Flaw density examinations of a clad boiling water reactor pressure vessel segment

Reactor Pressure Vessel Embrittlement—i

Aging and Life Management System of Reactor Pressure Vessel

Reactor pressure vessel (RPV), the only key component that can not be replaced in nuclear power plants (NPPs), is the main barrier against the radioactive leakage. The lifetime of NPPs is dependent heavily on the life of RPV, and thus, the aging and life research on a RPV is a key factor in determining the life extension of NPPs. The purpose of this paper is to introduce an aging and life manag...

Positron Annihilation Measurements on Nuclear Reactor Pressure Vessel Steels

Positron Annihilation Spectroscopy is a valuable microscopic method to study radiation damage in nuclear reactor pressure vessel steels. At SCKoCEN, a new positron lifetime setup, suited to measure positron lifetimes in irradiated steel, is being constructed. The particularity of this setup is that the prompt count rate originating from the induced 60Co-activity in the steel is highly reduced. ...

Grain Boundary Segregation in Commercial Nuclear Reactor Pressure Vessel Steels

Grain boundary (GB) segregation of impurity/solute atoms in surveillance test specimens of a commercial western-type pressurized water reactor pressure vessel (RPV) steel has been observed by using state-of-the-art 3D atom probe (3DAP) field ion microscope (laser-assisted local electrode-type atom probe: laser-LEAP). The GB segregation is considered to be an origin of the embrittlement of the R...

A lattice Boltzmann framework to simulate boiling water reactor core hydrodynamics

This paper presents a consistent LBM formulation for the simulation of a two-phase water–steam system. Results of initial model validation in a range of thermodynamic conditions typical for BoilingWater Reactors (BWRs) are also shown. The interface between the two coexisting phases is captured from the dynamics of the model itself, i.e., no interface tracking is needed. The model is based on th...