TY - GEN
T1 - Thermal analysis safety margins using ABAQUS for the MP-2 experiment in the advanced test reactor
AU - Hawkes, Grant L.
AU - Crawford, Douglas S.
AU - Housley, Gregory K.
N1 - Publisher Copyright:
Copyright © 2018 ASME.
PY - 2018
Y1 - 2018
N2 - The Mini-Plate 2 (MP-2) irradiation test is a fueled experiment designed for irradiation in multiple test locations in the Advanced Test Reactor (ATR). MP-2 is considered a non-instrumented drop-in test where small aluminum-clad fuel plate samples are cooled directly by the ATR Primary Coolant System (PCS) water. The MP-2 fuel plate experiment will be irradiated in several different irradiation locations of the ATR. This fueled experiment contains aluminum-clad fuel mini plates consisting of monolithic U-Mo. Four different types of fuel plates were analyzed. A thermal analysis has been performed on the MP-2 experiment to be irradiated in the ATR at Idaho National Laboratory (INL). A new technique for calculating Departure from Nucleate Boiling Ratio (DNBR) and Flow Instability Ratio (FIR) using the commercial finite element and heat transfer code ABAQUS is demonstrated. This new technique calculates DNBR for the fuel plate surfaces and FIR for all water components for each finite element surface and node. Pressure drop data is fed into the calculations in order to geometrically calculate the water saturation temperature. Results from the DNBR and FIR calculations are displayed with the ABAQUS post processor named Viewer. By calculating these parameters at each location in the finite element model, conservatism is replaced with accuracy. This allows for a greater margin for the thermal hydraulic safety parameters.
AB - The Mini-Plate 2 (MP-2) irradiation test is a fueled experiment designed for irradiation in multiple test locations in the Advanced Test Reactor (ATR). MP-2 is considered a non-instrumented drop-in test where small aluminum-clad fuel plate samples are cooled directly by the ATR Primary Coolant System (PCS) water. The MP-2 fuel plate experiment will be irradiated in several different irradiation locations of the ATR. This fueled experiment contains aluminum-clad fuel mini plates consisting of monolithic U-Mo. Four different types of fuel plates were analyzed. A thermal analysis has been performed on the MP-2 experiment to be irradiated in the ATR at Idaho National Laboratory (INL). A new technique for calculating Departure from Nucleate Boiling Ratio (DNBR) and Flow Instability Ratio (FIR) using the commercial finite element and heat transfer code ABAQUS is demonstrated. This new technique calculates DNBR for the fuel plate surfaces and FIR for all water components for each finite element surface and node. Pressure drop data is fed into the calculations in order to geometrically calculate the water saturation temperature. Results from the DNBR and FIR calculations are displayed with the ABAQUS post processor named Viewer. By calculating these parameters at each location in the finite element model, conservatism is replaced with accuracy. This allows for a greater margin for the thermal hydraulic safety parameters.
UR - http://www.scopus.com/inward/record.url?scp=85088773698&partnerID=8YFLogxK
U2 - 10.1115/nuclrf2018-7600
DO - 10.1115/nuclrf2018-7600
M3 - Conference contribution
AN - SCOPUS:85088773698
T3 - ASME 2018 Nuclear Forum, NUCLRF 2018, collocated with the ASME 2018 Power Conference and the ASME 2018 12th International Conference on Energy Sustainability
BT - ASME 2018 Nuclear Forum, NUCLRF 2018, collocated with the ASME 2018 Power Conference and the ASME 2018 12th International Conference on Energy Sustainability
PB - American Society of Mechanical Engineers (ASME)
T2 - ASME 2018 Nuclear Forum, NUCLRF 2018, collocated with the ASME 2018 Power Conference and the ASME 2018 12th International Conference on Energy Sustainability
Y2 - 24 June 2018 through 28 June 2018
ER -