Published May 2021 | Version v1
Journal article

AZTUSIA: A new application software for Uncertainty and Sensitivity analysis for nuclear reactors

  • 1. Instituto Politécnico Nacional, Avenida Instituto Politécnico Nacional s/n Edificio 9 Unidad Profesional "Adolfo López Mateos" Col. San Pedro Zacatenco, Alcadía Gustavo A. Madero, 07738, Ciudad de México (Mexico)
  • 2. Instituto Nacional de Investigaciones Nucleares, Carretera México Toluca s/n, La Marquesa, Ocoyoacac, 52750, Estado de México (Mexico)
  • 3. Universidad Politécnica de Madrid, Department of Energy and Fuels, Alenza 4, 28003 Madrid (Spain)

Description

Highlights: • AZTUSIA is a new tool to perform sensitivity and uncertainty analysis. • Parametric and non-parametric analysis can be performed with AZTUSIA. • AZTUSIA includes scatter, cobweb and histogram plots to facilitate analysis. • AZTUSIA calculates correlation coefficients for global sensitivity measures. The AZTLAN Platform project is a Mexican national initiative which aims to have a platform for analysis and design of nuclear reactors. In order to enhance the AZTLAN Platform with Uncertainty and Sensitivity (U&S) capabilities, the AZTUSIA (AZtlan Tool for Uncertainty and SensItivity Analysis) code has been developed to perform U&S analysis. The main characteristics and capabilities of AZTUSIA are briefly described together with some verification exercises. The versatility of the AZTUSIA code has been used to analyze a transient of a BWR-5 with the SIMULATE 3-K code. An artificial perturbation has been caused for creating a more challenging case and to demonstrate the capabilities of an extended interface in which AZTUSIA can be easily adapted to other codes outside AZTLAN Platform. The U&S analysis conducted using the AZTUSIA code reflect, as expected, the impact of uncertain parameters and all capabilities of the tool are demonstrated. It is possible to assess the influence of uncertainty in the calculations and to distinguish trends and readily group and/or separate results by means of scatter and cobweb color plots. As a main conclusion, a new tool has been developed allowing U&S analysis. It is foreseen to continue increasing the tool capabilities.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.ress.2021.107441

Additional details

Identifiers

DOI
10.1016/j.ress.2021.107441;
PII
S0951832021000107;

Publishing Information

Journal Title
Reliability Engineering and System Safety
Journal Volume
209
Journal Page Range
vp.
ISSN
0951-8320
CODEN
RESSEP

INIS

Country of Publication
United Kingdom
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
54018415
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S97: MATHEMATICAL METHODS AND COMPUTING;
Descriptors DEI
BWR TYPE REACTORS; PARAMETRIC ANALYSIS; REACTOR DESIGN; SENSITIVITY ANALYSIS; TRANSIENTS
Descriptors DEC
DESIGN; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR LIFE CYCLE; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Copyright
Copyright (c) 2021 Elsevier Ltd. All rights reserved.