Muhammad et al., 2015 - Google Patents
ICONE23-2061 RELIABILITY MONITOR DEVELOPMENT FOR PASSIVE SAFETY SYSTEM OF AP1000 IN NEW CONCEPT OF RISK MONITOR SYSTEMMuhammad et al., 2015
View PDF- Document ID
- 9619909551478577219
- Author
- Muhammad H
- Yoshikawa H
- Matsuoka T
- Ma Z
- Publication year
- Publication venue
- The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23
External Links
Snippet
College of Nuclear Science and Technology, College of Nuclear Science and Technology, Harbin Engineering University, Heilongjiang, Harbin Engineering University, Heilongjiang, Harbin, 150001, PR China, Harbin, 150001, PR China, mats@ cc. utsunomiya-u. ac. jp …
- 238000011161 development 0 title description 3
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 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
- G05—CONTROLLING; REGULATING
- G05B—CONTROL OR REGULATING SYSTEMS IN GENERAL; FUNCTIONAL ELEMENTS OF SUCH SYSTEMS; MONITORING OR TESTING ARRANGEMENTS FOR SUCH SYSTEMS OR ELEMENTS
- G05B23/00—Testing or monitoring of control systems or parts thereof
- G05B23/02—Electric testing or monitoring
- G05B23/0205—Electric testing or monitoring by means of a monitoring system capable of detecting and responding to faults
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/001—Computer implemented control
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| Hashim et al. | Quantitative dynamic reliability evaluation of AP1000 passive safety systems by using FMEA and GO-FLOW methodology | |
| Cho et al. | Framework to model severe accident management guidelines into Level 2 probabilistic safety assessment of a nuclear power plant | |
| Burgazzi | Reliability of passive systems in nuclear power plants | |
| Petruzzi et al. | The BEPU Evaluation Model with RELAP5-3D for the Licensing of the Atucha-II NPP | |
| Lee et al. | Application of dynamic probabilistic safety assessment approach for accident sequence precursor analysis: case study for steam generator tube rupture | |
| Muhammad et al. | ICONE23-2061 RELIABILITY MONITOR DEVELOPMENT FOR PASSIVE SAFETY SYSTEM OF AP1000 IN NEW CONCEPT OF RISK MONITOR SYSTEM | |
| Choi et al. | Development of risk assessment framework and the case study for a spent fuel pool of a nuclear power plant | |
| Jung et al. | Quantitative assessment of severe accident management strategies in a nuclear power plant | |
| Bašić et al. | Assessment of potential impact of combustible gases from reactor core damage on risk of outside containment spent fuel pool damage | |
| Zubair | Investigation of Loss of Feedwater (LOFW) Accident in the APR‐1400 Using Fault Tree Analysis | |
| Guo | Model-Based Cyber-Security Framework for Nuclear Power Plant | |
| Wang et al. | The implementation of diverse actuation system in ACPR1000 nuclear power plants | |
| Kosowski et al. | External Hazard Coinciding With Small Break LOCA—Thermohydraulic Calculation With System Code ATHLET | |
| Trifanov | Pressurized heavy water reactors probabilistic safety assessment | |
| Yu et al. | Study on Methodology and Application of Seismic-Induced Flood Level 2 PSA for PWR in China | |
| Zheng | Study on Methodology and Application of Seismic Level 2 Probabilistic Safety Assessment for Nuclear Power Plants | |
| Vicini | Final design of the safety-relevant Chilled Water System (CHWS-1) of ITER plant | |
| Liu et al. | PROBABILISTIC RISK ASSESSMENT FOR FIRE INDUCED INTERFACING SYSTEM LOCA IN NUCLEAR POWER PLANTS | |
| Varde | Risk Simulation | |
| Statsura et al. | Using the unit software model to improve design solutions and optimize process management | |
| Liu et al. | Study on Shutdown Fire PRA for Nuclear Power Plant | |
| Lee et al. | A framework for evaluating hydrogen control and management | |
| Muhlheim | Identification of Initiating Events for aSMRs | |
| Verma et al. | Applications of Probabilistic Safety Assessment | |
| Uspuras | Status of Ignalina's safety analysis reports |