Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor

•Extension of the TRANSURANUS fuel performance code to the MYRRHA pin cladding material.•Creep and void swelling modelling of DIN1.4970.•Application of TRANSURANUS to the fuel and cladding performance analysis of MYRRHA.•Simulation of MYRRHA normal operating conditions and identification of worst-ca...

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Published in:Nuclear engineering and design 2022-01, Vol.386, p.111581, Article 111581
Main Authors: Magni, A., Barani, T., Belloni, F., Boer, B., Guizzardi, E., Pizzocri, D., Schubert, A., Van Uffelen, P., Luzzi, L.
Format: Article
Language:English
Subjects:
Cladding
Cladding creep and swelling
Creep (materials)
Design
Design specifications
Fuel performance code
Fuels
Generation IV
MYRRHA reactor
Nuclear fuels
Nuclear safety
Sensitivity analysis
Simulation
TRANSURANUS
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cited_by cdi_FETCH-LOGICAL-c3071-8bfdaaf697c9ef8d4b39f65cb2fd9484dc13b5a1317b2c0f2baf276dec81af7c3
cites cdi_FETCH-LOGICAL-c3071-8bfdaaf697c9ef8d4b39f65cb2fd9484dc13b5a1317b2c0f2baf276dec81af7c3
container_end_page
container_issue
container_start_page 111581
container_title Nuclear engineering and design
container_volume 386
creator Magni, A.
Barani, T.
Belloni, F.
Boer, B.
Guizzardi, E.
Pizzocri, D.
Schubert, A.
Van Uffelen, P.
Luzzi, L.
description •Extension of the TRANSURANUS fuel performance code to the MYRRHA pin cladding material.•Creep and void swelling modelling of DIN1.4970.•Application of TRANSURANUS to the fuel and cladding performance analysis of MYRRHA.•Simulation of MYRRHA normal operating conditions and identification of worst-case scenarios.•Assessment of the code predictions adopting conservative design limits. This work deals with the performance analysis of the MYRRHA hottest fuel pin in normal operating conditions, employing the TRANSURANUS fuel performance code, with the aim of assessing the current design specifications considering conservative design limits. To allow the proper simulation of the MYRRHA pin behaviour, TRANSURANUS is extended with novel correlations for the creep and void swelling response of the specific cladding material (DIN 1.4970). The analysis of the best-estimate reference scenario is complemented by a sensitivity analysis on models describing fuel and cladding phenomena and properties, determining those which most affect the pin performance results and identifying the worst-case scenarios. The simulation outcomes point out the high level of safety related to the MYRRHA fuel pin performance in normal operating conditions, which keeps far from any design or critical limit, even in the most challenging (worst-case) scenarios.
doi_str_mv 10.1016/j.nucengdes.2021.111581
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source ScienceDirect Journals
subjects Cladding
Cladding creep and swelling
Creep (materials)
Design
Design specifications
Fuel performance code
Fuels
Generation IV
MYRRHA reactor
Nuclear fuels
Nuclear safety
Sensitivity analysis
Simulation
TRANSURANUS
title Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor
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