TY - JOUR
T1 - P2M simulation exercise on past fuel melting irradiation experiments
AU - D’Ambrosi, V.
AU - Sercombe, J.
AU - Bejaoui, S.
AU - Chaieb, A.
AU - Baurens, B.
AU - Largenton, R.
AU - Ambard, A.
AU - Boer, Brian
AU - Bonny, Giovanni
AU - Ševeček, M.
AU - Herranz, L. E.
AU - Feria Marquez, F.
AU - Inagaki, K.
AU - Ohta, H.
AU - Boldt, F.
AU - Sappl, J.
AU - Armstrong, R.
AU - Mohamad, A.
AU - Udagawa, Y.
AU - Cozzo, C.
AU - Klouzal, J.
AU - Vitezslav, M.
AU - Corson, J.
AU - Peltonen, J.
N1 - Score=10
Funding Information:
The authors would like to acknowledge MNF, Studsvik, the SCIP II community, and SCK‧CEN for the extensive data used during this Simulation Exercise on the xM3 and HBC4 power ramps in the frame of the FIDES/P2M JEEP. The reviewers are also greatfully acknowledged for their numerous comments and corrections that have significantly improved the content of this paper.
Publisher Copyright:
© 2023 The Author(s). Published with license by Taylor & Francis Group, LLC.
PY - 2024
Y1 - 2024
N2 - This paper presents the results of the Power To Melt and Maneuverability (P2M) Simulation Exercise on past fuel melting irradiation experiments, organized within the Organisation for Economic Co-operation and Development/Nuclear Energy Agency Framework for IrraDiation ExperimentS (FIDES) framework by the Core Group (CEA, EDF, and SCK‧CEN) and open to all FIDES members. The exercise consisted in simulating two past power ramps where fuel melting was detected: (1) the xM3 staircase power transient [ramp terminal level (RTL) 70 kW‧m−1, average burnup 27 GWd‧tU−1], carried out in 2005 in the R2 reactor at Studsvik (Sweden), where the rodlet maintained its integrity, and (2) the HBC4 fast power transient (RTL 66 kW‧m−1, average burnup 48 GWd‧tU−1), carried out in 1987 in the BR2 reactor at SCK‧CEN (Belgium), where the cladding failed during the experiment. The exercise was joined by 13 organizations from 9 countries using 11 different fuel performance codes. In this paper, the main results of the Simulation Exercise are presented and compared to available postirradiation examinations (PIE) or on-line measurements during the power ramps (fuel and clad diameters, rod elongation, pellet-clad gap, and fission gas release). Since the focus of the Simulation Exercise is on fuel melting assessment, determination of the boundary between melted/nonmelted fuel and the consequent definition of a melting radius from PIE are first discussed. During the HBC4 ramp, fuel melting was predicted by most of the codes despite differences in the melting models. Higher discrepancies were observed for the xM3 rod that can be attributed partly to power uncertainty and partly to the limited capability of the models to describe partial melting of the fuel during this ramp. Finally, possible code developments to improve simulation results are presented.
AB - This paper presents the results of the Power To Melt and Maneuverability (P2M) Simulation Exercise on past fuel melting irradiation experiments, organized within the Organisation for Economic Co-operation and Development/Nuclear Energy Agency Framework for IrraDiation ExperimentS (FIDES) framework by the Core Group (CEA, EDF, and SCK‧CEN) and open to all FIDES members. The exercise consisted in simulating two past power ramps where fuel melting was detected: (1) the xM3 staircase power transient [ramp terminal level (RTL) 70 kW‧m−1, average burnup 27 GWd‧tU−1], carried out in 2005 in the R2 reactor at Studsvik (Sweden), where the rodlet maintained its integrity, and (2) the HBC4 fast power transient (RTL 66 kW‧m−1, average burnup 48 GWd‧tU−1), carried out in 1987 in the BR2 reactor at SCK‧CEN (Belgium), where the cladding failed during the experiment. The exercise was joined by 13 organizations from 9 countries using 11 different fuel performance codes. In this paper, the main results of the Simulation Exercise are presented and compared to available postirradiation examinations (PIE) or on-line measurements during the power ramps (fuel and clad diameters, rod elongation, pellet-clad gap, and fission gas release). Since the focus of the Simulation Exercise is on fuel melting assessment, determination of the boundary between melted/nonmelted fuel and the consequent definition of a melting radius from PIE are first discussed. During the HBC4 ramp, fuel melting was predicted by most of the codes despite differences in the melting models. Higher discrepancies were observed for the xM3 rod that can be attributed partly to power uncertainty and partly to the limited capability of the models to describe partial melting of the fuel during this ramp. Finally, possible code developments to improve simulation results are presented.
KW - Fuel melting
KW - Fuel performance codes
KW - Postirradiation examinations
KW - Power ramp
KW - Pressurized water reactor
UR - http://www.scopus.com/inward/record.url?scp=85153316082&partnerID=8YFLogxK
U2 - 10.1080/00295450.2023.2194270
DO - 10.1080/00295450.2023.2194270
M3 - Article
AN - SCOPUS:85153316082
SN - 0029-5450
VL - 210
SP - 189
EP - 215
JO - Nuclear Technology
JF - Nuclear Technology
IS - 2
ER -