524 results about "Nuclear reaction" patented technology

The invention provides a beam shaper for neutron-capture therapy in order to improve flux and quality of a neutron source. The beam shaper comprises a target, a slowing body adjacent to the target, a reflector wrapping the slowing body, a thermal neutron absorber adjacent to the slow body, a radiation shield arranged in the beam shaper and a beam outlet. The target generates nuclear reaction with a proton beam incident from a beam inlet so as to generate neutrons, the neutrons form a neutron beam which defines a main axis, the slowing body slows down the neutrons generated from the target to an epithermal neutron energy region, the reflector guides the neutrons deviating from the main axis to the main axis so as to improve intensity of the epithermal neutron beam, a gap passage is arranged between the slowing body and the reflector so as to improve epithermal neutron flux, the thermal neutron absorber is used for absorbing the thermal neutron so as to avoid causing overmuch dosed with shallow normal tissue during therapy, and the radiation shield is used for shielding leaked neutrons and photon so as to reduce normal tissue dose in a non-radiation region.

A system and apparatus for a magnetized plasma nuclear fusion reactor, incorporating special design features which induce a plasma heat engine cycle in a rapidly rotating plasma. The heat engine operates either continuously or by oscillations. A continuous heat engine is formed in the open field outside a field reversed configuration. The oscillatory system operates in synchronism with cyclic acceleration, collision, and deceleration of plasma masses to produce nuclear fusion reactions at an economically useful rate with a relatively small driving power required. A special magnetic field design is combined with applied electrical voltages at the end of the field lines to produce required conditions. Design features allow recovery of large fraction of collision heat which would otherwise be dissipated as a parasitic loss.

In order to improve the flux and the quality of a neutron source, the invention provides a beam shaping body for neutron capture therapy. The beam shaping body comprises a beam inlet, a target, a retarding body adjacent to the target, a reflecting body surrounding the external of the retarding body, a thermal neutron absorber adjacent to the retarding body, and a radiation shield and a beam outlet formed in the beam shaping body, wherein the target has nuclear reaction with proton beam entering from the beam inlet, so as to produce a neutron; the neutron forms a neutron beam; the neutron beam defines a main axis; the retarding body slows down the neutron produced by the target to an epithermal neutron energy region; the retarding body is designed to a shape containing at least one cone; the reflecting body guides the neutron deviated from the main axis back to the main axis, so as to improve the strength of an epithermal neutron beam; the thermal neutron absorber is used for absorbing a thermal neutron, so as to prevent the thermal neutron from causing excessive dosage with a superficial normal tissue during therapy; the radiation shield is used for shielding leaked neutron and photon, so as to reduce the normal tissue dosage of a non-irradiated region.

A nuclear reactor (1) is provided, in particular a nuclear reactor cooled with a liquid metal (for example, a heavy liquid metal, such as lead or lead-bismuth eutectic), of the type having a cylindrical inner vessel (15) that divides a hot collector (6) over a core (4) from a substantially annular cold collector (7) surrounding the hot collector; housed in the cold collector (7) is a plurality of integrated circulation and heat-exchange assemblies (20), each of which includes a pump (9), two heat exchangers (10) set at the sides of the pump, and a conveying structure (21) through which a primary fluid (8) for cooling the core passes from the pump to the heat exchanger, all of which are fixedly connected to one another to form a unitary structure; each integrated assembly has an inlet (26) connected to the hot collector (6) and two outlet sections (34) in the cold collector (7).

The present invention relates to a fast reactor type coupling nuclear reaction implementation method and a nuclear reactor for same. The main contents comprise: a fast reactor type coupling nuclear reaction implementation method, a reactor modular design approach, a fast reactor type coupling nuclear reactor, a reactor core, a fuel element, a nuclear control system, and a proliferation fuel system. The fast reactor type coupling nuclear reactor mainly combusts thorium and nuclear waste, and has inherent security. The reactor main container is composed of a fission pool and a moderating pool that are completely isolated from each other but coupling to each other. A primary coolant is separated from a moderator. A thermal insulation layer is disposed between the fission pool and the moderating pool so that both can perform neutron exchange but heat exchange is blocked. Fast neutrons produced by the fission pool and moderated neutrons reflected by the moderating pool may enable the reactor core to simultaneously perform coupling nuclear reaction of the two types of neutrons. The moderating pool may be provided with the nuclear control system, and ex-core coupling core control may be implemented. The moderating pool is provided with a thorium purification fuel system, and on-line extraction of the purification fuel can be performed, and separation of nuclide is safe and simple, thereby providing a solution to the technical bottleneck of "thorium reactor".

Silicon particles are irradiated with neutrons so that 30Si of silicon isotopes is transformed to 31P through nuclear reaction. A negative electrode material comprising the P-doped silicon powder exhibits good cycle performance of silicon and is endowed with a high conductivity while maintaining the high initial efficiency and high battery capacity of silicon, and is thus useful as an active material in a negative electrode of a non-aqueous electrolyte secondary battery.

A method and apparatus are provided for correcting gamma ray data representative of gamma ray energies for spectral degradation. The method and apparatus include degrading reference gamma ray spectra. At least one correction factor is calculated between the degraded gamma ray spectra and the reference gamma ray spectra. The gamma ray data are then corrected using a calculated correction factor. Another method is provided for determining a correction factor for correcting data representative of gamma ray energies for spectral degradation. The method includes disposing a downhole tool in a simulated environment representative of actual downhole conditions, the tool including a neutron source and at least one gamma ray detector. The temperature of at least one of the gamma ray detectors of the tool is then varied while the simulated environment is irradiated with neutrons emitted from the neutron source. Gamma ray energy signals are then detected at the at least one detector in response to gamma rays produced during nuclear reactions between the neutrons and materials in and of the simulated environment. A characteristic of the simulated environment is then determined along with a characteristic of the at least one detector. The determined characteristics of the simulated environment and of the at least one detector are then correlated to determine at least one correction factor.

The invention provides a thermal hydraulic experiment device and method for simulating a nuclear reactor neutron reactivity feedback process. The thermal hydraulic experiment device comprises an electric heating experiment section, a shell-tube type cooler, a voltage stabilizer, a pressurizing nitrogen gas tank, a circulating pump, a cooling water pump, a cooling water tank, a cooling water tower, a pipeline, a valve, a measuring instrument, a data acquisition system, a control computer, a high-frequency direct-current power supply and a conductive copper bar. The high-frequency direct-current power supply is used for electrifying the electric heating experiment section. The circulating pump is connected with an inlet of the electric heating experiment section through a pipeline; the circulating pump is provided with a bypass pipeline; an outlet of the electric heating experiment section is connected with a pipe side inlet of the shell-tube type cooler through a pipeline. A control system for simulating nuclear reactor neutron reactivity is additionally arranged on the thermal hydraulic experiment device, and can be used for simulating the reactivity feedback process and a thermal hydraulic response process of nuclear reactors under various instant working conditions; the thermal hydraulic experiment device has the advantage of simulating various types of experiment working conditions, which are not easy to carry out in the nuclear reactor, under a nuclear-radiation-free environment.

A device is provided that can capture and store electrically neutral excited species of antimatter or exotic matter (a mixture of antimatter and ordinary matter), in particular, excited positronium (Ps*). The antimatter trap comprises a three-dimensional or two-dimensional photonic bandgap (PBG) structure containing at least one cavity therein. The species are stored in the cavity or in an array of cavities. The PBG structure blocks premature annihilation of the excited species by preventing decays to the ground state and by blocking the pickoff process. A Bose-Einstein Condensate form of Ps* can be used to increase the storage density. The long lifetime and high storage density achievable in this device offer utility in several fields, including medicine, materials testing, rocket motors, high power / high energy density storage, gamma-ray lasers, and as an ignition device for initiating nuclear fusion reactions in power plant reactors or hybrid rocket propulsion systems.

Aspects of the invention relate to several methods to deposit and regenerate target materials in neutron generators and similar nuclear reaction devices. In situ deposition and regeneration of a target material reduces tube degradation of the nuclear reaction device and covers impurities on the surface of the target material at the target location. Further aspects of the invention include a method of designing a target to generate neutrons at a high efficiency rate and at a selected neutron energy from a neutron energy spectrum.

New [GOD, I], [GOD, II], & [GOD, III] dual-plasma fuel cells provide the electric start systems to start their warm-up processes, automatically. After their warm-up processes done and the operation temperatures reached, the dual-plasma fuel cells will run independently by continuously supplying fuels and moisture into the units. In dual-plasma nuclear [fusion and / or fission] fuel cells' configuration, electrical power will be generated from the nuclear-thermal-plasmas reaction by exothermal heating from combustion & nuclear reactions. With conducting high-electrons' current, the cable, loads, and electrodes are connected among one another between two plasmas' ionizing chambers for civil utility purposes. In the [GOD, II] dual-plasma fusion fuel cell, heavy water [D2O] injection into the atomizing chambers increases the plasmas heating and electrical conductivities. And the un-like charges of the heavy water's [D2O+], & [D2O−] react with plasmas' [2H+& O=] combustion heating which will induce the fusion reaction and release much more nuclear heating power for initiation of the next plasmas-generation cycle much easily. For the [GOD, III] dual-plasma fission fuel cell, fission fuels located in the combustion & nuclear reaction space through robotic movements provide additional nuclear-thermal energy that allows for initiation of the plasmas-generation process for the next cycle. For [GerTh. I] dual-plasma jet thruster, the dual plasmas are ejected to an opening end of a ‘C’ shaped magnet, and linear thrust is generated, according to the right-hand rule as in a jet thruster of propulsion for space traveling.

The invention relates to an inherent safety tube-pool type nuclear reactor for research. The cooling-water main pump and the after-heat deriving pump of the reactor are set at back of the main heat-exchanger and connected in parallel in the main circuit room. The after-heat heat-exchanger is fitted in the water pool of the reactor. The main circuit room is provided at upper part of the water pool and at the bottom of the main circuit room there is a pipeline communicated to the under-water part of the water pool. At the inlet and the outlet of the reactor core is respectively provided with a hydraulic control open-close valve communicated with the water pool of the reactor. When the main pipeline occurs water-loss fault, water in the main circuit room can return to the water pool. At same time, as the pressure in the reactor container is low, the hydraulic control open-close valves at inlet and outlet of the reactor core automatically opens. When the after-heat deriving pump occurs fault, the inlet-outlet hydraulic control open-close valve is opened by a signal of high reactor-core temperature to make the reactor core and the water pool form a natural circulation to derive the after heat of reactor core into the water pool of the reactor.

The invention relates to the technical field of nuclear reactor core measuring system detector signal processing, and specifically discloses a signal delay eliminating method based on Kalman filtering for rhodium self-powered detector. The method comprises the following steps: step one, establishing a nuclear reaction model of rhodium and neutron; step two, establishing a Kalman filtering model; step three, utilizing the Kalman filtering to eliminate the current signal delay for rhodium self-powered neutron detector; wherein the step three comprises the following steps: step one, obtaining the systematic procedure white noise variance matrix Q and the systematic observation white noise variance matrix R of the Kalman filtering algorithm; step two, collecting the current value of the rhodium self-powered detector, converting the analogue signal into digital signal, and then utilizing the Kalman filtering to eliminate the current signal delay for rhodium self-powered neutron detector. The signal delay eliminating method based on Kalman filtering for rhodium self-powered detector can carry out a noise reducing treatment on measured current signals, and is capable of limiting the noise magnification times in a range of 1 to 8 under the situation that the responding time is small enough.

A low energy nuclear thermoelectric system for a vehicle which provides a cost-effective and sustainable means of transportation for long operation range with zero emission using an onboard low energy nuclear reaction thermal generator. The present invention generally includes a thermal generator within a thermal enclosure case, an energy conversion system linked with the thermal generator, an energy storage system linked with the energy conversion system, a cooling system and a central control system. The thermal generator reacts nickel powder with hydrogen within a reactor chamber to produce heat. The heat is then transferred to the energy conversion system to be converted into electricity for storage in the energy storage system. The cooling system provides cooling for the various components of the present invention and the control system regulates its overall operation. The present invention may be utilized to power a vehicle in an efficient, sustainable and cost-effective manner.

The invention provides a radiation detection system which aims to improve accuracy of neutron beam irradiation dosage of a neutron capture treatment system, and can timely discover a fault portion. The neutron capture treatment system comprises a charged particle beam, a charged particle beam inlet for pass of the charged particle beam, a neutron generation portion used for realizing nuclear reaction with the charged particle beam to generate a neutron beam, a beam shaping body used for adjusting flux and quality of the neutron beam generated by the neutron generation portion and a beam outlet adjacent to the beam shaping body, the radiation detection system comprises a radiation detection device, and the radiation detection device is used for detecting prompt Gamma rays after neutron beam irradiation in real time The invention further provides a radiation detection method which aims to improve accuracy of neutron beam irradiation dosage of the neutron capture treatment system, and can timely discover the fault portion.

Disclosed is an 18F-FDG automatic synthesis method and equipment, relating to prepare the 18F-FDG through a nucleophilic reaction. In the invention, a vessel for reaction solution is communicated with a reaction vessel through a valve and a pipe. Under the control of a stepping motor, the reaction solution can be put into the reaction vessel in batch according to the need. The reaction vessel is communicated with plurality sets of product collecting devices through the pipe and a valve with one inlet and a plurality of outlets with which the product in the reaction vessel can be moved into the collecting devices. With the above-mentioned method, when the nucleophilic reaction is processed and the sealed reaction vessel is between 100 DEG C to 120 DEG C, the water removal and the nucleophilic reaction can be processed in one heating device. The equipment can realize one time charge and multiple synthesis. The method simplifies the heating device. The invention is mainly used in one-time charge and batch production of the radiopharmaceuticals.

A device, method and system for causing a controlled collapse of cavities formed within liquid droplets wherein a pressurized jet comprising a liquid and nanoparticle material and possibly fuel produces droplets from the breakup of the jet stream. The liquid droplets are irradiated with energy to produce and expand cavities formed within the droplets by irradiation of the nanoparticles contained within the droplets. The droplets are collided with a target to collapse the cavities within the droplets. The irradiating and colliding are timed to enhance implosion energy resulting from the cavities' collapse. The implosion energy and the fuel in the cavity may be used to activate and sustain a fusion reaction.

The invention discloses a high-temperature and high-pressure water vapor environment structural material testing device. The testing device is provided with a pipe, wherein high-temperature water flows inside and outside the pipe. The testing device comprises an autoclave, a test tube loading system, a loop system inside a test tube, a loop system outside the test tube, a controlling and measuring system and a data acquisition and processing system. The testing device which can be used for simulating the temperature, pressure, flow velocity, water chemical conditions, load and the like of a high-temperature and high-pressure water vapor environment structural material is applicable to tests in the aspects of corrosion, stress corrosion, corrosion fatigue, flow accelerated corrosion and the like of tubular specimens through complex flow and complex load coupling effect. Especially, the working conditions of different flow, different inner-side and outer-side temperatures, different pressures and different water chemistry in a heat exchange tube of a steam generator in a nuclear reaction pressurized-water reactor can be simulated to carry out related testing and research on the heat exchange tube.

A beam shaping assembly for neutron capture therapy includes a beam inlet, a target having nuclear reaction with an incident proton beam from the beam inlet to produce neutrons forming a neutron beam defining a main axis, a moderator adjoining to the target, a reflector surrounding the moderator, a thermal neutron absorber adjoining to the moderator, a radiation shield arranged inside the beam shaping assembly and a beam outlet. The neutrons are moderated to epithermal neutron energies. An outer surface of the moderator includes at least a first tapered section. The reflector leads the neutrons deviated from the main axis back. The thermal neutron absorber is used for absorbing thermal neutrons so as to avoid overdosing in superficial normal tissue during therapy. The radiation shield is used for shielding leaking neutrons and photons so as to reduce dose of the normal tissue not exposed to irradiation.

The subject of the present invention is to provide a nuclear reactor plant of which is a direct cycle nuclear reactor using a carbon dioxide as a coolant such that a heat evacuation for liquefying coolant is reduced while a compressive work is reduced by using a condensation capability of a carbon dioxide for enhancing a cycle efficiency.The nuclear reactor plant is comprised of a nuclear reactor 1, a turbine 2, and wherein, the coolant of supper critical state is heated by a heat of a nuclear reactor to directly drive a turbine, a gaseous coolant discharged from said turbine is chilled and compressed after said turbine is driven for keeping in a critical state, and then said coolant is circulated again into said nuclear reactor, and wherein, a carbon dioxide is used as said coolant, and a predetermined ratio of gaseous coolant discharged from said turbine is liquefied for being compressed in a liquid state while a rest of gaseous coolant is compressed in a gaseous state.

The invention provides a compactly arranged small-sized reactor primary loop overall structure. The structure is suitable for a marine operation environment, and comprises a pressure container, double-layer sleeve structures, inner-pile components, a control rod driving mechanism, a main pump, a steam generator, a pressure stabilizer, a main equipment integral support, a suppression pool, a primary shielding structure and the like. The steam generator is connected with the pressure container through one double-layer sleeve structure; the main pump is connected with the pressure container through one double-layer sleeve structure; the pressure stabilizer is connected with an evaporator through a surge pipeline; and the pressure container, the steam generator, the main pump and the pressurestabilizer are installed in the suppression pool through the integrated integral support. According to the system provided by the invention, the circulation of a nuclear reaction coolant in a reactorcoolant system can be ensured, realization of compact arrangement of a nuclear steam supply system is facilitated, and the heat exchange efficiency is improved.

This invention relates to a cement multi-element analysis device. The neutron multi-element analysis device uses the neutron generator in the D-D reaction as neutron source and emits rapid neutrons of 2.5 Mev. The neutron reacts with the cement element to generate multi-nuclear reaction with different energy radiation gamma rays. The gamma ray detector is to detect the r rays generated by the elements in the cements. The r signals are through main amplifier and are transmitted to the micro machine for monitoring. It uses multi-path gamma spectrum device to test the area of the characteristics gamma ray peak and gives the relative nucleus content through test formula.

Liquid nitrogen, the densest and highly transportable form of nitrogen, and the cold nitrogen gas it produces when released from its container, for emergency cooling of fuel rods and nuclear reaction chambers and fighting hazardous fires is disclosed. Liquid nitrogen may be disbursed via a thermally-activated heat valve attached to a container of liquid nitrogen.

One technical scheme of the invention provides a beam diagnosis system for a neutron capture therapy system. On one hand, the accuracy of the neutron beam irradiation dose of the neutron capture therapy system is improved, and on the other hand, the beam diagnosis system is provided for being used in the neutron capture therapy system for fault diagnosis. The neutron capture therapy system comprises a charged particle beam, a neutron generating part for generating a neutron beam through a nuclear reaction with the charged particle beam through a charged particle beam inlet of the charged particle beam, a beam shaping body for adjusting the neutron beam flux and the quality generated by the neutron generating part and a beam outlet adjacent to the beam shaping body, wherein the charged particle beam inlet is accommodated in the beam shaping body; and the neutron generating part is accommodated in the beam shaping body. The beam diagnosis system comprises a charged particle beam diagnosis device and a neutron beam diagnosis device. The beam diagnosis system is used for simultaneously diagnosing whether fault happens to the neutron capture therapy system and / or the beam diagnosis system.

An insulating coating is applied to the metallic components in a nuclear reactor water environment to decrease and / or mitigate general corrosion and erosion-corrosion of the reactor component's metallic surfaces. Preferably, the coating is a 0.1 micron to 0.3 mm thin layer of an oxide coating such as titania (TiO2), zirconia (ZrO2), tantala (Ta2O5), Al2O3, CeO2 or similar oxides; or a thin layer of the metal, such as Ti, Zr, Ta, Hf, Ce, Al, which will oxidize in the reactor water environment. The applied coating provides a protective layer between the component surfaces and the reactor water environment. By reducing and / or eliminating the potential for corrosion on reactor metallic components, the coating eliminates or minimizes the potential for activated corrosion products to contaminate the reactor water. The coating is especially beneficial for nickel-alloy based metals that contribute significant cobalt-related corrosion products, and will also be effective on austenitic stainless steel components.

The invention relates to a comprehensive analysis method for steam explosion of nuclear reactors. The method mainly comprises the following steps of: 1, obtaining initial parameters of the steam explosion; 2, calculating the change of melt in the steam explosion process; 3, calculating the energy exchange on a phase interface; 4, calculating the mass transfer on the phase interface; 5, calculatingthe momentum exchange on the phase interface; 6, semi-implicitly solving energy and momentum equations; 7, full-implicitly solving a mass conservation equation and outputting distribution of pressurewaves; 8, carrying out geometric modeling on main components by using a finite element program ABAQUS; 9, creating material physical properties and analyzing and inputting by taking the pressure wavedistribution in the step 7 as a load; 10, carrying out grid dividing on the main components established in the step 8; and 11, submitting analysis and outputting the stress change of the main components. The comprehensive analysis method disclosed by the invention has the advantages that the distribution situation of the pressure waves and the impact effect of the pressure waves on the main components under steam explosion accidents of the nuclear reactors can be comprehensively analyzed, so that bases are provided for more comprehensively and effectively evaluating the safety of the reactors.

A method for conducting a device proton signal-event test through an accelerator high-energy proton comprises the steps that test samples are processed and the requirements of a signal-event test board and the requirements for selection of high-energy proton energy, the fluence rate and the fluence are satisfied. Single event upset of a large-scale circuit tends to be sensitive along with the increase of the integration degree and the reduction of the feature size. Single event upset can be generated through the method that a nuclear reaction of the proton occurs or the proton is directly ionized. An electronic system fault probably caused by single event upset happens to an on-orbit satellite. The method is used for conducting the device proton single event upset test on the ground. According to the method, the proton single event upset sensitivity of a key device for the satellite can be evaluated, proton single event upset sensitive parameters of the device can be obtained, a basis is provided for anti-radiation reinforcing design of the satellite, and the method for conducting the device proton signal-event test through the accelerator high-energy proton has important significance in the guarantee of the reliability of the new-generation satellite.

A system and method is provided for a continual updating of the optimization of multiple operational control-variables during the operation of a nuclear reactor over a plurality of fuel cycles. A networked computer system includes one or more hosts programmed to execute an optimization process to identify and make changes in quantitative values of operational control-variables that result in improved efficiency and operational flexibility. Optimization and updating of operational control-variables may proceed selectively under manual control for inputting specific optimization constraints and reactor state-point information or may proceed autonomously through a repetitive performing of the optimization process based upon a predetermined user-defined strategy stored on the network. Communications between users and networked processors is facilitated by use of a TCP / IP server connected to the Internet so that portions of the optimization process may be conducted contemporaneously at remote locations and / or the results made accessible to users via conventional browser enabled computers.