7121 results about "Nuclear engineering" patented technology

A nuclear fusion reaction device, system and method. The outer wall of a vacuum chamber (301) in the nuclear fusion reaction device (30) comprises an inner ring surface (M1) and an outer ring surface (M2) which are connected to each other; the outer ring surface (M2) surrounds the inner ring surface (M1); the inner ring surface (M1) protrudes toward the central axis of the vacuum chamber (301); the vacuum chamber (301) surrounds a plurality of first coils (302); at least some of the plurality of first coils (302) extend in the circumferential direction of the inner ring surface (M1) and are sequentially arranged in the axial direction of the vacuum chamber (301); a plurality of second coils (303) surround the vacuum chamber (301), extend in the circumferential direction of the outer ring surface (M2), and are sequentially arranged in the axial direction of the vacuum chamber (301); a plurality of third coils (304) all surround the vacuum chamber (301) and are sequentially arranged in the circumferential direction of the vacuum chamber (301); and the plurality of first coils (302), the plurality of second coils (303), and the plurality of third coils (304) are used for generating a magnetic field, such that plasma rings with negative triangular deformation are generated in the vacuum chamber (301), and a fusion reaction occurs.

The invention relates to the technical field of nuclear fusion devices, and discloses a nuclear fusion device and a monitoring system and an installation method thereof, the monitoring system comprises a cold shield main body, the cold shield main body is of an annular rotation structure, and the cold shield main body is arranged in a cavity and wraps the circumferential outer side of a vacuum chamber; the cold shield main body comprises a plurality of groups of fan-shaped cold shield sections which are sequentially arranged in the circumferential direction, and the plurality of groups of fan-shaped cold shield sections are encircled to form the cold shield main body; the distance measuring assembly is arranged on the cold shield main body, the distance measuring assembly comprises a plurality of groups of distance measuring sensors which are arranged in the circumferential direction of the cold shield main body at intervals, and each group of distance measuring sensors comprises a plurality of distance measuring sensors; the distance measuring sensor is used for detecting the size of a gap between the cold shield body and the longitudinal field coil and the size of a gap between the cold shield body and the vacuum chamber. Therefore, the cold shield main body can be assisted to be assembled at a position in the nuclear fusion device, and the matching position of the cold shield main body, the vacuum chamber and the longitudinal field coil can be monitored in real time.

The invention relates to the technical field of radiation measurement, in particular to a radiation data calibration method for a regional radiation monitor, which comprises the following steps of: according to the variation trend of data in a local range of each moment in a radiation slope sequence of each position and the difference of time intervals between all adjacent extreme points in a radiation data curve, calculating the radiation data of the regional radiation monitor; obtaining the interference degree of the radiation data at each moment of each position; according to the correlation degree between the radiation data sequence of each position and the radiation data sequence of other positions and the interference degree, the corrected interference degree of the radiation data of each moment of each position is obtained; and correcting the radiation data of all positions at each moment according to the distribution of the radiation data of all positions at each moment in the region and the corrected interference degree to obtain the radiation data after region calibration. According to the invention, the accuracy of regional radiation data monitoring is improved.

The invention relates to the technical field of intelligent evaluation and early warning methods, in particular to a nuclear radiation dose space distribution intelligent evaluation and early warning method and system, and the method comprises the following steps: obtaining multi-source monitoring data which comprises gamma radiation dose, alpha radiation dose and beta radiation dose measuring instrument data; performing fusion and enhancement processing on the multi-source monitoring data to obtain an enhanced radiation monitoring signal; based on the enhanced radiation monitoring signal, high-precision prediction of nuclear radiation dose spatial distribution is carried out through a deep probabilistic neural network model; according to the high-precision prediction result, in combination with a nuclear accident severity level standard, a radiation alert evaluation result and early warning information are generated, short-term radiation fluctuation can be captured, a long-term change trend can be identified, and the understanding ability of the system to a complex radiation field is greatly improved.

The invention relates to the field of medical equipment, and provides a compact multi-chamber proton treatment system based on a shared beam line, and the system comprises a fixed beam transmission line which is used for guiding the movement direction of a proton beam into a vertical direction; the rotating beam transmission line is used for guiding the movement direction of the proton beam into the horizontal direction; one end of the fixed beam transmission line is connected with the proton cyclotron, the other end of the fixed beam transmission line is connected with one end of the rotary beam transmission line, and the other end of the rotary beam transmission line is in butt joint with a plurality of treatment rooms; the rotating beam transmission line rotates around a central axis extending in the vertical direction. According to the invention, the proton beam can be safely, efficiently and accurately transmitted to each treatment room, and a fixed beam transmission system and a rotating rack do not need to be independently arranged for each treatment room, so that the beam control assembly and the system occupied area of the multi-room particle treatment device are minimized, and the number of treated patients can be remarkably increased.

The invention discloses a processing method of a fusion device, and belongs to the technical field of nuclear fusion. The processing method comprises the following steps: carrying out at least one time of vacuum heat treatment on a Dewar embedded part blank; carrying out cleaning anti-corrosion treatment and physical correction treatment on the surface of the dewar embedded part blank subjected to heat treatment; carrying out grinding and polishing treatment on the surface of the Dewar embedded part blank subjected to the cleaning and antiseptic treatment and the physical correction treatment to obtain the Dewar embedded part; the Dewar embedded part is transported to the installation position of the window to be installed, and the Dewar embedded part located at the installation position is temporarily fixed; performing concrete pouring on the mounting position of the Dewar embedded part; and after the concrete is solidified, a cast-in-place concrete structural body is formed in the area below the Dewar embedded part, and a part of the Dewar embedded part is embedded into the cast-in-place concrete structural body. By means of the method, the magnetic conductivity of the Dewar embedded part is reduced, and the risk that elements are activated to form isotopes with the long decay period and the high irradiation dose rate or isotopes with the short decay period and the high irradiation dose rate is reduced.

The invention provides a solid target system for simultaneously producing Ge-68 and PET nuclides under a high-power beam, and the system comprises an intermediate-energy cyclotron which is used for transmitting an intermediate-energy high-intensity proton beam; the cascade target is arranged beside the intermediate-energy cyclotron and comprises a shell, and a first aluminum target body, a second aluminum target body, a Ga4Ni alloy capsule target and a metal sealing target which are sequentially arranged along the emission direction of the intermediate-energy high-current proton beam, and the shell is filled with cooling water; the target film is erected between the intermediate energy cyclotron and the first aluminum target body; the helium cooling unit is erected between the target film and the first aluminum target body; and the control unit is used for controlling to start the helium cooling unit and the medium-energy cyclotron, so that the medium-energy high-intensity proton beam sequentially passes through the target film, the first aluminum target body, the shell and the cooling water, then enters the Ga4Ni alloy capsule target to produce Ge-68 nuclide, and then enters the metal sealing target to produce PET nuclide. The method has the beneficial effects that the melting of the target material can be reduced, the probability of direct chemical reaction of molten Ga and Nb is reduced, and the types of nuclide production are increased.

A coolant system for an electric vehicle for circulating a liquid coolant, comprising a plurality of components through which the coolant can flow. The components can be connected to one another, at least in at least one subset, in a coolant-conducting manner via valves and via coolant lines. Only a single multi-way valve and a single non-return valve are arranged in such a way that one of the components and another of the components can be fluidically connected to one another only via a further component, designed as a coolant pump, and via a predetermined switching state of the multi-way valve to permit a flow through the multi-way valve and the non-return valve independently of the rest of the components. A thermal management system is also provided.

The utility model relates to the technical field of electron beam transmission, in particular to a magnet system. Comprising a first shaping unit and a second shaping unit, and the first shaping unit comprises first quadrupole iron tightly attached to an outlet of the accelerating tube and first octupole iron arranged at the focus position of the first quadrupole iron; the second shaping unit comprises second quadrupole iron and second octupole iron, the second quadrupole iron and the first octupole iron meet a first preset distance, the second octupole iron is arranged at the focus position of the second quadrupole iron, and the second shaping unit and the radiation field area meet a second preset distance; the inner diameter of the first octupole iron and the inner diameter of the second octupole iron are both larger than or equal to the maximum size of an electron beam group. Therefore, the quadrupole iron and the octupole iron are utilized to form the shaping unit which is homogenized in one direction, so that the problems that in the prior art, in the electron beam transmission process, a large amount of dose is lost, the size of a radiation field is limited, and the radiation field cannot be adjusted at will are solved; therefore, the electron beam bunch generated by the linear accelerator can be expanded and homogenized in a short distance.

A positron emission tomography (PET) scanner includes a plurality of gamma radiation detector modules arranged to form a detector ring. Each detector module includes an array of scintillator detectors. Each scintillator detector comprises a monolithic scintillation crystal and a plurality of photodetector arrays, such as silicon photomultipliers (SiPMs). A photodetector array is positioned on at least two nonparallel faces of each scintillation crystal. In some examples, a photodetector array is positioned on each of three orthogonal faces of each scintillation crystal.

A method comprises: providing FIB and CPB columns with FIB and CPB optical axes coinciding at a wafer surface; in the coincidence arrangement, removing a cross section surface layer of a measurement site of a wafer using the FIB column to make a new cross section accessible for imaging; reducing a working distance between the CPB imaging column and the wafer surface in a direction along the axis of the CPB imaging column; imaging the new cross section at the measurement site of the wafer with the CPB imaging column at the reduced working distance and thus not in the coincidence arrangement; and increasing the working distance between the CPB imaging column and the wafer surface in the direction along the axis of the CPB imaging column until the coincidence arrangement is reached.

The invention discloses a method and tool for manufacturing a cold shield of a nuclear fusion device, and relates to the technical field of metal plate machining. The manufacturing method of the cold shield of the nuclear fusion device comprises the following steps: providing a sub-panel, a flange and a pipe fitting; the multiple sub-panels are welded, and a first middleware is obtained; welding the edge of the first middleware and the turnup to obtain a second middleware; after the pipe fitting is welded to the surface of the second middleware, a third middleware is obtained; and the third middleware is shaped. According to the method, the third middleware is shaped, that is, the third middleware is shaped after all welding procedures are completed, so that the third middleware has relatively small profile tolerance, the profile tolerance of the cold shield meets the design requirement, the assembly difficulty of the cold shield is reduced, and the risk of failure of the cold shield is reduced.

An apparatus comprising a radiation source, coincident positron emission detectors configured to detect coincident positron annihilation emissions originating within a coordinate system, and a controller coupled to the radiation source and the coincident positron emission detectors, the controller configured to identify coincident positron annihilation emission paths intersecting one or more volumes in the coordinate system and align the radiation source along an identified coincident positron annihilation emission path.

The invention discloses a method and a system for rapidly measuring the concentration of radioactive radon in air in a gas flow mode based on scintillation. According to the method, the net counting rate of alpha particles is measured based on a scintillation method, and the net counting rate of the alpha particles in a corresponding time period needs to be obtained during measurement; in combination with a radon and daughter decay rule and a chamber ventilation condition, establishing a relationship between the net count of alpha particles generated by radon and daughter decay in newly sucked air in a corresponding measurement time period in the measurement chamber and the volume, the pump speed and the original air radioactivity concentration in the chamber; and a corresponding sensitivity coefficient for measuring the radioactive radon concentration of the to-be-measured air is obtained, so that the radioactive radon concentration of the to-be-measured air is obtained in real time. According to the method, the radioactive radon concentration in the air can be rapidly measured in real time under the dynamic gas flow type condition, the measurement time can be greatly saved, the change of the radon concentration in the air can be reflected in time, workers and the public can be protected against the harm of radon radiation, safety production of the nuclear industry can be promoted, and the method has wide application prospects.

The invention discloses an ocean in-situ radioactivity monitoring method, which is characterized in that feature extraction is carried out based on a maximum likelihood expected value maximization (MLEM) algorithm, and spectrum unfolding operation is carried out by adopting a multi-layer perceptron. The method comprises the following steps: firstly, measuring FWHM related parameters of a CeBr3 detector by adopting a standard source, simulating the response of the detector to gamma rays in a marine environment based on a Monte Carlo method, and establishing a full-spectrum response matrix H in a range of 0-2048keV; based on the response matrix H, reconstructing a gamma energy spectrum y obtained by the detector by using an MLEM iterative algorithm; and the reconstructed spectrum is used as the input of a multi-layer perceptron (MLP), and qualitative and quantitative analysis of radionuclides in the energy spectrum is realized. According to the method, the discrete characteristic peak signal is convolved into the single path address corresponding to the characteristic energy, so that the accuracy of the MLP model in the spectrum unfolding process is effectively improved.

The invention provides an integrated containment pressure suppression, filtration and discharge system. The integrated containment pressure suppression, filtration and discharge system comprises a containment, a discharge valve, a discharge pipeline, a spray pipe, a first-stage pressure suppression water tank, a second-stage pressure suppression water tank, a baffle plate steam-water separator, an expansion tank, a rupture disk structure, a combined metal fiber filter layer, a radioactivity monitor, a first stop valve and a second stop valve. The two-stage pressure suppression water tank is arranged, the high removal efficiency of airborne radioactive substances is achieved through two-stage bubbling water washing, then the combined metal fiber filter is arranged by means of an existing cabin, and the requirements for rapid pressure reduction and radioactive substance removal of the containment under the LOCA accident working condition can be met; meanwhile, the problem that the containment filtering and discharging system of the existing nuclear power station occupies too many resources is solved, and the economical efficiency is high.

The invention belongs to but is not limited to the technical field of three-dimensional space dose visualization, and discloses a three-dimensional nuclear emergency radiation field calculation and visualization method and system, based on a point nuclear method, a cumulative factor, mass attenuation factor and flux rate-dose rate conversion factor database is established, a mean free path solving algorithm is optimized, and a three-dimensional nuclear emergency radiation field is obtained. The geometric types of radioactive sources are expanded, and the dose calculation efficiency is improved through parallel calculation; plane dose rate drawing at a certain height is realized based on a two-dimensional texture mapping method; three-dimensional space dose rate contour surface drawing is realized based on a moving cube algorithm; and three-dimensional space dose rate volume rendering is realized based on a three-dimensional texture volume rendering technology. Radiation field dose calculation, three-dimensional radiation field dose visualization and GIS are integrated, and the system is used as a subsystem of a nuclear emergency aid decision simulation platform. The dose distribution diagram in the area can be judged more visually, and the method has a good help effect on nuclear emergency command.

The invention provides a device and method for removing aerosol based on a charged spraying coupling pool washing mechanism, and belongs to the field of nuclear auxiliary systems. The problem that radioactive aerosol particles generated when a radioactive contamination structure in a reactor is cut underwater can be released into the external environment is solved. Wherein the underwater laser cutting assembly is used for cutting a to-be-cut piece; the auxiliary gas chamber is communicated with the laser cutting nozzle; the aerosol charging assembly can enable aerosol particles generated by underwater laser cutting to carry negative charges; the baffle can gather the aerosol particles and guide the aerosol particles to the aerosol charging assembly; the liquid drop charged spraying assembly can spray liquid drops carrying positive charges, the liquid drops carrying positive charges and aerosol particles carrying negative charges can attract each other and fall to the liquid level, and the Venturi washing assembly can extract gas above the liquid level and spray the gas below the liquid level. The device can efficiently remove radioactive aerosol particles generated by cutting and disassembling radioactive contaminated components in a nuclear power plant, and radioactive contamination to the environment is prevented.

The invention discloses a high-gradient particle accelerator and a cancer treatment device, and the high-gradient particle accelerator comprises an ion source which is used for generating and leading out a particle beam for treatment; an inlet of the superconducting radio frequency quadrupole field accelerator is connected with the ion source through a low-energy transmission line, and the superconducting radio frequency quadrupole field accelerator is used for pre-accelerating the particle beam generated by the ion source to obtain a low-energy particle beam; an inlet of the superconducting linear acceleration section is connected with an outlet of the superconducting radio frequency quadrupole field accelerator through a first beam transport line, and the superconducting linear acceleration section is used for accelerating the low-energy particle beam led out by the superconducting radio frequency quadrupole field accelerator again to obtain an intermediate-energy particle beam; and an inlet of the annular accelerator is connected with an outlet of the superconducting linear acceleration section through a second beam transport line, and the annular accelerator is used for carrying out ultimate acceleration on the intermediate-energy particle beam led out by the superconducting linear acceleration section so as to obtain a high-energy particle beam with target energy. The scheme that the superconducting linear accelerator is combined with the annular accelerator is adopted, so that particle beam energy is accelerated to target energy meeting cancer treatment.

A method for dose calculation in a boron neutron capture therapy planning system based on a track tracking Monte Carlo method comprises the following steps: sampling according to input description source item particles, carrying out transport calculation by using the track tracking Monte Carlo method under voxel grid geometry, calculating a transport distance while calculating the transport distance, and calculating the dose in the boron neutron capture therapy planning system by using the track tracking Monte Carlo method. Counting based on the voxel grid to obtain particle flux and dose; by adopting the operation of track tracking method acceleration based on voxel grid geometry, the surface crossing judgment method is improved, and the problem that the surface crossing operation takes too long time in the calculation process is solved; counting is carried out while the transportation distance is calculated, the counting time is saved on the premise that the counting precision is guaranteed, and compared with a traditional Monte Carlo method based on CSG geometry, the method is more suitable for a voxel model obtained from a medical image, and the calculation speed is higher.

The invention provides a near-earth orbit neutron and gamma ray detector group, detection equipment and a detection method, and the detection equipment is a neutron / gamma spectrometer which is small in size, small in mass, low in power consumption and high in speed and is designed based on a multilayer single / double sensitive area Si detector and a cadmium zinc telluride (CZT) detector array. The neutron / gamma spectrometer can serve as an independent load to be carried on a small satellite, and measurement of thermal neutrons, fast neutrons below 20 MeV and gamma rays is achieved. Different layers of the detector group in the detection equipment are matched to form a plurality of anticoincidence groups, so that the accuracy of energy spectrum inversion is improved. According to the detection method, a stacking and discarding algorithm is provided, so that interference caused by signal overlapping is avoided, and the system resolution of the whole neutron / gamma spectrometer is improved.

The invention discloses a helium cold fusion cladding experiment module device, which mainly comprises a first wall proliferation agent area and a rear baffle plate, is circumferentially provided with a cover plate, a bottom plate, a left side plate and a right side plate, has higher engineering characteristics similar to a cladding design scheme, is convenient to carry out neutronics measurement, and is high in reliability. Based on the device, the technical level of fusion blanket neutronics verification and measurement technology and blanket tritium breeding performance evaluation in China can be improved, independent tritium production blanket performance data is accumulated, the requirement of ITER-TBM engineering development is met, and a foundation is laid for CFETR helium cooling blanket engineering design.

A multi-beam particle beam system 1 with improved resolution and higher acquisition speed is revealed. For this purpose, an electrostatic booster lens 112 is arranged in an upper focal plane of the objective lens 102 at the level of the crossing region of the primary particle beams. The electrostatic booster lens 112 selectively increases the kinetic energy of the primary beams 3 significantly in the crossing region 108, thereby reducing the Coulomb interaction between the charged particles.

The invention provides a solid material doping detection method, device and system. The method comprises the following steps: acquiring first intensity before fast neutrons transmit a to-be-detected material and second intensity after the fast neutrons transmit the to-be-detected material, and gamma-ray energy spectrum data of the to-be-detected material; obtaining a neutron macroscopic cross section of the to-be-detected material according to the first strength and the second strength; judging whether doping exists or not according to the neutron macroscopic cross section of the to-be-detected material and the neutron macroscopic cross section of a preset undoped material; and according to the gamma-ray energy spectrum data of the to-be-detected material, obtaining the element category and content in the to-be-detected material. According to the method, the doping condition of the solid material to be detected is quantitatively and nondestructively judged, whether the doping possibility exists in the material or not is quickly judged by detecting the change of the penetration yield of fast neutrons, and deeper analysis is carried out based on gamma-ray energy spectrum data; the detection process is carried out in a full-automatic mode, human intervention is not needed, and many defects of manual detection are overcome.

The invention discloses a BNCT dose calculation method, which comprises the following steps: S1, constructing a voxel model, initializing one or more particles in a simulation system, and respectively acquiring the initial position, energy and movement direction of each particle; s2, adaptively selecting a Monte Carlo particle tracking algorithm and a flux counting mode based on the region where the particles are located and the energy of the particles; s3, repeating the step S2 until the particles leave the simulation system or are killed when meeting a truncation condition; and S4, cumulatively calculating dose distribution. Through the BNCT dose calculation method, the Monte Carlo particle transport simulation time is greatly shortened, the BNCT dose calculation efficiency is optimized, and the method is suitable for rapid and high-precision radiation dose simulation under a BNCT complex tissue structure.

The invention relates to the technical field of gamma-ray spectrum analysis, particularly provides a gamma-ray detector activation analysis method and a PGNAA detection system, and aims to solve the problems that gamma rays obtained by detection of an existing gamma-ray detector comprise rays generated by decay of crystals after activation in a neutron field; therefore, the component detection result of the to-be-detected sample is not accurate. In order to achieve the purpose, the activation analysis method for the gamma detector comprises the steps that a to-be-detected sample is irradiated through a neutron source; repeatedly collecting a plurality of groups of gamma-ray energy spectrums of the sample to be detected by using a gamma-ray detector; constructing an energy spectrum signal matrix based on the gamma-ray energy spectrum of the to-be-detected sample, wherein the energy spectrum signal matrix is a mixed signal composed of instant gamma rays generated by neutron activation of the to-be-detected sample, environmental background gamma rays and interference signals generated by crystal activation in a gamma detector; and obtaining the effective instant gamma ray based on the energy spectrum signal matrix. The self-interference influence of the detector is effectively reduced, and the target element content evaluation precision of the to-be-detected object is improved.

The invention relates to the technical field of Tokamak nuclear fusion, and discloses an assembling method of a pre-assembled assembly of a nuclear fusion device and an installing method of the nuclear fusion device. The pre-assembled assembly comprises a vacuum chamber, a window neck tube in the vacuum chamber, a vacuum chamber cold shield and a TF magnet; the assembling method of the nuclear fusion device preassembled assembly comprises the following steps: supporting between a cold shield inner sector and a vacuum chamber through a first tool; a first tool is supported between the cold shield outer sector and the vacuum chamber; the TF magnet is connected with the middle window position of the vacuum chamber through a second tool, the upper arc-shaped section of the outer fan section of the cold shield is connected with the hoisting tool of the TF magnet through a third tool, and the lower window section of the outer fan section of the cold shield is connected with the second tool; and the middle window section and the annular field magnet supporting seat are connected through a fourth tool. According to the assembling method of the nuclear fusion device pre-assembled assembly, interference among installation of the vacuum chamber, the window neck tube in the vacuum chamber, the vacuum chamber cold shield and the TF magnet can be avoided, and the stability and functionality of the pre-assembled assembly structure are guaranteed.

A radiation irradiation system including a radiation generating device and a carrying table, a beam generated by the radiation generating device irradiates an irradiated object on the carrying table, the radiation irradiation system further includes a carrying table positioning device, the carrying table is supported by the carrying table positioning device, the carrying table positioning device includes a positioning mechanism, the positioning mechanism includes a linear axis, the carrying table positioning device may horizontally move along the linear axis, and an extending direction of the linear axis is parallel to an irradiation direction of beams generated by the radiation generating device. In the positioning process of the carrying table, most of the carrying table positioning device is located in the space between the linear axis and the beam outlet, the radioactivity and life-span shortening caused by the radiation of the various components of the carrying table positioning device are reduced.

The invention discloses an ionization chamber internal electric field modeling and radioactive interference suppression method. The method comprises the following steps: modeling by adopting a multi-physical simulation software package to obtain a geometric model of an ionization chamber; analyzing electric field distribution in the ionization chamber through finite element analysis software, and simulating a plurality of parameters by adopting a particle physical experiment simulation program to set a drift trajectory and a drift end point of secondary electrons so as to obtain ionization chamber parameters meeting conditions; and optimizing the ionization gas chamber according to the ionization gas chamber parameters meeting the conditions, and monitoring and outputting particle drift and current induction results based on the optimized ionization gas chamber. The radiation interference caused by the detector can be shielded on the basis of the original functions of the traditional ionization gas chamber, and the background emissivity of the alpha particle measuring device is reduced, so that the detection efficiency and accuracy of low-level radioactive measurement are improved.

The invention provides a reactor building, an arrangement method thereof and a nuclear power station. The arrangement method of the reactor building comprises the following steps: dividing a vertical surface space of the reactor building into layers along the vertical direction, arranging a reactor pit and a containment pit on a third underground layer, and arranging a first loop main equipment compartment, a second loop main equipment compartment and a third loop main equipment compartment on a second underground layer and above the second underground layer. A high-position refueling water tank of the passive safety injection system is arranged in a high-position refueling water tank compartment of a first underground layer, so that water in the high-position refueling water tank can submerge a reactor pit and main equipment of a reactor coolant system under the action of gravity. The method comprises the following steps: arranging core equipment of a passive special safety system in a containment; a special safety system related to safety can resist external disasters by means of the containment, and meanwhile, the system does not need to be switched between the inside and the outside of the containment during operation, so that the reliability of the system is greatly improved.