TY - JOUR
T1 - Contribution to BWR stability analysis Part I
T2 - Analytical approach using a reduced order model
AU - Suárez-Ántola, Roberto
AU - Flores-Godoy, José Job
PY - 2014/5
Y1 - 2014/5
N2 - In this first part, we justify the use of a simple nonlinear set of ordinary integral differential equation to study the onset of global and regional power oscillations due to neutron-thermo-hydraulic coupling and possible malfunctions of the automatic control system of a boiling water reactor. This approach is framed in the construction of a new nodal-modal reduced order model of the core. Symmetry considerations are applied in the derivation of analytical formulae for direct and cross reactivities, including thermo-hydraulic and automatic control terms. Local bifurcations from the steady state of the reactor are studied from an analytical point of view, using both prompt-jump and effective life time approximation. Both thermal-hydraulic and automatic control system feedbacks are included. Asymptotic methods are used in the derivation of closed form analytical formulae of the stability boundaries in the space of reactor parameters as well as for amplitudes and frequencies of global and regional power oscillations. Besides analytical formulae for limit cycle oscillations are obtained.
AB - In this first part, we justify the use of a simple nonlinear set of ordinary integral differential equation to study the onset of global and regional power oscillations due to neutron-thermo-hydraulic coupling and possible malfunctions of the automatic control system of a boiling water reactor. This approach is framed in the construction of a new nodal-modal reduced order model of the core. Symmetry considerations are applied in the derivation of analytical formulae for direct and cross reactivities, including thermo-hydraulic and automatic control terms. Local bifurcations from the steady state of the reactor are studied from an analytical point of view, using both prompt-jump and effective life time approximation. Both thermal-hydraulic and automatic control system feedbacks are included. Asymptotic methods are used in the derivation of closed form analytical formulae of the stability boundaries in the space of reactor parameters as well as for amplitudes and frequencies of global and regional power oscillations. Besides analytical formulae for limit cycle oscillations are obtained.
KW - Boiling water reactors
KW - In-phase and out-of-phase oscillations
KW - Mathematical modeling
KW - Reduced order models
KW - Stability theory
UR - http://www.scopus.com/inward/record.url?scp=84894668515&partnerID=8YFLogxK
U2 - 10.1016/j.anucene.2013.11.017
DO - 10.1016/j.anucene.2013.11.017
M3 - Artículo
AN - SCOPUS:84894668515
SN - 0306-4549
VL - 67
SP - 129
EP - 145
JO - Annals of Nuclear Energy
JF - Annals of Nuclear Energy
ER -