Arrange detector；
Step (2), the subcriticality ρ for determining by pulsed neutron source method or source jerk method subcritical reactor core$, record subcritical
Netron-flux density p (0) at the lower detector of systematic steady state external source driving, with the outside interruption in the subcritical Inverse kinetic formula of scale
Item s (t)；
Step (3), by detector readings obtain reactor state change (transient state) when netron-flux density when ordinal number
Inputted according to p (t) in subcritical Inverse kinetic formula (1-12) and realize that subcriticality measures,
(1-12)
Wherein, t is the time, t0For initial time, p (t) is the netron-flux density changed with time t, and p (ζ) is at any time
Between the netron-flux densities that change of ζ, ζ is from t0Change between t, Ck(t0) it is kth group delayed-neutron precursor concentration, s (t) is
Outside interruption item, λkFor kth group delayed-neutron precursor decay coefficient, ρ (t) is subcriticality, and β is total effectively delayed neutron part
Volume (βkFor kth group effective delayed neutron fraction), Λ is neutron generation time.
Wherein, step (1) is specially：Calculated by program under fixed source module, differential responses heap state i, different spaces
Opening position netron-flux density j, the netron-flux density under same state is normalized as netron-flux density shape letter
NumberI.e.Netron-flux density shape function value after selection reactor state changesConstant position
Put arrangement detector, to meet the export of subcritical Inverse kinetic formula used by assumed condition：K is constant,
Φλ0 *For initial lambda pattern adjoint flux, subscript " 0 " represents original state, and υ is neutron speed,For netron-flux density shape letter
Number so that measurement result is not influenceed by netron-flux density changes in spatial distribution.
Wherein, in step (2), according to pulsed neutron source method or the initial subcriticality ρ of reactor core of source jerk method determination$Face with secondary
Netron-flux density p (0) at detector under boundary's systematic steady state external source driving, outer neutron is exported using subcritical Inverse kinetic formula
Source scale formula：S=-p (0) β ρ$。
The present invention compared with prior art the advantages of be：
(1), the present invention can realize that the change of netron-flux density distribution of shapes function is not made after by reactor state change
Into three-dimensional effect influence.
(2), source multiplication method (ASM) or improvement source multiplication method (MSM) and the strong method of flux stream, it is impossible to respond delayed neutron and prolong
Slow effects, and the inventive method can respond influence caused by the delay effect of delayed neutron.
(3) low-power or height can, be realized compared to single pulsed neutron source method and single source jerk method, the inventive method
The On-line sampling system of subcriticality under power.
Brief description of the drawings
In order to illustrate more clearly about the embodiment of the present invention or technical scheme of the prior art, below will be to embodiment or existing
There is the required accompanying drawing used in technology description to be briefly described, it should be apparent that, drawings in the following description are this hairs
Some bright embodiments, for those of ordinary skill in the art, without having to pay creative labor, can be with
Other accompanying drawings are obtained according to these accompanying drawings.
What Fig. 1 was represented is the reactor core display figure of IAEA_ADS benchmark problems 1/4 that the present invention uses；
What Fig. 2 was represented is that the present invention is calculated without three-dimensional effect sensing point schematic diagram using IAEA_ADS benchmark problems；
What Fig. 3 was represented is to carry out subcriticality calculation procedure simulation and forecast result using method provided by the invention；
What Fig. 4 was represented is the operational flowchart of the present invention.
Embodiment
To make the purpose, technical scheme and advantage of the embodiment of the present invention clearer, below in conjunction with the embodiment of the present invention
In accompanying drawing, the technical scheme in the embodiment of the present invention is clearly and completely described, it is clear that described embodiment is
Part of the embodiment of the present invention, rather than whole embodiments.Based on the embodiment in the present invention, those of ordinary skill in the art
The every other embodiment obtained under the premise of creative work is not made, belongs to the scope of protection of the invention.
With reference to the figures above 1-4, the embodiment of the present invention is described in further detail：
1st, according to subcritical Core Design, calculated by program under fixed source module, differential responses heap state i, different skies
Between opening position netron-flux density j, the netron-flux density under same state is normalized as netron-flux density shape
FunctionI.e.Netron-flux density shape function value after selection reactor state changesConstant
Location arrangements detector, to meet the export of subcritical Inverse kinetic formula used by assumed condition：K is constant,
So that measurement result is not influenceed by netron-flux density changes in spatial distribution, subcritical Inverse kinetic formula and assumed condition expire
Foot export is as follows：
(1) represent as follows with the operator of the related instantaneous neutron-pioneer's core coupled wave equation of outside interruption：
(1-1a)：
(1-1b)：
Wherein Φ is Φ (r, E, Ω, t), and F is fission neutron generation rate operator, and M is absorbs, neutron caused by leakage loses
Rate operator, SdFor delayed neutron source item operator, the time correlation item of delayed neutron, F are representeddFor delayed neutron static state source item operator,
S is outside interruption item, ξkFor kth group delayed-neutron precursor concentration.
(2) initial lambda pattern adjoint flux is selectedMake weighting function (to consider different-energy, diverse location, different angles
Spend the contribution of netron-flux density) multiply (1-1a) formula, and to space, energy integral (being represented with []), obtain：
(1-2)：
(3) netron-flux density function factor is decomposed such as (1-3), increases one degree of freedom newly, but it is not approximate, and p (t) is
Amplitude function,For shape function：：
(1-3)：
(4) the typically change of netron-flux density shape function is little, using some form of normalizing condition (1-4) (tool
Have certain arbitrariness), free degree constraint is carried out to (1-3) formula：
(1-4)：
(5) (1-3), (1-4) step formula are substituted into the Transient Equations of (1-1a) step, by equation both sides divided byMerger integration is carried out to continuous item, obtained available for subcritical reactor
Accurate Points dynamics neutron equation group：
(1-5)：
(1-6)：
(6) corresponding kinetic parameter is during listing export：
(1-7):
(1-8):
(1-9):
(7) according to subcritical heap-type design parameter, Geometric Modeling is carried out to it using PARTICLE TRANSPORT FROM program, using stationary source
Calculating is transported, the neutron flux of diverse location is counted using point probe, and is normalized, finds the condition of satisfaction：Locus, that is, selectThe sensing point not changed in state change process,
Sub-critical point heap dynamics formula (1-10), (1-11) and subcritical inverse kinematics can be applied based on this probe position data
Formula (1-12)：
(1-10)
(1-11)
(1-12)
2nd, the subcriticality ρ of subcritical reactor core is determined by pulsed neutron source method or source jerk method$(in units of member), record
Netron-flux density data p (0) at the lower detector of subcritical system stable state external source driving, utilizes subcritical Inverse kinetic formula (1-
12) outer source item, (1-13) s=-p (0) ρ (0)=- p (0) β ρ are demarcated under the conditions of stable state external source$,
3rd, such as Fig. 2, shown in 3, change of the netron-flux density with the time is taken out using the sensing point opening position without three-dimensional effect
Change can realize subcriticality on-line measurement according to the subcritical inverse kinematics method formula (1-14) after scale.
(1-14)
Embodiment is as follows：As shown in figure 4,
(1) according to subcritical heap-type design parameter such as IAEA_ADS benchmark models, it is imitative to assess calculation using super Monte Carlo
True software SuperMC carries out Geometric Modeling to it, and carries out stationary source and transport calculating, and diverse location is counted using point probe
Netron-flux density；
(2) change of reactor state can be to change enrichment (or control rod position), or fuel temperature, cooling agent
The various disturbances such as temperature, CRITICAL CALCULATION is carried out after disturbance and draws effective multiplier factor, difference is faced using SuperMC programs again
Source calculating is fixed in the reactor state of boundary's degree, obtains the netron-flux density spatial distribution under multigroup different state of disturbances
Data, Fig. 1 embodiments are change enrichment；
(3) the netron-flux density spatial distribution data under multigroup different state of disturbances is normalized, obtained
Netron-flux density shape function, the locus (also known as without three-dimensional effect position) that shape function value does not change is found,
Meet condition：It has selectedThe sensing point not changed in state change process；
(4) pulsed neutron source method or source jerk method, measurement sub-critical reactor cold conditions subcriticality ρ are utilized$(in units of member), its
It is secondary, in the case of with stable state external source, neutron density data p (0) of the reactor without disturbance is obtained from sensing point, is faced by secondary
Boundary's Inverse kinetic formula (1-12) demarcates outer source item, (1-13) s=-p (0) ρ (0)=- p (0) β ρ under the conditions of stable state external source$；
(5) being changed with time using the sensing point opening position taking-up netron-flux density without three-dimensional effect can be according to quarter
Subcritical inverse kinematics method formula (1-14) after degree online calculates subcriticality.The data obtained using program calculating simulation are entered
Row tentative confirmation, as shown in Figure 3.
(1-14)
The techniques well known being related in the present invention does not elaborate.
Claims (2)
1. a kind of subcriticality inverse kinematics measuring method of no three-dimensional effect, can realize the online of subcritical system subcriticality
Measurement, it is characterised in that realize that step is as follows：
Step (1), according to subcritical Core Design, calculate differential responses heap state i under fixed source module, at different spatial
Netron-flux density j, the netron-flux density under same state is normalized as netron-flux density shape function
I.e.Netron-flux density shape function value after selection reactor state changesConstant location arrangements
Detector；
Step (2), the subcriticality ρ for determining by pulsed neutron source method or source jerk method subcritical reactor core$, record subcritical system
Netron-flux density p (0) at the lower detector of stable state external source driving, with the outside interruption item s in the subcritical Inverse kinetic formula of scale
(t)；
Step (3), pass through netron-flux density time series data p (t) inputs during detector readings acquisition reactor state change
Realize that subcriticality measures in subcritical Inverse kinetic formula (1-12),
<mfenced open = "" close = "">
<mtable>
<mtr>
<mtd>
<mrow>
<mo>(</mo>
<mn>1</mn>
<mo>-</mo>
<mn>12</mn>
<mo>)</mo>
<mfrac>
<mrow>
<mi>&rho;</mi>
<mrow>
<mo>(</mo>
<mi>t</mi>
<mo>)</mo>
</mrow>
</mrow>
<mi>&beta;</mi>
</mfrac>
<mo>=</mo>
<mn>1</mn>
<mo>+</mo>
<mfrac>
<mi>&Lambda;</mi>
<mi>&beta;</mi>
</mfrac>
<mfrac>
<mrow>
<mi>d</mi>
<mi>p</mi>
<mrow>
<mo>(</mo>
<mi>t</mi>
<mo>)</mo>
</mrow>
</mrow>
<mrow>
<mi>p</mi>
<mrow>
<mo>(</mo>
<mi>t</mi>
<mo>)</mo>
</mrow>
<mi>d</mi>
<mi>t</mi>
</mrow>
</mfrac>
<mo>-</mo>
<mfrac>
<mn>1</mn>
<mrow>
<mi>&beta;</mi>
<mi>p</mi>
<mrow>
<mo>(</mo>
<mi>t</mi>
<mo>)</mo>
</mrow>
</mrow>
</mfrac>
<munder>
<mo>&Sigma;</mo>
<mi>k</mi>
</munder>
<msub>
<mi>&lambda;</mi>
<mi>k</mi>
</msub>
<msub>
<mi>C</mi>
<mi>k</mi>
</msub>
<mo>(</mo>
<msub>
<mi>t</mi>
<mn>0</mn>
</msub>
<mo>)</mo>
<msup>
<mi>e</mi>
<mrow>
<mo>-</mo>
<msub>
<mi>&lambda;</mi>
<mi>k</mi>
</msub>
<mrow>
<mo>(</mo>
<mi>t</mi>
<mo>-</mo>
<msub>
<mi>t</mi>
<mn>0</mn>
</msub>
<mo>)</mo>
</mrow>
</mrow>
</msup>
</mrow>
</mtd>
</mtr>
<mtr>
<mtd>
<mrow>
<mo>-</mo>
<mfrac>
<mn>1</mn>
<mrow>
<mi>&beta;</mi>
<mi>p</mi>
<mrow>
<mo>(</mo>
<mi>t</mi>
<mo>)</mo>
</mrow>
</mrow>
</mfrac>
<munder>
<mo>&Sigma;</mo>
<mi>k</mi>
</munder>
<msub>
<mi>&lambda;</mi>
<mi>k</mi>
</msub>
<msub>
<mi>&beta;</mi>
<mi>k</mi>
</msub>
<msubsup>
<mo>&Integral;</mo>
<msub>
<mi>t</mi>
<mn>0</mn>
</msub>
<mi>t</mi>
</msubsup>
<mi>p</mi>
<mrow>
<mo>(</mo>
<mi>&zeta;</mi>
<mo>)</mo>
</mrow>
<msup>
<mi>e</mi>
<mrow>
<mo>-</mo>
<msub>
<mi>&lambda;</mi>
<mi>k</mi>
</msub>
<mrow>
<mo>(</mo>
<mi>t</mi>
<mo>-</mo>
<mi>&zeta;</mi>
<mo>)</mo>
</mrow>
</mrow>
</msup>
<mi>d</mi>
<mi>&zeta;</mi>
<mo>-</mo>
<mfrac>
<mrow>
<mi>s</mi>
<mrow>
<mo>(</mo>
<mi>t</mi>
<mo>)</mo>
</mrow>
</mrow>
<mrow>
<mi>&beta;</mi>
<mi>p</mi>
<mrow>
<mo>(</mo>
<mi>t</mi>
<mo>)</mo>
</mrow>
</mrow>
</mfrac>
</mrow>
</mtd>
</mtr>
</mtable>
</mfenced>
Wherein, t is the time, t0For initial time, p (t) is the netron-flux density changed with time t, and p (ζ) is to become with time ζ
The netron-flux density of change, ζ is from t0Change between t, Ck(t0) it is kth group delayed-neutron precursor concentration, s (t) is outer neutron
Source item, λkFor kth group delayed-neutron precursor decay coefficient, ρ (t) is subcriticality, and β is total effective delayed neutron fraction, βkFor
Kth group effective delayed neutron fraction, Λ are neutron generation time；
Step (1) is specially：Calculated by program under fixed source module, neutron at differential responses heap state i, different spatial
Flux density j, the netron-flux density under same state is normalized as netron-flux density shape functionI.e.Netron-flux density shape function value after selection reactor state changesConstant location arrangements are visited
Survey device, to meet the export of subcritical Inverse kinetic formula used by assumed condition：K is constant, Φλ0 *To be first
Beginning λ pattern adjoint flux, subscript " 0 " represent original state, and υ is neutron speed,For netron-flux density shape function so that
Measurement result is not influenceed by netron-flux density changes in spatial distribution.
A kind of 2. subcriticality inverse kinematics measuring method of no three-dimensional effect according to claim 1, it is characterised in that：Step
Suddenly in (2), according to pulsed neutron source method or the initial subcriticality ρ of reactor core of source jerk method determination$With subcritical system stable state external source
Netron-flux density p (0) at detector under driving, outside interruption scale formula is exported using subcritical Inverse kinetic formula：s
=-p (0) β ρ$。
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610708257.1A CN106297920B (en) | 2016-08-23 | 2016-08-23 | A kind of subcriticality inverse kinematics measuring method of no three-dimensional effect |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610708257.1A CN106297920B (en) | 2016-08-23 | 2016-08-23 | A kind of subcriticality inverse kinematics measuring method of no three-dimensional effect |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN106297920A CN106297920A (en) | 2017-01-04 |
| CN106297920B true CN106297920B (en) | 2018-01-05 |
Family
ID=57615498
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201610708257.1A Expired - Fee Related CN106297920B (en) | 2016-08-23 | 2016-08-23 | A kind of subcriticality inverse kinematics measuring method of no three-dimensional effect |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN106297920B (en) |
Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN107066745B (en) * | 2017-04-20 | 2020-01-17 | 西安交通大学 | Method for obtaining three-dimensional neutron flux density distribution in fast neutron reactor core transient process |
| CN107689256B (en) * | 2017-09-19 | 2019-06-07 | 中国核动力研究设计院 | A kind of nuclear reactor subcriticality measurement method |
| CN109273119B (en) * | 2018-09-13 | 2022-02-11 | 中国核动力研究设计院 | Method for optimizing the position of a neutron detector during the measurement of high reactivity on a critical device |
| CN109215822B (en) * | 2018-09-13 | 2022-08-05 | 中国核动力研究设计院 | Rod drop reactivity measurement method |
| CN109256226B (en) * | 2018-11-05 | 2020-07-03 | 三门核电有限公司 | Reactor critical extrapolation monitoring system and method |
| CN113936825A (en) * | 2021-10-12 | 2022-01-14 | 中国原子能科学研究院 | Method for measuring reactor reactivity and subcritical degree |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8462909B2 (en) * | 2007-07-30 | 2013-06-11 | Nuclear Fuel Industries, Limited | Doppler reactivity coefficient measuring method |
| CN104934083A (en) * | 2015-04-27 | 2015-09-23 | 中国原子能科学研究院 | Method for measuring effective share of delayed neutrons |
-
2016
- 2016-08-23 CN CN201610708257.1A patent/CN106297920B/en not_active Expired - Fee Related
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US8462909B2 (en) * | 2007-07-30 | 2013-06-11 | Nuclear Fuel Industries, Limited | Doppler reactivity coefficient measuring method |
| CN104934083A (en) * | 2015-04-27 | 2015-09-23 | 中国原子能科学研究院 | Method for measuring effective share of delayed neutrons |
Non-Patent Citations (3)
| Title |
|---|
| DF-VI快中子临界装置2号堆芯临界实验;杨历军;《核动力工程》;20071231;第28卷(第6期);第13-15页 * |
| 塔毕罗（Tapiro）反应堆逆动态落棒实验分析;叶长源;《核科学与工程》;19871231;第7卷(第3、4期);第322-327页 * |
| 快中子临界装置逆动态法反应性测量系统研制与应用;李勐等;《原子能科学技术》;20141031;第48卷;第160-164页 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN106297920A (en) | 2017-01-04 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN106297920B (en) | A kind of subcriticality inverse kinematics measuring method of no three-dimensional effect | |
| Espinosa-Paredes et al. | Fractional neutron point kinetics equations for nuclear reactor dynamics | |
| Dokhane | BWR stability and bifurcation analysis using a novel reduced order model and the system code RAMONA | |
| Pan et al. | Single-step Monte Carlo criticality algorithm | |
| Sjenitzer et al. | General purpose dynamic Monte Carlo with continuous energy for transient analysis | |
| Park | McCARD/MIG stochastic sampling calculations for nuclear cross section sensitivity and uncertainty analysis | |
| Belanger et al. | Variance reduction and noise source sampling techniques for Monte Carlo simulations of neutron noise induced by mechanical vibrations | |
| Santamarina et al. | Re-estimation of Nuclear Data and JEFF3. 1.1 Uncertainty Calculations,“ | |
| KR20090100505A (en) | A two dimentional kinetics code for fluid fuel reactors and the method of simulation using it | |
| Diniz et al. | Calculation of delayed neutron precursors’ transit time in the external loop during a flow velocity transient in a Molten Salt Reactors | |
| Smith et al. | An analysis of various solution strategies and perturbations on inputs of the reactor shielding problem | |
| Zhang et al. | Thermal power prediction of nuclear reactor core based on LSTM | |
| El Yaakoubi et al. | Validation study of the reactor physics lattice transport code DRAGON5 & the Monte Carlo code OpenMC by critical experiments of light water reactors | |
| Cao et al. | MCNPX Monte Carlo burnup simulations of the isotope correlation experiments in the NPP Obrigheim | |
| Nease et al. | Dominance ratio calculations with MCNP | |
| Wang et al. | Phonon parameters fitting for the simulated Thermal-Neutron scattering cross section of H in ZrHx using Unified Monte Carlo method | |
| Palmiotti et al. | Methods in use for sensitivity analysis, uncertainty evaluation, and target accuracy assessment | |
| Tran et al. | A multi-group neutron noise simulator for fast reactors | |
| Jinaphanh et al. | Implementation and Testing of Generalized Perturbation Theory Capabilities in TRIPOLI-4® | |
| Persson | Reactivity determination and Monte Carlo simulation of the subcritical reactor experiment–“Yalina” | |
| Filiciotto et al. | Super-history methods for adjoint-weighted tallies in monte carlo time eigenvalue calculations | |
| Royston et al. | Secondary-Source Core Reload Modeling with VERA | |
| Morton | Neutron-proton elastic scattering at 15.7 MeV | |
| Wu et al. | Neutronics Experiments of Advanced Fission Systems | |
| Kuz’min | Increasing approximate-solution accuracy by using perturbation theory |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant | ||
| CF01 | Termination of patent right due to non-payment of annual fee | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20180105 |