134 results about "Inherent safety" patented technology

A haptic feedback device including a fluid viscosity-controlled brake that outputs high forces to the device user at low cost while maintaining inherent safety. An interface device includes a manipulandum physically contacted by the user. A sensor senses a position of the manipulandum and outputs a sensor signal. The interface device also includes a brake including a field-controlled fluid having a viscosity that can be controlled by controlling an electric current in a coil, where a resistive force or drag on the manipulandum is controlled by controlling the fluid's viscosity. The fluid can be an electrorheological fluid controlled by an electric field or a magnetorheological fluid controlled by a magnetic field. In one preferred embodiment, the resistive force is controlled by adjusting a degree of contact of the brake with the manipulandum based on the fluid's viscosity. Disclosed embodiments include fishing devices, bicycle simulators, and control knobs.

The present invention relates to electrochromic polymeric solid films, manufacturing electrochromic devices using such solid films and processes for making such solid films and devices. The electrochromic polymeric solid films of the present invention exhibit beneficial properties and characteristics, especially when compared to known electrochromic media. The electrochromic polymeric solid films are transformed in situ from a low viscosity electrochromic monomer composition by exposure to electromagnetic radiation, and in so doing minimum shrinkage occurs. The electrochromic polymeric solid films of the present invention also perform well under prolonged coloration, outdoor weathering and all-climate exposure, and provide an inherent safety aspect not known to electrochromic media heretofore.

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".

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.

A transonic speed controllable vortex gas dehumidifier adopts a mode generating vortex through a static cascade of a vortex generator. A shell of the dehumidifier and a vortex controller form an annular jet tube, the vortex intensity of gas-liquid phase flows is controlled by changing the flow passage area of an annular space to realize the condensation and separation process of components and achieve the purpose for improving the separation efficiency and lowering the flow loss by combining a high-effective back-pressure device. The dehumidifier can change the mode generating vortex, control the change of the vortex intensity in the processes of component condensation, component separation, back pressure, and the like, improve the component separation efficiency and reduce the total pressure loss. The invention has the advantages of no addition of medical agent, low weight, compact space structure, small occupied area, low cost, unmanned operation, high inherent safety, and the like, thereby having wide application prospect in the fields of the separation and the liquefaction of high-pressure mixed gases, and the like.

A special-designed motionless safety reactor study and low temperature heat input reactor facilities in nuclear reactor field. To the side of the reactor installed a large volume water pool whose top is 10-30 meters higher than the reactor top. To the bottom of the water pool a water injection pipe is linked to the reactor inlet, a pipe linked to the reactor outlet is connected to the pool and in a position higher than water level. Outside the plant there is an emergency water tank which is 25-28 meters higher than the main heat exchanger and an air cooler which is 15-18 meters higher than the main heat exchanger. Both the water tank and the air cooler are linked to the recycle pipe between the main heat exchanger and the second heat exchanger.

Successful cryopreservation by the vitrification method depends on high chilling speed. Practitioners of vitrification prefer to use liquid nitrogen as the chilling cryogen due to its inherent safety and low cost. Plunging vitrification cryocontainers in to a quiescent pool of liquid nitrogen invariably results in a chilling rate less than the theoretical potential. The shortfall is attributed to the well-known Leidenfrost effect. The purpose of this invention it to provide improve chilling rates during vitrification using liquid nitrogen. One feature of this invention is a contacting device that invokes convective heat transfer principles to increase chilling speed. In another feature of this invention, cryogen velocity is derived from a self-pressurized dewar containing a saturated cryogen. The self-pressurization is achieved by ambient heating of the dewar's contents. In another embodiment, a sub-cooled cryogen, such as propane, is used in tandem with a saturated cryogen, such as LN2, in a self-pressurized dewar.

The invention discloses a method and a device for fast multiplicating and transforming nuclear fuel with high inherent security and low cost, and the method and the device adopt 'moving solid nuclear fuel' which can flow and is similar to fluid, can be applied in a fast neutron reactor, and produce more nuclear fuel with less fissile fuel initial installation quantity and lower cost in a shorter time, thus satisfying the nuclear fuel demand at the current world nuclear power big development stage. The method and the device for fast multiplicating and transforming nuclear fuel are real nuclear reactors with inherent security, and can thoroughly eliminate the serious accident of massive radioactive release caused by element melting of the nuclear fuel which still possibly occurs in the current nuclear power station.

The present invention provides an inherent security pool-shell combination low temperature nuclear heating device and an operation program thereof, which belongs to nuclear energy centralized heat-supply field. The invention mainly comprises the following procedures: adopting separated layout, forced circulation and high effective small temperature difference heat exchange in primary loop of reactor; under the precondition that parameter requirements of centralized heat-supply by big cities heat supply network satisfied, reducing work temperature of shell-type heating reactor as far as possible; meanwhile optimized layout of equipment, and organic combination of normal pressure pool in large volume (47) and shell-style heating reactor(29) remove accident possibility of water loss and coldness loss of reactor core (1). Complete inherent safety principle is carried out in the invention. Thus, absolute security of nuclear heating can be guaranteed by using mature pressurized water reactor technology, and enterprises have develop nuclear station pressurized water reactor experience can possibly jump over research and develop stage and enter into nuclear heating market directly, and make a real contribution for energy-saving and emission-reduction and improving country energy structure.

The proper sizing of microchannel dimensions and the management of internal features offer the possibility of inherently safe operation within the flammable limits of a combustible fluid stream while preserving the largest-possible flow dimensions for industrial-scale process capacity. Specifically, the microchannel dimensions need not be restricted to gap distances below the quenching distance to be operated safely. Microchannel performance can be engineered to provide adequate heat transfer for flame propagation. However, it is essential to maintain flame characteristics in such a manner that it cannot transition to a detonation flame front. A detonation takes place when the combustion wave propagates at supersonic speeds at the existing local temperature and pressure conditions in the system. It results in a much larger energy release over a much smaller period of time as compared to a laminar flame or deflagration, the later of which is a combustion wave propagating at subsonic speed. Detonations can be potentially highly destructive and very hazardous and therefore should be avoided for most industrial applications.

The invention discloses a continuous drying device for powdery simple substance explosive. A drying station is placed on the upper end face of a hot water circulating jacket and supported by an inner support frame body, a static rotation connecting unit can drive the drying station under the action of a driving transmission unit to rotate at a proper rotational speed, and thermostatic hot water in a hot water storage tank can be circularly supplied to the hot water circulating jacket; and a distribution plate, a scraping plate and a rake feeder are arranged along the radial direction of the drying station through an outer support frame body. The powdery simple substance explosive is conveyed to the drying station between the distribution plate and the scraping plate by a feeder; the powdery explosive is subjected to processes of spreading, water evaporation, raking and water evaporation in turn along with the circular motion of the drying station; and when the drying station rotates for one circle, the dried powdery simple substance explosive is scraped into a hopper by the scraping plate. The device solves the problems of continuous operation and field isolation in the powdery simple substance explosive drying process, and has the predominant advantages of good inherent safety, short drying process period, low energy consumption, high efficiency and the like.

The present invention related to a novel process for accelerating the breeding and conversion of fissile fuel in various types of nuclear reactors. In said process a movable nuclear fuel ball bed filled with a coolant creeps through the reactor core. The said process could provide higher specific power per unit fuel volume inside the reactor core and proceed on-line refueling, thus requires much less initial fissile fuel inventory per unit power output as compared with the traditional breeding or conversion reactors. The said process has full inherent safety characteristics and could follow the external power demand with the inherent negative temperature coefficient of reactivity. The said process, therefore, is a more efficient and economic approach to meeting the enormous demand of fissile fuel for the forthcoming “second nuclear era”.

The invention relates to a reactor core component of a neutron source device of a hospital neutron irradiator-I. The reactor core component has the advantages of being low in production cost, easy and convenient to operate and maintain, safe to use, low in operation cost, pollution-free to environment and can be built directly in hospitals and the like, so that the reactor core component is an ideal device as a neutron source of the neutron irradiator. The device realizes innovation and invention of the four reactor core important components, such as a high-equivalent central control rod, a high-effect responsive regulator, a graphite tile and aluminium tile piece adaptive to neutron spectrum as well as low-concentration design of a reactor core fuel element and update of fuel assembly structure material and the like. On the basis that the intrinsic security of a reactor and extremely-low uranium filling volume are maintained and operation is done under nuclear-free engineering personnel caring conditions, the reactor for scientific research which is only used in small sample element activation analysis is developed to be a high-tech clinic cancer-curing medical instrument. The specially-designed reactor core component forms the four mutually-associated invention points in the invention.

The invention discloses a deep negative feedback transmutation reactor core based on accelerator driven subcritical clean nuclear energy system and belongs to the field of nuclear reactors. The reactor core comprises a target area (A), a quick spectrum area (B) and a deep negative feedback area (C). According to the deep negative feedback transmutation reactor core provided by the invention, the problem that the reactor is instable in power because the accelerator beam is instable under the conventional technical conditions can be solved, the reactor can stably operate under different subcritical depths, and the reactor has extremely high inherent safety due to a large fuel Doppler coefficient.

The invention provides a temperature and humidity adjusting device for a chemical fire explosion safety test chamber system. The device provided by the invention comprises a temperature adjusting device and a humidity adjusting device. According to the chemical fire explosion safety test chamber system with the temperature and humidity adjusting device, harms of a runaway reaction, combustion explosion, decomposable explosion and the like which are generated during the process of large-scale chemical risk assessment test are eliminated, and simultaneously, effluents, exhaust gas and waste residues that are generated during collection test process undergo centralized processing. Inherent safety of the fire explosion risk test process is raised, and the effect of reducing environmental pollution is also achieved.

A method for rendering a half-bridge circuit containing normally on switches such as junction field effect transistors (JFETs) inherently safe from uncontrolled current flow is described. The switches can be made from silicon carbide or from silicon. The methods described herein allow for the use of better performing normally on switches in place of normally off switches in integrated power modules thereby improving the efficiency, size, weight, and cost of the integrated power modules. As described herein, a power supply can be added to the gate driver circuitry. The power supply can be self starting and self oscillating while being capable of deriving all of its source energy from the terminals supplying electrical potential to the normally on switch through the gate driver. The terminal characteristics of the normally on switch can then be coordinated to the input-to-output characteristics of the power supply.

The invention provides a thermoplastic composite solid propellant applicable to a solid booster. The thermoplastic composite solid propellant is prepared from components in percentage by mass as follows: 55%-70% of an oxidant, 10%-20% of a thermoplastic resin adhesive, 10%-20% of a plasticizer, 5%-20% of metal fuel and 3%-8% of auxiliaries. According to the prepared thermoplastic composite solid propellant, relative independence of mixing and pouring, integrated formation of the propellant and secondary formation of engine charge can be realized according to temperature adjustment, and melt mixing and formation of the thermoplastic propellant can be realized at relatively low temperature lower than 90 DEG C, so that inherent safety of preparation of the thermoplastic propellant is greatlyimproved; compared with a traditional thermosetting propellant, crosslinking curing process is omitted, technological process is shortened, recovery and repeated processing of waste products can be realized, and production cost is reduced. The thermoplastic propellant is prepared with a hot melt mixing-cooling formation technology, and application of components absorbing moisture easily in the propellant is realized.

The invention discloses a safe multifunctional fast neutron zero power device capable of being coupled with a neutron source, which can implement corresponding component functions by adding corresponding materials or structures into shells of a unified specification of standard components so as to ensure the flexibility of disassembling and assembling of core structures and facilitate the implementation of a better safety performance. Meanwhile, a reactive control system of the device adopts two sets of shutdown systems which are independent and have different principles, a control rod drive mechanism for experiments is arranged alone additionally, the control rod drive mechanism for experiments is also provided with a safety rod shutdown system for verification, but the device carries out shutdown protection without relying on the system, and the layout and installation of the control rod drive mechanism for experiments have flexibility, so that the device has a function of simulating the actual layouts of various cores, and has a better security performance; and in addition, the reactive control system also comprises a redundant safety protection measure, so that the device has a better inherent safety performance while ensuring the flexibility of simulated layouts of cores so as to ensure multifunctionality.

In one embodiment, an improved programming system and language for application development is provided that combines elements of the C and Objective-C languages without the constraints imposed by a requirement to maintain compatibility with the C language. The language provides the functionality of the C language compatibility in certain areas to improve the inherent safety of software written in the language. The new language includes default safety considerations such as bounds and overflow checking.

The invention discloses an electric automatic protective device of an anti-explosion diesel locomotive, comprising a flame-proof type indicating box for the anti-explosion diesel locomotive, a flame-proof and inherent safety type control box used for the anti-explosion diesel locomotive, an intrinsic safety junction box and sensors. The electric automatic protective device is characterized in that the indicating box, the control box, the intrinsic safety junction box and each sensor form a gas self-checking circuit, a safety control loop, an operation instruction control circuit, an auxiliary protective circuit and a creepage protective circuit, wherein the operation instruction control circuit comprises a relay board 2 arranged in the flame-proof and inherent safety type control box used for the anti-explosion diesel locomotive, and the relay board 1 is connected with each sensor. The electric automatic protective device of the anti-explosion diesel locomotive adopts a reliable relay control way to control signals acquired by the sensors in the way of switching value and is simple and reliable.

The invention belongs to the technical field of reactors, and particularly relates to a swimming pool type regional low-temperature heat supply reactor which comprises a reactor core and a loop. The reactor core is arranged at the bottom of a reactor pool, and the depth of pool water in the reactor pool is 20-30 meters; an upper hanging basket, a middle hanging basket, a lower hanging basket and areactor core base are sequentially arranged in the reactor pool from top to bottom; drive wires of a control rod drive mechanism are arranged in the upper hanging basket, control rod guide barrels are arranged in the middle hanging basket, the reactor core is arranged in the lower hanging basket, the lower hanging basket is arranged on the upper side of the reactor core base which is fixed to thebottom surface of the reactor pool, and the reactivity of reactors is controlled by control rod clusters; the loop is communicated with the lower hanging basket, and heated pool water in the reactorcore can be delivered to the outside of the reactor pool via the loop, can be subjected to heat exchange and can flow back into the reactor pool. The swimming pool type regional low-temperature heat supply reactor has the advantages of high inherent safety level and reliability, economical efficiency and practicality.

The invention discloses a heat pipe-cooled mixed fuel reactor system. The heat pipe-cooled mixed fuel reactor system includes a reactor core active zone, a liquid storage tank, control drums, a reflecting layer and a reactor core cylinder body, wherein the reactor core active zone is composed of multiple hexagonal fuel components, multiple heat pipes are evenly distributed inside the fuel components, the reflecting layer is located on the periphery of the reactor core active zone, multiple symmetrically-arranged control drums are arranged inside the reflecting layer, and the liquid storage tank is arranged below the reactor core active zone. The reactor core active zone, the liquid storage tank, the control drums and the reflecting layer are all arranged inside the reactor core cylinder body. The reactor core of the invention has advantages of both a solid reactor core and a liquid reactor core, and the critical size of the reactor core can be changed by the discharge of a liquid fuelin an accident, so as to realize emergency shutdown of the reactor and improve the inherent safety of the reactor.

The invention discloses a shell-and-tube lead base alloy cooling reactor. The reactor comprises a reactor vessel, a reactor core, fuel channels and pressure pipes, wherein each fuel channel is formed by placing a nuclear fuel assembly and a lead base alloy coolant into one pressure pipe, and multiple fuel channels ate placed in a reactor vessel pool to form the reactor core. The reactor is applied the design requirement background of large lead base alloy cooling reactors, so that a reactor system has the characteristics of high power and high inherent safety realized only by the aid of material characteristics, the reactor core meltdown probability is eliminated in design, the massive radioactive release probability is eliminated in reality, and off-site emergency is canceled; in the fuel channels formed by placing the nuclear fuel assemblies and the lead base alloy coolants into the pressure pipes, the flow of the coolant in each pressure pipe can be adjusted according to single-pipe power design of the pressure pipe.

The invention belongs to the technical field of containment pressure suppression and cooling systems, and particularly relates to a containment pressure suppression and cooling system having inherent safety. The containment pressure suppression and cooling system can perform pressure suppression and cooling on a containment after a loss of coolant accident and a steam pipe rupture accident happen to a reactor. A reactor pressure vessel is positioned in a steel containment, a reactor is positioned in the reactor pressure vessel, the lower part of the reactor pressure vessel is arranged in a round reactor cavity at the lowest elevation position in the steel containment, and the upper part of the steel containment is immersed in a shielding pond; the upper space in the steel containment is a dry well, the lower space of the steel containment is a wet well, the dry well and the wet well are separated by a reinforced concrete wall and a floor slab to form respectively independent spaces, and a communicating pipe is the only connection channel for the dry well and the wet well; and the lower part of the wet well is a pressure suppression pond, and the upper part of the wet well is a gas space. The containment pressure suppression and cooling system provided by the invention can perform pressure suppression and cooling on the containment after a loss of coolant accident and a steam pipe rupture accident happen to the reactor.

Techniques for providing phase change electrolytes that can be used to improve safety of electrochemical devices, such as lithium batteries, are disclosed herein. At normal operation temperature, the phase change electrolyte is capable of switching “on” with high ionic conductivities in a liquid state. When an electrochemical device system (filled with the phase change electrolyte) encounters abnormal high temperature due to overcharge or shorting, the phase change electrolyte inside the device is capable of switching “off” with low ionic conductivities in a gel state and shut down ionic conductive flow to prevent disastrous electrochemical or chemical events, such as thermal runaway and explosion. When temperature of the electrochemical device returns to normal, the phase change material inside the electrochemical device can switch back to “on” with high ionic conductivities in a liquid state, thereby providing electrochemical devices with inherent safety, especially for rechargeable lithium batteries.

A natural safety, nuclear diffusion-proof and low cost nuclear energy production method and device adopts a 'quasi liquid nuclear fuel' made of mixed fine coating nuclear fuel particles and high boiling point liquid heat carrying agent. The reactor core of the nuclear reactor is immerged at the bottom of a big pond filled with the same high boiling point heat carrying agent, to constitute a fully sealed type reactor system. When the quasi liquid nuclear fuel peristaltic pass through the reactor core of the reactor with very-low speed, that generating fission energy, the generated heat energy are carried by the high boiling point heat carrying agent to be used for generating and heat supplying. The reactor system is controlled by computer completely, without any human disturbance. Nuclear materials sealed into the reactor system are real-time and long-distance monitored and remote controlled by the international nuclear safety guarantee organization through the satellite. The nuclear energy production method and device provided by the present invention can generate nuclear energy cheaply, and have business compete ability in the future energy source market.

The invention provides a nuclear power supply system for an underwater unmanned submersible vehicle. The nuclear power supply system can improve the inherent safety and unmanned autonomous control capability of a reactor. The system comprises a reactor core, a high-temperature heat pipe, an alkali metal thermoelectric conversion device, a medium-temperature heat pipe, a storage battery and a pressure-resistant shell, wherein the evaporation section of the high-temperature heat pipe is inserted into the reactor core; the condensation section of the high-temperature heat pipe is inserted into the alkali metal thermoelectric conversion device; the alkali metal thermoelectric conversion device comprises a plurality of groups of thermoelectric conversion modules; a heating end of each thermoelectric conversion module is connected with the high-temperature heat pipe; a condensation end of each thermoelectric conversion module is connected with the medium-temperature heat pipe; the condensation section of the medium-temperature heat pipe is connected with the pressure-resistant shell; waste heat is conducted into surrounding seawater; the alkali metal thermoelectric conversion device is further connected with a storage battery; and the alkali metal thermoelectric conversion device converts heat energy into electric energy and stores the electric energy in the storage battery.