KR101922967B1 - Module reactor - Google Patents

Abstract

The present invention relates to a small or micro module nuclear power plant. In the module nuclear power plant of the present invention, a circulating fluid heated by a reactor is cooled and compressed through a turbine, a heat exchanger, and an isothermal compressor, Circulating the circulating fluid from the isothermal compressor cooled and compressed by the heat exchanger having the isothermal compressor to the reactor through the recuperator to form an isothermal-Breton cycle, wherein the isothermal compressor performs an isentropic compression process and an isobaric cooling process To increase the overall isothermal-Breton cycle efficiency through multi-stage compression, which is repeated several times.

Description

Module reactor

[0001] The present invention relates to a module nuclear power plant, and more particularly, to a small or micro module using a supercritical fluid such as supercritical carbon dioxide (S-CO ₂ ) as a circulating fluid of a core coolant and a power generation cycle. It is about the nuclear power plant.

Conventional nuclear power generation transfers heat energy of a coolant such as water heated by a reactor to a fluid used in a power generation cycle through a heat exchanger and rotates the turbine connected to the generator by the energy of the vaporized fluid, . The steam passing through the turbine is liquefied through the heat exchange with the cooling seawater in the condenser, and then supplied to the heat exchanger. Such a conventional nuclear power plant requires a large construction cost, requires a large site, and has difficulty in site selection for supplying cooling seawater.

In order to solve such a problem, recently, small modular reactors (SMR) or micro modular reactors (MMR) which can be manufactured in factories and can be connected to each other are attracting attention. Since the power generation system is the steam Rankine cycle in most small / ultra-small-scale module reactors, complete modularization including the power generation system is extremely difficult. In addition, the safety systems of most small / ultra small module reactors do not operate passively for a long period of time.

As related prior art documents, U.S. Patent Application Publication No. US2013 / 0180259, Japanese Patent Application Laid-Open No. 2003-057391, and the like can be referred to.

SUMMARY OF THE INVENTION The present invention has been made to solve the above problems, and it is an object of the present invention to provide a compact / ultra-small module nuclear power plant using supercritical carbon dioxide as a coolant for a reactor and a circulating fluid for a Brayton cycle.

It is also an object of the present invention to provide a small / ultra-small module nuclear power plant with a complete passive safety system.

According to an aspect of the present invention, there is provided a modular nuclear power plant comprising: a cooling unit for cooling and circulating a circulating fluid heated by a reactor through a turbine, a heat exchanger, and an isothermal compressor, Circulating fluid circulated through the heat exchanger to the reactor through the recuperator to form an isothermal-Breton cycle, the isothermal compressor comprising: The isothermal compression process and the equi-pressure cooling process are repeated a plurality of times to increase the overall isothermal-Breton cycle efficiency through a process close to the isothermal compression by the multi-stage compression process. The minimum process may be repeated 100 to 10000 times in each isothermal-Breton cycle.

The module nuclear power plant may further include a precooler coupled between the isothermal compressor and the heat exchanger to ensure a predetermined temperature difference between the inlet and outlet of the heat exchanger.

The circulating fluid may be supercritical carbon dioxide, supercritical helium, or a mixture thereof.

And a passive residual heat eliminating heat exchanger connected to a cooling passage formed so as to surround the core of the reactor and configured to allow a coolant to flow through the outer wall of the reactor, wherein the driven residual heat eliminating heat exchanger is connected to an external air cooling loop, The core can be cooled by circulation.

The reactor includes a plurality of fuel rods in a core portion and a plurality of main rods arranged at regular intervals along the circumference around the fuel rods. The main control rods are drum-shaped.

The reactor may further comprise at least one secondary control rod extending from the enclosure at the center of the core to a vicinity of the beginning of the gas plenum space.

The module nuclear power plant can be made compact so as to include the reactor in a containment vessel having a width, a length, and a height ranging from 3 to 10 m.

According to another aspect of the present invention, there is provided a method for operating a modular nuclear power plant, comprising cooling and compressing a circulating fluid heated by a reactor through a turbine, a refractor, and an isothermal compressor, Circulating the circulating fluid cooled by the heat exchanger having the cooling fan and the circulating liquid from the heat exchanger compressed by the isothermal compressor to the reactor through the recuperator to form an isothermal-Breton cycle The step of increasing the overall isothermal-Breton cycle efficiency through a process close to the isothermal compression by a multi-stage compression process of repeating a very small process consisting of isentropic compression process and equi-pressure cooling process in the isothermal compressor .

The compact / ultra-small-sized module nuclear power plant according to the present invention can be fully modularized including the power generation system and the passive safety system, so that the manufactured module can be installed immediately through minimal construction work to produce electric power .

Also, the small / micro module nuclear power plant according to the present invention can satisfy the demand for small and medium sized nuclear power plants in a country or a city where it is difficult to introduce a large capacity nuclear power plant.

In addition, the small / ultra-small module nuclear power plant according to the present invention has the effect of eliminating the possibility of a serious accident including the melting of the core.

C 에서 최적 효율 설계점의 결과를 나타낸다.1 is a view for explaining a Brayton cycle of a conventional micro module nuclear power plant.
2A is a view for explaining a module nuclear power plant according to an embodiment of the present invention.
2B is a view for explaining a module nuclear power plant according to another embodiment of the present invention.
Figure 2c is a more detailed view of the reactor core and control rod of Figure 2a.
3 is a diagram for explaining an isothermal-Breton cycle in a module nuclear power plant according to the present invention.
4A is a temperature-entropy (Ts) diagram when applying a Brayton cycle using supercritical carbon dioxide to an isothermal compressor in the present invention.
FIG. 4B is a view for explaining the steps 4-> 5 of FIG. 4A in more detail.
Fig. 5 shows the reduction rate of compression days from the adiabatic to isothermal compression for each working fluid, which is an example where the compressor inlet temperature = 35 [deg.] C, the compressor outlet pressure = 20 MPa, and the compressor inlet pressure = 7.4 MPa.
6 is a graph showing the efficiency of the isothermal compressor according to the compression process number in the isothermal-Breton cycle of the present invention.
7 is a graph showing the cycle net efficiency at various maximum temperatures of an isothermal-Breton cycle and a conventional Breton cycle of the present invention, wherein the compressor inlet temperature 35

C shows the result of the optimum efficiency design point.

Hereinafter, the present invention will be described in detail with reference to the accompanying drawings. In the drawings, the same components are denoted by the same reference symbols as possible. In addition, detailed descriptions of known functions and / or configurations are omitted. The following description will focus on the parts necessary for understanding the operation according to various embodiments, and a description of elements that may obscure the gist of the description will be omitted. Also, some of the elements of the drawings may be exaggerated, omitted, or schematically illustrated. The size of each component does not entirely reflect the actual size, and therefore the contents described herein are not limited by the relative sizes or spacings of the components drawn in the respective drawings.

1 is a view for explaining a Brayton cycle of a conventional micro module nuclear power plant.

As shown in Fig. 1, in the conventional micro-module nuclear power plant, steam having thermal energy by the reactor 5 is circulated through the turbine 11, cooled from the heat exchanger 12 through the cooler 13 and the compressor 14 It forms a Brayton cycle that cycles back to the reactor (15).

2A is a view for explaining a module nuclear power plant according to an embodiment of the present invention. 2A, an embodiment of a modular nuclear power plant according to the present invention comprises a containment vessel 10, an outer containment vessel 20, a reactor 30, a circulation line 40, a turbine 50, An isothermal compressor 60, a recuperator 70, a generator 80, and a driven residual heat eliminating heat exchanger 34.

2B is a view for explaining a module nuclear power plant according to another embodiment of the present invention. FIG. 2B is an embodiment in which a precooler 90 is added to the module nuclear power plant of FIG. 2A.

The reactor 30 except for the generator 80, the circulation pipe 40, the turbine 50, the isothermal compressor 60, and the heat exchanger 70 are installed in the containment vessel 10.

The containment vessel 10 is disposed in the outer containment vessel 20 and the generator 80 is installed between the containment vessel 10 and the outer containment vessel 20.

The reactor 30 includes a reactor core 31, a reactor vessel 32, a control rod 33, and the like.

FIG. 2C is a more detailed view of the reactor core 31 and the control rod 33 of FIGS. 2A and 2B.

2C, in the reactor 30, the reactor core 31 and the control rod 33 are made of an enclosure 340. The core portion 31 has active core fuel rods 311 mounted on a bottom neutron reflector 312 and a gas plenum space 313 at the top. The control rod 33 includes drum type primary control rods 331 arranged at regular intervals around the core fuel rods 311 in the enclosure 340 along the circumference thereof, Shaped secondary control rod 332 arranged to descend to the vicinity of the beginning of the central upper gas plenum space 313 (regardless of whether it is slightly shorter or longer than need to match the vicinity of the start). The sub control rods 332 may be two or more. For example, the core fuel rods 311 may be composed of 18 nuclear fuel assemblies and 12 drum-shaped (hollow cylindrical or hollow cylindrical openings of some of the walls) main control rods 331 may be used. The outside of the fuel assembly can be enclosed by a reflector of PbO material and a shield of B4C material to form an enclosure. The output of the core 31 may be 36 MWth and the radius of the active core 31 may be 0.5-1.5 m and the height of the active core 31 may be 0.8-2 m. The total height of the reactor vessel 32 is designed to be small / small so that it can enter the internal module of the containment vessel 10 (for example, the length / width / height is in the range of 3 to 10 m) with a height of 2 to 4 m . It is possible to use ODS (Oxide-dispersed Strengthened) Steel as a covering material, using UN with a concentration of 19% as fuel.

The core portion 31 is a central portion of the nuclear reactor 30, where the atomic nucleus of the nuclear fuel is combined with neutrons to generate a split fission and generate energy. The control rods 331/332 absorb neutrons and control the reactivity of the fuel. The reactor vessel 32 refers to a hermetically sealed container for accommodating the core 31 and the reactor cooling system. The control rod 33 is covered with a material that absorbs thermal neutrons well. In addition, the reactor vessel 32 forms a space through which the coolant for circulating the core portion 31 and the circulating fluid flow.

As the coolant for cooling the core portion 31, the same gas as that of water, carbon dioxide, a circulating fluid (for example, supercritical carbon dioxide, supercritical helium, or a mixed gas thereof), or a mixed gas thereof may be used , For example, supercritical carbon dioxide is preferably used.

A passive decay heat removal (PDHR) heat exchanger 34 is connected to the cooling passage formed to flow the coolant to the outer wall of the reactor 30 surrounding the reactor core 31, The core portion 31 is cooled by natural circulation using a phase change or a heat transfer rate during circulation of the coolant without intervention of a separate power source so that the decay heat due to the fission of the core portion 31 can be released to the outside .

The isothermal compressor 60 is connected to the isothermal compressor 30 through the circulation piping 40, the turbine 50, the heat exchanger 70, and the isothermal compressor 60, It forms the iso-Brayton cycle.

The reactor 30 heats a circulating fluid in a supercritical state as a heat source of the isothermal-Breton cycle, and the circulation pipe 40 forms a circulation path of the supercritical circulating fluid discharged from the reactor 30, The turbine 50 rotates in the expansion process of the circulating fluid in the supercritical state. The circulating fluid exiting the turbine 50 is cooled from the heat exchanger 70 through the isothermal compressor 60 and then circulated back to the reactor 30 (see FIG. 3).

The isothermal compressor 60 cools and compresses the circulating fluid in the supercritical state through heat exchange with the heat exchanger 61 outside the outer containment vessel 20 to complete the isothermal-Breton cycle. Specifically, the isothermal compressor (60) is a turbo machine that uses an isothermal compression process to minimize the work required for compression, and can simultaneously perform the functions of a conventional compressor and a pre-cooler. Accordingly, the volume occupied by the precooler 90 can be reduced, and the entire cycle efficiency is increased by the isothermal compression process.

As shown in FIG. 4A, when the isothermal compressor 60 is used, the entropy change can be induced by keeping the temperature constant in the multistage compression process of 4- > 5, so that more heat can be recovered and heat exchange efficiency .

At this time, the heat recovery unit 70 recovers heat from the circulating fluid in the middle of the cycle and returns the cooled circulating fluid back to the reactor 30, thereby increasing the efficiency of the cycle.

The circulating fluid in the supercritical state can be filled in the inner space of the containment vessel 10 and the space between the containment vessel 10 and the outer containment vessel 20. As the circulating fluid in the supercritical state, supercritical carbon dioxide, supercritical helium, or a mixed gas thereof may be used, and supercritical carbon dioxide is preferably used as the circulating fluid.

Supercritical carbon dioxide, which is the circulating fluid, plays a role of absorbing and releasing heat energy by temperature change. Supercritical fluid refers to a fluid at a point where it can not distinguish a liquid from a gas by reaching a state exceeding a certain high temperature and high pressure limit. The density of the molecules is close to the liquid, but the viscosity is low and has a property close to the gas. The supercritical carbon dioxide circulates along the circulation line 40 connecting the respective components of the isothermal-Breton cycle to each other to transfer heat energy.

C, 7.39MPa 근처에서 높은 밀도를 갖는 특성을 보인다. 이를 더욱 활용하기 위해서는 온도 상승이 유발되는 일반 압축기(예, 공기, 헬륨 등 사용)를 사용하기 보다는, 도 5과 같이 등온 압축기(60)를 통해 동일한 온도에서 압축이 이뤄지도록 등온 압축을 하게 되어 임계점 근처에서 압축일을 더욱 감소할 수 있게 하는 것이 최대 이점이라 할 수 있다. 이산화탄소를 작동 유체로 사용하면 다른 유체에 비해 등온압축기를 사용할 때 압축일을 더 효과적으로 감소할 수 있게 된다.In particular, supercritical carbon dioxide has a critical point of 31.1

C and 7.39 MPa, respectively. In order to further utilize this, isothermal compression is performed so that compression is performed at the same temperature through the isothermal compressor 60 as shown in FIG. 5, rather than using a general compressor (e.g., air or helium) It is the greatest advantage to be able to further reduce the compression work in the vicinity. Using carbon dioxide as the working fluid can reduce compression work more effectively when using isothermal compressors compared to other fluids.

The isothermal-Breton cycle using supercritical carbon dioxide has the following advantages. First, since there is no phase change in the cycle, there is no risk of destruction of the blade due to abnormal flow in turbine or isothermal compressor. Second, since the inlet condition of the isothermal compressor is located near the critical point, the high density of the circulating fluid causes the isothermal compressor to behave like a pump, thereby greatly reducing the consumption. As a result, the heat utilization efficiency of the cycle increases greatly due to an increase in the amount of the circulation day represented by the difference between the turbine work and the isothermal compressor work. Third, since supercritical carbon dioxide is vaporized and leaves only contaminants when it is blown, no secondary waste such as water contaminated with radioactivity remains.

The supercritical carbon dioxide is supplied to the turbine 50 while being heated to a temperature above the critical temperature and the pressure by the thermal energy supplied from the reactor 30. The supercritical carbon dioxide supplied to the turbine 50 rotates the turbine 50. When the turbine (50) rotates, power is generated in the rotary generator (80) connected to the turbine (50). The turbine 50 and the generator 80 are connected to each other through the magnetic coupling with the containment vessel 10 therebetween. This is to prevent leakage which may occur in the sealing part. The rotary shaft of the turbine 50 and the isothermal compressor 60 are also connected to each other so that the isothermal compressor 60 can compress the circulating fluid by rotating the rotary shaft using the rotational power of the turbine 50.

Supercritical carbon dioxide, which consumes thermal energy in the process of rotating the turbine 50, is discharged from the turbine 50. The thermal energy of the supercritical carbon dioxide discharged from the turbine 50 is partially recovered from the heat exchanger 70. The recovered heat energy is used to maintain or heat supercritical carbon dioxide cooled through the isothermal compressor 60 to a predetermined temperature in the heat recovery unit 70.

The supercritical carbon dioxide passing through the recuperator (70) is cooled to a predetermined temperature in the isothermal compressor (60) and discharged to the reactor (30). The isothermal compressor (60) is connected through an air-cooled heat exchanger (61) provided outside the outer containment vessel (20) and a heat exchanger circulation pipe (62). The supercritical carbon dioxide of the isothermal compressor 60 is supplied to the heat exchanger 61 through the heat exchanger circulation pipe 62. The supercritical carbon dioxide is supplied to the heat exchanger 61 through the air- Heat exchange occurs. Supercritical carbon dioxide cooled in the heat exchanger (61) is supplied again to the isothermal compressor (60).

The cooled supercritical carbon dioxide is compressed in the isothermal compressor (60) and absorbs heat in the recuperator (70). And then supplied to the reactor 30 again to complete the cycle.

2B, when the precooler 90 is coupled between the isothermal compressor 60 and the heat exchanger 61, the circulating fluid passing through the heat exchanger 70 flows from the precooler 90 to the heat exchanger 61, And is discharged to the isothermal compressor (60). The circulating fluid of the precooler 90 is supplied to a heat exchanger 61 connected through a circulation pipe. In the heat exchanger 61, heat exchange is performed between supercritical carbon dioxide and outside air supplied through an air cooling fan or the like. The supercritical carbon dioxide cooled in the heat exchanger 61 is supplied to the precooler 90 and is supplied from the precooler 90 to the isothermal compressor 60 again. The rest of the cycle is completed as described above.

Hereinafter, a method in which a module nuclear power plant according to an embodiment of the present invention is operated in an emergency will be described.

In normal operation, the isothermal compressor 60 and the air cooling fan of the heat exchanger 61 are operated by using a part of the electric power generated by the generator 80, thereby removing and circulating the supercritical carbon dioxide. At this time, heat is also partially discharged through the driven residual heat eliminating heat exchanger (34).

However, in an emergency in which the core portion 31 is overheated, the turbocharger mode is changed to a turbocharger mode in which the isothermal compressor 60 is rotated by using the rotational power of the turbine 50 for a few minutes to remove the heat of the core portion 31 . Further, the decay heat of the core portion 31 is directly discharged to the outside through the driven residual heat eliminating heat exchanger (34). This makes it possible to prevent serious accidents such as melting of the core portion (31).

Generally, in the conventional system using the precooler (2) as shown in FIG. 1, heat exchange is performed by forming a Bleiton cycle of isentropic expansion, isobaric heat dissipation, isentropic compression, and isobaric quenching process.

On the other hand, in the system using the isothermal compressor 60 of the present invention, an isothermal-Breton cycle (1-> 2-> 3-> 4-> 5-> 6 -> 1) and the heat exchange takes place.

4A, when the isothermal compressor 60 is used together with the heat exchanger 70, the temperature T is kept constant in the multi-stage compression process of 4-> 5, and the change of the entropy S is induced So that more heat can be recovered and the heat exchange efficiency can be increased. Referring to FIG. 4B, which is an enlarged view of the 4 > 5 multi-step compression process of FIG. 4A, a minimal process of the isentropic compression process and the isobaric cooling process is repeated near a predetermined pressure P ₂ . By dividing the number of compression steps of the multi-stage compression process or the isothermal compression process by 200 times (for example, 100 or more and 10000 or less) in each isothermal-Breton cycle in this way, Can be calculated. This infinitesimal compression process is a virtual multi-stage compression process that allows calculation of the actual compression date, but it is different from the actual multi-stage compression process. However, such a compression process number Depending on the variable, an operation close to the ideal isothermal compression process can be achieved.

6 is a graph showing the efficiency of the isothermal compressor according to the compression process number in the isothermal-Breton cycle of the present invention. In Fig. 6, it is assumed that CIT (Compressor inlet temperature) = 35 ^o C, CIP (Compressor inlet pressure) = 7.5 MPa, and PR (Pressure ratio, inlet / outlet pressure ratio) = 2.67. As shown in FIG. 6, it can be seen that the efficiency of the isothermal compressor increases as the compression process number of the minimum process increases under a predetermined design condition ( _s ).

C 에서 최적 효율 설계점의 결과를 나타낸다.7 is a graph showing the cycle net efficiency at various maximum temperatures of the recuperated iso-Brayton cycle and the conventional simple Breton cycle of the present invention. Figure 7 shows the compressor inlet temperature 35

C shows the result of the optimum efficiency design point.

As shown in Equation (1), the cycle efficiency η _iso-c can be expressed by the relationship between the ideal isothermal compression date W _ideal and the actual isothermal compression date W _actual .

[Equation 1]

7, it was confirmed that the recuperated iso-Brayton efficiency of the present invention was significantly improved compared to the conventional system (Reference Recuperated), and the cycle efficiency was also increased as the turbine inlet temperature was increased. I could. It was also found that the isothermal-Breton cycle efficiency of the present invention is close to the Carnot efficiency (Carnot efficiency) under the ideal gas assumption.

On the other hand, based on the cycle efficiency of Equation (1), the actual total isothermal-Breton cycle efficiency? _Net of the modular nuclear power plant of the present invention can be roughly calculated as shown in Equation (2).

&Quot; (2) "

Where q _{out and precooler} represent the rows discarded through the _precooler 90 and q _{out and iso-c} represent the rows discarded during cooling through the isothermal compressor 60. Since the isothermal compressor 60 performs the role of the pre-cooler 90 and the isothermal compressor 60 in this way, it can be designed to reduce the volume / capacity of the pre-cooler 90 when applied to the cycle, The precooler 90 may be unnecessary as shown in FIG. 2A. However, in order to ensure a predetermined temperature difference between the inlet and outlet of the heat exchanger 70 in the simple double heat Brayton cycle, the precooler 90 may be added as shown in FIG. In FIG. 4A, the 3-> 4 process shows the thermodynamic state value of the precooler 90, and it can be deduced that the required capacity of the precooler 90 is small when the temperature difference is small.

As above, the supercritical carbon dioxide cycle has very small size and high efficiency. Turbomachines in the supercritical carbon dioxide cycle are considerably smaller than the steam rankine cycle or the helium cycle. It also has the advantage of achieving high efficiency even in the relatively low turbine inlet temperature range (550 to 850 degrees Celsius). This cycle is therefore suitable for reactors with a core outlet temperature above 500 degrees Celsius. The supercritical carbon dioxide cycle does not undergo a phase change, and the carbon dioxide has a property change abruptly near the supercritical point, so that the work / energy required for compression can be greatly reduced, thus achieving high efficiency. The supercritical carbon dioxide cycle has a very large heat recovery from recuperation and therefore the recuperation (70) takes up most of the cost and volume. The plate-type heat exchanger (PCHE) can be used in a supercritical carbon dioxide cycle because it can be used in a fluid having a high degree of integration and a poor heat transfer performance and drastically reducing the volume of the heat exchanger 61.

As described above, the (small / ultra-small) module nuclear power plant according to the present invention can be fully modularized including the power generation system and the passive safety system, so that the manufactured module is transported and installed immediately through the minimum construction work, Can be produced. In addition, it can meet the demand for small and medium size nuclear power plants in countries and cities where it is difficult to introduce large-capacity nuclear power plants, and it can eliminate the possibility of serious accidents including melting of core.

As described above, the present invention has been described with reference to particular embodiments, such as specific elements, and specific embodiments and drawings. However, it should be understood that the present invention is not limited to the above- Those skilled in the art will appreciate that various modifications and variations can be made without departing from the essential characteristics of the present invention (e.g., applicable to large module nuclear power plants). Therefore, the spirit of the present invention should not be construed as being limited to the embodiments described, and all technical ideas which are equivalent to or equivalent to the claims of the present invention are included in the scope of the present invention .

The containment vessel (10)
The outer containment vessel (20)
Reactors (30)
The driven residual heat removal heat exchanger (34)
Circulating piping (40)
Turbine (50)
Isothermal compressors (60)
Heat exchanger (70)
Generators (80)
Cooler (90)

Claims (10)

Cooling and compressing the circulating fluid heated by the reactor through the turbine, recuperator, and isothermal compressors,
Circulating fluid from the isothermal compressor is cooled by a heat exchanger having a cooling fan and circulating fluid from the heat exchanger is compressed by the isothermal compressor to circulate the circulating fluid to the reactor through the recuperator,
The isothermal compressor repeats the isothermal-brittle cycle using the isothermal compressor so that the phase change of the circulating fluid does not occur in the cycle during the cooling and compression of the circulating fluid in the supercritical state through heat exchange with the heat exchanger ,
A process close to isothermal compression in which a very small process consisting of an isentropic compression process and an isobaric cooling process is repeated a plurality of times in one isothermal compressor is used and a compression process is performed by compressing near the critical point by a process close to the isothermal compression To minimize the total isothermal-Breton cycle efficiency. The method according to claim 1,
Wherein the minimal process is repeated 100 to 10000 times in each isothermal-Breton cycle. The method according to claim 1,
In order to ensure a predetermined temperature difference between the inlet and outlet of the heat exchanger, a precooler, which is coupled between the isothermal compressor and the heat exchanger,
≪ / RTI > The method according to claim 1,
Wherein the circulating fluid comprises supercritical carbon dioxide, supercritical helium, or a mixture thereof. The method according to claim 1,
And a passive residual heat eliminating heat exchanger surrounding the core of the reactor and connected to a cooling passage formed so that a coolant flows through the outer wall,
Wherein the driven residual heat eliminating heat exchanger cooperates with an external air cooling loop to cool the core portion by natural circulation of the coolant without a separate power source. The method according to claim 1,
The reactor,
A plurality of main rods arranged at regular intervals along the circumference around the fuel rods and a plurality of main rods
Wherein the module comprises: The method according to claim 6,
Wherein the main control rods are of the drum type. The method according to claim 6,
The reactor,
At least one sub control rod extending from the enclosure at the center of the core to the vicinity of the start of the gas plenum space,
Further comprising: a module reactor. The method according to claim 1,
Characterized in that it is made compact so as to include said reactor in a containment vessel having a width, a length, and a height ranging from 3 to 10 m. Cooling and compressing a circulating fluid heated by the reactor through a turbine, a refractor, and an isothermal compressor,
Wherein the circulating fluid from the isothermal compressor is cooled by a heat exchanger having a cooling fan and the circulating fluid from the heat exchanger is compressed by the isothermal compressor to circulate the circulating fluid through the heat exchanger to the reactor, Repeating the isothermal-brittle cycle using the isothermal compressor so that the isothermal compressor does not cause a phase change of the circulating fluid in the cycle during the cooling and compression of the circulating fluid in the supercritical state through heat exchange with the heat exchanger / RTI >
A process close to isothermal compression in which a very small process consisting of an isentropic compression process and an isobaric cooling process is repeated a plurality of times in one isothermal compressor is used and a compression process is performed by compressing near the critical point by a process close to the isothermal compression And increasing the total isothermal-Breton cycle efficiency by minimizing the total isothermal-Breton cycle efficiency.

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