KR20220031171A - Method for designing shielding both photons and neutrons at the same time, recording medium storing program for executing same, and computer program stored in recording medium for executing same - Google Patents

Abstract

The present invention relates to a simultaneous photon and neutron shielding design method to easily provide a simultaneous photon and neutron shielding design, a recording medium storing program for executing the same, and a computer program stored in a recording medium for executing the same. According to the present invention, the method comprises: a step of performing Monte Carlo simulation for a structure set of a shielding design-using facility for each characteristic of a radiation source/generator to build simulation results into a library; a step of receiving information on an actually used facility to extract geometric data, thereby setting a candidate group (among the structure set); a step of loading the simulation results having the closest geometric data to the candidate group from the library to extract functions performing optimization and correction in response to the geometric data of the actually used facility; and a step of using the functions to extract a design plan for simultaneously shielding photons and neutrons in consideration of a coupled transport phenomenon of photon-neutron-photon or neutron-photon-neutron without an actual Monte Carlo simulation process in a site.

Description

Simultaneous photon and neutron shielding design method, a recording medium storing a program for implementing the same, and a computer program stored in the medium for implementing the same COMPUTER PROGRAM STORED IN RECORDING MEDIUM FOR EXECUTING SAME}

The present invention relates to a photon and neutron simultaneous shielding design method, a recording medium storing a program for implementing the same, and a computer program stored in the medium for implementing the same, and more particularly, to a shielding design using facility according to characteristics of a radiation source/generating device. By performing Monte Carlo simulations on a structure set in advance, the simulation results are built into a library, and geometric data is derived by receiving information on actual facilities used to set a candidate group (from the structure group), , derives functions for performing optimization and correction in response to the geometric data of the actual facility by retrieving the simulation result that the candidate group and the geometric data are closest to from the library, and using the functions to simulate the actual Monte Carlo in the field Considering the coupled transport phenomenon of photon-neutron-photon or neutron-photon-neutron without process, It relates to a photon and neutron simultaneous shielding design method for deriving a design proposal for photon and neutron simultaneous shielding, a recording medium storing a program for implementing the same, and a computer program stored in the medium for implementing the same.

"Radiation shielding" can be defined as attenuating the intensity of a radiation field in a specific area. That is, the intensity of the radiation field is attenuated by interacting with the members of the material while passing through a material. Using this phenomenon to physically attenuate the intensity of radiation is called radiation shielding, and at this time, the material or material used is It's called a shield.

In general, heavy charged particles such as fission fragments, α-rays, heavy protons, and protons have very short crystals, so they can be shielded with paper or rubber gloves. not. Also, β-ray irregularity is larger than that of medium-charged particles, but with a little care, there is no big problem. However, in the case of shielding high-energy β-rays, the importance of shielding the secondary radiation of photons (X-rays) by braking radiation from the β-ray shielding material should be considered.

On the other hand, in the case of X-ray or γ-ray shielding, two aspects should be considered. One is shielding for a narrow beam, in which the radiation field is uniform and physical phenomena are easily expressed by equations, and the other is shielding by a broad beam that forms a radiation field by compounding the phenomenon caused by scattering that occurs a lot in practice. In general, for shielding X-rays or γ-rays with strong penetrating power, it is shielded with a material with a high density and high atomic number (lead, iron, concrete, tungsten, depleted uranium).

In addition, the shielding of neutrons is achieved by using the property that neutrons easily lose their energy when they collide with materials containing light atomic nuclei such as hydrogen and are elastically scattered. If γ-rays with high penetrating power and high-speed neutrons are effectively blocked, others are automatically blocked, so blocking these radiations is the basis for actual shielding facilities.

The shielding design of a radiation facility focuses on radiation stability, and at the same time, it is designed in consideration of economic efficiency, minimum weight, and structural stability. Energy, strength, geometric shape of source, thickness of shielding body, impact evaluation on scattered radiation in laboratory, duct, and trough structures passing through shielding, fire resistance, seismic resistance, durability, construction characteristics and maintenance of the designed shielding structure It is necessary to review architectural engineering such as method, and considerations for shielding materials to be used when designing radiation shielding include shielding ability, physical and chemical properties, difficulty in obtaining, economic feasibility, and construction characteristics. It's about choosing what suits your purpose. The shielding material should be selected with effective shielding ability according to the type of radiation.

The thickness of the shield required to shield X-rays or γ-rays is almost inversely proportional to the density of the material. In general, elements with large atomic numbers are effective in attenuating γ-rays, so heavy elements such as iron, lead, and uranium are good for X-rays or γ-rays. However, as a problem raised experimentally, it is necessary to satisfy the requirements for engineering strength, characteristics for heat, construction characteristics, and economic feasibility.

In particular, when the space where the shielding structure is to be constructed is not restricted, it is effective to use general aggregate with a large wall thickness in terms of constructability, stability, and economic feasibility, and the probability of problems occurring during the purchase or construction of aggregate is low.

However, in cases where the thickness of the shielding wall is limited, such as around the windows for multi-purpose research reactors or experimental reactors, it is impossible to shield with general aggregates, so heavy concrete aggregates with high density should be used. In addition, when it is necessary to satisfy the shielding performance with a limited wall thickness, the specific gravity of concrete must be increased, so that it is necessary to use a heavy aggregate.

As a related prior art document, according to Korean Patent Publication No. 10-2012-0106191 "Radiation shielding concrete composition for replacing concrete aggregate", it is an invention to give concrete a radioactive shielding function by including oxidized slag in an electric furnace, A radioactive shielding concrete composition containing cement, coarse aggregate of 5 mm or more, fine aggregate of 5 mm or less, and electric furnace oxidation slag for replacement of concrete fine aggregate consisting of unavoidable foreign substances, wherein the fine aggregate is oxidized in an electric furnace having a unit volume mass of 3500 kg/m3 or more and at least one of slag and powder iron. By including at least one of electric furnace oxidized slag and magnetite having a unit volume mass of 3500 kg/m or more as the coarse aggregate, the electric furnace oxidized slag generated in the smelting and refining process of the iron ore is used as the building frame This becomes possible, so that various incidental costs associated with the reprocessing of the oxidized slag in the electric furnace can be reduced, as well as the manufacturing cost of the concrete can be reduced.

However, the composition to contain at least one of electrooxidation slag or magnetite is an attempt to block radiation by increasing the density of concrete. and the purpose of reducing the concrete manufacturing cost is strong.

Also, as a prior art, Korean Patent Registration No. 10-1578697 "Chemically bonded ceramic radiation shielding material and manufacturing method" relates to a composition and a method for forming a radiation shielding member at ambient temperature, wherein the composition is a 'low temperature-fired' chemical bond oxide-phosphate ceramic cement matrix; and one or more suitably prepared and distributed radiation shielding materials dispersed in a 'cold-fired' chemically bonded oxide-phosphate ceramic cement matrix.

However, it is difficult to believe that low-temperature firing chemically bonded oxide phosphate ceramics with a certain thickness satisfy radiation blocking, and neutron shielding is not mentioned, so continuous research on shielding for each type of radiation is still needed.

On the other hand, the spent fuel storage and transport container contain both a gamma source and a neutron source at the same time. shall.

As the field of application of particle accelerators expands, the energy of accelerated particles is also increasing significantly. In the case of a facility that intends to utilize photons generated from high-energy electron accelerators of 10 MeV or more, photonuclear reaction between tungsten, a target material for generating photons, and heavy metal elements such as lead, tungsten, iron, and aluminum as a facility structure or shielding material Simultaneous photon-neutron shielding design is required even in the case of high-energy accelerator facilities by generating photoneutrons.

In the case of DT Neutron Generator, DD Neutron Generator, and Cf-252 spontaneous fission sources, which are representative neutron sources, such as nuclear reactors or neutron generators, as they generate neutron trapping photons as a result of the neutron absorption (n,gamma) reaction of the neutron shielding material, In addition to neutron shielding, photon shielding is also required.

Korean Patent Laid-Open Patent [10-2012-0106191] (published date: 2012. 09. 26) Korean Patent Publication [10-2014-0049049] (published date: 2014. 04. 24) Korean Patent Registration [10-1508957] (Registration Date: 2015.03.31)

Accordingly, the present invention has been devised to solve the above problems, and an object of the present invention is to perform Monte Carlo simulations for a structure set of a shielding design using facility according to the characteristics of a radiation source/generating device in advance. Thus, a simulation result is built into a library, and geometric data is derived by receiving information on an actual facility used to set a candidate group (from the structural group), and the simulation result in which the candidate group and geometric data are closest to the library from the library to derive functions that perform optimization and correction in response to the geometric data of the actual facility, and using the functions, photon-neutron-photon or neutron-photon-neutron without actual Monte Carlo simulation process in the field Considering the phenomenon of coupled transport of It is to provide a photon and neutron simultaneous shielding design method for deriving a design for photon and neutron simultaneous shielding, a recording medium storing a program for implementing the same, and a computer program stored in the medium for implementing the same.

The purpose of the embodiments of the present invention is not limited to the above-mentioned purpose, and other objects not mentioned will be clearly understood by those of ordinary skill in the art to which the present invention belongs from the following description. .

In the photon and neutron simultaneous shielding design method according to an embodiment of the present invention for achieving the above object, the actual Monte Carlo for the structure set of the shielding design and use facility according to the characteristics of the radiation source / generator A library construction step (S100) of performing a simulation and building a library by storing the simulation results; a design candidate group determination step (S200) for receiving information on an actual use facility, deriving geometric data, and determining a candidate group according to the geometric data from the structure group; a first Monte Carlo result calling step (S300) of calling a Monte Carlo simulation result that is closest to the determined candidate group and geometric data from the library; a function deriving step (S400) for deriving a function for performing optimization and correction in response to the change of the geometric data; a library update step (S500) of storing the function derived in the function deriving step in the library; and a shielding design deriving step (S600) for deriving a shielding design capable of simultaneously shielding photons and neutrons without Monte Carlo simulation based on the updated library.

The library building step (S100) includes: a first simulation performing step (S110) of performing an actual Monte Carlo simulation on the characteristics and specifications of the radiation source/generating device; a first Monte Carlo simulation result storage step of storing the first simulation execution result (S120); A second simulation performing step of performing an actual Monte Carlo simulation on the geometric data of the facility used (S130); a second Monte Carlo simulation result storage step of storing the second simulation execution result (S140); a third simulation performing step (S150) of performing an actual Monte Carlo simulation on the shielding design of the structure set of the facility; and a third Monte Carlo simulation result storage step (S160) of storing the third simulation execution result.

The geometric data is characterized in that it includes a spatial volume, a geometric shape, and a position of a radiation source, and the function deriving step (S400) includes the steps of deriving an interpolation function for a change in the spatial volume; deriving a correction function for the change of the geometric shape; and deriving a correction function for a change in the position of the radiation source.

The shielding design deriving step (S600) includes a second Monte Carlo result calling step (S610) of calling a simulation result for the shielding laminated structure combination of the corresponding facility; an optimization step for optimizing the shielding stacked structure combination based on the simulation result called in the second Monte Carlo result calling step (S620); and a thickness determination step (S630) for determining the thickness of the shielding laminated structure and the thickness of each layer according to the calculation result of the optimization step.

The shielding design deriving step (S600) includes a third Monte Carlo result calling step (S640) of calling a simulation result for the mixing ratio of the shielding mixture of the corresponding facility; an optimization step for optimizing the mixing ratio of the shielding mixture based on the simulation result called in the third Monte Carlo result calling step (S650); and a thickness determination step (S660) for determining the thickness of the shielding mixture according to the calculation result of the optimization step.

In addition, according to an embodiment of the present invention, a computer-readable recording medium storing a program for implementing the photon and neutron simultaneous shielding design method is provided.

In addition, according to an embodiment of the present invention, in order to implement the photon and neutron simultaneous shielding design method, a program stored in a computer-readable recording medium is provided.

According to the photon and neutron simultaneous shielding design method according to an embodiment of the present invention, a recording medium storing a program for implementing the same, and a computer program stored in the medium for implementing the same, according to the characteristics of the radiation source/generating device, the shielding design and use of the facility A Monte Carlo simulation for a structure set is performed in advance, the simulation results are built into a library, and geometric data is derived by receiving information on actual facilities used to set a candidate group (from the structure group), and , retrieves the simulation result that the candidate group and geometric data are closest to from the library, derives functions for optimization and correction in response to the geometric data of the actual facility, and uses the functions to simultaneously shield photons and neutrons It has the effect of deriving a design proposal.

In addition, according to the photon and neutron simultaneous shielding design method according to an embodiment of the present invention, a recording medium storing a program for implementing the same, and a computer program stored in the medium for implementing the same, without going through a Monte Carlo simulation process in the actual field Considering the coupled transport phenomenon of photon-neutron-photon or neutron-photon-neutron, it is possible to provide a simple photon and neutron simultaneous shielding design method by determining the optimization and shielding thickness for photon and neutron simultaneous shielding. can have an effect.

In addition, according to the photon and neutron simultaneous shielding design method according to an embodiment of the present invention, a recording medium storing a program for implementing the same, and a computer program stored in the medium for implementing the same, existing using ten layers of a photon and neutron shielding material This has the effect of reducing the cost of excessive shielding due to the maintenance design of the method.

In addition, according to the photon and neutron simultaneous shielding design method according to an embodiment of the present invention, a recording medium storing a program for implementing the same, and a computer program stored in the medium for implementing the same, an increase in load due to excessive shielding of doors, etc. By preventing an accident where the door cannot be operated, the risk of being trapped inside the user can be prevented and the operating efficiency of the facility can be improved.

In addition, according to the photon and neutron simultaneous shielding design method according to an embodiment of the present invention, a recording medium storing a program for implementing the same, and a computer program stored in the medium for implementing the same, radiation transport theory and Monte Carlo computational analysis It has the effect of reducing the cost and time of performing Monte Carlo, which requires specialized knowledge.

1 is a flow chart of one embodiment of a method for designing a photon and neutron simultaneous shielding according to the present invention.
2 is a detailed flowchart of the library construction step (S100) of FIG.
3 is a detailed flowchart of an embodiment of the shielding design deriving step (S600) of FIG.
Figure 4 is a detailed flowchart of another embodiment of the shielding design deriving step (S600) of Figure 1.

Since the present invention can have various changes and can have various embodiments, specific embodiments are illustrated in the drawings and described in detail. However, this is not intended to limit the present invention to specific embodiments, and it should be understood to include all modifications, equivalents, and substitutes included in the spirit and scope of the present invention.

When an element is referred to as being “connected” or “connected” to another element, it is understood that it may be directly connected or connected to the other element, but other elements may exist in between. it should be

On the other hand, when it is said that a certain element is "directly connected" or "directly connected" to another element, it should be understood that the other element does not exist in the middle.

The terms used herein are used only to describe specific embodiments, and are not intended to limit the present invention. The singular expression includes the plural expression unless the context clearly dictates otherwise. In the present application, terms such as "comprise" or "have" are intended to designate that a feature, number, process, operation, component, part, or a combination thereof described in the specification exists, but one or more other features It is to be understood that this does not preclude the existence or addition of numbers, processes, operations, components, parts, or combinations thereof.

Unless defined otherwise, all terms used herein, including technical or scientific terms, have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs. Terms such as those defined in a commonly used dictionary should be interpreted as having a meaning consistent with the meaning in the context of the related art, and should not be interpreted in an ideal or excessively formal meaning unless explicitly defined in the present application. does not

Hereinafter, the present invention will be described in more detail with reference to the accompanying drawings. Prior to this, the terms or words used in the present specification and claims should not be construed as being limited to conventional or dictionary meanings, and the inventor should properly understand the concept of the term in order to best describe his invention. Based on the principle that can be defined, it should be interpreted as meaning and concept consistent with the technical idea of the present invention. In addition, if there is no other definition in the technical terms and scientific terms used, it has the meaning commonly understood by those of ordinary skill in the art to which this invention belongs, and the summary of the present invention in the following description and accompanying drawings Descriptions of known functions and configurations that may be unnecessarily obscure will be omitted. The drawings introduced below are provided as examples so that the spirit of the present invention can be sufficiently conveyed to those skilled in the art. Accordingly, the present invention is not limited to the drawings presented below and may be embodied in other forms. Also, like reference numerals refer to like elements throughout. It should be noted that the same components in the drawings are denoted by the same reference numerals wherever possible.

For photon shielding, concrete can be used in terms of cost reduction, but it has a drawback in that the space occupied by the shielding material is excessive. Its use is on the rise.

As a neutron shielding material, polyethylene containing boron (B-10) with a large neutron absorption cross-sectional area, that is, BPE (Borated Polyethylene), has been developed and is being used as a shielding material for accelerator facilities or hot cells using neutron sources.

When each material is used as a shielding material for the simultaneous shielding of photons and neutrons, photoneutrons are generated through photonuclear reaction of heavy metal materials for shielding high-energy photons, and the result of neutron capture by a neutron absorber for shielding neutrons , the surplus energy is emitted again in the form of secondary radiation of a photon (Neutron Induced Photon).

Therefore, in order to calculate the mixing ratio of the shielding material or the thickness of the stacked structure in the shielding design process to satisfy the photon-neutron simultaneous shielding design criteria, a photon->neutron->photon or neutron->photon->neutron type coupled transport (Coupled Transport) A process that can interpret the phenomenon is required.

For photon-neutron coupled transport analysis, there are deterministic and Monte Carlo methods for solving the radiation transport equation, and the Monte Carlo method with a high degree of freedom in simulating the geometry of sources and shielding facilities is widely used.

However, for accurate interpretation of the Monte Carlo method, it is necessary to be clear in basic theories such as radiation transport theory, and expert-level skills for related computer codes are required. Moreover, the time for Monte Carlo simulation/verification of the relevant facility is also significant.

When designing the shielding of radiation source facilities, it is possible to increase economic feasibility with excessive shielding walls by performing extremely conservative calculations with the Tenth Value Layer (TVL) representing the shielding ability of photons and neutrons at sites where Monte Carlo experts cannot be hired. In addition to lowering, in particular, in the case of a door shielding facility of a user facility, the door bearing is crushed due to an excessive load and has a disadvantage in that it becomes inoperable.

The photon and neutron shielding design method according to the present invention is a Monte Carlo simulation process in which the coupled transport of 'photon-> neutron-> photon' or 'neutron-> photon-> neutron' must be analyzed. Without directly performing it, by deriving a function according to the change of geometric data of an actual facility from the library built according to the Monte Carlo simulation already performed, it is possible to easily determine the structural optimization and shielding thickness for photon-neutron simultaneous shielding in the field. there is.

1 is a flowchart of an embodiment of a method for designing a photon and neutron simultaneous shielding according to the present invention.

First, an actual Monte Carlo simulation is performed on a structure set of a shielding design using facility for each characteristic of a radiation source/generating device, and a library is built by storing the simulation results (S100).

The radiation source may be a gamma-emitting nuclide and neutron source contained in a spent nuclear fuel storage, a hot cell as a radioactive waste treatment facility, or a transport container.

In addition, the radiation source may be a DT Generator or D-Generator as a neutron generator, or a neutron beam source of a Cf-252 spontaneous fission source. It may be gamma rays that are generated.

The basic Monte Carlo simulation (simulation) for obtaining the energy spectrum and angular distribution as neutron and photon source terms can simulate the photon source and the neutron source independently, respectively.

However, the process of finding a source term from a source or generator that is independent of photons and neutrons is a couple of 'neutron->photon->neutron' or 'photon->neutron->photon' depending on the physical properties of the structure constituting the device. The coupled transport phenomenon can be simulated.

Detailed steps of the library building step (S100) will be described with reference to FIG. 2 .

Thereafter, geometric data is derived by receiving information on actual facilities used, and a candidate group according to the geometric data is determined from the structural group (S200).

By receiving design drawings or actual measurement data for an actual facility, the spatial volume occupied, the geometric shape, and the location of the radiation source are derived as geometric data. A candidate group is determined from among a large number of structural groups according to the derived geometric data.

Thereafter, the Monte Carlo simulation result with the closest geometric data to the determined candidate group is called from the library ( S300 ).

Thereafter, a function for performing optimization and correction in response to the change of the geometric data is derived (S400).

The geometric data includes the spatial volume of the facility used, the geometric shape, and the location of the radiation source, and each geometric data can be independently analyzed.

In the function deriving step (S400), an interpolation function for a change in the spatial volume, a correction function for a change of the geometric shape, and a correction function for a change in the position of the radiation source are derived.

The structural form of the facility can be a square with the same length on all four sides except for the height of the ceiling, and can be a standard for deriving a correction function for changes in geometric shape and radiation source position.

As a factor for changing the spatial volume, it may be a change in the length of one wall, or it may be a simple interpolation that makes the grid dense in the corresponding section.

In addition, the interpolation function for the spatial volume of the facility can be in the form of expressing the law of inverse square proportionality of the distance using the length of one wall as an independent variable.

On the other hand, the correction function for the geometric shape of the facility may be a function of the ratio of the sum of the areas constituting the four wall surfaces excluding the ceiling and the floor for a rectangular space based on the square space.

The correction for the location change of the radiation source in the facility may be based on the location installed from the floor at the center of gravity in the facility space.

The correction function for the change in the location of the radiation source in the facility may be a function in which the distance from the location, which may be changed according to the characteristics of the environment of use, as an independent variable, is based on the installation location from the floor at the center of gravity in the facility space.

In addition, the correction function for the change in the location of the radiation source in the facility is, when the location of the radiation source is close to a specific wall by greatly deviating from the center of gravity of the source in the facility in use under a specific environment, the distance between the location of the source and the wall of the facility as an independent variable It can be a function that does

Thereafter, the function derived in the function deriving step (S300) is stored and updated in the library (S500).

Then, based on the updated library, a shielding design capable of simultaneously shielding photons and neutrons without Monte Carlo simulation is derived (S600).

That is, it is possible to determine the optimum arrangement and thickness of the stacked structure, or the optimum mixing ratio and thickness of the mixed material, which can be considered with respect to the energy spectrum and angular distribution as the source terms of photons and neutrons.

2 is a detailed flowchart of the library construction step (S100) of FIG.

In the library building step (S100), first, an actual Monte Carlo simulation is performed on the characteristics and specifications of the radiation source/generating device (S110).

Basic Monte Carlo simulations are performed on the neutron and photon source terms by reflecting the production type of the source of the neutron source and the photon source, or the characteristics of the source.

Thereafter, the result of performing the first simulation is stored (S120).

Thereafter, an actual Monte Carlo simulation is performed on the geometric data of the facility used (S130).

Thereafter, the second simulation execution result is stored (S140).

Thereafter, an actual Monte Carlo simulation for the shielding design of the structure set of the facility is performed (S150).

Thereafter, the third simulation execution result is stored (S160).

3 is a detailed flowchart of an embodiment of the shielding design deriving step (S600) of FIG.

First, the simulation result for the combination of the shielding laminated structure of the corresponding facility is called (S610).

Thereafter, the shielding stacked structure combination is optimized based on the simulation result called in the result calling step (S610) (S620).

Thereafter, the thickness of the shielding laminated structure and the thickness of each layer are determined according to the calculation result of the optimization step (S620) (S630).

Lead, tungsten, iron, or an alloy thereof having a high atomic number may be used in order to use a high photoelectric effect as a material for shielding photons in the shielding laminate structure.

As a material for shielding neutrons in the shielding laminated structure, it contains B-10 having a high neutron absorption cross-sectional area and is a boron compound containing C, H, O, etc. for decelerating neutrons, such as boron carbide (B4C), or boronization It may be polyethylene (Borated Polyethylene; BPE).

The shielding laminate structure is an arrangement sequence for effective shielding of secondary radiation generation by photon-neutron or neutron-photon coupled transport in the case of lead as a photon shielding agent and BPE as a neutron shielding material. Lead-BPE from the source direction , Lead-BPE-Lead, BPE-Lead, or BPE-Lead-BPE structure.

4 is a detailed flowchart of another embodiment of the shielding design deriving step (S600) of FIG.

First, the simulation result for the mixing ratio of the shielding mixture of the corresponding facility is called (S640).

Thereafter, the mixing ratio of the shielding mixture is optimized based on the simulation result called in the calling step (S640) (S650).

Thereafter, the thickness of the shielding mixture is determined according to the calculation result of the optimization step (S650) (S660).

In the case of tungsten as a photon shielding material of the shielding mixture, tungsten carbide (WC) may be used to improve the attenuation coefficient and stability due to the photoelectric effect of tungsten by photon deceleration.

In the case of a boron compound as a neutron shielding material of the shielding mixture, it may be a boron nitride nanotube (BNNT) that can increase the neutron absorption cross-sectional area of B-10 nuclides, including nitrogen atoms with high neutron deceleration ability, The effect of improving stability and durability can be expected.

In the configuration of the shielding mixture, the BNNT structure may have a synthetic structure in which lead (Pb) or tungsten atoms are coated from the viewpoint of optimizing mechanical strength, structural stability, and neutron absorption enhancement.

Although the photon and neutron simultaneous shielding design method according to an embodiment of the present invention has been described above, a computer readable recording medium storing a program for implementing the photon and neutron simultaneous shielding design method and the photon and neutron simultaneous shielding design method Of course, a program stored in a computer-readable recording medium for implementation can also be implemented.

That is, those skilled in the art will readily understand that the above-described method for simultaneously shielding photons and neutrons may be provided by being included in a computer-readable recording medium by tangibly implementing a program of instructions for implementing it. In other words, it may be implemented in the form of program instructions that can be executed through various computer means and recorded on a computer-readable recording medium. The computer-readable recording medium may include program instructions, data files, data structures, etc. alone or in combination. The program instructions recorded on the computer-readable recording medium may be specially designed and configured for the present invention, or may be known and used by those skilled in the art of computer software. Examples of the computer-readable recording medium include magnetic media such as hard disks, floppy disks and magnetic tapes, optical media such as CD-ROMs and DVDs, and floppy disks. magneto-optical media, and hardware devices specially configured to store and carry out program instructions, such as ROM, RAM, flash memory, USB memory, and the like. The computer-readable recording medium may be a transmission medium such as an optical or metal wire or waveguide including a carrier wave for transmitting a signal designating a program command, a data structure, and the like. Examples of program instructions include not only machine language codes such as those generated by a compiler, but also high-level language codes that can be executed by a computer using an interpreter or the like. The hardware device may be configured to operate as one or more software modules to perform the operations of the present invention, and vice versa.

The present invention is not limited to the above-described embodiments, and various modifications can be made without departing from the gist of the present invention as claimed in the claims.

S100: Library building stage
S200: Design candidate group decision stage
S300: first Monte Carlo result call step
S400: function derivation step
S500: Library update step
S600: Shielding design drafting stage

Claims (5)

In the photon and neutron simultaneous shielding design method,
A library construction step (S100) of performing an actual Monte Carlo simulation on a structure set of a shielding design using facility for each characteristic of a radiation source/generating device, and building a library by storing the simulation results;
a design candidate group determination step (S200) for receiving information on actual facilities to be used, deriving geometric data, and determining a candidate group according to the geometric data among the structure groups;
a first Monte Carlo result calling step (S300) of calling a Monte Carlo simulation result that is closest to the determined candidate group and geometric data from the library;
a function deriving step (S400) for deriving a function for performing optimization and correction in response to the change of the geometric data;
a library update step (S500) of storing the function derived in the function deriving step in the library; and
Shielding design derivation step (S600) for deriving a shielding design that can simultaneously shield photons and neutrons without Monte Carlo simulation based on the updated library
A photon and neutron simultaneous shielding design method comprising a.

According to claim 1,
The library construction step (S100) is,
a first simulation performing step (S110) of performing an actual Monte Carlo simulation on the characteristics and specifications of the radiation source/generating device;
a first Monte Carlo simulation result storage step of storing the first simulation execution result (S120);
A second simulation performing step of performing an actual Monte Carlo simulation on the geometric data of the facility used (S130);
a second Monte Carlo simulation result storage step of storing the second simulation execution result (S140);
a third simulation performing step (S150) of performing an actual Monte Carlo simulation for the shielding design of the structure set of the facility; and
A third Monte Carlo simulation result storage step of storing the third simulation execution result (S160)
Photon and neutron simultaneous shielding design method comprising a.
According to claim 1,
The geometric data is
characterized in that it includes the volume of space, the geometry, and the location of the radiation source,
The function deriving step (S400) is,
deriving an interpolation function for the change in the spatial volume;
deriving a correction function for the change of the geometric shape; and
deriving a correction function for a change in the position of the radiation source;
Photon and neutron simultaneous shielding design method comprising a.
According to claim 1,
The shielding design drawing step (S600) is,
a second Monte Carlo result calling step (S610) of calling a simulation result for the shielding laminated structure combination of the corresponding facility;
an optimization step for optimizing the shielding laminated structure combination based on the simulation result called in the second Monte Carlo result calling step (S620); and
Thickness determination step (S630) for determining the thickness of the shielding laminated structure and the thickness of each layer according to the calculation result of the optimization step
Photon and neutron simultaneous shielding design method comprising a.
According to claim 1,
The shielding design drawing step (S600) is,
a third Monte Carlo result call step (S640) of calling a simulation result for the mixing ratio of the shielding mixture of the corresponding facility;
an optimization step for optimizing the mixing ratio of the shielding mixture based on the simulation result called in the third Monte Carlo result calling step (S650); and
Thickness determination step (S660) for determining the thickness of the shielding mixture according to the calculation result of the optimization step
Photon and neutron simultaneous shielding design method comprising a.

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