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INVENTION
Patent of the Russian Federation RU2296388

LOADING DEVICE FOR TESTS OF THERMO-EMISSION ELECTRIC GENERATING ASSEMBLY AND METHOD OF TESTS OF A LOTION DEVICE WITH THERMO-EMISSION ELECTRIC GENERATING ASSEMBLY

The name of the inventor: Viktor Sinyavsky
The name of the patent holder: Open Joint-Stock Company "Rocket and Space Corporation Energia" named after SP Korolev "
Address for correspondence: 141070, Moscow Region, Korolev, ul. Lenin, 4a, RSC Energia after SP Korolev, Department of Intellectual Property
Date of commencement of the patent: 2005.03.09

The group of inventions refers to space power plants with a thermionic method of converting thermal energy into electrical energy and is intended for use in the development of thermionic power generating assemblies (EGS). The loop device for testing thermionic ECS contains a housing. In the housing there is a heat-sink system equipped with electric heaters, a source of cesium vapor and a cesium path. The heat-sink system is made with the possibility of placing the test thermionic ECS inside it. The heat-sink system is cooled from the outside by the water of the research reactor. The cesium path is made with the possibility of connecting to the interelectrode gaps of the thermoemission ECS and to the system of evacuation of the reactor stand. To the cesium channel through a controlled heated shut-off valve, a tank for collecting liquid cesium, installed outside the housing and cooled by the water of the research reactor, is connected. The container is designed to be sealed and disconnected from the housing. The group of inventions allows to reduce the radiation hazard with the discharge of the loop device for extraction of EGS for subsequent studies and simplification of the utilization of loop devices after the tests.

DESCRIPTION OF THE INVENTION

The invention relates to space power plants with a thermionic method of converting thermal energy into electrical energy and to reactor technology and can be used in a program for the development of thermionic power generating assemblies.

The most important stage in the design and development of one of the most complex units of the thermionic reactor-converter (TRP) is the reactor test of thermionic power generating assemblies (EGS) in the composition of test loop devices (PU), usually called loop channels (PCs). The main purpose of such tests is to study the processes and factors that lead to a change in the energy and resource characteristics of EGS, and the causes of failure of elements and EGS as a whole. Based on the results of loop reactor tests and post-reactor studies, recommendations for improving the design and technology of EGS production should be developed. The ultimate goal of the reactor testing of EGS is the creation of a reliable operating thermionic ECS with stable and reproducible characteristics for a given time.

The success of the loop tests of thermionic ECSs is largely determined by the reliability of the functioning of all loop device systems and the testing methodology. The design of the control system and the test procedure should ensure that not only the operating conditions of the EGS, as close as possible to the conditions of EGS functioning in the TRP, but also the subsequent convenient and safe disposal of the tested PU, are tested during the tests.

Loop devices are designed taking into account the design features of the EGS tested, the need to provide close to the actual test conditions, the ability to measure and regulate the main parameters of EGS and the specifics of the research reactor where EGS loop tests are to be conducted.

Several PU designs were developed and tested in research reactor cells [1]. The first PU were close to ampoule test devices. The peculiarity of the first versions of the PU was, to some extent, the copying of laboratory devices for testing conventional thermionic transducers (TICs), including the use of a conventional thermostat as a source of cesium vapor placed in the lower part of the PU, the presence of often even an unheated valve in the path Connection to the vacuum system for sealing the volume of "thermostat-EGS", the presence of an electric collector heater, the introduction of a getter device into the PU or an autonomous vacuum pump.

Since the beginning of the first loop tests to date, the design of the PU has undergone significant changes. The composition and design features of PU differ depending on the design and quantity of EGS in one PU, the tasks and test modes and characteristics of the reactor test cell. In the tests on one reactor, as a rule, the external dimensions of the PU remain unchanged, while the sources of cesium vapor, the elements of the heat-sink system, the evacuation system, the sensors for measuring the basic characteristics of EGS are changed. Perfection of the design of the UE took place from the point of view of adapting to the programs for working out certain types of EGS, increasing the reliability of these devices, including for providing resource tests, the possibility of testing EGS with increased heat fluxes and the density of generated power, the possibility of testing several ECSs in one PU, X and 4), to provide EGS testing in the presence of a collector package of liquid metal coolant (NaK or Li) outside the carrier tube, to increase the number of sensors integrated in the PU to increase the information content of the tests, and so on. In recent years, the main task of the designers of the PU design has been the creation of the so-called universal loop channel (CCP), meaning its application for EGS tests of various modifications, including those developed in different organizations, and use at different reactors.

It is known that the PU for testing the EGS of the space nuclear power plant "Topaz" in the reactor of the first nuclear power plant ([1], p. 27-28, Fig. 2.10). The PU consists of a housing inside which is placed a coolant system cooled by a heat carrier, for example water of a reactor, a heat dissipation system (STS) made with the possibility of installing EGS inside it. The heat-sink system, in turn, contains a thermal control system, which is a small gap that can be evacuated or filled with gas. The PU contains a source of cesium vapor and heated cesium channels. Outside, the STS is cooled by the reactor water. The PU is equipped with vacuum systems, gas supply, parameter measurements and others.

Such a reactor should be kept in a special settler for a long time after the reactor tests, and after that it must pass the so-called "cutting" and be disposed of. However, cesium when it was in the reactor during the tests as a result of neutron irradiation became radioactive and contained in the thermostat, and possibly in the tracts and EGS, which makes it difficult to recycle the PU.

One of the latest PU designs tested in the reactor of the first nuclear power plant is known [2]. In the lower part of the PU there is a so-called working area with an installed EGS with emitter and collector current leads installed inside it. The working section is connected in series with a pumping system, heated throughout the cesium path by electric heaters. In the pumping unit there is a thermostat, which is filled with liquid cesium from the ampoule (usually after the thermovacuum preparation of EGS and PU systems). For the continuous pumping of gases from the cavity "interelectrode gap (MEZ) - fuel-emitting unit", a cesium vapor separator from gases intended for condensing the cesium vapor and returning the liquid cesium is located in the loopback system (loopback) and maintaining the necessary interelectrode medium in the pumping unit In the thermostat. The pumping unit may end with a pneumatic valve, which opens when the IES is evacuated by the EGS tested. In order to remove heat from the collector bag, the cooling jacket in the PU usually uses a gas gap between the outer carrying tube of the collector bag (CP) and the jacket of the cooling jacket. The thermal conductivity of a gas gap is controlled by changing the gas pressure, usually helium, or the composition of a mixture of gases, usually helium and nitrogen.

However, the radioactive cesium contained in the thermostat, and possibly in the tracts and EGS, makes it difficult to recycle the PU after reactor tests.

The closest to the invention in terms of technical essence is the PU for testing thermionic EGS, proposed in [3]. The UE includes a housing in which a cesium vapor source is provided, equipped with electric heaters, a heated cesium path and a heat-sink cooled by the heat-transfer agent of the research reactor, configured to house the test thermionic ECG with current leads inside it, the CTC comprising an annular gap filled with gas or a mixture of gases.

Such a reactor should be kept in a special settler for a long time after the reactor tests, and after that it must pass the so-called "cutting" and be disposed of. However, cesium when found in the reactor during the tests as a result of neutron irradiation became radioactive and contained in a thermostat, and in case of uncorrected test regimes and in cesium channels and possibly in EGS, which makes it difficult to dispose of PU.

Several versions of the test method for PU with a multi-element thermionic ECS are known. The test method depends on the specific research tasks, the features of EGS and PU, the permissible operating conditions of the research reactor. It is influenced not only by the possibilities of measuring and controlling the main parameters in the testing process, but also the need to ensure the operability and reliability of the main systems, both EGS and PU and the test reactor stand (loop).

A method for testing PU with a multielement thermionic ECS described in [4] is known. After loading the PU into the cell of the research reactor, the connection of all technological, electrical and measuring communications with the corresponding systems of the test bench, control testing of all systems, degassing all EGS and PU systems with a gradual increase of the reactor thermal power to an intermediate level. After this, a liquid cesium inlet is introduced into the cesium thermostat or another source of cesium vapor. A smooth rise in the temperature of the source of cesium vapor to the working value is made, after which the thermal power of the reactor is raised to the operating value. EGS begins to generate electrical power. Resource tests are conducted most often in the mode of selection of the maximum electric power for a given thermal power. In the course of resource tests, scheduled shutdowns and the possibility of resetting the reactor emergency protection rods are envisaged. In the latter case condensation of cesium vapor on the electrical insulation is possible, followed by a short-circuit of electrodes of EGS. After the test, the PU is removed from the reactor. After holding for a decrease in activity, the PU is transferred to the "hot" chambers for cutting the PU with extraction of EGS for subsequent postreactor studies.

However, cesium when it was in the reactor during the tests as a result of neutron irradiation became radioactive and contained in a thermostat, and possibly in cesium channels and EGS. This makes it difficult to cut the PU to extract EGS for subsequent research, as well as the disposal of PU.

A method of reactor testing of a thermionic assembly, proposed in [5], is known. It includes the hermetic separation of the cavity of EGS and the source of cesium vapor from the external vacuum system by means of a sealing device in the form of a valve, measuring the temperature of the STS, periodic evacuation of the IES EGS at a lower temperature of the cesium vapor source.

The disadvantage of the process is that cesium, when it was in the reactor during the tests as a result of neutron irradiation, became radioactive and contained in a thermostat, and possibly in tracts and EGS. This makes it difficult to cut the PU to extract EGS for subsequent research, as well as the disposal of PU.

The closest in terms of technical essence is the method of testing PU with thermoemission ECS [6], which includes loading the PU from the test EGS into the cell of the research reactor, evacuation of the EGS and the cesium channel, increasing the thermal power of the reactor to the operating value, heating the cesium vapor source and the cesium channel with feed Cesium vapor in the IES EGS through the heated cesium path, carrying out energy resource tests, switching off the heating of the cesium and cesium steam source, suppressing the reactor and removing the PU from the reactor cell.

However, cesium, when found in the reactor during the tests as a result of neutron irradiation, became radioactive and can be contained both in the cesium vapor source under completely normal test conditions, and in the cesium channel and even inside the EGS in abnormal test modes, for example, when the reactor is quickly shut down. This makes it difficult to cut the PU to extract EGS for subsequent studies due to the possibility of radioactive cesium entering the room. The utilization of PU is also becoming more complicated, when radioactive cesium can be found in various PU systems and even EGS.

The aim of the invention is to reduce the radiation hazard in cutting the PU to extract EGS for subsequent studies and to simplify the utilization of the PU after the tests.

The object is achieved by a loop device for testing thermionic ECS comprising a housing in which a heat-sink system is housed inside which the EGS is tested and cooled by the water of a research reactor, a cesium vapor source provided with an electric heater, a heated cesium path, Connection to the interelectrode gap of the EGS and the external system of evacuation of the reactor stand in which a container for collecting liquid cesium is mounted to the cesium channel through a controlled heated shut-off valve, a container for collecting liquid cesium, which is sealed and detachable from the housing.

And the task is solved using a test method for PU with thermionic EGS, which includes loading the PU into the cell of the research reactor, increasing the thermal power of the reactor to the operating value, heating the cesium channel to a temperature above the operating temperature of the cesium vapor source, heating the cesium vapor source to the operating value with feed Cesium vapor in the IES EGS through the heated cesium path, conducting energy tests of EGS, switching off heating of the cesium vapor source, switching off the heating of the cesium channels, muffling the reactor, removing the PU from the reactor cell, conducting post-reactor studies of the tested EGS, in which, after resource tests before switching off the heating Cesium channels and a source of cesium vapor open a controlled heated shut-off valve, increase the temperature of the cesium vapor source and cesium channels to the maximum possible value, hold until the liquid cesium disappears into the cesium vapor source, and then close the shut-off valve, seal the liquid cesium tank, And after removing the PU from the reactor cell or before carrying out post-reactor studies, disconnect the tank for collecting liquid cesium from the PU casing.

In the drawing, a structural diagram of the proposed PU for testing multi-element thermionic ECS is given.

The UE contains an outer shell 1 inside which a heated cesium vapor source 2, a heated cesium channel 3 and a STS 4 are located. Inside the STS 4, a thermoemission ECS 5 consisting of separate electrogenerating elements (EGE) 6, each containing a fuel-emitter A node 7, a manifold 8 and a commutation jumper 9. The ECS has a collector insulation 10 common to all EGEs and a cover 11 in the form of a body of EGS. The extreme EGEs have current leads 12 and 13, one of which is electrically insulated from the cover 11, extends inside the cesium channel 3, and is led out of the cesium channel 3 into the safety lumen 15 through a special seal-out terminal 14. The STS 4 has a gap 16 that can be evacuated or filled with gas , For example helium, of different pressures. The gap 16, which is placed opposite the EGS 5 and its current leads 12 and 13, can be profiled, including increased opposite to the current leads 17 and 18 of the gap 16, respectively. Outside, the STS 4 is cooled by the water of the 19 research reactor 20. To the cesium channel 3, a liquid cesium storage tank 22 is installed outside the housing 1 and cooled by the water 19 of the reactor 20 to the cesium channel 3 through a controlled heated shut-off valve 21, the container 22 being provided with a sealing device 23, for example in the form of And a device 24 for disconnecting the container 22 from the housing 1. The cesium vapor source 2, the cesium channel 3 and the controlled shut-off valve 21 are provided with electric heaters 25, 26 and 27, respectively. The PU is provided with connection devices 28 via a control valve 29 to an external vacuum system and a gas supply device 30, and also measurement and parameter monitoring systems that are not shown in the drawing.

A loop device for testing thermionic EGS operates, and the method for testing PU with thermionic EGS is realized as follows. Prior to the installation of the UE, a test EGS 5 is installed inside the STS 4, and the source of the cesium vapor 2 is filled with liquid cesium 31. After the PU is installed with the test EGS 5, the leads 12 and 13 are connected to the cells of the research reactor 20, Generated EGS power (not shown in the drawing) and connecting devices 28 and 30 to the gas evacuation and gas supply systems external to the PU, respectively, but also to all other systems: electric power supply for electric heaters 25, 26 and 27, measurements and parameter monitoring, which The drawings are not shown. Produce all necessary checks. After that, the vapor source of cesium 2, the cesium channel 3 and the interelectrode gaps 32 of the EGS 5 are evacuated through the open valve 29. The liquid-cesium tank 22 installed outside the housing 1 is evacuated with a temporarily open cut-off valve 21. A gradual increase in the thermal power of reactor 20 is made to an intermediate level. In the gaps 16, 17, 18, a gas, for example helium, is supplied through the connection device 30 at a pressure providing a desired level of temperature of the collector 8 and the STS 4. The electric heaters 26 and 27 of the cesium channel 3 and the controllable shut-off valve 21 are switched on, respectively, 3 and valve 21 above the operating temperature of the cesium vapor source 2. Close the shutoff valve 21 as well and the valve 29, thereby sealing the entire cesium cavity: the cesium vapor source 2, the cesium path 3 and the interelectrode gaps 32 of the ECG 5. Then, using the electric heater 25 Gradually increase the temperature of the source of cesium vapor 2 to the operating value, usually up to 310-360 ° C. As a result of heating of cesium 31 in the source of cesium vapor in MEZ 32, cesium vapor enters at a pressure whose saturation temperature is equal to the temperature of liquid cesium 31. When uranium nuclei are fissioned in the fuel-emitting unit 7, it heats and in the presence of cesium vapor in MEZ 32, each element , Consisting of the fuel-emitting unit 7, the MEZ 32, the collector 8, the commutation bridge 9, generates electric power which is summed in the EGS 5 and measured via the current leads 12 and 13 on the external load relative to the PU (not shown in the drawing). The heat energy not converted in the MEZ 32 in the thermodynamic cycle through the collector 8, the collector insulation 10 and the case - the body EGS-11 - is discharged to the water of the 19 research reactor 20. The thermal power of the reactor rises to the nominal value at which the energy tests of the EGS are performed. The next step of the test reduces the thermal power of the research reactor 20 to an intermediate value, the electric heater 25 of the cesium vapor source 2 is turned off, an exposure is held to collect the cesium vapor from the MEZ 32 and the cesium channel 3 into the cesium vapor source 2. Then the reactor is silenced, for example, Or scheduled maintenance. Then, the reactor power is again raised and the next stage of testing is carried out in the same way as described above. After the completion of all stages of reactor tests, the UE must be removed from the reactor 20 and, after some holding for activity decay, sent to the so-called "cutting", i.e. Cutting the PU into parts and extracting the tested EGS 5 for post-reactor studies in so-called "hot" chambers. After that, the cut sections of the PU must be disposed of. However, the presence of cesium, which in long tests has acquired a sufficiently high activity, at the source of the cesium vapor 2 makes it extremely difficult to cut both the PU and subsequent disposal due to the possibility of radiation contamination of equipment and premises. Therefore, before cutting the PU, it is desirable to collect all the radioactive cesium in a special small ampoule and dispose of it in accordance with the existing rules. For this, after the reactor 20 has been reduced to an intermediate value, with the valve 29 closed, a controllable heated shut-off valve 21 is opened. Open and, if it was closed, and a sealing device 23, for example in the form of a control valve, mounted outside the housing 1 and water-cooled 19 of the research reactor 20 of the reservoir 22 for collecting liquid cesium. After depressurization, the ampoules 22 increase the power of the electric heaters 25, 26 and 27 to the maximum permissible value and in this mode produce an exposure. During the soaking, the liquid cesium 31 in the cesium vapor source 2 will evaporate and condense at the coldest point of the closed volume, i. E. In the water-cooled 19 ampoule 22. In case, for any reason, for example, when the heaters 26 fail, the liquid cesium could be in the cesium channel 3 ("false" thermostat), then it will evaporate and condense in ampoule 22. This Is due to the fact that, with the reactor 20 operating, due to the gamma heating of the construction materials, the temperature of the inner walls of the cesium path, even with the electric heaters 26 turned off, will always be above the temperature of the ampoule 22, approximately equal to the temperature of the cooling water, usually 40-60 ° C. During exposure by known methods, for example, by changing the temperature fields, the fact of the liquid cesium 31 disappearance from the cesium vapor source 2 is recorded, and, in the case of supernumerary regimes, and from the cesium channel 3. When the liquid cesium is only in the source of the cesium vapor 2, the holding time can be tens of minutes, in non-standard modes (the presence of a "false" thermostat) - hours or even tens of hours. After the registration of the disappearance of liquid cesium 31 in the cesium vapor source 2, and in the case of supernumerary conditions and in the cesium channel 3, the heated shut-off valve 21 is closed and by means of the device 23, for example in the form of a controlled valve, the ampoule 22 with the collected liquid radioactive cesium is sealed. After that, lower the reactor power to zero and turn off the electric heaters. After a short exposure of the PU in the muffled reactor, disconnection from the PU of external vacuum systems, filling with gas, power supply, measuring lines is performed. The remote unloading of the UE from the reactor 20 is then carried out remotely from the reactor 20. After unloading the PU from the reactor or after holding the PU to remove the EGS by means of the device 24, the container 22 with the collected radioactive cesium from the body 1 is sealed with the aid of the device 23 and sent for disposal. As a result, the PU is ready for safe cutting and extraction of the tested EGS for subsequent post-reactor studies in "hot" chambers. After that, the cut PU parts that do not contain radioactive cesium are safely and easily disposed of by conventional methods. Thus, the proposed inventions allow to reduce the radiation hazard when cutting the PU after reactor tests to extract the tested EGS for subsequent studies and to simplify the utilization of the PU after the tests.

USED ​​BOOKS

1. VVSinyavsky and others. Designing and testing of thermionic fuel elements. Moscow: Atomizdat, 1981.

2. V.V. Sinyavsky. Methods and means of experimental research and reactor testing of thermionic emission assemblies. Moscow: Energoatomizdat, 2000, p. 209-212.

3. The patent of the Russian Federation No. 2070751 is a prototype.

4. V.V. Sinyavsky. Methods for determining the characteristics of thermionic fuel elements. Moscow: Energoatomizdat, 1990, p. 6-9.

5. The patent of the Russian Federation №2127466.

6. Patent of the Russian Federation No. 2333518.

CLAIM

1. A loop device for testing a thermionic power generating assembly, comprising: a housing in which a heat-sink system is arranged to house a test thermionic power generating assembly inside it and externally cooled by the water of a research reactor, equipped with electric heaters, a cesium vapor source and a cesium path, Interelectrode gap of the thermionic power generating assembly and to the reactor stand evacuation system, characterized in that a container for collecting liquid cesium is installed to the cesium channel through a controlled heated shut-off valve, a container for collecting liquid cesium, mounted outside the housing and cooled by the water of the research reactor, the container being sealed and disconnected from the housing.

2. A method for testing a loop device with a thermionic power generating assembly, including loading a loop device into the cell of a research reactor, increasing the reactor's thermal power to an operating value, heating the cesium vapor source and cesium channels, conducting energy-resource tests, switching off the heating of a cesium vapor source and cesium channels, Damping of the reactor and removal of the loop device from the reactor cell, characterized in that, after the resource tests, before the heating of the cesium vapor source and the cesium channels is switched off, the controlled heated shut-off valve is opened, the temperature of the cesium vapor source and the cesium channels is raised to the maximum possible value, Liquid cesium in a cesium vapor source, after which the controlled heated shut-off valve is closed, and after removing the loop device from the reactor cell, a container for collecting liquid cesium is sealed and disconnected from the body of the loop device.

print version
Date of publication 05.04.2007gg

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