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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
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Science and Engineering. Khalifa Univ, Dept Mech & Nucl Engn, Abu Dhabi 127788, U Arab Emirates; Khalifa Univ Sci & Technol, Emirates Nucl Technol Ctr ENTC, Abu Dhabi 127788, U Arab Emirates; Univ Tuscia UNITUS, Sch Engn, Largo Univ SNC, I-01100 Viterbo, Italy.ORCID iD: 0000-0003-2007-8158
Khalifa Univ, Dept Mech & Nucl Engn, Abu Dhabi 127788, U Arab Emirates; Khalifa Univ Sci & Technol, Emirates Nucl Technol Ctr ENTC, Abu Dhabi 127788, U Arab Emirates.
Fed Author Nucl Regulat FANR, Abu Dhabi 112021, U Arab Emirates.
Khalifa Univ, Dept Mech & Nucl Engn, Abu Dhabi 127788, U Arab Emirates; Khalifa Univ Sci & Technol, Emirates Nucl Technol Ctr ENTC, Abu Dhabi 127788, U Arab Emirates.
2026 (English)In: Nuclear engineering and technology : an international journal of the Korean Nuclear Society, ISSN 1738-5733, E-ISSN 2234-358X, Vol. 58, no 3, article id 103991Article in journal (Refereed) Published
Abstract [en]

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.

Place, publisher, year, edition, pages
Elsevier BV , 2026. Vol. 58, no 3, article id 103991
Keywords [en]
Passive auxiliary feedwater system (PAFS), Code validation, RELAP5/MOD3.3, ATLAS test C2.3 experimental, APR1400
National Category
Energy Engineering
Identifiers
URN: urn:nbn:se:kth:diva-375545DOI: 10.1016/j.net.2025.103991ISI: 001608576500001Scopus ID: 2-s2.0-105029774367OAI: oai:DiVA.org:kth-375545DiVA, id: diva2:2032274
Note

QC 20260126

Available from: 2026-01-26 Created: 2026-01-26 Last updated: 2026-02-18Bibliographically approved

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Saraswat, Satya Prakash

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