CN115983049B - Discontinuous factor calculation method applied to pebble-bed high-temperature gas cooled reactor - Google Patents
Discontinuous factor calculation method applied to pebble-bed high-temperature gas cooled reactor Download PDFInfo
- Publication number
- CN115983049B CN115983049B CN202310265822.1A CN202310265822A CN115983049B CN 115983049 B CN115983049 B CN 115983049B CN 202310265822 A CN202310265822 A CN 202310265822A CN 115983049 B CN115983049 B CN 115983049B
- Authority
- CN
- China
- Prior art keywords
- neutron
- uniform
- calculation
- temperature gas
- gas cooled
- 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.)
- Active
Links
- 238000004364 calculation method Methods 0.000 title claims abstract description 44
- 230000004907 flux Effects 0.000 claims abstract description 53
- 238000009792 diffusion process Methods 0.000 claims abstract description 20
- 238000000034 method Methods 0.000 claims abstract description 13
- 239000006096 absorbing agent Substances 0.000 claims abstract description 12
- 239000002245 particle Substances 0.000 claims description 3
- 241000270295 Serpentes Species 0.000 claims 1
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 5
- 239000011449 brick Substances 0.000 description 5
- 229910052799 carbon Inorganic materials 0.000 description 5
- 238000010521 absorption reaction Methods 0.000 description 3
- 238000010586 diagram Methods 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 238000000265 homogenisation Methods 0.000 description 1
- 235000012149 noodles Nutrition 0.000 description 1
- 230000035755 proliferation Effects 0.000 description 1
Classifications
-
- 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
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a discontinuous factor calculation method applied to a pebble-bed high-temperature gas cooled reactor, which comprises the steps of firstly dividing the pebble-bed high-temperature gas cooled reactor into three-dimensional cylindrical geometric segments according to an actual layered structure of a reflecting layer of the pebble-bed high-temperature gas cooled reactor, constructing a calculation model by using a Monte Carlo physical calculation program, and carrying out neutron transport calculation to obtain outgoing neutron flow, incoming neutron flow and non-uniform neutron surface flux of each surface of each reflecting layer segment in each direction; then calculating to obtain uniform neutron surface flux of all the section surfaces by utilizing the emergent neutron flow and the incident neutron flow; and finally, calculating to obtain discontinuous factors of all surfaces of all the sections, and subsequently, using the discontinuous factors for strong absorber diffusion calculation and correction. The method omits the two-dimensional non-uniform transport calculation and the two-dimensional fixed source diffusion calculation steps, and the non-uniform neutron surface flux and the uniform neutron surface flux required by calculating the discontinuous factor are directly obtained through Monte Carlo non-uniform neutron transport calculation, so that the discontinuous factor is obtained in a simpler, more convenient and more accurate mode.
Description
Technical Field
The invention relates to the field of nuclear reactor physical computation, in particular to a discontinuous factor computing method applied to a pebble-bed high-temperature gas cooled reactor.
Background
The pebble-bed high-temperature gas cooled reactor adopts a reactive control mode of combining a control rod and an absorption ball outside an active area, and the channels of the control rod and the absorption ball are arranged in a reflecting layer. In addition, in order to effectively absorb neutrons leaking outside the reflecting layer, the outermost layer of the reflecting layer is also provided with a layer of carbon boride bricks. The control rods, the absorption spheres and the carbon boride bricks all belong to strong absorbers which will cause local distortions and strong anisotropies of the neutron flux, resulting in that the diffusion approximation is no longer applicable.
In the three-dimensional total pile diffusion calculation based on the segment expansion method, the condition of net neutron flux conservation before and after homogenization can lead to uniform neutron surface flux discontinuity between two segment interfaces, and the surface flux discontinuity phenomenon of the segment interfaces of the strong absorber area is more prominent, so that a non-negligible calculation error is introduced. In order to correct the diffusion calculation of the strong absorber region, a discontinuous factor is often used for correcting the relation between outgoing neutron flux and incoming neutron flux on the segment surfaces, so that the uniform neutron surface flux between the segment interfaces is continuous, and the error of the diffusion calculation is reduced. Thus, there is a need to provide a discontinuity factor suitable for three-dimensional full stack diffusion calculations for pebble-bed high temperature gas cooled reactors.
In the prior art, a two-dimensional non-uniform neutron transport calculation is needed to obtain a non-uniform neutron surface flux and a region uniform section, and then the non-uniform neutron surface flux and the region uniform section are substituted into the region uniform section to perform two-dimensional fixed source diffusion calculation on the uniform region to obtain the uniform neutron surface flux, so that a discontinuous factor is obtained through calculation, and the flow is complex.
Disclosure of Invention
In order to overcome the problems in the prior art, the invention aims to provide a discontinuous factor calculation method applied to a pebble-bed high-temperature gas cooled reactor, which is characterized in that firstly, according to the actual layered structure of a pebble-bed high-temperature gas cooled reactor reflecting layer, three-dimensional cylinder geometric sections are divided, a Monte Carlo physical calculation program is used for constructing a calculation model and carrying out neutron transport calculation to obtain the emergent neutron flow, the incident neutron flow and the non-uniform neutron surface flux of each surface of each layer of reflecting layer section in each direction; then calculating to obtain uniform neutron surface flux of the corresponding surfaces of all three-dimensional cylindrical geometric segments by utilizing the emergent neutron flow and the incident neutron flow; and finally, calculating to obtain discontinuous factors of all surfaces of all three-dimensional cylinder geometric section blocks by utilizing non-uniform neutron surface flux and uniform neutron surface flux of the corresponding surfaces of all three-dimensional cylinder geometric section blocks, and subsequently, calculating and correcting for strong absorber diffusion.
In order to achieve the above object, the present invention adopts the following technical scheme:
a discontinuous factor calculation method applied to a pebble-bed high-temperature gas cooled reactor comprises the following steps:
step 1: dividing the spherical high-temperature gas cooled reactor reflecting layer into three-dimensional cylindrical geometric sections according to the actual layered structure of the spherical high-temperature gas cooled reactor reflecting layer in the radial direction, the circumferential direction and the axial direction, and building a spherical high-temperature gas cooled reactor physical model by utilizing a Monte Carlo physical calculation program;
step 2: carrying out non-uniform neutron transport calculation on a pebble-bed high-temperature gas cooled reactor physical model by using a Monte Carlo physical calculation program, and calculating to obtain emergent neutron flow, incident neutron flow and non-uniform neutron surface flux of three-dimensional cylindrical geometric segments in each layer of reflecting layers in the pebble-bed high-temperature gas cooled reactor physical model in the radial, circumferential and axial directions;
step 3: calculating to obtain uniform neutron surface flux of the corresponding surface of each three-dimensional cylindrical geometric segment by utilizing the outgoing neutron flow and the incoming neutron flow obtained in the step 2;
according to the neutron diffusion theory approximation, the uniform neutron surface flux is equal to twice the sum of the outgoing neutron flow and the incoming neutron flow of the surface:
(1)
(2)
wherein:
-representing the direction, comprising radial +>Circumference->And axial->；
-the surface of the nub;
-segment number;
-differentiating the blocks in +.>Two faces in the direction, wherein +.>The faces represent the radial outer diameter face, the axially facing face and the circumferential clockwise face,/->The faces represent radially inner diameter faces, axially downwardly facing faces and circumferentially anticlockwise faces;
-the first part of%>Individual blocks->Direction +.>First->Uniform neutron surface flux of the population;
-the first part of%>Individual blocks->Direction +.>First->A stream of incident neutrons of the population;
-the first part of%>Individual blocks->Direction +.>First->An outgoing neutron stream of the population;
-the first part of%>Individual blocks->Direction +.>First->Uniform neutron surface flux of the population;
-the first part of%>Individual blocks->Direction +.>First->A stream of incident neutrons of the population;
-the first part of%>Individual blocks->Direction +.>First->An outgoing neutron stream of the population;
step 4: calculating a discontinuous factor of the corresponding surface of each three-dimensional cylinder geometric node block by utilizing the non-uniform neutron surface flux obtained in the step 2 and the uniform neutron surface flux obtained in the step 3, wherein a calculation formula is as follows;
(3)
(4)
wherein:
-the first part of%>Individual blocks->Direction +.>First->A discontinuity factor for the population;
-the first part of%>Individual blocks->Direction +.>First->A group non-uniform neutron surface flux;
-the first part of%>Individual blocks->Direction +.>First->A discontinuity factor for the population;
-the first part of%>Individual blocks->Direction +.>First->A non-uniform neutron surface flux of the population;
and (3) repeating the step (3) and the step (4) to obtain the discontinuous factors of all surfaces of all the sections, and then using the discontinuous factors for strong absorber diffusion calculation correction.
Compared with the prior art, the invention has the following advantages: the steps of two-dimensional non-uniform transport calculation and two-dimensional fixed source diffusion calculation are omitted, non-uniform neutron surface flux and uniform neutron surface flux required by calculating the discontinuous factors are directly obtained through the Monte Carlo calculation program, the discontinuous factors are accurately obtained in a simpler and more convenient mode, and the method is subsequently applied to full-stack diffusion calculation of the pebble-bed high-temperature gas cooled reactor, so that calculation errors caused by the existence of a strong absorber can be effectively reduced.
Drawings
FIG. 1a is an axial cross-sectional schematic view of an HTR-PM simplified model of an exemplary project of a high temperature gas cooled reactor nuclear power plant.
FIG. 1b is a schematic axial longitudinal section of a simplified HTR-PM model of an exemplary engineering of a high temperature gas cooled reactor nuclear power plant.
FIG. 2 is a general flow chart of a discontinuous factor calculation method applied to a pebble-bed high-temperature gas cooled reactor.
Detailed Description
The invention is described in further detail below with reference to the attached drawings and detailed description:
dividing the spherical bed type high-temperature gas cooled reactor into three-dimensional cylindrical geometric sections according to the actual layered structure of a reflecting layer of the spherical bed type high-temperature gas cooled reactor, constructing a physical model of the spherical bed type high-temperature gas cooled reactor by using a Monte Carlo physical calculation program, and carrying out neutron transport calculation to obtain outgoing neutron flow, incoming neutron flow and non-uniform neutron surface flux of each surface of the sections of the reflecting layer in each direction; then calculating to obtain uniform neutron surface flux of the corresponding surfaces of all three-dimensional cylindrical geometric segments by utilizing the emergent neutron flow and the incident neutron flow; and finally, calculating to obtain discontinuous factors of all surfaces of all three-dimensional cylinder geometric section blocks by utilizing non-uniform neutron surface flux and uniform neutron surface flux of the corresponding surfaces of all three-dimensional cylinder geometric section blocks, and subsequently, calculating and correcting for strong absorber diffusion.
The following describes the calculation of the discontinuity factor and the application of the discontinuity factor in the strong absorber diffusion calculation correction by taking HTR-PM as an example of the high temperature gas cooled reactor nuclear power station demonstration project, and specifically comprises the following steps:
step 1: an exemplary engineering HTR-PM simplified model schematic diagram of a high temperature gas cooled reactor nuclear power plant is shown in FIG. 1, and 7 reflecting layers and 1 carbon boride bricks are arranged outside a spherical reactor core. Constructing an HTR-PM model shown in FIG. 1 by utilizing Monte Carlo particle transport calculation software NECP-MCX, wherein the HTR-PM model is divided into 9 areas only in the radial direction according to a spherical reactor core, 7 reflecting layers and 1 layer of carbon boride bricks, the areas are not divided in the axial direction and the circumferential direction, and each layer of cylindrical ring is regarded as one area;
step 2: the Monte Carlo particle transport calculation software NECP-MCX is used for carrying out non-uniform neutron transport calculation on the HTR-PM model shown in the figure 1 to obtain the emergent neutron flow, the incident neutron flow and the non-uniform neutron surface flux of each layer of reflecting layer (comprising the boride carbon bricks) area with 2 surfaces (inner diameter surface and outer diameter surface) in the radial direction, wherein the inner diameter surface is taken as #) The external diameter surface is (++>) A noodle;
step 3: based on the outgoing neutron flow and the incoming neutron flow on the radial surface of each layer of reflecting layer area, the uniform neutron surface flux is calculated:
(1)
(2)
wherein:
-representing a radial direction;
-area number in radial direction, increasing from the core to the outside of the core, the value range is +.>；
-the first part of%>The +.about.th of the radially outer diameter surface of the individual zones>Uniform neutron surface flux of the population;
-the first part of%>The +.about.th of the radially outer diameter surface of the individual zones>A stream of incident neutrons of the population;
-the first part of%>The +.about.th of the radially outer diameter surface of the individual zones>An outgoing neutron stream of the population;
-the first part of%>The first +.>Uniform neutron surface flux of the population;
-the first part of%>The first +.>A stream of incident neutrons of the population;
-the first part of%>The first +.>An outgoing neutron stream of the population;
step 4: based on the non-uniform neutron surface flux and the uniform neutron surface flux of the radial surfaces of the areas of the reflecting layers, calculating the discontinuity factors of all radial surfaces of all areas:
(3)
(4)
wherein:
-the first part of%>The +.about.th of the radially outer diameter surface of the individual zones>A discontinuity factor for the population;
-the first part of%>The +.about.th of the radially outer diameter surface of the individual zones>A non-uniform neutron surface flux of the population;
-the first part of%>The first +.>A discontinuity factor for the population;
-the first part of%>The first +.>A non-uniform neutron surface flux of the population;
calculating HTR-PM one-dimensional cylinder problem using NEM diffusion program to obtain effective proliferation coefficients considering discontinuity factor and not considering discontinuity factor, respectivelyBy fine-mesh differential diffusionThe results of the calculation of the sequence CITATION are compared as a benchmark, and the results are shown in Table 1.
TABLE 1 comparison of the calculation results of HTR-PM one-dimensional cylindrical problem
As can be seen from table 1, the discontinuous factor is calculated based on the method of the invention, and the discontinuous factor is applied to the diffusion calculation of the high-temperature gas cooled reactor with the ball bed type and comprises a strong absorber, so that the calculation error can be effectively reduced. In addition, because neutron leakage correction is required to be considered in physical computation of the reactor core of the pebble-bed high-temperature gas cooled reactor, and the neutron leakage correction cannot be considered in the process of computing uniform neutron surface flux by the traditional method, and a high-precision discontinuous factor cannot be obtained through statistics, the effect of correcting strong absorber diffusion computation by using the discontinuous factor of the traditional method is inferior to that of correcting the discontinuous factor by using the method.
The innovation of the method is that: the method comprises the steps of directly calculating to obtain uniform neutron surface flux based on the outgoing neutron flow and the incoming neutron flow obtained through Monte Carlo non-uniform transport calculation according to neutron diffusion theory approximation, and calculating to obtain accurate discontinuity factors by combining the non-uniform neutron surface flux obtained through non-uniform transport calculation.
Claims (2)
1. A discontinuous factor calculation method applied to a pebble-bed high-temperature gas cooled reactor is characterized by comprising the following steps of: the method comprises the following steps:
step 1: dividing the spherical high-temperature gas cooled reactor reflecting layer into three-dimensional cylindrical geometric sections according to the actual layered structure of the spherical high-temperature gas cooled reactor reflecting layer in the radial direction, the circumferential direction and the axial direction, and building a spherical high-temperature gas cooled reactor physical model by utilizing a Monte Carlo physical calculation program;
step 2: carrying out non-uniform neutron transport calculation on a pebble-bed high-temperature gas cooled reactor physical model by using a Monte Carlo physical calculation program, and calculating to obtain emergent neutron flow, incident neutron flow and non-uniform neutron surface flux of three-dimensional cylindrical geometric segments in each layer of reflecting layers in the pebble-bed high-temperature gas cooled reactor physical model in the radial, circumferential and axial directions;
step 3: calculating to obtain uniform neutron surface flux of the corresponding surface of each three-dimensional cylindrical geometric segment by utilizing the outgoing neutron flow and the incoming neutron flow obtained in the step 2;
according to the neutron diffusion theory approximation, the uniform neutron surface flux is equal to twice the sum of the outgoing neutron flow and the incoming neutron flow of the surface:
(1)
(2)
wherein:
-representing the direction, comprising radial +>Circumference->And axial->；
-the surface of the nub;
-segment number;
、/>-differentiating the blocks in +.>Two faces in the direction, wherein +.>The faces represent the radial outer diameter face, the axially facing face and the circumferential clockwise face,/->The faces represent radially inner diameter faces, axially downwardly facing faces and circumferentially anticlockwise faces;
-the first part of%>Individual blocks->Direction +.>First->Uniform neutron surface flux of the population;
-the first part of%>Individual blocks->Direction +.>First->A stream of incident neutrons of the population;
-the first part of%>Individual blocks->Direction +.>First->An outgoing neutron stream of the population;
-the first part of%>Individual blocks->Direction +.>First->Uniform neutron surface flux of the population;
-the first part of%>Individual blocks->Direction +.>First->A stream of incident neutrons of the population;
-the first part of%>Individual blocks->Direction +.>First->An outgoing neutron stream of the population;
step 4: calculating a discontinuous factor of the corresponding surface of each three-dimensional cylinder geometric node block by utilizing the non-uniform neutron surface flux obtained in the step 2 and the uniform neutron surface flux obtained in the step 3, wherein a calculation formula is as follows;
(3)
(4)
wherein:
-the first part of%>Individual blocks->Direction +.>First->A discontinuity factor for the population;
-the first part of%>Individual blocks->Direction +.>First->A group non-uniform neutron surface flux;
-the first part of%>Individual blocks->Direction +.>First->A discontinuity factor for the population;
-the first part of%>Individual blocks->Direction +.>First->A non-uniform neutron surface flux of the population;
and (3) repeating the step (3) and the step (4) to obtain the discontinuous factors of all surfaces of all the sections, and then using the discontinuous factors for strong absorber diffusion calculation correction.
2. The method for calculating the discontinuity factor applied to the pebble-bed high-temperature gas cooled reactor according to claim 1, wherein the method comprises the following steps of: the Monte Carlo physical calculation program adopts MCNP, monte Carlo continuous energy neutron and photon transport program Serpent, stack Monte Carlo analysis program RMC or Monte Carlo particle transport calculation software NECP-MCX.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310265822.1A CN115983049B (en) | 2023-03-20 | 2023-03-20 | Discontinuous factor calculation method applied to pebble-bed high-temperature gas cooled reactor |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202310265822.1A CN115983049B (en) | 2023-03-20 | 2023-03-20 | Discontinuous factor calculation method applied to pebble-bed high-temperature gas cooled reactor |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN115983049A CN115983049A (en) | 2023-04-18 |
| CN115983049B true CN115983049B (en) | 2023-10-31 |
Family
ID=85972571
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202310265822.1A Active CN115983049B (en) | 2023-03-20 | 2023-03-20 | Discontinuous factor calculation method applied to pebble-bed high-temperature gas cooled reactor |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN115983049B (en) |
Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2004053420A (en) * | 2002-07-19 | 2004-02-19 | Mitsubishi Heavy Ind Ltd | Reactor core analyzing device and method for calculating diffusion constant in reflector region |
| CN105808503A (en) * | 2016-03-07 | 2016-07-27 | 西安交通大学 | Method for analyzing and solving discontinuous factors of lattice cells in bar-by-bar calculation of reactor |
| CN111950177A (en) * | 2020-07-22 | 2020-11-17 | 核工业西南物理研究院 | Multi-physical-field coupling neutron automatic optimization method for solid tritium production cladding |
| CN113254860A (en) * | 2021-06-04 | 2021-08-13 | 南京航空航天大学 | Method for calculating neutron flux of reactor core grid cells |
| CN114387421A (en) * | 2022-01-17 | 2022-04-22 | 哈尔滨工程大学 | Method for acquiring reactor core parameters of pebble bed reactor based on CMFD accelerated transport calculation |
| CN115358039A (en) * | 2022-04-28 | 2022-11-18 | 南京航空航天大学 | Variable segment block processing method, system and medium for complex reactor type core determination |
| CN115455669A (en) * | 2022-08-26 | 2022-12-09 | 华能核能技术研究院有限公司 | Method and system for determining homogenization group constant of high-temperature gas-cooled reactor pebble bed |
| CN115510374A (en) * | 2022-09-22 | 2022-12-23 | 华能核能技术研究院有限公司 | Detection method and device for safe operation of ball bed type high-temperature gas cooled reactor |
Family Cites Families (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US7233888B2 (en) * | 2002-07-09 | 2007-06-19 | General Electric Company | Monte Carlo criticality-mode systems and methods for computing neutron and gamma fluence in a nuclear reactor |
| US20050105675A1 (en) * | 2002-07-31 | 2005-05-19 | Shivakumar Sitaraman | Systems and methods for estimating helium production in shrouds of nuclear reactors |
-
2023
- 2023-03-20 CN CN202310265822.1A patent/CN115983049B/en active Active
Patent Citations (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2004053420A (en) * | 2002-07-19 | 2004-02-19 | Mitsubishi Heavy Ind Ltd | Reactor core analyzing device and method for calculating diffusion constant in reflector region |
| CN105808503A (en) * | 2016-03-07 | 2016-07-27 | 西安交通大学 | Method for analyzing and solving discontinuous factors of lattice cells in bar-by-bar calculation of reactor |
| CN111950177A (en) * | 2020-07-22 | 2020-11-17 | 核工业西南物理研究院 | Multi-physical-field coupling neutron automatic optimization method for solid tritium production cladding |
| CN113254860A (en) * | 2021-06-04 | 2021-08-13 | 南京航空航天大学 | Method for calculating neutron flux of reactor core grid cells |
| CN114387421A (en) * | 2022-01-17 | 2022-04-22 | 哈尔滨工程大学 | Method for acquiring reactor core parameters of pebble bed reactor based on CMFD accelerated transport calculation |
| CN115358039A (en) * | 2022-04-28 | 2022-11-18 | 南京航空航天大学 | Variable segment block processing method, system and medium for complex reactor type core determination |
| CN115455669A (en) * | 2022-08-26 | 2022-12-09 | 华能核能技术研究院有限公司 | Method and system for determining homogenization group constant of high-temperature gas-cooled reactor pebble bed |
| CN115510374A (en) * | 2022-09-22 | 2022-12-23 | 华能核能技术研究院有限公司 | Detection method and device for safe operation of ball bed type high-temperature gas cooled reactor |
Non-Patent Citations (4)
| Title |
|---|
| 周旭华 ; 李富 ; 王登营 ; 颜见秋 ; 韩松 ; .不连续因子应用于高温气冷堆三维扩散计算.原子能科学技术.2009,(第03期),全文. * |
| 张滕飞 ; 吴宏春 ; 曹良志 ; 李云召 ; 熊进标 ; 刘晓晶 ; .中子扩散三维非均匀变分节块法及平源加速方法研究.核动力工程.2018,(第02期),全文. * |
| 张竞宇 ; 李富 ; 孙玉良 ; 周夏峰 ; .球床高温气冷堆吸收体价值计算的验证.原子能科学技术.2013,(第S1期),全文. * |
| 田兆斐等.核动力装置建模与仿真.哈尔滨：哈尔滨工程大学出版社,2017,第53-54页. * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN115983049A (en) | 2023-04-18 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Zhang et al. | The Shandong Shidao Bay 200 MWe high-temperature gas-cooled reactor pebble-bed module (HTR-PM) demonstration power plant: an engineering and technological innovation | |
| Zhang et al. | Design aspects of the Chinese modular high-temperature gas-cooled reactor HTR-PM | |
| Beckert et al. | Development and verification of a nodal approach for solving the multigroup SP3 equations | |
| Balestra et al. | Pbmr-400 benchmark solution of exercise 1 and 2 using the moose based applications: Mammoth, pronghorn | |
| CN115983049B (en) | Discontinuous factor calculation method applied to pebble-bed high-temperature gas cooled reactor | |
| US20040096101A1 (en) | Calculation method of nuclear reactor core | |
| Haque et al. | Thermal response of a modular high temperature reactor during passive cooldown under pressurized and depressurized conditions | |
| Yang et al. | Core design study on CANDU-SCWR with 3D neutronics/thermal-hydraulics coupling | |
| CN103578579B (en) | A kind of fusion-fission subcritical energy reactor core of advanced person | |
| Jang et al. | Development of nodal diffusion code RAST-V for Vodo–Vodyanoi Energetichesky reactor analysis | |
| CN114203270A (en) | Subgroup parameter calculation method and system suitable for dispersed granular fuel | |
| Wang et al. | Improved nodal expansion method for solving neutron diffusion equation in cylindrical geometry | |
| Tran | Fuel burnup performance of an OTTO refueling pebble bed reactor with burnable poison loading | |
| CN114496314B (en) | Ultra-high flux reactor core with fast neutron thermal neutron concentric circle type partition | |
| Kunitomi et al. | Reactor core design of gas turbine high temperature reactor 300 | |
| Ma et al. | RMC/ANSYS Multi-physics Coupling solutions for Heat Pipe Cooled Reactors Analyses | |
| He et al. | Influence of Fuel Pellets’ Thermal Expansion on Temperature Feedback Regulation for Megawatt-Class Space Gas-Cooled Fast Reactor | |
| Fan et al. | Application of contour fitting method in CFETR VV assembly | |
| Jeong et al. | Verification of DeCART2D/CAPP code system for VHTR analysis with PMR-200 benchmark | |
| CN116502481A (en) | Multi-physical field coupling calculation method for thermoelectric integrated space reactor core | |
| Deokule et al. | Design of 33 pin annular fuel rod cluster for Advanced Heavy Water Reactor | |
| Wang et al. | KYLIN-V2. 0 Code Calculation Ability Verification Based on VERA Benchmar | |
| Khan et al. | Development of whole core pin-by-pin transport theory model in hexagonal geometry | |
| Chen et al. | Coaxial stacking disjoint model study of 10 MW high temperature gas-cooled reactor (HTR-10) | |
| Strydom | Phisics/relap5-3D results for exercises II-1 and II-2 of the OECD/NEA mhtgr-350 benchmark |
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 | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |