TY - GEN
T1 - Reactor dynamics model for the molten salt reactor based on P1approximation
AU - Altahhan, Muhammad Ramzy
AU - Avramova, Maria
AU - Ivanov, Kostadin
N1 - Publisher Copyright:
© 2018 International Conference on Physics of Reactors, PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems. All rights reserved.
PY - 2018
Y1 - 2018
N2 - In this paper, we study the use of the Telegraph Point Reactor Kinetics (TPRK) to model the kinetics and dynamics of Molten Salt Reactors (MSRs). TPRK is based on the full form of the P1approximation of the neutron transport equation without neglecting the time derivative of the neutron current term in the final form of the P1approximation system of equations. Inclusion of the neutron current time derivative term results in the addition of a new physical parameter called the relaxation time τ that will affect the solution and the dynamics of MSRs due to the homogeneity of the molten salt fuel. We used eight precursors groups of delayed neutrons in our analysis. We found that the general behavior of relaxation effect associated with the telegraph model in solid fuel systems is still persistent in this analysis. The first peak of the telegraph-based approximation shows similar behavior to other detailed spatial based models of MSRs in contrast to the diffusion model. Also, we found that when τ → 0, TPRK results tend to agree with the diffusion model. If a high amount of reactivity is inserted through any external contributions (control rod movements or any changes of state parameters such as fuel temperature feedback coefficient αFand the fuel salt mass flow rate mF) the difference between the two models is higher than for low reactivity insertions. This result, we contribute to the relaxation effect of the telegraph model.
AB - In this paper, we study the use of the Telegraph Point Reactor Kinetics (TPRK) to model the kinetics and dynamics of Molten Salt Reactors (MSRs). TPRK is based on the full form of the P1approximation of the neutron transport equation without neglecting the time derivative of the neutron current term in the final form of the P1approximation system of equations. Inclusion of the neutron current time derivative term results in the addition of a new physical parameter called the relaxation time τ that will affect the solution and the dynamics of MSRs due to the homogeneity of the molten salt fuel. We used eight precursors groups of delayed neutrons in our analysis. We found that the general behavior of relaxation effect associated with the telegraph model in solid fuel systems is still persistent in this analysis. The first peak of the telegraph-based approximation shows similar behavior to other detailed spatial based models of MSRs in contrast to the diffusion model. Also, we found that when τ → 0, TPRK results tend to agree with the diffusion model. If a high amount of reactivity is inserted through any external contributions (control rod movements or any changes of state parameters such as fuel temperature feedback coefficient αFand the fuel salt mass flow rate mF) the difference between the two models is higher than for low reactivity insertions. This result, we contribute to the relaxation effect of the telegraph model.
KW - Molten Salt Reactors
KW - Papproximation
KW - Ramp reactivity insertion
KW - Relaxation time
UR - https://www.scopus.com/pages/publications/85106014233
M3 - Conference contribution
AN - SCOPUS:85106014233
T3 - International Conference on Physics of Reactors, PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems
SP - 3448
EP - 3459
BT - International Conference on Physics of Reactors, PHYSOR 2018
PB - Sociedad Nuclear Mexicana, A.C.
T2 - 2018 International Conference on Physics of Reactors: Reactor Physics Paving the Way Towards More Efficient Systems, PHYSOR 2018
Y2 - 22 April 2018 through 26 April 2018
ER -