TY - JOUR
T1 - Code development and analysis of heat pipe cooled passive residual heat removal system of Molten salt reactor
AU - Wang, Chenglong
AU - Duan, Qianni
AU - Liu, Minghao
AU - Zhang, Dalin
AU - Qiu, Suizheng
AU - Su, G. H.
AU - Tian, Wenxi
N1 - Publisher Copyright:
© 2020 Elsevier Ltd
PY - 2020/9/1
Y1 - 2020/9/1
N2 - The high efficient and reliable Passive Residual Heat Removal System (PRHRS) is of great importance to the development of Molten Salt Reactor (MSR), whether the liquid fuel MSR or solid fuel MSR. In this research, based on the structure and operation performance of the new conceptual PRHRS, using high temperature heat pipe as heat transportation, a set of reasonable mathematical and physical models have been built, mainly including reactor core model, high temperature heat pipe model and PRHRS model. The new conceptual Passive Residual heat removal system Analysis Code (PRAC) has been developed using FORTRAN language. The verification and validation for PRAC is conducted by using existed Molten Salt Reactor Experiment (MSRE) data provided by Oak Ridge National Laboratory and the PRHRS experimental data in our previous work. The results show that the developed PRAC could predict the MSR transients reasonably and show high fidelity. The numerical results of reactor core neutronic and thermal–hydraulic model show a good agreement when compared with MSRE pump startup and shutdown transients. The numerical results by PRHRS model agree well with experimental data which the maximum error of the fluoride salt temperature and heat pipe wall temperature are within 1.2% and 2.8%. This research provides a valuable software basis for the design and analysis of PRHRS of MSR.
AB - The high efficient and reliable Passive Residual Heat Removal System (PRHRS) is of great importance to the development of Molten Salt Reactor (MSR), whether the liquid fuel MSR or solid fuel MSR. In this research, based on the structure and operation performance of the new conceptual PRHRS, using high temperature heat pipe as heat transportation, a set of reasonable mathematical and physical models have been built, mainly including reactor core model, high temperature heat pipe model and PRHRS model. The new conceptual Passive Residual heat removal system Analysis Code (PRAC) has been developed using FORTRAN language. The verification and validation for PRAC is conducted by using existed Molten Salt Reactor Experiment (MSRE) data provided by Oak Ridge National Laboratory and the PRHRS experimental data in our previous work. The results show that the developed PRAC could predict the MSR transients reasonably and show high fidelity. The numerical results of reactor core neutronic and thermal–hydraulic model show a good agreement when compared with MSRE pump startup and shutdown transients. The numerical results by PRHRS model agree well with experimental data which the maximum error of the fluoride salt temperature and heat pipe wall temperature are within 1.2% and 2.8%. This research provides a valuable software basis for the design and analysis of PRHRS of MSR.
KW - Code development and verification
KW - High temperature heat pipe
KW - Molten salt reactor
KW - Passive residual heat removal system
UR - https://www.scopus.com/pages/publications/85083311027
U2 - 10.1016/j.anucene.2020.107527
DO - 10.1016/j.anucene.2020.107527
M3 - 文章
AN - SCOPUS:85083311027
SN - 0306-4549
VL - 144
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
M1 - 107527
ER -