El-Hameed et al., 2021 - Google Patents
Machine Learning-Based Classification and Regression Approach for Sustainable Disaster Management: The Case Study of APR1400 in Korea. Sustainability 2021 …El-Hameed et al., 2021
View PDF- Document ID
- 1037525308948012550
- Author
- El-Hameed A
- Kim J
- Publication year
External Links
Snippet
During nuclear accidents, decision-makers need to handle considerable data to take appropriate protective actions to protect people and the environment from radioactive material release. In such scenarios, machine learning can be an essential tool in facilitating …
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
- G21C17/0225—Chemical surface treatment, e.g. corrosion
-
- 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
- Y02E30/40—Other aspects relating to nuclear fission
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21Y—INDEXING SCHEME RELATING TO NUCLEAR REACTORS, POWER PLANTS AND EXPLOSIVES, TO PROTECTION AGAINST RADIATION, TO THE TREATMENT OF RADIOACTIVELY CONTAMINATED MATERIAL, TO APPLICATIONS OF RADIOACTIVE SOURCES AND TO THE UTILISATION OF COSMIC RADIATION
- G21Y2004/00—SOLUTION
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Lee et al. | Risk and safety analysis of nuclear systems | |
Khan et al. | A PCTRAN-based investigation on the effect of inadvertent control rod withdrawal on the thermal-hydraulic parameters of a VVER-1200 nuclear power reactor | |
Beckjord et al. | Probabilistic safety assessment development in the United States 1972–1990 | |
Alrammah | Application of probabilistic safety assessment (PSA) to the power reactor innovative small module (PRISM) | |
Couturier et al. | Elements of nuclear safety: research reactors | |
Nourbakhsh et al. | The evolution of the US nuclear regulatory process | |
Menzel et al. | Proposal for systematic application of BEPU in the licensing process of nuclear power plants | |
El-Hameed et al. | Machine Learning-Based Classification and Regression Approach for Sustainable Disaster Management: The Case Study of APR1400 in Korea. Sustainability 2021, 13, 9712 | |
Hossain et al. | Analysis of a pressurised water reactor-based nuclear accident using PCTRAN simulator and fuzzy expert system | |
Stewart et al. | Examination of diversion and misuse detection for a generalized sodium-cooled fast test reactor | |
Vechgama et al. | Application of release starting time classification for planning emergency preparedness and response to the hypothetical accident scenario of iPWR-SMR in Thailand | |
Awan et al. | Sensitivity analysis of fission product activity in primary coolant of typical PWRs | |
Saleh et al. | Enhancing resilience through nuclear emergency preparedness at El Dabaa site | |
Nissan | Intelligent technologies for nuclear power systems: heuristic and neural tools | |
Trivedi et al. | Uncertainty analysis of large break LOCA for pressurized heavy water reactor | |
Salmassian et al. | Diagnosing core local flow blockages in a VVER-1000/446 reactor using ex-core detectors and neural networks | |
Bernero | Probabilistic risk analyses: NRC programs and perspectives | |
Chakinis | Reactivity feedback analysis for EBR-II benchmark | |
Wang et al. | Source term analysis and sorting scheme in post-irradiation spherical pyrometric elements | |
Haddad et al. | Comparative health and environmental risks for various energy sources. | |
Khubchandani et al. | Reliability assessment of the passive heat removal system of the VVER-1000 reactor at Kudankulam NPP | |
Choi et al. | A Simple Accident Management Support Tool based on source-term category using RNN-LSTM | |
Miyashita et al. | The evaluation of level 2 PRA in consideration of seismic risk | |
BOARD | DETERMINISTIC SAFETY ANALYSIS FOR WATER COOLED REACTOR BASED NUCLEAR POWER PLANTS | |
Xie et al. | Technical research on rapid source term calculation and prediction technology of nuclear accidents based on Bayesian network |