GB2509587A - Radioisotope nuclear generator - Google Patents
Radioisotope nuclear generator Download PDFInfo
- Publication number
- GB2509587A GB2509587A GB1319611.8A GB201319611A GB2509587A GB 2509587 A GB2509587 A GB 2509587A GB 201319611 A GB201319611 A GB 201319611A GB 2509587 A GB2509587 A GB 2509587A
- Authority
- GB
- United Kingdom
- Prior art keywords
- heat
- vessel
- generator
- thermal energy
- heat sink
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Withdrawn
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21H—OBTAINING ENERGY FROM RADIOACTIVE SOURCES; APPLICATIONS OF RADIATION FROM RADIOACTIVE SOURCES, NOT OTHERWISE PROVIDED FOR; UTILISING COSMIC RADIATION
- G21H1/00—Arrangements for obtaining electrical energy from radioactive sources, e.g. from radioactive isotopes, nuclear or atomic batteries
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21H—OBTAINING ENERGY FROM RADIOACTIVE SOURCES; APPLICATIONS OF RADIATION FROM RADIOACTIVE SOURCES, NOT OTHERWISE PROVIDED FOR; UTILISING COSMIC RADIATION
- G21H1/00—Arrangements for obtaining electrical energy from radioactive sources, e.g. from radioactive isotopes, nuclear or atomic batteries
- G21H1/10—Cells in which radiation heats a thermoelectric junction or a thermionic converter
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B64—AIRCRAFT; AVIATION; COSMONAUTICS
- B64G—COSMONAUTICS; VEHICLES OR EQUIPMENT THEREFOR
- B64G1/00—Cosmonautic vehicles
- B64G1/22—Parts of, or equipment specially adapted for fitting in or to, cosmonautic vehicles
- B64G1/42—Arrangements or adaptations of power supply systems
- B64G1/421—Non-solar power generation
- B64G1/422—Nuclear power generation
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B64—AIRCRAFT; AVIATION; COSMONAUTICS
- B64G—COSMONAUTICS; VEHICLES OR EQUIPMENT THEREFOR
- B64G1/00—Cosmonautic vehicles
- B64G1/22—Parts of, or equipment specially adapted for fitting in or to, cosmonautic vehicles
- B64G1/46—Arrangements or adaptations of devices for control of environment or living conditions
- B64G1/50—Arrangements or adaptations of devices for control of environment or living conditions for temperature control
- B64G1/503—Radiator panels
-
- B—PERFORMING OPERATIONS; TRANSPORTING
- B64—AIRCRAFT; AVIATION; COSMONAUTICS
- B64G—COSMONAUTICS; VEHICLES OR EQUIPMENT THEREFOR
- B64G1/00—Cosmonautic vehicles
- B64G1/22—Parts of, or equipment specially adapted for fitting in or to, cosmonautic vehicles
- B64G1/46—Arrangements or adaptations of devices for control of environment or living conditions
- B64G1/50—Arrangements or adaptations of devices for control of environment or living conditions for temperature control
- B64G1/506—Heat pipes
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
- G21C15/257—Promoting flow of the coolant using heat-pipes
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21H—OBTAINING ENERGY FROM RADIOACTIVE SOURCES; APPLICATIONS OF RADIATION FROM RADIOACTIVE SOURCES, NOT OTHERWISE PROVIDED FOR; UTILISING COSMIC RADIATION
- G21H3/00—Arrangements for direct conversion of radiation energy from radioactive sources into forms of energy other than electric energy, e.g. into light or mechanic energy
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
- Remote Sensing (AREA)
- Aviation & Aerospace Engineering (AREA)
- Life Sciences & Earth Sciences (AREA)
- Sustainable Development (AREA)
- Health & Medical Sciences (AREA)
- Biodiversity & Conservation Biology (AREA)
- Environmental & Geological Engineering (AREA)
- Environmental Sciences (AREA)
- General Health & Medical Sciences (AREA)
- Toxicology (AREA)
- Plasma & Fusion (AREA)
- Cooling Or The Like Of Electrical Apparatus (AREA)
Abstract
A nuclear generator 10 comprises: a heat source formed of a radioisotopic source 11; a heat sink; a thermal energy converter 12 arranged between said heat source and said heat sink so that a heat flux passes through the thermal energy converter; a vessel 16 in which are laid out the thermal energy converter 12 and the heat source; said vessel 16 being in contact with the heat sink; the generator being characterised in that the heat sink comprises at least one plate cooling fin 21 having an internal structure forming at least one diphasic network (see figure 2) enabling the evaporation, the circulation and the condensation of a working fluid. The generator is preferably used in satellites.
Description
Radioisotope nuclear generator
TECHNICAL FIELD
The present invention relates to a radioisotope nuclear generator used in
s particular in the space field.
PRIOR ART
During space missions, it is necessary to be able to produce in an autonomous manner electrical energy so as to supply the different on-board instruments, but also other types of energy such as mechanical energy.
During certain space missions, the solar power received by the space vehicle is too weak to be able to provide the necessary energy via solar panels.
In such situations, it is preferable to use nuclear electric generators to supply with electricity the space vehicle in a continuous manner over several years without direct maintenance.
Conventionally, a nuclear electric generator comprises a heat source formed of a radioisotope source in which the heat produced results from the radioactive disintegration of materials rich in one or more radioisotopes. The heat produced is converted into electricity by means of a thermal energy converter into electrical energy.
The conversion of thermal energy into electrical energy is achieved via a heat flux passing through the converter flowing between a heat source and a heat sink (forming the "cold source") situated on either side of the converter.
The conversion efficiency of the thermal energy is directly linked to the temperature difference between the hot temperature of the heat source and the cold temperature of the heat sink, which is why it is necessary to have available a cold temperature as low as possible in order to obtain the best possible efficiency.
In space, the only option of heat sink is radiation into space. To do this, it is known to use finned radiators which make it possible to evacuate the heat not used during the conversion, by radiation into space or instead by the circulation of a fluid by means of a loop and a pumping system.
However, finned radiators have an efficiency that is limited by the conductivity of the material used (generally based on aluminium or beryllium).
Consequently the thermal resistivity of the material does not make it possible to lower significantly the temperature of these radiators even if the size of the radiating surface of the fins is increased. This solution has in addition the drawback of increasing the weight and the size of such a system.
S The use of a cooling loop imposes the use of a cooling circuit, a pump, a regulation circuit, etc., and finally a radiator, which results in an increase in weight and a reduction in the reliability over time of the system for cooling the heat sink.
In this context, the invention aims to propose a nuclear generator comprising a cooling system of a thermal energy converter making it possible to lower significantly the temperature of the heat sink of the converter so as to increase the conversion efficiency.
DESCRIPTION OF THE INVENTION
To this end, the subject matter of the invention is a nuclear generator comprising: * a heat source formed of a radioisotope source; * a heat sink; * a thermal energy converter arranged between said heat source and said heat sink so that a heat flux passes through the thermal energy converter; * a vessel in which are laid out the thermal energy converter and the heat source; said vessel being in contact with the heat sink; the generator being characterised in that the heat sink comprises at least one plate cooling fin having an internal structure forming at least one diphasic network enabling the evaporation, the circulation and the condensation of a working fluid.
The internal structure of the fin forming at least one diphasic network of heat pipe type inside a cooling fin makes it possible to increase significantly the thermal conductivity of the fin. In fact, the heat pipe structure of the cooling fin is going to enable a better homogenisation of the temperature at the surface of the fin, consequently improving its radiation capacity over the whole length of the fin, including at its end.
Thus, thanks to the invention, an increase in the radiating surface of the fin becomes necessary since the temperature of the fin will be substantially homogenous (within a few degrees) over its whole length. Thus, unlike cooling means of the prior art, the increase of the radiating surface of the fin makes it possible to reduce significantly the temperature of the heat sink, and consequently makes it possible to improve the efficiency of the thermal energy converter.
The specific plate form of the cooling fins makes it possible to guarantee the maximum radiating surface while minimising the size of the cooling means.
As a reminder, heat pipes are means that are based on the physical principle of a thermodynamic cycle (condensation-evaporation) in closed loop of a fluid at saturation in a closed vessel with heat exchanges by change of phase.
The heat pipes make it possible to obtain low temperature gradients over the length of heat pipe compared to the exchanged thermal powers.
The system according to the invention may also have one or more of the characteristics below, considered individually or according to any technically possible combinations thereof: -said at least one diphasic network enabling the evaporation, the circulation and the condensation of a working fluid is a heat pipe; -said heat pipe is a capillarity heat pipe; -said at least one cooling fin is integral with said vessel; -said at least one plate cooling fin has an internal structure torming a network of heat pipes; -the heat sink comprises a plurality of cooling fins, the internal structure of which forms at least one diphasic network enabling the evaporation, the circulation and the condensation of a working fluid; -said vessel is in contact with the heat sink through at least one wall of said vessel, said wall having an internal structure forming a diphasic network enabling the evaporation, the circulation and the condensation of a working fluid; -said vessel comprises a thermally insulating material surrounding said radioisotope heat source and said thermal energy converter; -said thermal energy converter is a thermoelectric converter or a thermomechanical converter or a thermoacoustic converter.
The invention also relates to a satellite comprising a nuclear generator according to the invention.
BRIEF DESCRIPTION OF DRAWINGS
Other characteristics and advantages of the invention will become clear from the description that is given thereof below, by way of indication and in no s way limiting, with reference to the following figures: Figure 1 illustrates a schematic view of a nuclear generator according to the invention.
Figure 2 illustrates a schematic view of the internal structure of a cooling fin of the nuclear generator illustrated in figure 1.
DETAILED DESCRIPTION OF AT LEAST ONE EMBODIMENT
With reference to figure 1, the nuclear generator 10 is a nuclear electric generator with radioisotopic source.
The nuclear generator 10 comprises: -a vessel 16 in which are laid out a radioisotope source 11 forming a heat source in which the heat produced results from the radioactive disintegration of materials rich in one or more radioisotope and a thermal energy converter 12 able to transform the heat into electrical energy; -cooling means 20 formed of at least one cooling fin 21 forming a heat sink.
In the embodiment example illustrated in figure 1, several cooling fins 21 are formed; nevertheless the invention is also applicable with a single cooling fin.
The cooling fins 21 are integral with the wall 14 of the vessel 16.
Advantageously, the wall 14 of the vessel 10 is a metal wall such that it participates with the fins 21 in the cooling of the nuclear electric generator 10.
The cooling fins 21 may be joined to the surface of the wall 14 or instead partially built into the wall 14 so as to improve the robustness of the assembly.
The thermal energy converter 12 is arranged between the radioisotopic source 11 (heat source) and the wall 14 of the vessel 16 forming, with the cooling fins 21, the heat sink. In this way, a heat flux, symbolised by the reference 15, passes through the thermal energy converter 12.
The heat flux is concentrated and directed to the thermal energy converter 12 by the use of an insulating material 13 with low thermal conductivity inside the vessel 10 and around the radioisotope source and the thermal energy converter 12.
The cooling fins 21 make it possible to evacuate the heat not transformed into space by radiation.
The cooling fins 21 form plates with a lower height than the length and the width. As an example, the plate cooling tins 21 have a thickness of the order of a millimetre for a length dependent on the power of the generator and the targeted cold temperature, the order of magnitude of which is ten or so centimetres in width as well as in height.
The cooling fins 21 have a structure making it possible to form at least one diphasic network enabling the evaporation, the circulation and the condensation of a working fluid of heat pipe type inside the fin 21. Thus, the plate forming the tin forms the external covering of the heat pipe which is etched directly in the plate.
According to an embodiment variant of the invention, each cooling fin 21 has a network of heat pipes, which may be arranged in a parallel manner.
The cooling fins 21 are for example made of thermally conductive material such as aluminium for example. Figure 2 illustrates more particularly the internal structure of a cooling fin 21 forming a heat pipe.
The heat pipe operates on the principle of transfers by latent heat thanks to a fluid at saturation 22 enclosed in the fin 21. The fluid at saturation 22 is in equilibrium between the liquid phase and the steam phase and serves as means of transport of the heat between the hot zone of the heat pipe ZE and the cold zone of the heat pipe ZC.
The hot zone ZE of the heat pipe, known as evaporation zone, is a very reduced zone situated at the end of the fin 21 which is in contact with the wall 14 of the vessel 16. The cold zone ZC, known as condensation zone, is a very extended zone covering at least 2/3 of the surface of the fin 21.
Thus, the heat received by the liquid 22 at the evaporation zone ZE makes it change phase (passage from the liquid phase to the steam phase), the steam thereby created moves in a central channel 23 up to the condensation zone ZC, where it condenses. The operation in closed loop is assured by the return of the liquid 22 from the condensation zone ZC to the evaporation zone ZE by capillarity, through a capillary structure 24 situated at the periphery of the channel 23 and extended over the length of the fin 21.
Thus, the heat pipe structure of the cooling fin 21 enables a better homogenisation of the temperature at the surface of the fin 21, consequently improving its radiation capacity over the whole length and the width of the fin, including at its free end.
Advantageously, the internal structure of the fin 21 has a network of heat pipes so as to improve the evacuation of heat and to reduce the temperature of the fin forming the heat sink of the thermal energy converter 12.
The working fluid depends on the targeted cold temperature. It may be water or methanol or another fluid.
According to an embodiment variant, the wall 14 on which the fins 21 are fixed may also have an internal structure forming a heat pipe or a network of heat pipes.
The invention has been particularly described with a plurality of cooling fins arranged on a single wall 14 of the vessel 10. It is obvious that each wall of the vessel may have one or a plurality of cooling fins according to the invention so as to optimise the evacuation of heat as a function of the design of the generator, its power, the type of thermal energy converter and other parameters.
The invention has been particularly described with a thermoelectric converter, nevertheless, it is obvious that the invention is also applicable with a thermoacoustic converter, a thermomechanical converter.
Claims (12)
- CLAIMS1. Nuclear generator (10) comprising: S * a heat source formed of a radioisotope source (11); * a heat sink; * a thermal energy converter (12) arranged between said heat source and said heat sink so that a heat flux passes through the thermal energy converter; * a vessel (16) in which are laid out the thermal energy converter (12) and the heat source (11); said vessel (16) being in contact with the heat sink; the generator being characterised in that the heat sink comprises at least one plate cooling fin (21) having an internal structure forming at least one diphasic network enabling the evaporation, the circulation and the condensation of a working fluid.
- 2. Nuclear generator (10) according to the preceding claim characterised in that said at least one diphasic network enabling the evaporation, the circulation and the condensation of a working fluid is a heat pipe.
- 3. Nuclear generator (10) according to the preceding claim characterised in that said heat pipe is a capillarity heat pipe.
- 4. Nuclear generator (10) according to one of the preceding claims characterised in that said at least one cooling fin (21) is integral with said vessel (16).
- 5. Nuclear generator (10) according to one of the preceding claims characterised in that said at least one plate cooling fin (21) has an internal structure forming a network of heat pipes.
- 6. Nuclear generator (10) according to one of the preceding claims characterised in that the heat sink comprises a plurality of cooling fins (21). the internal structure of which forms at least one diphasic network enabling the evaporation, the circulation and the condensation of a
- 7. Nuclear generator(10) according to one of the preceding claims characterised in that said vessel (16) is in contact with the heat sink through at least one wall (14) of said vessel (16), said wall (14) having an internal structure forming a diphasic network enabling the evaporation, the circulation and the condensation of a working fluid.
- 8. Nuclear generator (10) according to one of the preceding claims characterised in that said vessel (16) comprises a thermally insulating material surrounding said radioisotope heat source and said thermal energy converter.
- 9. Nuclear generator (10) according to one of the preceding claims characterised in that said thermal energy converter is a thermoelectric converter or a thermomechanical converter or a thermoacoustic converter.
- 10. Satellite characterised in that it comprises a nuclear generator (10) according to one of claims 1 to 9.
- 11. Nuclear generator substantially as described with reference to the accompanying drawings.
- 12. Satellite substantially as described with reference to the accompnaying drawings.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR1260563A FR2997787B1 (en) | 2012-11-07 | 2012-11-07 | RADIOISOTOPE NUCLEAR GENERATOR |
Publications (2)
Publication Number | Publication Date |
---|---|
GB201319611D0 GB201319611D0 (en) | 2013-12-18 |
GB2509587A true GB2509587A (en) | 2014-07-09 |
Family
ID=48128393
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB1319611.8A Withdrawn GB2509587A (en) | 2012-11-07 | 2013-11-06 | Radioisotope nuclear generator |
Country Status (2)
Country | Link |
---|---|
FR (1) | FR2997787B1 (en) |
GB (1) | GB2509587A (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2019079137A1 (en) * | 2017-10-16 | 2019-04-25 | Pacific Scientific Energetic Materials Company | Satellite management system comprising a propulsion system having individually selectable motors |
Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3490718A (en) * | 1967-02-01 | 1970-01-20 | Nasa | Capillary radiator |
US5069274A (en) * | 1989-12-22 | 1991-12-03 | Grumman Aerospace Corporation | Spacecraft radiator system |
UA65039A (en) * | 2003-05-14 | 2004-03-15 | Nat Tech Univ Kyiv Polytech | System for passive removal of heat from the production rooms of a nuclear power plant |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3457436A (en) * | 1966-11-07 | 1969-07-22 | Teledyne Inc | Heat pipes with unique radiator configuration in combination with thermoionic converters |
-
2012
- 2012-11-07 FR FR1260563A patent/FR2997787B1/en not_active Expired - Fee Related
-
2013
- 2013-11-06 GB GB1319611.8A patent/GB2509587A/en not_active Withdrawn
Patent Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3490718A (en) * | 1967-02-01 | 1970-01-20 | Nasa | Capillary radiator |
US5069274A (en) * | 1989-12-22 | 1991-12-03 | Grumman Aerospace Corporation | Spacecraft radiator system |
UA65039A (en) * | 2003-05-14 | 2004-03-15 | Nat Tech Univ Kyiv Polytech | System for passive removal of heat from the production rooms of a nuclear power plant |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2019079137A1 (en) * | 2017-10-16 | 2019-04-25 | Pacific Scientific Energetic Materials Company | Satellite management system comprising a propulsion system having individually selectable motors |
Also Published As
Publication number | Publication date |
---|---|
GB201319611D0 (en) | 2013-12-18 |
FR2997787A1 (en) | 2014-05-09 |
FR2997787B1 (en) | 2014-11-21 |
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Legal Events
Date | Code | Title | Description |
---|---|---|---|
WAP | Application withdrawn, taken to be withdrawn or refused ** after publication under section 16(1) |