Results 51 to 60 of about 8,242 (166)

Simulation Study of Micro-Natural Circulation in the Reactor Pressure Vessel During Cold Shutdown Maintenance

Mathematics
To investigate the micro-natural circulation phenomenon within the pressure vessel of a small nuclear reactor during cold shutdown maintenance, a comprehensive reactor pressure vessel model was developed utilizing the RELAP5 3D program.
Fulong Tang, Yuqing Chen, Wei Wang, Hongguang Xiao   +3 more
doaj   +1 more source

Occupational ALARA Planning for Reactor Pressure Vessel Dismantling at Kori Unit 1. [PDF]

Int J Environ Res Public Health, 2020
Kim J, Tseren B.
europepmc   +1 more source

Pressurized Thermal Shock analysis of the reactor pressure vessel

Procedia Structural Integrity, 2018
Abstract PTS analysis is a substantial part of the technical analyses supporting the license application for operation beyond design life. Guidance for the analysis’ concept is given by the Hungarian nuclear regulator which is in line with the relevant international rules.
openaire   +1 more source

Experimental Study on Influence of External Pressure Vessel Cooling Parameters on Critical Heat Flux

Yuanzineng kexue jishu
In-vessel retention (IVR) of molten material, as one of the most important mitigation measures for serious accidents, can effectively prevent the leakage of molten material from the core to the outside of the pressure vessel, resulting in the release of ...
ZHANG Zhen1, 2, XIONG Wanyu2, XING Dianchuan2, ZAN Yuanfeng2, WANG Guangjin2, CHEN Deqi1, 3, , XU Jianjun2
doaj   +1 more source

Assessment of thermal safety margins for the IVR-ERVC strategy of the i-SMR using the CINEMA code

Nuclear Engineering and Technology
In-vessel corium retention with external reactor vessel cooling (IVR-ERVC) is a key severe accident mitigation strategy to prevent lower-head failure and retain fission products inside the reactor vessel. This study assesses the applicability of IVR-ERVC
Dong-Hun Shin, Sang Ho Kim, Donggun Son, Yonadan Choi, Young Hee Kim, Hyoung Suk Yu, Yong Hoon Jeong   +6 more
doaj   +1 more source

Dragon Reactor Pressure Vessel [PDF]

Nature, 1962
openaire   +1 more source

On the Elevated Temperature Thermal Stability of Nanoscale Mn-Ni-Si Precipitates Formed at Lower Temperature in Highly Irradiated Reactor Pressure Vessel Steels. [PDF]

Sci Rep, 2019
Almirall N, Wells PB, Ke H, Edmondson P, Morgan D, Yamamoto T, Odette GR.   +6 more
europepmc   +1 more source

Effects of Ar Ion Irradiation on Mechanical Properties and Microstructure of SA508 Grade 3 Class 1 and Class 2 Reactor Pressure Vessel Steels. [PDF]

Materials (Basel)
Kim HA, Kim M, Choi S, Kim S.
europepmc   +1 more source

Effects of triaxial rolling on the microstructure and installation characteristics of reactor pressure vessel studs. [PDF]

Sci Rep
Zhu W, Li H, Wang D, Cheng P, Li L, Feng F, Zhou P.   +6 more
europepmc   +1 more source

Evaluation of the Embrittlement in Reactor Pressure-Vessel Steels Using a Hybrid Nondestructive Electromagnetic Testing and Evaluation Approach. [PDF]

Materials (Basel)
Vértesy G, Rabung M, Gasparics A, Uytdenhouwen I, Griffin J, Algernon D, Grönroos S, Rinta-Aho J.   +7 more
europepmc   +1 more source