Design strategies for optimizing high burnup fuel in pressurized water reactors
Z Xu - 2003 - dspace.mit.edu
This work is focused on the strategy for utilizing high-burnup fuel in pressurized water
reactors (PWR) with special emphasis on the full array of neutronic considerations. The …
reactors (PWR) with special emphasis on the full array of neutronic considerations. The …
[HTML][HTML] Modelling and simulations of reactor neutron noise induced by mechanical vibrations
Mechanical vibrations of core internals are among the main perturbations that induce
oscillations in the neutron flux field, also known as neutron noise. In this work, different …
oscillations in the neutron flux field, also known as neutron noise. In this work, different …
[HTML][HTML] Monte Carlo analysis of BWR geometries using a cycle check-up methodology
Recent fuel anomalies at a Swiss power plant have motivated the development at PSI of the
“Cycle Check-Up”(CHUP) methodology which consists in performing Monte Carlo transport …
“Cycle Check-Up”(CHUP) methodology which consists in performing Monte Carlo transport …
Nuclear data uncertainty quantification in criticality safety evaluations for spent nuclear fuel geological disposal
Presently, a criticality safety evaluation methodology for the final geological disposal of
Swiss spent nuclear fuel is under development at the Paul Scherrer Institute in collaboration …
Swiss spent nuclear fuel is under development at the Paul Scherrer Institute in collaboration …
[PDF][PDF] Description of scenarios for the simulated data
C Demazière, A Dokhane - Deliverable D3, 2019 - cortex-h2020.eu
This report summarizes the different scenarios corresponding to the presence of various
noise sources in nuclear reactors. The definition of the noise sources and their modelling …
noise sources in nuclear reactors. The definition of the noise sources and their modelling …
Advances in nuclear fuel management for light water reactors
PJ Turinsky, GT Parks - Advances in nuclear science and technology, 1999 - Springer
Nuclear fuel management entails making decisions that influence how a reactor core's
reactivity and flux, power and burnup spatial distributions vary. These spatial distributions …
reactivity and flux, power and burnup spatial distributions vary. These spatial distributions …
Safety analysis of high-power-density annular fuel for PWRs
D Feng, P Morra, R Sundaram, WJ Lee, P Saha… - Nuclear …, 2007 - Taylor & Francis
This paper assesses the performance of internally and externally cooled annular fuel in a
four-loop pressurized water reactor during a variety of transients and accidents, namely, the …
four-loop pressurized water reactor during a variety of transients and accidents, namely, the …
Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data
Abstract At the Paul Scherrer Institute (PSI), a computational scheme aimed at high fidelity
fast neutron fluence estimations for Light-Water-Reactors (LWRs) was in previous years …
fast neutron fluence estimations for Light-Water-Reactors (LWRs) was in previous years …
Control rod drop transient analysis with the coupled parallel code pCTF-PARCSv2. 7
E Ramos, JE Roman, A Abarca, R Miró… - Annals of Nuclear …, 2016 - Elsevier
In order to reduce the response time when simulating large reactors in detail, a parallel
version of the thermal–hydraulic subchannel code COBRA-TF (CTF) has been developed …
version of the thermal–hydraulic subchannel code COBRA-TF (CTF) has been developed …
Uncertainty and sensitivity analysis in the neutronic parameters generation for BWR and PWR coupled thermal-hydraulic–neutronic simulations
F Ánchel, T Barrachina, R Miró, G Verdú… - … engineering and design, 2012 - Elsevier
The Best Estimate analysis consists of a coupled thermal-hydraulic and neutronic
description of the nuclear system's behavior; uncertainties from both aspects should be …
description of the nuclear system's behavior; uncertainties from both aspects should be …