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13.10 On-line stability monitoring  183





                   130
                       NINE OF TEN INTERNAL PUMPS OPERATING
                   120  PERCENT PUMP SPEED
                           0  0  NATURAL CIRCULATION
                   110     1  30
                           2  35                                          10
                           3  40                                       9
                   100            100% POWER = 3926 MWt             8
                           4  50
                           5  60                               7
                                              6
                   90      6  70  100% FLOW = 52.2 X 10 kg/h  6
                           7 80   100% SPEED = 157 rad/s  4  A  5

                             90
                   PERCENT POWER  70  PERCENT ROD LINE  1  2  3  B C  REGION IV
                           8
                   80
                             95
                           9
                           10 100
                          A 102
                          B 100
                   60
                          C 80
                          D 60
                   50
                          E 40
                          F20   0                   D
                                  REGION III
                   40
                                                    E
                   30
                                                                        REGION II
                   20             REGION I          F
                               TYPICAL                       STEAM SEPARATOR LIMIT
                   10          STARTUP
                                PATH
                    0
                     0    10   20   30   40    50   60   70   80   90   100   110  120
                                              PERCENT CORE FLOW
                  FIG. 13.10
                  A BWR power-flow map.
                  Courtesy of GE Hitachi Nuclear Energy Americas LLC (ABWR Design Control Document, prepared by GE Nuclear
                                                Energy for the U.S. Nuclear Regulatory Commission, 1997).
                  This scenario involves the use of control rods to reach the 100% line before switching
                  to recirculation flow changes to increase power.
                     Now consider an alternate scenario. In this case use control rods to reach the 50%
                  line. Then increase core flow to some power level at or below 50%. Then withdraw
                  control rods until the reactivity increase corresponds to the 100% line.
                     The power flow map for BWRs is roughly analogous to the steady state program
                  for PWRs. The BWR situation is more complicated because of the need to avoid
                  instability and because two reactivity control measures are available in BWRs.
                  The BWR power flow map indicates a range of acceptable conditions while a
                  PWR steady state program indicates desired conditions.
                  13.10 On-line stability monitoring
                  Stability in an operating BWR may be monitored by analyzing the natural fluctuations
                  inmeasuredsignals.Thisprocessisusuallycalledreactornoiseanalysis.Twoanalysis
                  methods are available: spectrum analysis and time-series analysis. Spectrum analysis
                  uses Fourier transforms of the measured fluctuations to provide the power spectrum
                  (signal energy vs. frequency). Time series analysis involves the estimation using the
                  following model, called an auto-regression (AR) model, from the measured data.
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