Pressurized Water Reactor
Experimental Validation of the Material Properties of the Inner Containment of the Pressurized Water Reactor (EPR Type)
6
Structural Analysis and Evaluation on the Containment Structure of the Pressurized Water Reactor Plants with Consideration of the Aging Effects
10
Impact Analysis of a Spacer Grid Assembly of Dual Cooled Fuel for Pressurized Water Reactor
7
Prognostic modelling utilizing a high fidelity pressurized water reactor simulator
7
Simulation of the static mechanical behaviour of a pressurized water reactor fuel assembly
7
IASCC Susceptibility On Core Baffle Barrel Structure In Pressurized Water Reactor
9
Neutron-gamma flux and dose calculations in a Pressurized Water Reactor (PWR)
8
Impact and benefit of the Pre-stressing System on the Inner Containment of the Pressurized Water Reactor (EPR Type)
7
Analysis of Neutronics and Thermal Hydraulic Behavior in a Fuel Pin of Pressurized Water Reactor (PWR)
10
Passive Cooldown Performance of Integral Pressurized Water Reactor
5
Comparison of Standard Light Water Reactor Cross-Section Libraries using the United States Nuclear Regulatory Commission Pressurized Water Reactor Standard Core Loading Benchmark Problem
9
Steam Generator Liquid Mass as a Control Input for the Movement of the Feed Control Valve in a Pressurized Water Reactor
129
HFR Informations for Users Survey of high flux facilities in the HFR Petten, selected for boiling water and pressurized water reactor (BWR and PWR) materials testing EUR 4639
48
Development of a Generalized Flaw Distribution as Input to the Re-evaluation of the Technical Basis for U.S. Pressurized Thermal Shock Regulation of Pressurized Water Reactor Vessels
8
The Use of Acoustic Monitoring to Manage Concrete Structures in the Nuclear Industry (O380)
15
Predictive Study of CAP1400 Core Barrel Flow-induced Vibration-Part1: Turbulence-induced Forcing Function
10
Cracking Susceptibility of Irradiated Stainless Steels in a Simulated PWR Environment
11
Risk-Informed Assessment of Degraded Containment Structures (D455)
8
Influence of Thermal Ageing and Specimen Size on Fracture Toughness of Z3CN20 09M Casting Duplex Stainless Steels
5
Contribution to the study of fission products release from nuclear fuels in severe accident conditions: effect of the pO2 on Cs, Mo and Ba speciation
10