... design and construction of high flux reactor. high flux reactors plate type fuel elements safety analysis thermal effects irradiation effects hydraulic effects corrosion effects Proceedings of the 2024 31st International Conference on Nuclear Engineering ICONE31 August 4-8, 2024, Prague...

... performance in various accident scenarios. This code thus provides an effective tool for the design and safety analysis of heat pipe cooled reactors. heat pipe thermal-hydraulic safety analysis system code Proceedings of the 2024 31st International Conference on Nuclear Engineering ICONE31 August...

... in design basis conditions and design extension conditions, as well as multi-plant tests in active and passive plant. In addition, the test facility has the ability to provide test data under accident conditions, verify safety analysis procedures, and study the impact of key equipment and main operating...

... not show significant influence on heat removal as the changes of the heat flux profile and the wall thickness (that are of interest in safety analysis) are insignificant; the main contribution to the enhancement of the safety margin by spray cooling would be from the expected significant improvement...

... for the efficient use of nuclear energy. combined heat and power generation nuclear power plant safety analysis Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-92883 SAFETY ANALYSIS ABOUT COMBINED HEAT AND POWER GENERATION...

.... After activation, the secondary neutron source assembly needs to be adapted to the simulated fuel assemblies by underwater operation, and then integrated into a dedicated secondary neutron source assembly transport cask and transported to the reactor core. Therefore, the safety analysis...

... parameters used in this paper, heaving and rolling motion cannot have a substantial impact on the safe operation of FNR under rated power operation. external force field ocean condition reactor operation safety analysis Proceedings of the 2022 29th International Conference on Nuclear Engineering...

... for the detection of the event, which is the development target of the plant protection system in pool-type SFR. pool-type SFR pump/diagrid link guillotine break safety analysis safety protection system signals Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August...

... established. In the future, it is more important to improve the regulatory capacity. Only by establishing a perfect technology R & D system can nuclear safety decision-making be based on sufficient scientific basis. nuclear facilities supervision technical support test bench safety analysis...

... of the core loaded with annular fuel by 50%. annular fuel PWR safety analysis Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29 August 8-12, 2022, Virtual, Online ICONE29-92118 PERFORMANCE EVALUATION OF TYPICAL 3-LOOP PWR WITH ANNULAR FUEL ASSEMBLIES UNDER TYPICAL...

... the predictions of outer vessel temperature and residual wall thickness while the influence on the inner vessel temperature is negligible. in-vessel retention boiling heat transfer code development safety analysis Proceedings of the 2022 29th International Conference on Nuclear Engineering ICONE29...

.... This article makes a safety analysis of this technical modification using PSA method to determine the necessity of the technical modification. Qinshan nuclear power plant the reactor coolant pump PSA safety analysis Proceedings of the 2021 28th International Conference on Nuclear Engineering...

...]. On the same time, SAMOFAR in the UE project solidification and melting process. has also developed freeze valve design for MSFR [4], this study is still limited in the computational. The EU researcher develop Keywords: Advanced Reactors, MSR, Safety analysis, CFD, a freeze valve which is different with MSRE...

.... transient LBE-cooled BLESS TRACE safety analysis Proceedings of the 2021 28th International Conference on Nuclear Engineering ICONE28 August 4-6, 2021, Virtual, Online ICONE28-63220 PRELIMINARY TRANSIENT ANALYSIS FOR LBE-COOLED FAST REACTOR BLESS-D Mian Xing, Linsen Li, Gang Zheng, Junlang Wen...

... As a latest developed computational code, TRACE is expected to be useful and effective for analyzing the thermal-hydraulic behaviors in design, licensing and safety analysis of nuclear power plant. However, its validity and correctness have to be verified and qualified before its application...

... exit temperature (CET) is significantly influenced by the bypass flow area between downcomer and hot leg. Key words: SBLOCA, LSTF, TRACE, thermal-hydraulics transient, safety analysis INTRODUCTION The ROSA program was initiated in 70s of last century to study the thermal-hydraulic phenomena of light...

... 1 Copyright © 2013 by ASME SAFETY ANALYSIS ON MITIGATION OVERPRESSURE ATWS IN VVER-1000 NPP QiTing1 China Nuclear Power Engineering Co., Ltd Beijing, China Yangchangjiang2 China Nuclear Power Engineering Co., Ltd Beijing, China ABSTRACT Safety analysis on operating nuclear power plant (NPP) plays...

... Best-Estimate Licensing FSAR Safety Analysis Atucha-2 Within the licensing process of the Atucha II PHWR (Pressurized Heavy Water Reactor) the BEPU (Best Estimate Plus Uncertainty) approach has been selected for issuing of the Chapter 15 on FSAR (Final Safety Analysis Report). The key...

... of the operational and safety systems. The effectiveness of the applied accident management measures and the effect on the accident progression were studied in order to assess the maximum response time for operators’ intervention. safety analysis accident management measures ATHLET VVER-1000 1 Copyright...

.... The work contributes to the reliability of the ASTEC code by means of plant applications. safety analysis severe accidents accident management measures ASTEC ATHLET ANSYS 1 Copyright © 2009 by ASME Proceedings of the 17th International Conference on Nuclear Engineering ICONE17 July 12-16...