| Predicate |
Object |
| assignee |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentassignee/MD5_eda37409f26cb8e833ba67f2b1bc1fd5 |
| classificationCPCAdditional |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G06F2113-08
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G06F2119-14 |
| classificationCPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G06F30-28
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G06F30-23
http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G16C10-00 |
| classificationIPCAdditional |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G06F119-14
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G06F113-08 |
| classificationIPCInventive |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G06F30-23
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G06F30-28
http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G16C10-00 |
| filingDate |
2021-03-29-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| inventor |
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_891d15bb9fc0f7c7255c71b582061d6a
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_5d9f5ff8de942cd5bbfbb506d3763ada
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_28d8c25019a8257ca8f9d662f7efa278
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_a469e3e8b958594dbc324178b2500def
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_4c0ae41f1cf9ec23c9b993f703e5f272
http://rdf.ncbi.nlm.nih.gov/pubchem/patentinventor/MD5_d66967c388f813c283c8f49fca3f6e0e |
| publicationDate |
2021-07-09-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| publicationNumber |
CN-113094947-A |
| titleOfInvention |
A nuclear reactor core thermal coupling analysis method |
| abstract |
The invention discloses a nuclear reactor core thermal coupling analysis method. The steps are as follows: 1. Build a grid model according to the core geometry; 2. Build a physical-thermal two-way feedback model, including a thermal-physical data transfer model and a physical ‑ Thermal data transfer model; 3. According to the grid model and feedback model, establish a nuclear thermal coupling calculation method: update the core macro section according to thermal parameters and a small group of macro section library; based on the finite volume method, according to the core macro section Solve the few-group neutron diffusion equation to obtain the core neutron flux distribution; convert the neutron flux distribution into the core heat source distribution; based on the porous medium method and the fuel rod temperature solution method, the thermal hydraulic calculation of the core is performed, Obtain relevant thermal parameters; repeat the above steps until the calculation converges. The invention can realize the high-precision steady-state thermal coupling analysis of the core of the nuclear reactor, and obtain the distribution results of actual thermal hydraulic parameters and neutron dynamics parameters of the core. |
| isCitedBy |
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-113609733-A
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-115662664-A
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-114282460-A
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-115358125-A
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/WO-2023116189-A1
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-115691708-B
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-113887097-A
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-115691708-A
http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-115662664-B |
| priorityDate |
2021-03-29-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
| type |
http://data.epo.org/linked-data/def/patent/Publication |