Application of sub-channel thermal-hydraulic analysis to core calculations with POLCA8 and VIPRE-W
This report investigates the steps of a one-way coupling between two simulation codes developed by Wesinghouse Electric Sweden AB. The Westinghouse POLCA8 is a three dimensional steady-state diffusion theory code used for simulating the neutronic, thermal and hydraulic behavior of a reactor core. In...
Main Author: | Castellanos Alvarez, Larisa |
---|---|
Format: | Others |
Language: | English |
Published: |
Uppsala universitet, Tillämpad kärnfysik
2019
|
Subjects: | |
Online Access: | http://urn.kb.se/resolve?urn=urn:nbn:se:uu:diva-393517 |
Similar Items
-
Compaction of Lattice Data : Improved Efficiency in Nuclear Core Calculation
by: Lundgren, Hanna
Published: (2017) -
Thermal-Hydraulic Analysis of Advanced Mixed-Oxide Fuel Assemblies with VIPRE-01
by: Bingham, Adam R.
Published: (2010) -
Response of the Gamma TIP Detectorsin a Nuclear Boiling Water Reactor
by: Fridström, Richard
Published: (2010) -
POLCA-T Neutron Kinetics Model Benchmarking
by: Kotchoubey, Jurij
Published: (2015) -
Thermal-Hydraulic Analysis of Seed-Blanket Unit Duplex Fuel Assemblies with VIPRE-01
by: McDermott, Patrick 1987-
Published: (2013)