Westinghouse AP1000 Internals Heating Rate Distribution Calculation Using a 3D Deterministic Transport Method
Effects Of Root Opening On The Mechanical Properties And Heat Affected Zone (HAZ) in High Strength Low Alloy (HSLA) Steel
Implementation of the SPINLINE 3 Nuclear Instrumentation System at the QINSHAN Phase II PWR nuclear power plants
Simulation Program of the Nuclear Reactor Core with WIMS and COBRA Source Code and Solution to Dynamic Equations by Finite Element Method
Defueling, Storage and Following Treatment of Spent Fuel of Heavy Liquid Metal Cooled Reactors: Status and Problems
IRIS(INTERNATIONAL REACTOR INNOVATIVE AND SECURE)Safety System and Equipment Design Verification Test Plan
Experimental Study Of Natural Convection In Horizontal And Vertical Cylindrical Pipe With Different End Temperatures(Effects of Piping Geometry and Temperature)