Insights into fuel behaviour during relatively fast thermal transients based on calculations for two tests of the Halden IFA-507 experiment

被引：1

作者：

Khvostov, Grigori ^{[1
]}

机构：

[1] PSI, Villigen, Switzerland

来源：

NUCLEAR ENGINEERING AND TECHNOLOGY | 2023年 / 55卷 / 10期

关键词：

GRSW-A model; Veri fication and Validation; Fuel temperature; Thermal transient; FALCON MOD01 code; CLADDING FAILURE; ROD BEHAVIOR; FALCON CODE;

D O I：

10.1016/j.net.2023.06.045

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

Outcomes of the project "Comprehensive Verification of the FALCON Code for Calculation of Nuclear Fuel Temperature" relating to calculation of fuel temperature during relatively fast thermal transients are presented. Good prediction capabilities of the FALCON MOD01 code coupled with the GRSW-A code are shown as applied to the data of the TF3 and TF5 tests from the Transient Temperature Experiment IFA507. The IFA-507 related dataset of the OECD/NEA International Fuel Performance Experiments (IFPE) Database is extended by the reconstructed dynamics of the axial power distribution in the rods during the transient phase of the experiment. Based on the code calculation, the time constant of the thermal fuel response to a power transient is estimated.(c) 2023 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).

引用

页码：3801 / 3807

页数：7