http://rdf.ncbi.nlm.nih.gov/pubchem/patent/CN-113221480-B
Outgoing Links
Predicate | Object |
---|---|
classificationCPCAdditional | http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G06F2119-08 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/Y02E30-30 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G06F2119-14 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G06F2119-02 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G06F2113-08 |
classificationCPCInventive | http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G16C10-00 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G06F30-28 http://rdf.ncbi.nlm.nih.gov/pubchem/patentcpc/G16C20-10 |
classificationIPCAdditional | http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G06F119-14 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G06F119-02 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G06F113-08 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G06F119-08 |
classificationIPCInventive | http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G16C20-10 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G06F30-28 http://rdf.ncbi.nlm.nih.gov/pubchem/patentipc/G16C10-00 |
filingDate | 2021-05-14-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
grantDate | 2022-10-28-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
publicationDate | 2022-10-28-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
publicationNumber | CN-113221480-B |
titleOfInvention | A failure analysis method for reactor vessel in sodium-cooled fast reactor core disintegration accident |
abstract | A method for analyzing the failure of a sodium-cooled fast reactor core disintegration accident reactor vessel, the steps are as follows: 1. The Euler method is used to establish the mass conservation equation, the momentum conservation equation and the energy conservation equation for the gas-liquid two-phase coolant, and the Lagrangian method is used to establish the mass conservation equation, the momentum conservation equation and the energy conservation equation. The daily method establishes the momentum conservation equation and the energy conservation equation for the core melt; 2. Establishes the fluid calculation area and the solid calculation area for the sodium-cooled fast reactor core; 3. The contact surface between the solid calculation area and the fluid calculation area in step 2 4. During the calculation, according to the parameters of the initial time t0 of the fluid calculation area and the solid calculation area in step 2, transfer the parameters of the coupling surface, and iteratively calculate the state parameters of the fluid calculation area at the next time t1, until the last time, get The stress-strain curve of the stack vessel in the solid calculation region. The method of the invention can comprehensively evaluate the failure situation of the reactor vessel after the core disintegration accident of the sodium-cooled fast reactor, and provide a basis for evaluating the safety of the reactor more comprehensively and effectively. |
priorityDate | 2021-05-14-04:00^^<http://www.w3.org/2001/XMLSchema#date> |
type | http://data.epo.org/linked-data/def/patent/Publication |
Incoming Links
Predicate | Subject |
---|---|
isDiscussedBy | http://rdf.ncbi.nlm.nih.gov/pubchem/compound/CID5360545 http://rdf.ncbi.nlm.nih.gov/pubchem/substance/SID419559553 |
Total number of triples: 25.