CN105468832B - A kind of supercritical water reactor reactor core nuclear heat couples alternative manner - Google Patents
A kind of supercritical water reactor reactor core nuclear heat couples alternative manner Download PDFInfo
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Abstract
Supercritical water reactor reactor core nuclear heat couples alternative manner, performs a thermal-hydraulic calculating after having performed m Neutronics calculation, m is the Neutronics calculation iterations of setting, and m is more than 5；Son is learned in calculating in commission, introduce adaptive relaxation factor ω and perform the power density distribution that Neutronics calculation obtains to the 2nd time to the m times using power density distribution iteration function and be adjusted, power density distribution is used in execution Neutronics calculation next time or in thermal-hydraulic calculating after adjustment.The present invention solves the problems, such as that the coupling of SCWR reactor cores nuclear heat iterates to calculate in calculating and is difficult to convergence, improves computational efficiency and numerical stability that nuclear heat coupling calculates.
Description
Technical field
The present invention relates to nuclear reactor designs technical field, in particular it relates to which a kind of supercritical water reactor reactor core nuclear heat couples
Alternative manner.
Background technology
The operating condition of supercritical water reactor (SCWR) possesses more than its thermodynamic critical point (374 DEG C, 22.1MPa) of water
Higher system thermal efficiency and reactor system is simplified, compact.But the density of supercritical water, specific heat and thermal conductivity are super
Critical zone change is violent, generally define operating pressure 25MPa, 280 DEG C/500 DEG C of Core cooling agent outlet/inlet temperature
Supercritical water reactor in, the density of cooling agent by reactor core entrance about 777kg/m3Change to the about 90kg/m of core exit3.It is acute
The water density of strong change significantly affects heap in-core moderation of neutrons ability, and power density distribution change is anti-caused by moderating power change
Come over and heap in-core water density will be significantly affected to be distributed.This physics-thermal technology's coupled characteristic is significantly stronger than traditional presurized water reactor,
Ask and must take into consideration nuclear heat coupling in the analysis of reactor core steady-state behaviour and conceptual design.
In SCWR reactor cores, coolant density, moderator-density skewness and change are violent, power density distribution it is micro-
Small change may cause the acute variation of coolant density, moderator-density, and then significantly change neutron cross section parameter, in turn
Power density distribution is set also to produce acute variation.Above-mentioned strong nuclear heat coupled characteristic so that the nuclear heat coupling of SCWR reactor cores calculates
Face the challenge of Iterations of Multi, numerical stability and computational efficiency.
In existing nuclear heat coupling iterative technique, coupling alternative manner generally use decoupling alternative manner and successive iteration side
Method.Decouple alternative manner to require in each iteration step, just start the iterative calculation of next step after all calculating Complete Convergences.For
One given iteration step, the discreet value based on current thermal technology-hydraulic parameters and neutron cross section parameter, is calculated complete to neutron fission source
Complete convergence.The computational efficiency of decoupling alternative manner is relatively low, and changes violent analysis object for iterative calculation parameter, such as cools down
The violent SCWR reactor cores of agent variable density, result even in iterative calculation and do not restrain.Iterative technique assumes that a power is close
Degree distribution, is constantly iterated by iterative formula, is received until adjacent power density distribution maximum relative deviation twice is less than
Hold back required precision.Change violent SCWR reactor cores for iterative calculation parameter, adjacent power density distribution twice easily occurs
Oscillation of power, lead to not restrain.Especially for multipaths SCWR reactor cores, work(may be formed respectively at the top and bottom of reactor core
Rate peak, this will further result in reactor core internal power Density Distribution and is difficult to restrain.
The content of the invention
The purpose of the present invention is that the shortcomings that overcoming above-mentioned prior art and deficiency, there is provided a kind of supercritical water reactor reactor core
Nuclear heat couples alternative manner, this method solve iterative calculation in supercritical water reactor reactor core nuclear heat coupling calculating process and is difficult to restrain
The problem of, and improve computational efficiency and numerical stability that nuclear heat coupling calculates.
Technical scheme is used by the present invention solves the above problems：
A kind of supercritical water reactor reactor core nuclear heat couples alternative manner, and a thermal technology is performed after having performed m Neutronics calculation
Water force, m are the Neutronics calculation iterations of setting, and m is more than 5.In the technical program, thermal-hydraulic meter is often walked performing
Outer iteration Complete Convergence is not required for before calculation and just performs thermal-hydraulic calculating, also carries out one without requiring often to perform an outer iteration
Secondary thermal-hydraulic calculates；The efficiency that nuclear heat coupling calculates is significantly improved.
As a further improvement on the present invention, son is learned in calculating in commission, is introduced adaptive relaxation factor ω and is utilized
Power density distribution iteration function performs the power density distribution that Neutronics calculation obtains to the 2nd time to the m times and is adjusted, and obtains
To adjustment after power density distribution be used for next time perform Neutronics calculation in or perform thermal-hydraulic calculate in, specifically include
Following steps：
S1, setting Neutronics calculation iterations m, build power density distribution iteration function, and initialization performs neutronics
Calculation times n；
S2, first time Neutronics calculation is performed, and step S3 is jumped to after counting Neutronics calculation number；
S3, perform second of Neutronics calculation using performing the power density distribution that first time Neutronics calculation obtains, and
Step S4 is jumped to after statistics Neutronics calculation number；
S4, the last relative deviation for performing the power density distribution that Neutronics calculation obtains is calculated, and according to the phase
Adaptive relaxation factor ω value is chosen to deviation；
S5, the adaptive relaxation factor ω chosen in step S4 value and the last Neutronics calculation that performs obtained
Power density distribution substitute into power density distribution iteration function calculate adjustment after power density distribution, judge Neutronics calculation
Whether number is equal to Neutronics calculation iterations, is to be set to Neutronics calculation number to jump to step S7 after initial value,
Otherwise step S6 is jumped to；
S6, perform Neutronics calculation again using power density distribution after the adjustment in step S5, count neutronics meter
Number is calculated, jumps to step S4；
S7, thermal-hydraulic calculating is performed using power density distribution after the adjustment in step S5, judge to perform thermal-hydraulic
Whether the power density distribution obtained after calculating restrains, and is, terminates to calculate, and otherwise jumps to step S2.In the technical program,
Relaxation factor is introduced in power density distribution iterative process to be adjusted power density distribution, can be avoided due to phase
The adjacent result difference of iterative calculation twice is excessive and causes iterative process to dissipate, and adaptive relaxation factor is with the convergence situation of iteration
And value is voluntarily adjusted, on the premise of Iterations of Multi and numerical stability is ensured, computational efficiency is improved as far as possible.
Further, the power density distribution iteration function is：
In formula (1), n is Neutronics calculation number；ωnTo perform the power density point that Neutronics calculation obtains to n-th
The adaptive relaxation factor ω used when cloth is adjusted value；Pn-1For (n-1)th power for performing Neutronics calculation and obtaining
Density Distribution, PnThe power density distribution obtained for n-th execution Neutronics calculation, P 'n-1For (n-1)th execution neutronics meter
Power density distribution after the adjustment of obtained power density distribution, P 'nFor using ωnTo PnAfter being adjusted obtained adjustment
Power density distribution.
Further, the obtaining value method of the adaptive relaxation factor ω of selection described in step S4 is：
In formula, εp nThe relative deviation for the power density distribution that Neutronics calculation obtains is performed for n-th, wherein：
In formula (3), Pn-1For (n-1)th power density distribution for performing Neutronics calculation and obtaining, P 'n-1Held for (n-1)th time
Power density distribution after the adjustment for the power density distribution that row Neutronics calculation obtains, PnNeutronics calculation is performed for n-th to obtain
The power density distribution arrived.
Further, the Neutronics calculation iterations m is 20-40.
Preferably, the Neutronics calculation iterations m is 30.
Further, judge whether the power density distribution that execution thermal-hydraulic obtains after calculating is convergent in the step S6
Specific method is：Judge to perform the power density distribution after thermal-hydraulic calculates and perform the power density before thermal-hydraulic calculates
Whether distribution meets formula (2), and satisfaction then restrains, is unsatisfactory for not restraining：
In formula (4), f (q 'm) divide to perform the power density after thermal-hydraulic calculates
Cloth, q'mFor power density distribution after the m times adjustment for performing the power density distribution that Neutronics calculation obtains, δ is the receipts of setting
Hold back value.
To sum up, the beneficial effects of the invention are as follows：
1st, the present invention efficiently solves by using improved outer iteration coupling process and the adaptive relaxation factor of matching
Iteration convergence sex chromosome mosaicism when the coupling of SCWR reactor cores nuclear heat calculates, and ensure that the numerical stability that coupling calculates；
2nd, SCWR reactor cores nuclear heat is coupled the computational efficiency calculated and improved more than three times by the present invention.
Brief description of the drawings
Fig. 1 is the supercritical water reactor reactor core nuclear heat coupling alternative manner of the present invention；
Fig. 2 is supercritical water reactor reactor core nuclear heat coupling calculation process.
Embodiment
The present invention improves nuclear heat coupling by using improved outer iteration coupling process and the adaptive relaxation factor of matching
Iterations of Multi, computational efficiency and the numerical stability of calculating.Its main thought is the neutronics for having performed setting number (m times)
Perform a thermal-hydraulic after calculating to calculate, m is the Neutronics calculation iterations of setting, and m is more than 5.Son learns meter in commission
In calculation, adaptive relaxation factor ω is introduced and using power density distribution iteration function to every the 2nd time to the m times execution neutron of wheel
The power density distribution that be calculated, which is adjusted, is adjusted rear power density distribution, and power density distribution is used after the adjustment
In performing in Neutronics calculation or performing thermal-hydraulic next time and calculate, ensure Iterations of Multi and efficiency.With reference to reality
Example and accompanying drawing are applied, makees detailed description further to the present invention, but the implementation of the present invention is not limited to this.
Embodiment 1：
As shown in figure 1, a kind of supercritical water reactor reactor core nuclear heat coupling alternative manner, comprises the following steps S1-S7：
S1, setting Neutronics calculation iterations m, build power density distribution iteration function；Initialization performs neutronics
Calculation times n, n value is set as 0 when n is initialized in the present embodiment；
S2, first time Neutronics calculation is performed, and step S3 is jumped to after counting Neutronics calculation number；The present embodiment
In, the method for statistics Neutronics calculation number is：Make Neutronics calculation number that n+1 value be assigned to n, this step from adding 1
In, n value is 1 to Neutronics calculation number certainly plus after 1；
S3, utilize the power density distribution P for performing first time Neutronics calculation and obtaining1Second of Neutronics calculation is performed,
And (now n value is 2) jumps to step S4 after counting Neutronics calculation number；In this step, Neutronics calculation number is counted
Method be：Make Neutronics calculation number that n+1 value are assigned into n from adding 1；
S4, the last relative deviation for performing the power density distribution that Neutronics calculation obtains is calculated, and according to the phase
Adaptive relaxation factor ω value is chosen to deviation；Wherein, the power density distribution that each execution Neutronics calculation obtains
Relative deviation εp nCalculation formula it is as follows：
In formula (3), Pn-1For (n-1)th power density distribution for performing Neutronics calculation and obtaining, PnIn being performed for n-th
Son learns the power density distribution being calculated, P 'n-1For (n-1)th tune for performing the power density distribution that Neutronics calculation obtains
Power density distribution after whole, in fact, P 'n-1And using adaptive relaxation factor ω to Pn-1After being adjusted obtained adjustment
Power density distribution.In nearest one after performing n-th and performing Neutronics calculation, before (n+1)th execution Neutronics calculation of execution
Secondary execution Neutronics calculation is that n-th performs Neutronics calculation, and the last time performs the power density point that Neutronics calculation obtains
Cloth is Pn.Power density distribution refers to the value using corresponding adaptive relaxation factor to performing neutron after the adjustment of the present invention
Learn the power density distribution after the power density distribution being calculated is adjusted.
An a thermal-hydraulic calculating referred to as wheel thermal coupling meter will be performed after m Neutronics calculation will be often performed in the present embodiment
Calculate；Then in every wheel thermal coupling calculates, the power density distribution after Neutronics calculation is performed for the first time without adjustment, therefore not
With calculating relative deviation；The relative deviation ε of power density distribution after second of execution Neutronics calculationp 2In being performed for second
Son learns the power density P being calculated2The power density P obtained with first time execution Neutronics calculation1Difference absolute value divided by
P1；The relative deviation ε of the power density distribution after execution Neutronics calculation for the third time and afterwardsp n(n=3,4 ..., m) for work as
The secondary power density P for performing Neutronics calculation and obtainingnThe adjustment for the power density distribution that Neutronics calculation obtains was performed with last time
Power density distribution P ' afterwardsn-1Difference absolute value divided by last time perform the adjustment of power density distribution that Neutronics calculation obtains
Power density distribution P ' afterwardsn-1。
The value formula for choosing adaptive relaxation factor ω is as follows：
In formula, ωnAs n-th is performed used when the obtained power density distribution of Neutronics calculation is adjusted from
Adapt to relaxation factor ω value, εp nThe relative deviation for the power density distribution that Neutronics calculation obtains is performed for n-th.
S5, the value ω by the adaptive relaxation factor ω chosen in step S4nNeutronics calculation is performed with the last time
Obtained power density distribution substitutes into power density distribution iteration function and calculates power density distribution after adjustment, judges neutronics
Whether calculation times are equal to Neutronics calculation iterations, are to jump to step after Neutronics calculation number is set into initial value
S7, otherwise jump to step S6；The power density distribution iteration function is mainly used in the 2nd to the m times execution neutronics meter
Obtained power density distribution is adjusted, and in the 2nd to the m times performs Neutronics calculation, has performed neutronics meter every time
Obtained power density distribution is once adjusted after calculation, under the power density distribution after the 2nd to the m-1 times adjustment is used for
During the deviation for performing the power density distribution of Neutronics calculation neutralization next time once calculates, the power after the adjustment of the m times
Density Distribution is used to perform in thermal-hydraulic calculating, and power density distribution iteration function formula is as follows：
In formula (1), n is Neutronics calculation number；Pn-1For (n-1)th power density point for performing Neutronics calculation and obtaining
Cloth, PnThe power density distribution obtained for n-th execution Neutronics calculation, P 'n-1Neutronics calculation is performed for (n-1)th time to obtain
Power density distribution adjustment after power density distribution, P 'nFor using ωnTo PnPower is close after being adjusted obtained adjustment
Degree distribution, by ωn、Pn-1、Pn、P′n-1Substitution formula (1) is with regard to that can calculate PnAdjustment after power density distribution P 'n。
In the present embodiment, Neutronics calculation number is set into initial value it is zeroed out operation n also is arranged into 0, unites
N+1 value is assigned to n by meter Neutronics calculation number, and new Neutronics calculation number is equal to last Neutronics calculation number
Add 1；In the present embodiment, perform a Neutronics calculation and carry out an outer iteration.In other embodiments, initialization is
N can be set as to other values, such as, but not limited to equal to m, in this case in this step, judge to perform Neutronics calculation
Number judges whether n is equal to 0 when whether reaching Neutronics calculation iterations, will perform Neutronics calculation number and be set as initial value
When n is arranged to m；The mode of statistics Neutronics calculation number in this step, step S2 and S3 is：Make Neutronics calculation number
From subtracting 1.
S6, perform Neutronics calculation again using power density distribution after the adjustment in step S5, count neutronics meter
Number is calculated, jumps to step S4.
S7, using power density distribution after the adjustment in step S5, (power is close after the adjustment in actually now step S5
Degree distribution is exactly the power density distribution P that the m times is performed Neutronics calculation and obtainedmPower after the adjustment obtained after being adjusted
Density Distribution P 'm) thermal-hydraulic calculating is performed, judge to perform whether the power density distribution obtained after thermal-hydraulic calculates is received
Hold back, be, terminate to calculate, otherwise jump to step S2.
In the present embodiment, the Neutronics calculation iterations m is 30 times, in practical application, Neutronics calculation iteration time
Number m can be adjusted in 20-40 underranges.But when Neutronics calculation iterations m is 30 times, compared to traditional decoupling iteration side
Method coupling, which calculates to take, reduces 2/3, significantly improves computational efficiency.
In step S4, formula (2) shows the power density distribution relative deviation when adjacent outer iteration twice (Neutronics calculation)
During more than 0.1, adaptive relaxation factor value is 0.2；When the power density distribution relative deviation of adjacent outer iteration twice is less than
Or during equal to 0.1, adaptive relaxation factor value is 0.9 and " 0.2-0.3 × lg (εp n) smaller value between the two.Experiment shows,
Using the adaptive relaxation factor of matching, computational efficiency has on the one hand been taken into account, has on the other hand efficiently solved the coupling of reactor core nuclear heat
Iteration convergence sex chromosome mosaicism during calculating, and ensure that the numerical stability that coupling calculates.
In step S7, judge to perform the whether convergent specific method of power density distribution obtained after thermal-hydraulic calculates
For：Judge to perform the power density distribution after thermal-hydraulic calculates and whether perform the power density distribution before thermal-hydraulic calculates
Meet formula (4), satisfaction then restrains, is unsatisfactory for not restraining：
In formula, f (q'm) it is to perform the power density after thermal-hydraulic calculates, q'mNeutronics calculation is performed for the m times to obtain
Power density distribution adjustment after power density distribution, δ is convergency value set in advance.In the present embodiment, during the m times performs
Power density distribution P ' after the adjustment for the power density distribution that son is calculatedmNamely to perform the 30th Neutronics calculation after
Power density q30It is adjusted power density distribution P ' after obtained adjustment30。
It is foregoing perform reactor core Neutronics calculation as whole supercritical water reactor reactor core nuclear heat couple alternative manner in it is outer repeatedly
Generation, in supercritical water reactor reactor core nuclear heat couples calculating process, according to traditional decoupling alternative manner, it is necessary to wait until outer iteration
After Complete Convergence, just perform thermal-hydraulic and calculate, then each thermal-hydraulic needs at least to perform 100 reactor core neutronics meters before calculating
Calculate, computational efficiency is relatively low and when coolant density change is violent, and iterative calculation does not restrain.If directly use outer iteration coupling side
Method just carries out thermal-hydraulic and calculated, it is necessary to often perform an outer iteration, due to perform a thermal-hydraulic calculate take compared with
Long, thermal-hydraulic calculating section is time-consuming excessive in whole iterative process, causes overall calculation less efficient.
In the present embodiment, a kind of supercritical water reactor reactor core nuclear heat coupling alternative manner uses improved outer iteration coupling side
Method, outer iteration Complete Convergence is often not required for before step thermal-hydraulic calculates in execution and just performs thermal-hydraulic calculating, is not also required
Often perform an outer iteration and just carry out a thermal-hydraulic calculating.Improved outer iteration coupling process in the present embodiment is often to hold
The outer iteration of row setting number (m times) performs a thermal-hydraulic and calculated after calculating.Using this improved outer iteration coupling side
Method, the convergence that nuclear heat coupling calculates are significantly improved, and emergent power or density do not restrain situation, while nuclear heat couples
The efficiency of calculating is significantly improved.In the present embodiment, often perform and a thermal-hydraulic calculating performed after 30 outer iterations calculate,
Calculate to take compared to traditional decoupling alternative manner coupling and reduce 2/3, significantly improve computational efficiency.
In nuclear heat couples calculating process, according to traditional iterative technique, due to SCWR Core cooling agent density,
Moderator-density skewness and change is violent, the minor variations of power density distribution may cause coolant density, slowing down
The acute variation of agent density, and then neutron cross section parameter is significantly changed, power density distribution is also produced acute variation in turn,
It emergent power will easily vibrate, and lead to not restrain.In the present embodiment, also introduced in power density distribution iterative process
Relaxation factor, it can avoid causing iterative process to dissipate because the adjacent result difference of iterative calculation twice is excessive.According to solid
Fixed relaxation factor, when relaxation factor is larger, although calculating is time-consuming relatively fewer, it is not easy to realize iterative calculation convergence, when
When relaxation factor is smaller, although easily realize iterative calculation convergence, it will spend and more calculate the time.It is general and
Speech, for particular problem, calculated as SCWR reactor cores nuclear heat couples, a most suitable relaxation factor be present.Therefore, the present embodiment
In propose the adaptive relaxation factor of matching.The adaptive relaxation factor of matching is voluntarily adjusted with the convergence situation of iteration
It is whole, on the premise of Iterations of Multi and numerical stability is ensured, computational efficiency is improved as far as possible.
To sum up, above-mentioned supercritical water reactor reactor core nuclear heat coupling alternative manner, by using improved outer iteration coupling process
With the adaptive relaxation factor of matching, the iteration convergence sex chromosome mosaicism when coupling of SCWR reactor cores nuclear heat calculates is efficiently solved, and really
The numerical stability that coupling calculates has been protected, while SCWR reactor cores nuclear heat is coupled to the computational efficiency calculated and improved more than three times.
Execution Neutronics calculation and execution thermal-hydraulic in the present embodiment calculate and use conventional side of the prior art
Method is calculated, and typically performs calculating by corresponding computer program, its specific method and flow are repeated no more in the present embodiment.
Power density distribution, execution thermal technology's water in the present embodiment after initial power Density Distribution, execution Neutronics calculation
The computational methods of power density distribution after Mechanics Calculation are prior art, are repeated no more in the present embodiment, the purpose of the present invention
It is that adaptive relaxation factor ω values are chosen by these power density distributions.
Embodiment 2：
A kind of supercritical water reactor heap core of the alternative manner based in embodiment 1 or embodiment 2 is provided in the present embodiment
Thermal coupling computational methods, as shown in Fig. 2 comprising the following steps：
(1), the different burnup operating mode of computation module；
(2) section process of fitting treatment, is performed；
(3), initially control stick position and water density distribution；
(4) control rod position, is adjusted；
(5), reactor core nuclear heat coupling iteration, the power density distribution convergence obtained after performing thermal-hydraulic and calculating；
(6), judge whether to critical condition, be, jump to step (7), otherwise jump to step (4)；
(7) maximum involucrum wall surface temperature, is calculated according to maximum power density distribution；
(8), burnup is performed to calculate；
(9), judge whether fuel reaches the end of term in longevity, be, terminate to calculate, otherwise jump to step (10)；
(10), burnup step plus 1, jumps to step (4).
In the computational methods, step 5 is the supercritical water reactor reactor core nuclear heat coupling alternative manner in embodiment 1, and remaining is walked
Suddenly all using processing method of the prior art, the processing method of each step is repeated no more in the present embodiment.
The above is only the preferred embodiment of the present invention, protection scope of the present invention is not limited merely to above-described embodiment,
All technical schemes belonged under thinking of the present invention belong to protection scope of the present invention.It should be pointed out that for the art
For those of ordinary skill, some improvements and modifications without departing from the principles of the present invention, the protection of the present invention should be regarded as
Scope.
Claims (5)
1. a kind of supercritical water reactor reactor core nuclear heat couples alternative manner, it is characterised in that is performed after having performed m Neutronics calculation
One time thermal-hydraulic calculates, and m is the Neutronics calculation iterations of setting, and m is more than 5；
Son is learned in calculating in commission, introduces adaptive relaxation factor ω and using power density distribution iteration function to the 2nd time
The power density distribution obtained to the m times execution Neutronics calculation is adjusted, and power density distribution is used for after obtained adjustment
Neutronics calculation is performed next time or is performed in thermal-hydraulic calculating, the supercritical water reactor reactor core nuclear heat coupling alternative manner tool
Body comprises the following steps：
S1, setting Neutronics calculation iterations m, build power density distribution iteration function, and initialization performs Neutronics calculation
Frequency n；
S2, first time Neutronics calculation is performed, and step S3 is jumped to after counting Neutronics calculation number；
S3, perform second of Neutronics calculation using performing the power density distribution that first time Neutronics calculation obtains, and count
Step S4 is jumped to after Neutronics calculation number；
S4, the last relative deviation for performing the power density distribution that Neutronics calculation obtains is calculated, and it is relatively inclined according to this
Difference chooses adaptive relaxation factor ω value；
S5, the work(for obtaining the adaptive relaxation factor ω chosen in step S4 value and the last execution Neutronics calculation
Rate Density Distribution substitutes into power density distribution iteration function and calculates power density distribution after adjustment, judges Neutronics calculation number
Whether it is equal to Neutronics calculation iterations, is to be set to Neutronics calculation number to jump to step S7 after initial value, otherwise
Jump to step S6；
S6, perform Neutronics calculation, statistics Neutronics calculation again using power density distribution after the adjustment in step S5
Number, jumps to step S4；
S7, thermal-hydraulic calculating is performed using power density distribution after the adjustment in step S5, judge that performing thermal-hydraulic calculates
Whether the power density distribution obtained afterwards restrains, and is, terminates to calculate, and otherwise jumps to step S2；
The obtaining value method that adaptive relaxation factor ω is chosen described in step S4 is：
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<mo>&prime;</mo>
</msup>
<mrow>
<mi>n</mi>
<mo>-</mo>
<mn>1</mn>
</mrow>
</msub>
</mrow>
<mo>|</mo>
</mrow>
<mrow>
<msub>
<msup>
<mi>P</mi>
<mo>&prime;</mo>
</msup>
<mrow>
<mi>n</mi>
<mo>-</mo>
<mn>1</mn>
</mrow>
</msub>
</mrow>
</mfrac>
<mo>,</mo>
<mi>n</mi>
<mo>=</mo>
<mn>3</mn>
<mo>,</mo>
<mn>4</mn>
<mo>,</mo>
<mn>5</mn>
<mo>,</mo>
<mn>...</mn>
<mo>,</mo>
<mi>m</mi>
</mrow>
</mtd>
</mtr>
<mtr>
<mtd>
<mrow>
<mfrac>
<mrow>
<mo>|</mo>
<mrow>
<msub>
<mi>P</mi>
<mi>n</mi>
</msub>
<mo>-</mo>
<msub>
<mi>P</mi>
<mrow>
<mi>n</mi>
<mo>-</mo>
<mn>1</mn>
</mrow>
</msub>
</mrow>
<mo>|</mo>
</mrow>
<msub>
<mi>P</mi>
<mrow>
<mi>n</mi>
<mo>-</mo>
<mn>1</mn>
</mrow>
</msub>
</mfrac>
<mo>,</mo>
<mi>n</mi>
<mo>=</mo>
<mn>2</mn>
</mrow>
</mtd>
</mtr>
</mtable>
</mfenced>
<mo>-</mo>
<mo>-</mo>
<mo>-</mo>
<mrow>
<mo>(</mo>
<mn>3</mn>
<mo>)</mo>
</mrow>
<mo>,</mo>
</mrow>
In formula (3), Pn-1For (n-1)th power density distribution for performing Neutronics calculation and obtaining, P 'n-1In being performed for (n-1)th time
Power density distribution after the adjustment for the power density distribution that son is calculated, PnPerform what Neutronics calculation obtained for n-th
Power density distribution.
A kind of 2. supercritical water reactor reactor core nuclear heat coupling alternative manner according to claim 1, it is characterised in that the work(
Rate Density Distribution iteration function is：
<mrow>
<msubsup>
<mi>P</mi>
<mi>n</mi>
<mo>&prime;</mo>
</msubsup>
<mo>=</mo>
<mfenced open = "{" close = "">
<mtable>
<mtr>
<mtd>
<mrow>
<msub>
<mi>&omega;</mi>
<mi>n</mi>
</msub>
<mo>&times;</mo>
<msub>
<mi>P</mi>
<mi>n</mi>
</msub>
<mo>+</mo>
<mrow>
<mo>(</mo>
<mn>1</mn>
<mo>-</mo>
<msub>
<mi>&omega;</mi>
<mi>n</mi>
</msub>
<mo>)</mo>
</mrow>
<mo>&times;</mo>
<msubsup>
<mi>P</mi>
<mrow>
<mi>n</mi>
<mo>-</mo>
<mn>1</mn>
</mrow>
<mo>&prime;</mo>
</msubsup>
<mo>,</mo>
<mi>n</mi>
<mo>=</mo>
<mn>3</mn>
<mo>,</mo>
<mn>4</mn>
<mo>,</mo>
<mn>...</mn>
<mo>,</mo>
<mi>m</mi>
</mrow>
</mtd>
</mtr>
<mtr>
<mtd>
<mrow>
<msub>
<mi>&omega;</mi>
<mi>n</mi>
</msub>
<mo>&times;</mo>
<msub>
<mi>P</mi>
<mi>n</mi>
</msub>
<mo>+</mo>
<mrow>
<mo>(</mo>
<mn>1</mn>
<mo>-</mo>
<msub>
<mi>&omega;</mi>
<mi>n</mi>
</msub>
<mo>)</mo>
</mrow>
<mo>&times;</mo>
<msub>
<mi>P</mi>
<mrow>
<mi>n</mi>
<mo>-</mo>
<mn>1</mn>
</mrow>
</msub>
<mo>,</mo>
<mi>n</mi>
<mo>=</mo>
<mn>2</mn>
</mrow>
</mtd>
</mtr>
</mtable>
</mfenced>
<mo>-</mo>
<mo>-</mo>
<mo>-</mo>
<mrow>
<mo>(</mo>
<mn>1</mn>
<mo>)</mo>
</mrow>
<mo>,</mo>
</mrow>
In formula (1), n is Neutronics calculation number；ωnThe power density distribution obtained to perform Neutronics calculation to n-th is carried out
The adaptive relaxation factor ω used during adjustment value；Pn-1For (n-1)th power density point for performing Neutronics calculation and obtaining
Cloth, PnThe power density distribution obtained for n-th execution Neutronics calculation, P 'n-1Neutronics calculation is performed for (n-1)th time to obtain
Power density distribution adjustment after power density distribution, P 'nFor using ωnTo PnPower is close after being adjusted obtained adjustment
Degree distribution.
A kind of 3. supercritical water reactor reactor core nuclear heat coupling alternative manner according to claim 1 or 2, it is characterised in that institute
It is 20-40 to state Neutronics calculation iterations m.
A kind of 4. supercritical water reactor reactor core nuclear heat coupling alternative manner according to claim 1 or 2, it is characterised in that institute
Neutronics calculation iterations m is stated as 30.
A kind of 5. supercritical water reactor reactor core nuclear heat coupling alternative manner according to claim 1 or 2, it is characterised in that institute
State and judge that performing the whether convergent specific method of power density distribution obtained after thermal-hydraulic calculates is in step S6：Judgement is held
Whether the power density distribution after row thermal-hydraulic calculates meets formula with the power density distribution before execution thermal-hydraulic calculating
(4), meet then to restrain, be unsatisfactory for not restraining：
<mrow>
<mfrac>
<mrow>
<mo>|</mo>
<mi>f</mi>
<mrow>
<mo>(</mo>
<msub>
<msup>
<mi>q</mi>
<mo>&prime;</mo>
</msup>
<mi>m</mi>
</msub>
<mo>)</mo>
</mrow>
<mo>-</mo>
<msub>
<msup>
<mi>q</mi>
<mo>&prime;</mo>
</msup>
<mi>m</mi>
</msub>
<mo>|</mo>
</mrow>
<mrow>
<msub>
<msup>
<mi>q</mi>
<mo>&prime;</mo>
</msup>
<mi>m</mi>
</msub>
</mrow>
</mfrac>
<mo>&le;</mo>
<mi>&delta;</mi>
<mo>-</mo>
<mo>-</mo>
<mo>-</mo>
<mrow>
<mo>(</mo>
<mn>4</mn>
<mo>)</mo>
</mrow>
<mo>;</mo>
</mrow>
In formula, f (q'm) it is to perform the power density distribution after thermal-hydraulic calculates, q'mNeutronics calculation is performed for the m times to obtain
Power density distribution adjustment after power density distribution, δ be setting convergency value.
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| Publication number | Priority date | Publication date | Assignee | Title |
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| US4711753A (en) * | 1986-03-19 | 1987-12-08 | Westinghouse Electric Corp. | Calibration of a nuclear reactor core parameter predictor |
| CN103902784A (en) * | 2014-04-11 | 2014-07-02 | 华北电力大学 | Safety analysis calculating device for transient nuclear heat coupling of supercritical water reactor |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4711753A (en) * | 1986-03-19 | 1987-12-08 | Westinghouse Electric Corp. | Calibration of a nuclear reactor core parameter predictor |
| CN103902784A (en) * | 2014-04-11 | 2014-07-02 | 华北电力大学 | Safety analysis calculating device for transient nuclear heat coupling of supercritical water reactor |
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| SCWR 堆芯三维瞬态物理-热工水力耦合程序开发;王连杰等;《核动力工程》;20141231;第35卷(第S2期);186-189 * |
| 基于不动点理论的核热耦合计算收敛特性研究;刘仕倡等;《核动力工程》;20140630;第35卷(第3期);152-157 * |
| 超临界水堆反应堆物理-热工水力耦合程序超临界水堆反应堆物理-热工水力耦合程序系统MCATHAS的开发;安萍 等;《核动力工程》;20101231;第31卷(第6期);52-74 * |
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