CN113283049A - Power distribution optimization method for modular prismatic high-temperature gas cooled reactor - Google Patents
Power distribution optimization method for modular prismatic high-temperature gas cooled reactor Download PDFInfo
- Publication number
- CN113283049A CN113283049A CN202110332505.8A CN202110332505A CN113283049A CN 113283049 A CN113283049 A CN 113283049A CN 202110332505 A CN202110332505 A CN 202110332505A CN 113283049 A CN113283049 A CN 113283049A
- Authority
- CN
- China
- Prior art keywords
- enrichment
- fuel
- fuel assemblies
- axial
- radial
- 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.)
- Pending
Links
Images
Classifications
-
- G—PHYSICS
- G06—COMPUTING; CALCULATING OR COUNTING
- G06F—ELECTRIC DIGITAL DATA PROCESSING
- G06F30/00—Computer-aided design [CAD]
- G06F30/20—Design optimisation, verification or simulation
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- Theoretical Computer Science (AREA)
- Computer Hardware Design (AREA)
- Evolutionary Computation (AREA)
- Geometry (AREA)
- General Engineering & Computer Science (AREA)
- General Physics & Mathematics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a power distribution optimization method for a modular prismatic high-temperature gas cooled reactor, which comprises the following steps: determining average enrichment, enrichment ratio factors of fuel assemblies in radial zones and enrichment ratio factors of fuel assemblies in axial layers; determining the enrichment degree of each fuel assembly according to the average enrichment degree, the enrichment degree ratio factors of the fuel assemblies in each radial zone and the enrichment degree ratio factors of the fuel assemblies in each axial layer; and outputting an optimization result according to the enrichment degree of each fuel assembly. The invention has the beneficial effects that: according to the invention, the enrichment degree of the fuel assemblies at different positions is optimized according to the partitioned hierarchical arrangement, the power distribution of the reactor core can be effectively optimized, the maximum temperature of the fuel in the reactor core is as low as possible, the temperature rise allowance of the reactor core is improved, and the realization of the inherent safety of the reactor core is ensured.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor engineering, and particularly relates to a modularized prismatic high-temperature gas-cooled power distribution optimization method.
Background
The rapid development of economy improves the energy demand, but the traditional fossil fuels such as coal and the like bring serious environmental problems, which prompts China to continuously explore and develop clean energy. Among various types of new energy, nuclear energy has advantages of cleanliness, high energy density, little emission of greenhouse gases, low fuel transportation pressure, and the like.
The modularized prismatic high-temperature gas cooled reactor belongs to an advanced reactor type of a fourth generation nuclear energy system and has excellent inherent safety. The ceramic fuel particles adopted by the pile type can effectively prevent the release of fission products; the graphite reactor core has large heat capacity, slow temperature transient state, capability of bearing high temperature and large emergency operation time allowance; the reactor core has small power density and strong temperature negative feedback, and can be shut down by means of the temperature negative feedback under the accident condition even if no emergency measures are taken, so that the structural integrity of the reactor core and fuel is ensured. The modularized and miniaturized design can simplify emergency measures, enables the reactor core to have extremely high design flexibility and environmental adaptability, and has great market potential in the fields of remote mountain power supply, aerospace, island power supply, deep sea power supply and the like.
The fuel temperature limit is one of the main limitations of the modular prismatic high temperature gas cooled reactor. When the fuel temperature is too high, the temperature rise allowance of the reactor core is reduced, the temperature negative feedback cannot introduce enough negative reactivity, the reactor core cannot be shut down only by the temperature negative feedback, and the inherent safety of the reactor core is damaged; under accident conditions, the fuel temperature may exceed the temperature limit, so that the damage rate of ceramic fuel particles is greatly improved, and radioactive substances such as fission products and the like are released. Therefore, the maximum temperature of fuel in the reactor core is ensured to be as low as possible by optimizing the power distribution of the reactor core, and the realization of the inherent safety of the modular prismatic high-temperature gas-cooled reactor is facilitated.
In view of the above, the present invention is particularly proposed.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a power distribution optimization method for a modular prismatic high-temperature gas-cooled reactor, which can optimize power distribution, improve the temperature rise allowance of a reactor core and ensure the realization of the inherent safety of the reactor core.
The technical scheme of the invention is as follows:
a power distribution optimization method for a modular prismatic high-temperature gas cooled reactor comprises the following steps:
determining average enrichment, enrichment ratio factors of fuel assemblies in radial zones and enrichment ratio factors of fuel assemblies in axial layers;
determining the enrichment degree of each fuel assembly according to the average enrichment degree, the enrichment degree ratio factors of the fuel assemblies in each radial zone and the enrichment degree ratio factors of the fuel assemblies in each axial layer;
and outputting an optimization result according to the enrichment degree of each fuel assembly.
Further, according to the power distribution optimization method of the modular prismatic high-temperature gas-cooled reactor, the enrichment degree of each fuel assembly is determined according to the average enrichment degree, the enrichment degree ratio factors of the fuel assemblies in each radial zone and the enrichment degree ratio factors of the fuel assemblies in each axial layer according to the following formula:
Cwt＝Cav*Er*Ez；
in the formula, Cwt is the enrichment degree of each fuel assembly;
cav is the average enrichment;
er is a radial enrichment ratio factor;
ez is an axial enrichment ratio factor.
Further, in the method for optimizing power distribution of the modular prismatic high-temperature gas-cooled reactor, the method for determining the enrichment ratio factor of the fuel assemblies in each radial zone comprises the following steps:
calculating the neutron flux distribution of the reactor core radial fuel assembly when the fuel enrichment degree of the whole reactor is the same;
and determining the enrichment ratio factor of the fuel assemblies in each radial region according to the ratio of the reciprocal neutron flux of the radial fuel.
Further, in the method for optimizing power distribution of the modular prismatic high-temperature gas-cooled reactor, the method for determining the enrichment ratio factor of each layer of the fuel assemblies in the axial direction comprises the following steps:
the axial power distribution is approximately exponentially distributed by calculating the enrichment ratio factor for each axial layer of fuel assemblies using the formula p (z) ═ C · exp (-a · z/b).
Further, according to the power distribution optimization method for the modular prismatic high-temperature gas-cooled reactor, similar enrichment degree parameters are processed approximately to reduce the types of the full-reactor fuel enrichment degree before the optimization result is output according to the enrichment degree of each fuel assembly.
Further, in the power distribution optimization method for the modular prismatic high-temperature gas-cooled reactor, the approximation processing on the similar enrichment degree parameters is weighted average processing of the similar enrichment degrees by taking the number of fuel assemblies corresponding to the similar enrichment degrees as a weight.
Further, in the power distribution optimization method of the modular prismatic high-temperature gas-cooled reactor, the similar enrichment degree parameter is determined according to six types of fuel enrichment degree types of the whole reactor.
The invention has the beneficial effects that:
1. according to the invention, the enrichment degree of the fuel assemblies at different positions is optimized according to the partitioned hierarchical arrangement, the power distribution of the reactor core can be effectively optimized, the maximum temperature of the fuel in the reactor core is as low as possible, the temperature rise allowance of the reactor core is improved, and the realization of the inherent safety of the reactor core is ensured.
2. Through the technical scheme of the invention, the power is flattened as much as possible in the radial direction, and the radial power peak factor is reduced; in the axial direction, the power distribution is expanded to be in the form of approximate exponential function; the highest temperature of the fuel of the modularized prismatic high-temperature gas-cooled reactor is minimized, the temperature rise allowance of the reactor core is increased, the integrity of the reactor core structure and the fuel is guaranteed, and the inherent safety of the reactor core is further improved. The invention can effectively reduce the highest temperature of the fuel and can be applied to the design of a prismatic high-temperature gas cooled reactor.
Drawings
Fig. 1 is a flow chart of a power distribution optimization method for a modular prismatic high-temperature gas-cooled reactor according to the present invention.
Fig. 2 is a radial layout diagram of the modular prismatic high temperature gas cooled reactor according to the present invention.
Fig. 3 is an axial layout diagram of the modular prismatic high-temperature gas-cooled reactor according to the invention.
FIG. 4 is a graph of fuel characteristics after a fuel enrichment zoning arrangement for a core in accordance with the present invention.
FIG. 5 is a nuclear energy spectrum of the reactor core before and after the fuel enrichment zoning arrangement of the reactor core of the present invention.
FIG. 6 is a normalized power distribution diagram before core optimization according to the present invention.
FIG. 7 is a normalized power distribution graph after core optimization according to the present invention.
FIG. 8 is a fuel average temperature distribution diagram before and after the core power distribution optimization according to the present invention.
FIG. 9 is a fuel maximum temperature distribution diagram before and after the core power distribution optimization according to the present invention.
In the above drawings: 1. a fuel assembly; 2. a control rod assembly; 3. a side reflective layer; 4. a control rod passage; 5. an upper reflective layer; 6. and a lower reflective layer.
Detailed Description
Embodiments of the invention are described below with reference to the accompanying drawings:
as shown in fig. 1, the present invention provides a power distribution optimization method for a modular prismatic high temperature gas cooled reactor, including:
s100, determining average enrichment, enrichment ratio factors of fuel assemblies in radial zones and enrichment ratio factors of fuel assemblies in axial layers;
s200, determining the enrichment degree of each fuel assembly according to the average enrichment degree, the enrichment degree ratio factors of the fuel assemblies in each radial zone and the enrichment degree ratio factors of the fuel assemblies in each axial layer;
s300, outputting an optimization result according to the enrichment degree of each fuel assembly.
In S200, determining the enrichment degree of each fuel assembly according to the average enrichment degree, the enrichment degree ratio factors of the fuel assemblies in each radial zone and the enrichment degree ratio factors of the fuel assemblies in each axial layer according to the following formula:
Cwt＝Cav*Er*Ez；
in the formula, Cwt is the enrichment degree of each fuel assembly;
cav is the average enrichment;
er is a radial enrichment ratio factor;
ez is an axial enrichment ratio factor.
According to the invention, the enrichment degree of the fuel assemblies at different positions is optimized according to the layered arrangement, the power distribution of the reactor core can be effectively optimized, the maximum temperature of the fuel in the reactor core is as low as possible, the temperature rise allowance of the reactor core is improved, and the realization of the inherent safety of the reactor core is ensured.
In S100, the method for determining the enrichment ratio factor of the fuel assemblies in each radial zone comprises the following steps:
calculating the neutron flux distribution of the reactor core radial fuel assembly when the fuel enrichment degree of the whole reactor is the same;
and determining the enrichment ratio factor of the fuel assemblies in each radial region according to the ratio of the reciprocal neutron flux of the radial fuel.
Therefore, the power can be flattened as much as possible in the radial direction, and the radial power peak factor is reduced.
In S100, the method for determining the enrichment ratio factor of each layer of fuel assemblies in the axial direction comprises the following steps:
the axial power distribution is approximately exponentially distributed by calculating the enrichment ratio factor for each axial layer of fuel assemblies using the formula p (z) ═ C · exp (-a · z/b).
Therefore, the highest temperature of the fuel of the modular prismatic high-temperature gas cooled reactor is minimized, the temperature rise allowance of the reactor core is increased, the integrity of the reactor core structure and the fuel is guaranteed, and the inherent safety of the reactor core is further improved.
The above formula p (z) ═ C · exp (-a · z/b) is derived from the following formula:
Tfuel(z)＝Tin+Tcool(z)+Tr(z)；
Tr(z)＝bP(z)；
wherein, Tfuel(z) represents the fuel temperature at axial position z, TinRepresents the inlet temperature, T, of the coolantcool(z) represents the temperature change of the coolant from the inlet to z, Tr(z) represents the location z from the coolant channel to the fuel pelletsTemperature variation by heat conduction of the inner surface in the radial direction, p (z) represents the axial power distribution, a and b represent constants related to coolant properties, core geometry, C is a normalized coefficient, and z represents the core axial position.
The maximum temperature of the fuel is generally located inside the fuel pellets, since the prismatic high temperature gas cooled reactor coolant flows from top to bottom. Due to coolant inlet temperature TinIs constant, and the total core power is constant, in order to improve the core safety, the fuel temperature T is required to be enabledfuelThe maximum value of (z) is minimal, i.e. T should be such thatfuel(z) is a constant. In this case, the axial power distribution p (z) can be derived, and the axial power should be approximately distributed in an exponential function.
In order to reduce the process difficulty, similar enrichment degree parameters are processed approximately to reduce the full-stack fuel enrichment degree types before the optimization result is output according to the enrichment degree of each fuel assembly.
The approximate treatment of the similar enrichment degree parameters is a weighted average treatment of the similar enrichment degrees by taking the number of fuel assemblies corresponding to the similar enrichment degrees as a weight.
In this embodiment, the similar enrichment parameter is determined by reducing the full stack fuel enrichment category to six or less.
The invention can effectively reduce the highest temperature of the fuel and can be applied to the design of a prismatic high-temperature gas cooled reactor.
The power distribution optimization method of the modular prismatic high-temperature gas-cooled reactor is applied to the core arrangement of the modular prismatic high-temperature gas-cooled reactor with the thermal power of 15MW and the service life of 20 years, and the radial diagram and the axial diagram of the core are shown in fig. 2 and fig. 3. The reactor core mainly comprises a fuel assembly 1, a control rod assembly 2 and a reflecting layer. The reflective layer includes a side reflective layer 3, an upper reflective layer 5, and a lower reflective layer 6. In the embodiment, the fuel assembly is divided into 4 areas, namely, zone 1-zone 4, in the radial direction according to different positions; the axial direction is divided into 6 layers, namely layer 1-layer 6 from top to bottom; the fuel assembly consists of fuel rods and coolant channels, wherein ceramic fuel particles are dispersed in a silicon carbide matrix, 54 fuel rods and 19 coolant channels are arranged in each fuel assembly, and the distance between the opposite sides of the hexagonal prism fuel assembly is 35.7cm, and the height of the hexagonal prism fuel assembly is 70 cm. The control rod assemblies are arranged with 7 groups in the active region and 6 groups in the reflective layer. The reactor core structure material and the reflecting layer are made of graphite materials. The diameter of the whole core is 280cm, and the height is 595 cm. To meet core design objectives, the core fuel mean enrichment is 9%, at which time the core life is 7360 EFPD.
When the fuel enrichment degrees are all 9%, the neutron flux distribution of the radial 4-zone fuel assemblies can be obtained, because the power is related to the neutron value, and the neutron value is proportional to the square of the neutron flux, if the fuel enrichment degrees are arranged in a partitioning mode according to the inverse of the square of the radial neutron flux, the radial power crest factor is small and is close to 1, but the radial power crest factor can cause the gradient of the fuel enrichment degrees in the reactor core to be overlarge, and the enrichment degrees of partial fuel assemblies can exceed the limit value (for example, the uranium enrichment degrees of the civil nuclear facilities are generally less than 20%). Thus, from the ratios of the inverses of neutron flux for the radial 4-zone fuel assemblies, radial zone 1-zone 4 fuel enrichment factors of 0.635, 0.867, 1.053, 1.393 may be obtained with a 2-fold weighting of the zone3 assemblies. To approximate the axial power distribution as an exponential function, the axial enrichment factors are 1.41, 1.15, 1.08, 0.84, 0.76, with the 5 th and 6 th layer axial factors set the same to account for neutron leakage. According to the analysis, the fuel enrichment degree of the reactor core can reach more than 20, in order to simplify the design of the reactor core, the similar enrichment degrees are subjected to weighted average approximate treatment, and the enrichment degree distribution of each fuel assembly in the reactor core can be obtained and is shown in the table 1, and the total enrichment degrees of 6 fuel assemblies are obtained.
TABLE 1 optimized Fuel enrichment distribution Table
| Axial | Zone | 1 | |
|
|
| |
7.3％ | 9.4％ | 12.2％ | 16.0 | |
| Layer | |||||
| 2 | 7.3％ | 9.4％ | 12.2％ | 16.0 | |
| Layer | |||||
| 3 | 5.7％ | 7.3％ | 9.4％ | 12.2 | |
| Layer | |||||
| 4 | 5.7％ | 7.3％ | 9.4％ | 12.2 | |
| Layer | |||||
| 5 | 4.4％ | 5.7％ | 7.3％ | 9.4 | |
| Layer | |||||
| 6 | 4.4％ | 5.7％ | 7.3％ | 9.4％ |
And calculating and analyzing the physical characteristics of the reactor core of the prismatic high-temperature gas cooled reactor by using a general Monte Care program.
FIG. 4 is a graph of optimized core burnup characteristics for a core life of approximately 6800EFPD, which is 560EFPD shorter than the core life for 9% full core enrichment due to increased core neutron leakage after fuel enrichment zoning. But considering 90% power factor, the optimized core life still meets the target of 15MW thermal power and 20 years life.
FIG. 5 is a nuclear neutron energy spectrum before and after optimization, after the optimization, the nuclear neutron energy spectrum is obviously softened, the thermal neutron share is obviously increased, and the fast neutron share is obviously reduced.
The power distribution of the core fuel assemblies before and after the optimization of zero-burn is shown in table 2 and table 3, and in fig. 6 and fig. 7. Before optimization, the enrichment degrees of all fuel assemblies are the same, and the radial power peak factor is larger and is about 1.47; the axial power distribution is distributed in a cosine function. After optimization, the fuel assemblies are arranged in a partition mode according to different positions and enrichment degrees, radial power is flattened, and the peak factor of the radial power is obviously reduced to about 1.18; the axial power distribution is approximately distributed in an exponential function on the whole; substantially meeting the optimized power distribution objective.
TABLE 2 normalized fuel assembly power distribution table of zero burnup when core is not optimized
TABLE 3 normalized fuel assembly power distribution table for zero fuel consumption after core optimization
| Axial layer/ | Zone | 1 | |
|
|
Radial power |
| Layer | ||||||
| 1 | 1.39 | 1.19 | 1.11 | 0.97 | 1.19 | |
| |
1.89 | 1.60 | 1.50 | 1.32 | 1.20 | |
| |
1.60 | 1.38 | 1.30 | 1.15 | 1.18 | |
| |
1.24 | 1.06 | 1.00 | 0.88 | 1.19 | |
| |
0.69 | 0.60 | 0.57 | 0.50 | 1.17 | |
| |
0.38 | 0.33 | 0.31 | 0.28 | 1.16 | |
| Axial power peak factor | 1.58 | 1.56 | 1.56 | 1.55 | / |
Considering the coolant flowing from top to bottom in the axial direction, the inlet temperature being 300 ℃ and the outlet temperature being 630 ℃, the average temperature distribution of the fuel in the axial direction in the core before and after the optimization of the power distribution is shown in fig. 8, in which the axial coordinate 0m represents the axial top of the fuel active area and 4.2m represents the axial bottom of the fuel active area, it can be seen that the maximum value of the average temperature of the fuel appears at the bottom of the fuel active area, and after the optimization of the power distribution, the maximum value of the average temperature of the fuel is slightly reduced, which is about 20 ℃. However, considering the distribution of the maximum fuel temperature, as shown in fig. 9, it can be seen that the maximum fuel temperature is reduced from 960 ℃ to about 820 ℃, which is reduced by about 140 ℃, and the reduction of the maximum fuel temperature is significant, which is beneficial to improving the safety of the core.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations. The above-described embodiments are merely illustrative of the present invention, and the present invention may be embodied in other specific forms or other specific forms without departing from the spirit or essential characteristics thereof. The described embodiments are, therefore, to be considered in all respects as illustrative and not restrictive. The scope of the invention should be indicated by the appended claims, and any changes that are equivalent to the intent and scope of the claims should be construed to be included therein.
Claims (7)
1. A power distribution optimization method for a modular prismatic high-temperature gas-cooled reactor is characterized by comprising the following steps:
determining average enrichment, enrichment ratio factors of fuel assemblies in radial zones and enrichment ratio factors of fuel assemblies in axial layers;
determining the enrichment degree of each fuel assembly according to the average enrichment degree, the enrichment degree ratio factors of the fuel assemblies in each radial zone and the enrichment degree ratio factors of the fuel assemblies in each axial layer;
and outputting an optimization result according to the enrichment degree of each fuel assembly.
2. The method of claim 1, wherein the determining the enrichment of each fuel assembly according to the average enrichment, the enrichment ratio factors of the fuel assemblies in each radial zone and the enrichment ratio factors of the fuel assemblies in each axial zone is performed according to the following formula:
Cwt＝Cav*Er*Ez；
in the formula, Cwt is the enrichment degree of each fuel assembly;
cav is the average enrichment;
er is a radial enrichment ratio factor;
ez is an axial enrichment ratio factor.
3. The method for optimizing power distribution of a modular prismatic high temperature gas-cooled reactor according to claim 2, wherein the method for determining the enrichment ratio factor of fuel assemblies in each radial zone comprises:
calculating the neutron flux distribution of the reactor core radial fuel assembly when the fuel enrichment degree of the whole reactor is the same;
and determining the enrichment ratio factor of the fuel assemblies in each radial region according to the ratio of the reciprocal neutron flux of the radial fuel.
4. The method for optimizing power distribution of a modular prismatic high temperature gas-cooled reactor according to claim 2, wherein the method for determining the enrichment ratio factor of each layer of fuel assemblies in the axial direction comprises:
calculating an enrichment ratio factor of each axial layer fuel assembly by using a formula P (z) ═ C.exp (-a.z/b) to enable the axial power distribution to be approximately distributed in an exponential function form;
in the above formula, a and b represent constants related to coolant properties, core geometry, C is a normalized coefficient, and z represents the core axial position.
5. The method according to any one of claims 1 to 4, wherein the similar enrichment parameters are approximated to reduce the fuel enrichment class of the full stack before outputting the optimization result according to the enrichment of each fuel assembly.
6. The method of claim 5, wherein the approximating the similar enrichment parameter is a weighted average of similar enrichments weighted by a number of fuel assemblies corresponding to each of the similar enrichments.
7. The method of claim 5, wherein the similar enrichment parameter is determined to reduce the full-stack fuel enrichment category to six.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110332505.8A CN113283049A (en) | 2021-03-29 | 2021-03-29 | Power distribution optimization method for modular prismatic high-temperature gas cooled reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110332505.8A CN113283049A (en) | 2021-03-29 | 2021-03-29 | Power distribution optimization method for modular prismatic high-temperature gas cooled reactor |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN113283049A true CN113283049A (en) | 2021-08-20 |
Family
ID=77276054
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202110332505.8A Pending CN113283049A (en) | 2021-03-29 | 2021-03-29 | Power distribution optimization method for modular prismatic high-temperature gas cooled reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN113283049A (en) |
-
2021
- 2021-03-29 CN CN202110332505.8A patent/CN113283049A/en active Pending
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN109509562B (en) | Reactor core structure, molten salt pebble bed reactor, fuel management method of molten salt pebble bed reactor and reactor core loading method | |
| CN111627572B (en) | Modularized molten salt reactor core and molten salt reactor | |
| WO2022206064A1 (en) | Reactor core system and gas-cooled micro reactor | |
| WO2022206072A1 (en) | Gas-cooled micro-reactor core and gas-cooled micro-reactor | |
| CN110853774B (en) | Zirconium hydride moderated metal cooling reactor miniaturization design method and reactor | |
| CN113270206B (en) | Small prismatic annular gas-cooled micro-reactor core system with densely arranged coolant channels | |
| CN112259263B (en) | Three-channel molten salt reactor core structure and three-channel molten salt reactor system | |
| Wei et al. | Neutronic/thermal‐hydraulic design features of an improved lead‐bismuth cooled small modular fast reactor | |
| CN113283049A (en) | Power distribution optimization method for modular prismatic high-temperature gas cooled reactor | |
| CN107767966A (en) | Nuclear reactor system | |
| He et al. | Research on power flattening method and neutron characteristic analysis of a megawatt-class space gas-cooled fast reactor | |
| CN110853769A (en) | Pellet fuel core, fuel rod and small-size reactor of metal cooling | |
| Hiscox et al. | Reactor physics analysis of a new Accident Tolerant Fuel called Fuel-in-Fibers | |
| RU2265899C2 (en) | Fuel cell and gas-cooled nuclear reactor using such fuel cells | |
| CN113205892B (en) | Reactor core system of prismatic gas-cooled micro-reactor | |
| JP5318312B2 (en) | Monolithic fuel element and fast spectrum boiling water reactor using the element | |
| CN115171924A (en) | Lead bismuth cooling solid reactor core system | |
| KR100756440B1 (en) | Nuclear fuel pebble having shell-shaped fuel zone for high temperature gas cooled reactors | |
| Nakano et al. | Conceptual reactor design study of very high temperature reactor (VHTR) with prismatic-type core | |
| CN114496313B (en) | Ultra-high flux reactor core with fan-shaped partitions of fast neutrons and thermal neutrons | |
| CN115101221B (en) | Integrated movable air-cooled miniature power reactor core | |
| CN113270207B (en) | Short-life-period air-cooled micro-reactor performance optimization structure | |
| CN107146641A (en) | The method of nuclear power system and control nuclear power system | |
| CN117238535A (en) | Annular fuel element and sodium-cooled fast reactor core based on same | |
| Kato | Advanced high temperature gas-cooled reactor systems |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination |