Stability analysis of BWR nuclear-coupled thermal-hydraulics using a simple model

نویسندگان

  • Atul A. Karve
  • Rizwan uddin
چکیده

A simple mathematical model is developed to describe the dynamics of the nuclear-coupled thermal-hydraulics in a boiling water reactor (BWR) core. The model, which incorporates the essential features of neutron kinetics and single-phase and two-phase thermal-hydraulics, leads to a simple dynamical system comprised of a set of nonlinear ordinary differential equations (ODEs). The stability boundary is determined and plotted in the inlet-subcooling-number (enthalpy)/external-reactivity operating parameter plane. The eigenvalues of the Jacobian matrix of the dynamical system also are calculated at various steady-states (fixed points); the results are consistent with those of the direct stability analysis and indicate that a Hopf bifurcation occurs as the stability boundary in the operating parameter plane is crossed. Numerical simulations of the time-dependent, nonlinear ODEs are carried out for selected points in the operating parameter plane to obtain the actual damped and growing oscillations in the neutron number density, the channel inlet flow velocity, and the other phase variables. These indicate that the Hopf bifurcation is subcritical, hence, density wave oscillations with growing amplitude could result from a finite perturbation of the system even when it is being operated in the parameter region thought to be safe, i.e. where the steady-state is stable. Finally, the power-flow map, frequently used by reactor operators during start-up and shut-down operation of a BWR, is mapped to the inlet-subcooling-number/neutron-density (operating-parameter/phase-variable) plane, and then related to the stability boundaries for different fixed inlet velocities corresponding to selected points on the flow-control line. Also, the stability boundaries for different fixed inlet subcooling numbers corresponding to those selected points, are plotted in the neutron-density/inlet-velocity phase variable plane and then the points on the flow-control line are related to their respective stability boundaries in this plane. The relationship of the operating points on the flow-control line to their respective stability boundaries in these two planes provides insight into the instability observed in BWRs during low-flow/high-power operating conditions. It also shows that the normal operating point of a BWR is very stable in comparison with other possible operating points on the power-flow map. © 1997 Elsevier Science S.A. * Corresponding author. Tel.: +1 804 9825473; e-mail: [email protected] 1 This research was supported in part by the US NRC under grant No. NRC-04-90-113 and in part by the US DOE under grant No. DE-FG05-92ER75788. The opinions, findings, conclusions, and recommendations expressed herein are those of the authors and do not necessarily reflect the views of the NRC or DOE. 2 Work performed while at the University of Virginia. 0029-5493/97/$17.00 © 1997 Elsevier Science S.A. All rights reserved. PII S0029 -5493 (97 )00192 -1 A.A. Kar6e et al. / Nuclear Engineering and Design 177 (1997) 155–177 156

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Thermal-Hydraulics analysis of pressurized water reactor core by using single heated channel model

Thermal hydraulics of nuclear reactor as a basis of reactor safety has a very important role in reactor design and control. The thermal-hydraulic analysis provides input data to the reactor-physics analysis, whereas the latter gives information about the distribution of heat sources, which is needed to perform the thermal-hydraulic analysis. In this study single heated channel model as a very f...

متن کامل

A Relap/nestle Engineering Simulator for Shared-memory Multiprocessors

The RELAP5/MOD3.2 R/T engineering quality plant simulation code has been developed based on the system thermal-hydraulics code RELAP5 and the nodal spatial kinetics code NESTLE. Preliminary validation of the code as an engineering simulator was performed using a series of NEA PWR control rod ejection and withdrawal problems. Real time performance for simulator applications was demonstrated for ...

متن کامل

Stability analysis of support systems using a coupled FEM-DFN model (Case study: a diversion tunnel at Lorestan dam site, Iran)

Various structural discontinuities, which form a discrete fracture network, play a significant role in the failure conditions and stability of the rock masses around underground excavations. Several continuum numerical methods have been used to study the stability of underground excavations in jointed rock masses but only few of them can take into account the influence of the pre-existing natur...

متن کامل

Investigation of efficient and reliable numerical algorithms for coupled reactor calculations X-TREAM project: Task 1b Survey of the state-of-the-art numerical techniques for solving coupled non-linear multi-physics equations

Nowadays, the precise modeling of a nuclear reactor core is a challenge. This task involves several aspects, from the computational power needed to perform simulations, to the physics and analysis of the outcome. The need to better understand the physical phenomena is critical in order to quantify and qualify nuclear safety parameters. Currently, substantial research has been done in order to o...

متن کامل

Osiris: a Modern, High-performance, Coupled, Multi- Physics Code for Nuclear Reactor Core Analysis

To meet the simulation needs of the GNEP program, LLNL is leveraging a suite of high-performance codes to be used in the development of a multi-physics tool for modeling nuclear reactor cores. The Osiris code project, which began last summer, is employing modern computational science techniques in the development of the individual physics modules and the coupling framework. Initial development ...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 1998