TY - JOUR
T1 - Extension and application of the TRANSURANUS code to the normal operating conditions of the MYRRHA reactor
AU - Magni, Arianna
AU - Barani, Tommaso
AU - Belloni, Francesco
AU - Boer, Brian
AU - Guizzardi, Erik
AU - Pizzocri, Davide
AU - Schubert, Arndt
AU - Van Uffelen, Paul
AU - Luzzi, Lelio
N1 - Score=10
PY - 2022/1
Y1 - 2022/1
N2 - 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.
AB - 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.
KW - Generation IV
KW - MYRRHA reactor
KW - Cladding creep and swelling
KW - Fuel performance code
KW - TRANSURANUS
UR - https://ecm.sckcen.be/OTCS/llisapi.dll?func=ll&objaction=overview&objid=53450080
U2 - 10.1016/j.nucengdes.2021.111581
DO - 10.1016/j.nucengdes.2021.111581
M3 - Article
SN - 0029-5493
VL - 386
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
M1 - 111581
ER -