Work

Validation of RELAP5/MOD3.3 for passive auxiliary feedwater system (PAFS) performance using ATLAS test C2.3 data: a detailed analysis of double-ended guillotine break scenarios

Year: 2025

Type: article

Abstract: This study presents a comprehensive validation of the RELAP5/MOD3.3 system thermal-hydraulic code against the ATLAS Test C2.3, which simulates a Double-Ended Guillotine Break (DEGB) in the main steam line of an APR1400 steam generator with Passive Auxiliary Feedwater System (PAFS) activation. The validation effort emphasized refining the input system model to more accurately reflect experimental conditions, highlighting RELAP5’s capability to simulate complex passive safety scenarios with high fidelity. A pre-test simulation was first performed using nominal input data; while it reproduced general system trends, it exhibited notable deviations in steam generator water level, pressure response, and passive flow behavior. A post-test model was then developed with improvements including an updated decay heat profile, corrected heat transfer areas, enhanced control logic for PAFS and MSSV actuation and break modelling. The post-test simulation showed excellent agreement with experimental data, maintaining an error margin within ±2.5% across key thermal-hydraulic parameters such as pressure, temperature, flow rate, and water level. In addition, a code-to-code comparison with TRACE was conducted using identical boundary and initial conditions. The RELAP5 simulation with the refined system model demonstrated comparable or improved accuracy in capturing critical phenomena, including asymmetric depressurization and PAFS-induced natural circulation. This work underscores the importance of detailed input modeling in achieving high-fidelity simulations and confirms the suitability of RELAP5/MOD3.3 for evaluating passive safety systems in advanced reactor designs. • RELAP5/MOD3.3 was validated for the Passive Auxiliary Feedwater System (PAFS) using ATLAS test C2.3 data, focusing on a Double-Ended Guillotine Break (DEGB) in the main steam line of Steam Generator 1. • The code demonstrated high accuracy, maintaining an error margin below 2.5% for key thermal-hydraulic parameters, aligning closely with experimental data. • A code-to-code comparison with TRACE under identical conditions confirmed RELAP5/MOD3.3's robustness, highlighting its reliability for simulating passive safety systems and enhancing reactor safety during accidents.

Source: Nuclear Engineering and Technology

DOI: 10.1016/j.net.2025.103991

Authors: Satya Prakash Saraswat, Mubashir Hassan, Nourah Alyammahi, Yacine Addad

Institutions: Università degli Studi della Tuscia, Khalifa University of Science and Technology, KTH Royal Institute of Technology, Federal Authority for Nuclear Regulation

Language: English

Topic: Nuclear Engineering Thermal-Hydraulics

Subfield: Aerospace Engineering

Field: Engineering

Domain: Physical Sciences

Open Access status: gold

Estimated APC paid: $200

Funder: ARC Training Centre in Lightweight Automotive Structures