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This web page is intended for individuals who know little or nothing about Fast Neutron Reactors (FNRs). To assist the reader, at the end of this web page is an introductory Glossary of Terms.
Fissile atomic isotopes such as U-233, U-235 and Pu-239 have the interesting property that when they capture a free neutron they usually fission. During each atomic fission, in addition to fission products, an atom emits about 200 MeV of thermal energy and two to four free neutrons, each with a kinetic energy of about 2 MeV. Thse are known as fast neutrons. Fast neutrons have desirable properties in terms of recycling of nuclear fuels.
Atomic fission becomes remarkable when there is a sufficient concentration of fissile atoms in close proximity to one another. Then neutrons emitted by one fissile atom can be captured by other nearby fissile atoms. Then the number of free neutrons N within the assembly of atoms will exponentially change over time in accordance with the formula:
N = No exp[k(t- to)] where:
No = number of free neutrons in the assembly at time t = to;
k = a material geometry dependent parameter that can be either positive or negative. The parameter k is known as the assembly reactivity.
At any instant in time the fission thermal power (heat per unit time) emitted by the assembly is proportional to N.
Note that if k > 0 the thermal power rapidly increases, if k < 0 the thermal power rapidly decreases and if k = 0 the thermal power remains constant.
Thus power reactors are designed such that in normal operation:
k ~ 0.
If the the assembly of atoms is shaped like a thin disk the outside surface area of the assembly is large compared to its volume, so most of the emitted neutrons escape from the assembly without being captured by other atoms, making k less than zero, which causes N to decrease over time.
If the assembly of atoms is shaped like a sphere, which has a relatively small outside surface area as compared to its volume, then k can be greater than zero, which causes N to rapidly increase over time. That situation is known as a rapid chain reaction.
If the fissile atoms are distributed like two parallel flat pancakes, then slowly bringing the two pancakes closer together makes their net behaviour change from being like two separate disks to being like one single sphere. That is, there is a distance between the two pancakes at which k = 0.
We can build such an assembly at room temperature and immerse it in a pool of liquid sodium. Then at time:
t = to
we can move the two solid fissile fuel pancakes slightly closer together which reduces their combined ratio of outside surface area to volume. As a result k becomes slightly greater than zero and the number of free neutrons increases causing a brief large increase in N and hence in the thermal power emitted by fission reactions. This thermal power heats the solid fissile fuel causing it to thermally expand, so that the fissile atoms move further apart. In effect the ratio of surface area to volume of the assembly of fissile atoms increases with increasing temperature which reduces k back to below zero. This reduction in k stops the nuclear fission and hence the heat output. However now the fissile atoms are hotter than they were at time:
t = to
We can gradually decrease the distance between the two fissile fuel pancakes until their temperature rises to about 460 degrees C. At that point we have a created a practical Fast Neutron Reactor (FNR). We can harvest its thermal energy output by extracting heat from the highly thermally conductive liquid sodium pool.
A FNR is simply a pool of primary liquid sodium, comparable in size to a large swimming pool, which contains fully immersed bundles of sealed vertical, half inch diameter, thin wall chrome-steel fuel tubes. Inside the fuel tubes are metallic fuel rods formed from uranium-zirconium and uranium-plutonium-zirconium alloys. A small amount of liquid sodium fills the narrow gap between the outside surface of the metallic fuel rods and the inside wall of the chrome-steel fuel tubes, providing a good thermal connection between the fuel rods and the steel. Inside the fuel tubes, above the top of the fuel rods, is a gas space known as the fuel tube plenum.
The geometry of the fuel assembly enables a passive nuclear process which keeps the liquid sodium pool top surface at a nearly constant temperature. During normal FNR operation that temperature is typically set at 460 degrees C. The exposed top surface of the primary sodium pool is almost entirely covered by 5.0 inch to 5.25 inch (127 mm to 133 mm) diameter floating hollow stainless steel spheres which reduce the exposed liquid sodium surface area and assist in air exclusion during primary sodium fire suppression.
The thermal power rating of a FNR is the rate at which heat can be safely withdrawn from the liquid sodium pool by immersed heat exchange bundles located adjacent to the pool walls. Since the sodium is heated by thermal conduction through the fuel tube walls the maximum thermal power rating of a FNR is limited by the total active fuel rod length and by the maximum allowable temperature difference between the fuel rod centerline and the primary liquid sodium coolant.
FNR NUCLEAR POWER PLANT (NPP) FACILITY:
This web page titled: FNR Facility briefly describes the appearance of a FNR based nuclear power plant (NPP) that can be safely located in the middle of a population center of about 100,000 people to provide up to 300 MWe of electricity and up to 700 MWt of low grade district heat.
Not including the perimeter roads the FNR NPP above grade structures fully occupy one city block (a space 114 m X 114 m). The NPP footprint consists of a 49 m X 49 m central structure with a central steel dome roof separated by laneways from 12 surrounding structures. The above grade structure heights vary from 20 m to 50 m.
The primary sodium pool is centrally located, mostly below grade, in the central nuclear structure. Normally there is no personnel access to the primary sodium pool space because it is very hot, there is gamma radiation and there is no oxygen to breath. However, one can view the top of the primary sodium pool of an operating FNR either through a thick window or via a video camera.
When the FNR is off and has cooled down to about 120 degrees C equipment can be transferred in and out of the primary sodium pool space via four truck dock level airlocks.
In the primary sodium pool space there is a circular pool, 20 m in diameter, in the middle of an octagonal room which is 25 m face to face. The liquid sodium surface is about 1 m below the pool deck and the ceiling is about 14.5 m above the pool deck. The pool contains liquid sodium, which is a low density metal that melts just below the boiling point of water. The liquid sodium is 15 m deep.
In the middle of the primary sodium pool there is a 12.6 m diameter array of 464 vertical indicator tubes which, during normal reactor operation, project about 0.9 m above the primary sodium surface. These indicator tubes show the actual elevations of the reactor's movable fuel bundles and also provide gamma ray intensity and temperature data to an overhead monitoring system that is used to monitor the FNR operation.
Close examination of the primary sodium pool surface reveals a slight ripple because, when the reactor is producing power, natural circulation causes liquid sodium to rise in the center of the pool and to sink near the pool walls.
If the overhead lighting is extinguished one may sense a faint near infrared glow, because normally the exposed surface of the pool and the pool enclosure are at about 460 degrees C.
There are 96 horizontal radial pipes which cross over the pool deck and then dip down into the pool. These pipes contain a sodium-potassium alloy (NaK) which conveys heat captured by immersed intermediate heat exchange bundles to NaK-salt heat exchangers located outside the reactor space, in heat exchange galleries located around the upper perimeter of the nuclear building.
Other pipes containing hot molten nitrate salt convey heat from the NaK-salt heat exchangers to electricity generation equipment in nearby buildings (turbogenerator halls). That equipment converts about 30% of the transported heat into electricity and rejects the balance of the transported heat to district heating pipes. Note that both the nitrate salt pipes and the NaK pipes are mounted so that they can thermally expand and contract without causing significant material stress.
Just above the pool deck level are four radial trays that are used, in combination with an overhead polar gantry crane, to move fuel bundles and other equipment in and out of the reactor space. The trays point to air locks that are concealed behind removable sections of the insulated side walls.
The reactor building is very quiet. In most industrial installations there is a lot of background noise. However, in the FNR central nuclear building there are few mechanical moving parts. Within this building liquids move by natural circulation, by smooth induction pumping or by differential gas pressure.
If you listen carefully you may hear fan or blower noise from the ventilation system. The sodium pool and the various radial pipes are hot. In spite of good thermal insulation part of that heat leaks through the enclosure walls, so to keep the human occupied perimeter spaces comfortable forced air ventilation with closed circuit cooling is used.
In simple language the FNR passively supplies nuclear heat at a variable the rate up to 1000 MWt. Near the primary sodium pool perimeter heat is extracted from 460 degree C surface sodium by cooler pumped NaK flowing through intermediate heat exchange bundles. This heat extraction increases the density of the cooled adjacent primary sodium causing it to sink. This cooler sodium sinking establishes a natural circulation flow pattern in the primary sodium pool where the primary sodium sinks near the pool perimeter and rises near the pool center. As a result of this natural circulation the temperature at the pool bottom center can fall to as low as 410 degrees C. The rate of heat generation by the nuclear process is proportional to the temperature difference between the pool bottom and the pool surface and to the primary sodium natural circulation flow rate.
In principle the faster that the pumped NaK removes heat from the primary sodium the more electric power can be generated.
If the NaK flow stops the cooling of the primary sodium stops. Hence the primary sodium natural circulation flow stops which causes the heat production process to stop.
The design maximum power capacity of the FNR NPP is 300 MWe electrical, 700 MWt low grade thermal or 1000 MWt high grade thermal. In practical application during the summer most of the low grade heat rejected by electricity generation is discarded by cooling towers. However, in the winter up to 700 MWt of low grade heat are available for comfort heating. Generally this low grade heat should be used as a heat source for high COP water source heat pumps.
Note that the FNR primary sodium discharge temperature is fixed at 460 degees C and the FNR thermal power output increases with increasing NaK flow. Variable speed induction pumps control the NaK flow rate. The heat transport system design prevents the primary sodium pool bottom temperature falling below 410 degrees C. This thermal power constraint limits the maximum heat flux through the FNR fuel tubes, which prevents metallic nuclear fuel center line melting and protects the fuel tubes from excessive heat flux.
A FNR has the virtue of rugged simplicity. However, a lot of work has gone into designing the FNR to safely tolerate both peripheral equipment failures and extreme events such as earthquakes, tsunamis, hurricanes, airplane impacts and terrorist attacks.
A practical FNR must be maintainable. Eventually the nuclear fuel will be consumed and it will be necessary to reconfigure and/or recycle the nuclear fuel. If air leaks into the reactor space over time the oxygen and water vapor in the air will react with the liquid sodium forming a sludge that must be filtered out of the liquid sodium.
Changes in thermal load cause thermal expansion and contraction of the NaK pipes, nitrate salt pipes and heat exchange bundles which cause long term wear. Internal pipe scouring causes further long term wear, eventually leading to equipment repair or replacement. Any suspended particulates in the heat transport fluids will aggravate long term scouring of the insides of pipes, fittings and heat exchange bundles. Hence, in spite of the apparent equipment simplicity, there are important ongoing maintenance considerations related to fluid cleanliness.
Note that there are 48 heat transport circuits, so various combinations of them can be shut down for service without impacting the performance of the remainder.
Most of the system maintenance is non-nuclear in nature and is related to the heat transport system, steam turbines, condensers, cooling towers, electricity generators, cooling water pumps and other non-nuclear electrical and mechanical equipment.
Normally the FNR can operate for months with minimal maintenance attention. The reactor power can be remotely adjusted by changing the induction pump set NaK flow rate. If anything in a heat transport circuit fails the simple solution is to turn that heat transport circuit off and drain its fluids to its dump tanks until such time as competent maintenance personnel can attend to the problem. There is sufficient equipment redundancy to permit the FNR NPP to continue operation at reduced power with some of its heat transport circuits and some of its turbogenerators out of service.
The primary liquid sodium pool operates at atmospheric pressure with argon cover gas. Unlike water cooled reactors there is nothing to blow up. This reactor will passively default to its setpoint temperature. The main concern is fire prevention by continuous exclusion of both air and water from the reactor primary sodium pool space.
INTRODUCTORY GLOSSARY OF TERMS:
FNR: Fast Neutron Reactor;
NPP Nuclear Power Plant;
Fission: Breakup of an atomic nucleus;
Fissile Fuels: Materials that readily liberate nuclear energy via neutron capture induced fission;
Fission Thermal Power: Rate of heat generation by a nuclear reactor;
Reactivity k: A mathematical parameter which indicates the rate of change of fission thermal power;
Power Reactor: A nuclear reactor intended for providing a large flow of electricity and/or heat to a public utility;
Sodium: A highly thermally conductive metal that melts at 98 degrees C, below the atmospheric pressure boiling point of water;
Primary Sodium Pool: A pool of liquid sodium about 20 m in diameter X 15 m deep which captures both the heat and radiation emitted by centrally contained nuclear fuel;
Indicator Tubes: Vertical metal tubes, 5.25 inch diameter, which project above the surface of the liquid sodium to transmit reactor status information to overhead electronic monitoring equipment;
Hollow Stainless Steel Spheres: Buoyant 5 inch diameter stainless steel balls that float on the surface of the liquid sodium to reduce its exposed surface area;
NaK: An alloy of the metals sodium and potassium that is liquid at a low pressure from room temperature up to over 700 degrees C;
Intermediate heat exchange bundle: A device which transfers heat from the hot liquid sodium to slightly cooler but fully isolated NaK;
Induction Pump: A non-contact pump type used for safe circulation of NaK. This sealed pump type operates by electromagnetically inducing a circulating current in the NaK which current magnetically interacts with an externally applied magnetic field;
Molten Nitrate Salt: A liquid used to safely transfer heat from low pressure NaK to the high pressure steam and water used for generation of electricity;
1000 MWt: One thousand million watts thermal (sufficient energy per unit time to meet all the power requirements of about 100,000 North American people)
This web page last updated August 6, 2022
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