CN109753712A - A kind of optimum design method of Neutron Dose Equivalent Rate instrument - Google Patents

A kind of optimum design method of Neutron Dose Equivalent Rate instrument Download PDF

Info

Publication number
CN109753712A
CN109753712A CN201811618609.XA CN201811618609A CN109753712A CN 109753712 A CN109753712 A CN 109753712A CN 201811618609 A CN201811618609 A CN 201811618609A CN 109753712 A CN109753712 A CN 109753712A
Authority
CN
China
Prior art keywords
dose equivalent
model
variable
rate instrument
neutron dose
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN201811618609.XA
Other languages
Chinese (zh)
Inventor
张清民
许硕
陈斐
危光友
邵壮
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Xian Jiaotong University
Original Assignee
Xian Jiaotong University
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Xian Jiaotong University filed Critical Xian Jiaotong University
Priority to CN201811618609.XA priority Critical patent/CN109753712A/en
Publication of CN109753712A publication Critical patent/CN109753712A/en
Pending legal-status Critical Current

Links

Abstract

A kind of optimum design method of Neutron Dose Equivalent Rate instrument, steps are as follows: 1, describing Neutron Dose Equivalent Rate instrument basic model using Monte Carlo software;2, the performance indicator for wanting optimization is chosen;3, its adjustable material variables, size variable, configuration variable, location variable is determined according to basic model;4, genetic algorithm parameters are set;5, in preset range of variables, primary population of a variety of different models as genetic algorithm is generated at random;6, simulation calculates performance indicator selected by the step 2 of this every kind of model of generation;7, all models of filial generation are obtained according to genetic algorithm, selects the model X of best performance;Whether reached by genetic algebra and presets whether total algebra N and performance close to preset need decide whether return step 6;Through the Neutron Dose Equivalent Rate instrument that can mostly obtain required function admirable for genetic optimization;The method of the present invention can be designed the Neutron Dose Equivalent Rate instrument of different essential structures for different demands performance, widely used.

Description

A kind of optimum design method of Neutron Dose Equivalent Rate instrument
Technical field
The invention belongs to neutron detection technical fields, and in particular to a kind of optimization design side of Neutron Dose Equivalent Rate instrument Method.
Background technique
China's nuclear industry is in high-speed development period, and nuclear safety more shows important, proposes newly to the exhibition of radiation-measurment equipment Requirement.To realize effective dosage supervision, it is ensured that the safe and smooth development of related work, ambient dose equivalent of neutron rate instrument are wide It is general to be applied to each field of nuclear industry.
From the point of view of radiation protection, people often concern radiation damage caused by human body, theoretically This possible damage should be assessed by effective dose, and in actual measurement, generally use Neutron Ambient Dose Equivalent close as it It instructs to protect like value.
Neutron Dose Equivalent Rate instrument be exactly it is a kind of for measuring neutron field at certain point caused by ambient dose equivalent of neutron Radiation meter, can be divided by application places fixed and two kinds portable, design principle is similar.In addition to above-mentioned Each field of the nuclear industry referred to, Neutron Dose Equivalent Rate instrument are also widely used for environmental monitoring, large-scale activity security and science The fields such as research guarantee.
At present lot of domestic and international scholar designed many Neutron Dose Equivalent Rate instrument, many function admirables of successful design Instrument models, while there are also deficiencies: since actual neutron field energy range is very wide, existing ambient neutron dose equivalent meter Energy response it is generally poor, intermediate energy region and hot-zone are respectively present significantly to cross and respond and response is insufficient especially near 5keV Problem, and domestic market is monopolized by external product for a long time.Therefore, develop that a kind of performance is more excellent, lower-cost new neutron week Enclosing Dose Equivalent Ratemeter seems particularly necessary and urgent.
Summary of the invention
In order to solve the above-mentioned problems of the prior art, the purpose of the present invention is to provide a kind of Neutron Dose Equivalent Rates The optimum design method of instrument, 1) its model is optimized by Monte Carlo simulation combination genetic algorithm program, without manually pass through through Test adjustment.It 2), can as long as setting different quantitative targets reaches corresponding effect of optimization for required different performance For optimizing the Neutron Dose Equivalent Rate instrument in various different application fields, different performance requirement.
To achieve the above objectives, the present invention adopts the following technical scheme:
A kind of optimum design method of Neutron Dose Equivalent Rate instrument, includes the following steps:
Step 1: the basic model of Neutron Dose Equivalent Rate instrument is described using Monte Carlo software;
Step 2: choosing the Neutron Dose Equivalent Rate instrument performance indicator to be optimized;
Step 3: determining that the i.e. preset model of its adjustable variable becomes according to the basic model of Neutron Dose Equivalent Rate instrument Amount, including material variables m, size variable d, configuration variable f and location variable p;
Step 4: setting the parameters of genetic algorithm, comprising: material variables m, size variable d, configuration variable f and position Variation range, number of bits PRECI, total genetic algebra N, total population number M, crossing-over rate px, aberration rate pm and the generation gap of variable p GGAP;Material variables m, size variable d, configuration variable f and position is set according to the realistic model of Neutron Dose Equivalent Rate instrument to become Number of bits PRECI is arranged according to the variation range of variable m, d, f, p in the variation range for measuring p, substantially former according to genetic algorithm Reason sets total genetic algebra N, total population number M, crossing-over rate px, aberration rate pm and generation gap GGAP.
Step 5: it is random to generate the different model of M kind in the parameter ranges of preset model variable, as genetic algorithm Population primary, each model X correspond to the material of Neutron Dose Equivalent Rate instrument a kind of, size, shape, position design side Case;
Step 6: for each model X in this generation, calculating in step 2 and to optimize using Monte Carlo software simulation Neutron Dose Equivalent Rate instrument performance indicator;
Step 7: follow-on M kind model being generated according to the basic principle of genetic algorithm, therefrom selecting in step 2 will optimize The optimal model X of Neutron Dose Equivalent Rate instrument performance indicatorIt is excellent;Decide whether return step 6 according to following judgment rule;
Judgment rule are as follows: whether genetic algebra i at this time is more than or equal to preset total genetic algebra N and at this time Whether performance is close to required performance;If the relative error of the performance and required performance that simulate at this time is less than or equal to default precision, Then illustrate to be optimized to default precision, then exports the optimal model of the Neutron Dose Equivalent Rate instrument performance indicator to be optimized at this time XIt is excellent;If i is more than or equal to N, illustrates the final algebra for being optimized to setting, then exports the Neutron Dose Equivalent Rate to be optimized The optimal model X of instrument performance indicatorIt is excellent;Otherwise, illustrate the total algebra N of the heredity of also not up to setting and the neutron dose to be optimized Equivalent rates instrument performance indicator also unmet demand, return step 6 carry out follow-on simulation.
The step 2 Neutron Dose Equivalent Rate instrument performance indicator to be optimized is energy response curve flatness η, angular response curve Consistency ζ or detection efficient maximum value ε.
Step 5, step 6 and step 7 use genetic algorithm, pass through the selection operator of genetic algorithm, crossover operator and variation Operator generates filial generation model to carry out the optimization of model.
The setting scheme of parameter in step 4 are as follows: total genetic algebra N is more than or equal to 80, and total population number M is more than or equal to 80, hands over Fork rate px is 0.95~0.99, and aberration rate pm is 0.001, and generation gap GGAP is 0.8~0.9.
The present invention optimizes the geometry mould of Neutron Dose Equivalent Rate instrument by genetic algorithm combination Monte Carlo software simulation Type structure has the advantage that compared with prior art
The basic geometry of Neutron Dose Equivalent Rate instrument in step 1 according to circumstances can be selected arbitrarily, such as spherical structure Or tubular structure, method have universality, flexibility using upper.
Performance indicator can define according to demand in step 2, including energy response curve flatness η, angular response curve one Cause property ζ and detection efficient maximum value ε, method have universality and flexibility using upper.
Detailed description of the invention
Fig. 1 is flow chart of the present invention.
Fig. 2 is example Neutron Dose Equivalent Rate instrument basic model schematic diagram.
Fig. 3 is Neutron Dose Equivalent Rate instrument model energy response curve after genetic algorithm optimization.
Fig. 4 is every generation optimum performance change curve during genetic algorithm optimization.
Specific embodiment
Below in conjunction with drawings and the specific embodiments, the present invention is described in further detail.
Below to design a kind of new neutron Neutron Ambient Dose Equivalent rate instrument model for pursuing Neutron energy responce plateau It is described in detail, specific method process is as shown in Figure 1.
Step 1: the basic model of Neutron Dose Equivalent Rate instrument is described using Monte Carlo software, as shown in Fig. 2, three ball of helium Slowing down layer is wrapped up outside shape counter, includes one layer of cadmium layer in slowing down layer, and outermost layer is metal-back, arrangement cylinder in slowing down layer Hanker subchannel.Wherein, slowing down layer choosing polyethylene layer, metal-back select iron material.
Step 2: choosing the instrument performance index for wanting optimization, the present embodiment wants optimality criterion to be set as neutron dose The energy response curve flatness η of equivalent rates instrument.
η is specific is defined as:
Wherein σ is the standard deviation of data in each energy area,For the average value of data, n is fetched by each energy area The total number at strong point, i indicate the data sequence number from 1 to n, xiFor for each energy point, the energy response of the model.In reality In program, n is neutron energy 101 points that section is uniformly chosen in logarithmic coordinates from 1E-8MeV to 100MeV.
Step 3: according to the basic model of Neutron Dose Equivalent Rate instrument determine its adjustable variable (including material variables m, Size variable d, configuration variable f, location variable p).
The basic geometry of Neutron Dose Equivalent Rate instrument is as shown in Figure 2, it is contemplated that angular response consistency, on slow body It has been arranged symmetrically 26 and has hankered subchannel.Five size variable d are set altogether1~d5, it is position d1, the cadmium piece of cadmium piece respectively Thickness d 2, the thickness d 3 of entire polyethylene slow body, the thickness d of iron plate 4 and the radius d5 for hankering subchannel.
Following table is the unit vector of thermal neutron channel direction:
Table 1 hankers subchannel azimuth table
Step 4: setting the parameters of genetic algorithm, comprising: the variation range of variable m, d, f, p, number of bits PRECI, total genetic algebra N, total population number M, crossing-over rate px, aberration rate pm and generation gap GGAP.According to Neutron Dose Equivalent Rate instrument Realistic model setting variable m, d, f, p variation range, according to the variation range of variable m, d, f, p setting determine number of bits PRECI sets total genetic algebra N, total population number M, crossing-over rate px, aberration rate pm and generation gap according to genetic algorithm basic principle GGAP。
Model structure variable d1~d5Range constrained by following equations group, unit cm:
1.65≤d1≤10
0≤d2≤2
d1+d2≤d3≤d1+d2+15
0≤d4≤2
0≤d5≤1
Specific parameter setting are as follows: total algebra N is set as 80, total population number M and is set as 80, generation gap GGAP being set as 0.90, intersect Probability p x is set as 0.97, mutation probability pm and is set as 0.001, number of bits PRECI being set as 20.
Step 5: it is random to generate the different model of M kind in the parameter ranges of preset model variable m, d, f, p, as The population primary of genetic algorithm, each model X correspond to the material of Neutron Dose Equivalent Rate instrument a kind of, size, shape, position Design scheme;
Step 6: for each model X in this generation, being simulated using Monte Carlo software selected by calculating in step 2 Performance indicator, i.e. energy response curve flatness η;
Neutron source in Monte Carlo software is set as being parallel to the rounded face source of sphere model, and neutron radioactivity uniformly divides Be distributed in face source, NEUTRON EMISSION direction be it is unidirectional, perpendicular to face source, energy is single energy.The energy for repeating to change neutron source can mould It is quasi- to obtain energy response curve.
Step 7: generating all models of filial generation further according to the basic principle of genetic algorithm, therefrom select performance indicator η most Excellent model XIt is excellent,.Decide whether return step 4 according to following judgment rule;
Judgment rule are as follows: whether genetic algebra i at this time is more than or equal to preset total algebra N and performance at this time is It is no close to required performance.By taking the energy response curve flatness η in example as an example, if | (η-η0)/η0| < < ε00For precision, η0For demand flatness), then illustrate to be optimized to default precision, then exports the mould that energy response curve flatness η is optimal at this time Type XIt is excellent;If i is more than or equal to N, illustrates the final algebra for being optimized to setting, then exports energy response curve flatness η Optimal model XIt is excellent.Otherwise, then illustrate the total algebra N of the heredity of also not up to setting and energy response curve flatness η is also not Meet demand, return step 6 carry out follow-on simulation.
Wherein: desired unevenness degree η0It is set as 3%, precision ε0It is set as 0.1%, final operation to 80 generations terminates, no Flatness η0It is optimized to 8.2%, if algebra N setting is bigger, can also be advanced optimized.
Embodiment
A kind of Neutron Dose Equivalent Rate instrument model that pursuit energy response curve is flat has been obtained by the method for the invention.Its Energy response as shown in figure 3, the energy response curve of the model from 1E-8MeV to 1MeV, section is very flat,.
The best unevenness degree performance of every generation in genetic algorithm is recorded, as shown in Figure 4, it is seen that genetic algorithm is in entire mistake Effect of optimization in journey is significant, if computing resource is enough, can set the more genetic algebras of more populations, advanced optimize knot Fruit.
The size variable d of final mask1~d5Numerical value it is as shown in the table, length unit is cm:
2 final mask structural parameters table of table
Three radius of sphericity of helium Cadmium piece position Cadmium piece thickness Slowing down body thickness Iron-clad thickness Thermal neutron channel radius Number of perforations
1.65 3.2648 0.425 7.5574 0.7547 0.7246 26
This Neutron Dose Equivalent Rate instrument is more consistent to the remolding sensitivity of the neutron of 1E-8MeV to 1MeV as seen from Figure 3, Energy response maximum value and minimum in entire scope are 0.2384cm2And 0.4538cm2, maximum all near 0.01MeV Fluctuation is 31.1%, and the uneven degree that average relative fluctuation is for we is 8.2%, and average neutron sensitivity is 0.3745cm2, preferably realize performance objective.The Neutron Dose Equivalent Rate model that this method obtains, for complicated energy The detection of neutron field can obtain reliable result.
Compared with the flat long counter of existing pursuit energy response curve, performance is also more excellent, especially in 1E-6MeV With down toward the section 1E-8MeV, model energy response is flat more than current long counter, the long counter design of existing literature Energy response flat region can not be extended to thermal neutron range.
It is designed additionally, due to using symmetrical structure, designed model has excellent angular response curve conformity.
The Neutron Dose Equivalent Rate instrument of other geometrical constructions can also be optimized, not limited to the method for the present invention The bulbous configuration lifted in example, other such as tubular structures.It can also be to neutron Dose Equivalent Ratemeter with the method Other parameters (material, shape, location parameter) optimize, the geometric dimension parameter being not limited in example.We Method can also (energy response curve flatness η, angular response curve be consistent for different performance needed for the Neutron Dose Equivalent Rate instrument Property ζ or detection efficient maximum value ε) it optimizes respectively.For example, the angular response optimization of Neutron Dose Equivalent Rate instrument is carried out, The variable increase of model can be hankered to the parameters such as density, direction, the depth of subchannel, with the Dose Equivalent Ratemeter to different angle And the relative fluctuation δ of the sensitivity of different-energy neutron carries out Genetic Algorithm optimized design to model as performance indicator.It is comprehensive On, the method for the present invention can be designed the Neutron Dose Equivalent Rate instrument of different essential structures for different demands performance, purposes Extensively.

Claims (4)

1. a kind of optimum design method of Neutron Dose Equivalent Rate instrument, characterized by the following steps:
Step 1: the basic model of Neutron Dose Equivalent Rate instrument is described using Monte Carlo software;
Step 2: choosing the Neutron Dose Equivalent Rate instrument performance indicator to be optimized;
Step 3: the i.e. preset model variable of its adjustable variable being determined according to the basic model of Neutron Dose Equivalent Rate instrument, is wrapped Include material variables m, size variable d, configuration variable f and location variable p;
Step 4: setting the parameters of genetic algorithm, comprising: material variables m, size variable d, configuration variable f and location variable Variation range, number of bits PRECI, total genetic algebra N, total population number M, crossing-over rate px, aberration rate pm and the generation gap of p GGAP;Material variables m, size variable d, configuration variable f and position is set according to the realistic model of Neutron Dose Equivalent Rate instrument to become Number of bits PRECI is arranged according to the variation range of variable m, d, f, p in the variation range for measuring p, substantially former according to genetic algorithm Reason sets total genetic algebra N, total population number M, crossing-over rate px, aberration rate pm and generation gap GGAP.
Step 5: it is random to generate the different model of M kind in the parameter ranges of preset model variable, as the first of genetic algorithm For population, each model X correspond to the material of Neutron Dose Equivalent Rate instrument a kind of, size, shape, position design scheme;
Step 6: for each model X in this generation, being calculated using Monte Carlo software simulation in being optimized in step 2 Sub- Dose Equivalent Ratemeter performance indicator;
Step 7: follow-on M kind model being generated according to the basic principle of genetic algorithm, is therefrom selected in step 2 in being optimized The optimal model X of sub- Dose Equivalent Ratemeter performance indicatorIt is excellent;Decide whether return step 6 according to following judgment rule;
Judgment rule are as follows: whether genetic algebra i at this time is more than or equal to preset total genetic algebra N and performance at this time Whether close to required performance;If the relative error of the performance and required performance that simulate at this time is less than or equal to default precision, say It is bright to be optimized to default precision, then export the optimal model X of the Neutron Dose Equivalent Rate instrument performance indicator to be optimized at this timeIt is excellent;Or If person i is more than or equal to N, illustrate the final algebra for being optimized to setting, then exports the Neutron Dose Equivalent Rate instrument to be optimized It can the optimal model X of indexIt is excellent;Otherwise, illustrate the total algebra N of the heredity of also not up to setting and the neutron DE to be optimized Rate instrument performance indicator also unmet demand, return step 6 carry out follow-on simulation.
2. optimum design method according to claim 1, it is characterised in that: step 2 neutron DE to be optimized Rate instrument performance indicator is energy response curve flatness η, angular response curve conformity ζ or detection efficient maximum value ε.
3. optimum design method according to claim 1, it is characterised in that: step 5, step 6 and step 7 are using heredity Algorithm generates filial generation model by the selection operator of genetic algorithm, crossover operator and mutation operator to carry out the optimization of model.
4. optimum design method according to claim 1, it is characterised in that: the setting scheme of parameter in step 4 are as follows: total to lose Passage number N is more than or equal to 80, and total population number M is more than or equal to 80, and crossing-over rate px is 0.95~0.99, and aberration rate pm is 0.001, generation Ditch GGAP is 0.8~0.9.
CN201811618609.XA 2018-12-28 2018-12-28 A kind of optimum design method of Neutron Dose Equivalent Rate instrument Pending CN109753712A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201811618609.XA CN109753712A (en) 2018-12-28 2018-12-28 A kind of optimum design method of Neutron Dose Equivalent Rate instrument

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201811618609.XA CN109753712A (en) 2018-12-28 2018-12-28 A kind of optimum design method of Neutron Dose Equivalent Rate instrument

Publications (1)

Publication Number Publication Date
CN109753712A true CN109753712A (en) 2019-05-14

Family

ID=66404252

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201811618609.XA Pending CN109753712A (en) 2018-12-28 2018-12-28 A kind of optimum design method of Neutron Dose Equivalent Rate instrument

Country Status (1)

Country Link
CN (1) CN109753712A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111767518A (en) * 2020-06-05 2020-10-13 国家核安保技术中心 Method, device and equipment for determining parameter value of AWCC (active-vector configuration center) and computer storage medium

Citations (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20010054977A1 (en) * 2000-05-26 2001-12-27 Courtney Clifton C. Method for creation of planar or complex wavefronts in close proximity to a transmitter array
US20020141529A1 (en) * 2001-03-09 2002-10-03 Olsher Richard H. Proton recoil scintillator neutron rem meter
US20060188062A1 (en) * 2005-02-24 2006-08-24 Dileep Agnihotri Material analysis using multiple x-ray reflectometry models
CN102337979A (en) * 2011-08-11 2012-02-01 浙江大学 Automatic calibration parameter optimization method of engine based on genetic algorithm
CN103529469A (en) * 2013-10-14 2014-01-22 苏州大学 Method for screening radiation-damaged biomarkers at early stage of rat and application
CN105467515A (en) * 2014-09-10 2016-04-06 中国辐射防护研究院 Cadmium-doped fiber and neutron measuring method thereof
US9465120B1 (en) * 2011-10-27 2016-10-11 Kansas State University Research Foundation Apparatus and method for the determination of one or more neutron source characteristics
CN107316665A (en) * 2017-06-01 2017-11-03 西安交通大学 A kind of Optimization Design of self-power neutron detector structure
CN108549753A (en) * 2018-03-28 2018-09-18 中国船舶重工集团公司第七〇九研究所 A kind of radiation shield computational methods that Point- kernel integral method is coupled with Monte Carlo method

Patent Citations (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20010054977A1 (en) * 2000-05-26 2001-12-27 Courtney Clifton C. Method for creation of planar or complex wavefronts in close proximity to a transmitter array
US20020141529A1 (en) * 2001-03-09 2002-10-03 Olsher Richard H. Proton recoil scintillator neutron rem meter
US20060188062A1 (en) * 2005-02-24 2006-08-24 Dileep Agnihotri Material analysis using multiple x-ray reflectometry models
CN102337979A (en) * 2011-08-11 2012-02-01 浙江大学 Automatic calibration parameter optimization method of engine based on genetic algorithm
US9465120B1 (en) * 2011-10-27 2016-10-11 Kansas State University Research Foundation Apparatus and method for the determination of one or more neutron source characteristics
CN103529469A (en) * 2013-10-14 2014-01-22 苏州大学 Method for screening radiation-damaged biomarkers at early stage of rat and application
CN105467515A (en) * 2014-09-10 2016-04-06 中国辐射防护研究院 Cadmium-doped fiber and neutron measuring method thereof
CN107316665A (en) * 2017-06-01 2017-11-03 西安交通大学 A kind of Optimization Design of self-power neutron detector structure
CN108549753A (en) * 2018-03-28 2018-09-18 中国船舶重工集团公司第七〇九研究所 A kind of radiation shield computational methods that Point- kernel integral method is coupled with Monte Carlo method

Non-Patent Citations (10)

* Cited by examiner, † Cited by third party
Title
R.J.TANNER .ETAL: "A new design of neutron survey instrument", 《RADIATION MEASUREMENTS》 *
WASEEM KHANA .ECT: "Monte Carlo simulation of the full energy peak efficiency of an HPGe detector", 《APPLIED RADIATION AND ISOTOPES》 *
卓金武 等: "《MATLAB 数学建模方法与实践 第 3 版》", 31 July 2018, 北京航空航天大学出版社 *
吴福源 等: "高能γ探测系统中的光耦合部件参数优化", 《强激光与粒子束》 *
张跃庆 等: "《经济百科辞典》", 30 November 1989 *
杨国召: "宽谱中子剂量当量及注量探头优化设计", 《中国优秀硕士学位论文全文数据库-工程科技II辑》 *
杨国召: "宽谱中子剂量当量及注量探头优化设计", 《中国优秀硕士学位论文全文数据库——工程科技II辑》 *
汲长松 等: "《中子探测》", 31 May 2014, 原子能出版社 *
田时海: "中子剂量当量仪的设计", 《核技术》 *
魏迎光: "高灵敏度环境中子剂量当量仪的优化设计与实验验证", 《中国优秀硕士学位论文全文数据库》 *

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111767518A (en) * 2020-06-05 2020-10-13 国家核安保技术中心 Method, device and equipment for determining parameter value of AWCC (active-vector configuration center) and computer storage medium

Similar Documents

Publication Publication Date Title
CN105930933B (en) Wind power plant theoretical power curve determines method and device
CN108549753B (en) Radiation shielding calculation method for coupling point kernel integration method and Monte Carlo method
CN107038294B (en) For the Resonance self-shielding calculation method based on equivalent one-dimensional stick model of light water reactor
CN107038293B (en) Resonance self-screen calculation method for plate-shaped fuel based on equivalent one-dimensional plate model
CN109376418A (en) A kind of pneumatic Robust Optimal Design method of small wind airfoil type suitable for turbulent flow operating condition
CN106227943B (en) A kind of random pore generation method of two dimension different surface roughness
CN103871511B (en) A kind of monitoring method of nuclear power plant reactor axial power distribution
CN104968395A (en) Apparatus for determining a number of beams in IMRT
CN107551411A (en) For the probabilistic proton heavy ion intensity modulated radiation therapy robust Optimal methods of range
CN104599302A (en) Method for obtaining PET crystal energy peak value and setting energy frequency discriminator
CN109753712A (en) A kind of optimum design method of Neutron Dose Equivalent Rate instrument
CN110765618A (en) Method for calculating response current of self-powered neutron detector in pressurized water reactor
Leppänen CAD-based geometry type in Serpent 2–application in fusion neutronics
CN106597560B (en) A kind of neutron gamma density logging method characterized using fast neutron field distribution
CN110781593B (en) Characterization method of neutron energy spectrum and photon energy spectrum in self-powered neutron detector
CN107103189B (en) A method of carrying out the search of reactor critical buckling
CN105335581A (en) Optimization method of airplane wiring harness mass distribution data
Daeubler et al. Development of a high-fidelity Monte Carlo thermal-hydraulics coupled code system Serpent/SUBCHANFLOW–first results
CN105046096B (en) A kind of power window parameter automatic generation method pre-processed based on free path
CN102800373A (en) Method for scaling reactor absolute power by fission detection sheet
Wang et al. Development of spectrum unfolding code for multi-sphere neutron spectrometer using genetic algorithms
Yi-xue et al. Effect of fusion neutron source numerical models on neutron wall loading in a DD tokamak device
CN106772546B (en) One kind is considered by medium to heteropical charged particle equivalent depth acquisition methods
CN105825067B (en) The optimization method of the virtual source model of linear accelerator
Chai et al. The linear source approximation in three dimension characteristics method

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
RJ01 Rejection of invention patent application after publication
RJ01 Rejection of invention patent application after publication

Application publication date: 20190514