Validation of 3D Code KATRIN For Fast Neutron Fluence Calculation of VVER-1000 Reactor Pressure Vessel by Ex-Vessel Measurements and Surveillance Specimens Results

Modeling the measurement of VVER-1000 reactor power by neutron and gamma radiation with MCNP code

The present study deals with a new method for measuring the power of a reactor. This method uses gamma and neutron radiation resulted from the entire reactor structure, without changing its structure (online). In terms of functionality, this method can measure the reactor power in real-time and report it instantly. In order to obtain the relationship between reactor power and gamma and neutron ...

Reactor Pressure Vessel Embrittlement—i

Detailed Cfx-5 Study of the Coolant Mixing within the Reactor Pressure Vessel of a Vver-1000 Reactor during a Non-symmetrical Heat-up Test

As part of the reactor dynamics activities of FZK/IRS, the qualification of a detailed 3D CFD model of a reactor pressure vessel is a key step in safety evaluations for improving predictive capabilities and acceptability of commercial CFD tools in reactor physics. The VVER-1000 Coolant Transient Benchmark, initiated by OECD, represents an excellent opportunity for validation. In this work a CFD...

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. ...

Two Benchmarks for Qualification of Pressure Vessel Fluence Calculational Methodology

Two benchmarks for the qualification of the pressure vessel fluence calculational methodology were formulated and are brieily described. The Pool Critical Assembly (PCA) benchmark is based on the experiments performed at the PCA in Oak Ridge. The measured quantities to be compared against the calculated values are the equivalent fission fluxes at several locations in front, behind, and inside t...