Relap 5 Analysis of AP1000 Pressured Water Reactor Containment

Relap 5 Analysis of AP1000 Pressured Water Reactor Containment

碩士 === 國立清華大學 === 核子工程與科學研究所 === 99

Bibliographic Details
Main Authors:	Tseng, Shao-Wei, 曾紹維
Other Authors:	Lee, Min
Format:	Others
Language:	zh-TW
Published:	2011
Online Access:	http://ndltd.ncl.edu.tw/handle/77710661284707583651

Similar Items

AP1000 Large Break LOCA Analysis using RELAP5-3D
by: Wang, Chun-Lung, et al.
Published: (2011)

Margin Assessment of AP1000 In-vessel Retention using RELAP5-3D
by: 劉相君
Published: (2011)

Transformation of pressurized water reactor AP1000 to fuzzy graph
by: Ashaari, Azmirul, et al.
Published: (2018)

Development of MAAP 5 Model for safety analysis in Advanced Pressurized Water Reactor (AP-1000)
by: 吳思穎
Published: (2012)

Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code
by: Eltayeb Yousif, et al.
Published: (2017-01-01)

Applicability Study and Assessment for RELAP5-3D Light Water Reactor Containment Model
by: Liang-Che Dai, et al.
Published: (2016)

Code Development in Coupled PARCS/RELAP5 for Supercritical Water Reactor
by: Po Hu, et al.
Published: (2014-01-01)

Transient Analyses of Advanced Boiling Water Reactor of Lungmen Nuclear Power Station using RELAP5/MOD3
by: 劉紹楷
Published: (2008)

Study of the Reactor Control System of MSHIM in AP1000
by: Xinyu Wei, et al.
Published: (2015-01-01)

Transient Analyses of Supercritical Water Reactor using RELAP5/MOD3
by: Ya-Lin Li, et al.
Published: (2008)

Analysis for the Effect of Spatial Discretization Method on AP1000 Reactor Pressure Vessel Fluence Calculation
by: Junxiao Zheng, et al.
Published: (2016-01-01)

The Investigation of Nonavailability of Passive Safety Systems Effects on Small Break LOCA Sequence in AP1000 Using RELAP5 MOD 4.0
by: Anwar Hussain, et al.
Published: (2016-01-01)

RELAP5 SIMULATION FOR SEVERE ACCIDENT ANALYSIS OF RSG-GAS REACTOR
by: Andi Sofrany Ekariansyah, et al.
Published: (2018-01-01)

Thermal-hydraulic analysis of VVER-1000 residual heat removal system using RELAP5 code, an evaluation at the boundary of reactor repair mode
by: Z. Tabadar, et al.
Published: (2018-09-01)

Assessment of RELAP5 model for the University of Massachusetts Lowell Research Reactor
by: Bousbia-Salah Anis, et al.
Published: (2006-01-01)

Transient Analysis of Advanced Boiling Water Reactor of Lungmen Nuclear Power Station using RELAP5-RT
by: Hsu, Keng-Hsien, et al.
Published: (2009)

Simulation of Spray Injection in the Pressurizer Using RELAP5
by: S. Dibyo, et al.
Published: (2017-08-01)

THE THERMAL-HYDRAULICS ANALYSIS ON RADIAL AND AXIAL POWER FLUCTUATION FOR AP1000 REACTOR
by: Muh. Darwis Isnaini, et al.
Published: (2015-06-01)

Core Design of a Small Pressurized Water Reactor with AP1000 Fuel Assembly Using SRAC and COBRA-EN Codes
by: Van Khanh Hoang
Published: (2020-01-01)

RELAP5/MOD3 Analyses of Loss Residual Heat Removal Event in the Mid-Loop Operation of a Pressurized Water Reactor
by: Wu, Peng-Fei, et al.
Published: (1998)

PRELIMINARY ANALYSIS OF CORE TEMPERATURE DISTRIBUTION OF EXPERIMENTAL POWER REACTOR USING RELAP5
by: Andi Sofrany Ekariansyah, et al.
Published: (2018-11-01)

Thermal-hydraulic calculations for a fuel assembly in a European Pressurized Reactor using the RELAP5 code
by: Skrzypek Maciej, et al.
Published: (2015-09-01)

Simulation of a TRIGA Reactor Core Blockage Using RELAP5 Code
by: Patrícia A. L. Reis, et al.
Published: (2015-01-01)

DEVELOPMENT OF EXPERIMENTAL POWER REACTOR (EPR) MODEL FOR SAFETY ANALYSES USING RELAP5
by: Andi Sofrany Ekariansyah, et al.
Published: (2019-07-01)

Nodalization effects on RELAP5 results related to MTR research reactor transient scenarios
by: Khedr Ahmed, et al.
Published: (2005-01-01)

HPR1000: Advanced Pressurized Water Reactor with Active and Passive Safety
by: Ji Xing, et al.
Published: (2016-03-01)

Influence of Modelling Options in RELAP5/SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity
by: Siniša Šadek, et al.
Published: (2010-01-01)

Startup Thermal Analysis of a Supercritical-Pressure Light Water-Cooled Reactor CSR1000
by: Yuan Yuan, et al.
Published: (2018-11-01)

Relap5-3d model validation and benchmark exercises for advanced gas cooled reactor application
by: Moore, Eugene James Thomas
Published: (2006)

SPES3 Facility RELAP5 Sensitivity Analyses on the Containment System for Design Review
by: Andrea Achilli, et al.
Published: (2012-01-01)

Effects of superimposed cyclic operation on corrosion products activity in reactor cooling system of AP-1000
by: Fiaz Mahmood, et al.
Published: (2019-07-01)

PENGEMBANGAN MODEL UNTUK SIMULASI KESELAMATAN REAKTOR PWR 1000 MWe GENERASI III+ MENGGUNAKAN PROGRAM KOMPUTER RELAP5
by: Andi Sofrany Ekariansyah, et al.
Published: (2015-04-01)

THERMAL-HYDRAULICS PARAMETER ANALYSIS OF THE BANDUNG TRIGA 2000 REACTOR BASED ON CFD AND RELAP5/MOD3.2
by: Reinaldy Nazar
Published: (2015-04-01)

New RELAP5-3D Lead and LBE Thermophysical Properties Implementation for Safety Analysis of Gen IV Reactors
by: P. Balestra, et al.
Published: (2016-01-01)

ANALYSIS OF REACTIVITY COEFFICIENT CHANGE DUE TO BURN UP IN AP1000 REACTOR CORE USING NODAL3
by: Iman Kuntoro, et al.
Published: (2017-10-01)

Benchmarking COMSOL Multiphysics Single-Subchannel Thermal-Hydraulic Analysis of a TRIGA Reactor with RELAP5 Results and Experimental Data
by: Ahmed K. Alkaabi, et al.
Published: (2019-01-01)

Effect of Air Temperature on Failure Prognosis of Passive Containment Cooling System in AP1000
by: Y. Yu, et al.
Published: (2013-07-01)

Coupling RELAP5-3D and Fluent to analyze a Very High Temperature Reactor (VHTR) outlet plenum
by: Anderson, Nolan Alan
Published: (2006)

TRIGA-2000 Research Reactor Thermal-hydraulic Analysis using RELAP/SCDAPSIM/MOD3.4
by: Anhar Riza Antariksawan, et al.
Published: (2017-07-01)

CFD Investigating the Pressure Thermal Shock Behavior in Pressurized Water Reactor
by: Tseng, Ting-Kang, et al.
Published: (2014)

Cannot write session to /tmp/vufind_sessions/sess_d041bmi1i8n40nc68hn01a2hhn