Results 81 to 90 of about 176 (127)

Design process of the nanofluid injection mechanism in nuclear power plants. [PDF]

Nanoscale Res Lett, 2011
Kang MS, Jee C, Park S, Bang IC, Heo G.
europepmc   +1 more source

Vibration analysis of reactor internals in SMART and APR1400

The Proceedings of the Dynamics & Design Conference, 2016
PARK, No-Cheol, CHOI, Youngin, PARK, Jong-Beom, LEE, Sang-Jeong, PARK, Young-Pil, KIM, Yong Beum   +5 more
openaire   +1 more source

Sensitivity neutronic analysis of accident tolerant fuel concepts in APR1400

Journal of Nuclear Materials, 2023
Nouf T. Alhattawi, Mohammad Alrwashdeh, Saeed A. Alameri, Maitha M. Alaleeli   +3 more
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Development of Engineering Program for APR1400 Feedwater Supplying System

Journal of Energy Engineering, 2017
Dong Un Yeom, Tae Young Ju, Jin Woo Hyun
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Advantages of the AFWS for APR1400 in Response to SBO using MARS Code

International Journal of Engineering Research and, 2016
null Islam Elaswakh, null Oh Seung-Jong
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Economic Evaluation of Coupling APR1400 with a Desalination Plant in Saudi Arabia

Journal of the Korea Society of Systems Engineering, 2016
M. Gomaa Abdoelatef, Robert M. Field, YongKwan Lee   +2 more
openaire   +2 more sources

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Reduction of EPZ area for APR1400 and its public acceptance

Progress in Nuclear Energy, 2004
Abstract Since ALWRs are anticipated to provide an enhanced margin of safety and newer nuclear power plants have a higher standard of severe accident safety performance than the existing plant designs, recent efforts aimed at simplifying the concept of EPZ for ALWR standard plant designs had been made by a group of utility companies through the EPRI ...
Young Wook Lee, Chang Sun Kang, Joo Hyun Moon   +2 more
exaly   +2 more sources

Computerized procedure system for the APR1400 simulator

Nuclear Engineering and Design, 2009
Abstract The ShinKori Unit 3&4 which is the reference plant for APR1400 simulator plans to utilize various display devices and computerized Human Machine Interface (HMI) as well as many kinds of digitalized instrumentation and control. The operating crew will be given a lot of information on display devices in order to diagnose the system states and ...
Jin-Hyuk Hong, Myeong-Soo Lee, Do-Hyun Hwang   +2 more
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Verification of SAMG entry condition for APR1400

Annals of Nuclear Energy, 2015
Abstract The entry condition of the Severe Accident Management Guideline (SAMG) for APR1400 has been evaluated on the basis of the Core Exit Temperature (CET) and Peak Cladding Temperature (PCT) calculated by the MARS-KS code. Although the APR1400 is a new type of reactor in Korea, it has been used the same entry condition to the SAMG as the former ...
Junghyun Yun, Taewan Kim, Jonghyun Kim
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Preliminary feasibility study of PCM condenser for PCCS of APR1400

Annals of Nuclear Energy, 2021
Abstract Passive cooling has become an important factor in safety of nuclear reactors. Many ideas were proposed for the passive cooling of the containment but most are limited in application on existing power plants. A passive containment cooling system using PCM (Phase Change Material) is introduced in this study. Among various PCMs, one organic PCM
Jai Oan Cho, Areum Ko, Sung Gil Shin, Hwa-Young Jung, Jeong Ik Lee   +4 more
openaire   +1 more source