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 …

[HTML][HTML] Modelling and simulations of reactor neutron noise induced by mechanical vibrations

A Vidal-Ferràndiz, D Ginestar, A Carreño… - Annals of Nuclear …, 2022 - Elsevier
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 …

[HTML][HTML] Monte Carlo analysis of BWR geometries using a cycle check-up methodology

M Hursin, A Vasiliev, D Rochman, A Dokhane… - Annals of Nuclear …, 2024 - Elsevier
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 …

Nuclear data uncertainty quantification in criticality safety evaluations for spent nuclear fuel geological disposal

M Frankl, M Hursin, D Rochman, A Vasiliev… - Applied Sciences, 2021 - mdpi.com
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 …

[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 …

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 …

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 …

Towards modeling and validation enhancements of the PSI MCNPX fast neutron fluence computational scheme based on recent PWR experimental data

A Dupré, A Vasiliev, H Ferroukhi, A Pautz - Annals of Nuclear Energy, 2015 - Elsevier
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 …

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 …

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 …