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| DOE-HDBK-1115-98
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core exposure
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fuel temperature
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local thermal neutron flux.
C
Describe the effect of operating the control- and power-shaping rods both inside and
outside specified control bands for varying facility conditions.
C
Describe the core parameters that affect the following coefficients, and evaluate how
changes in these coefficients affect facility operations
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moderator and/or coolant temperature coefficient
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Doppler coefficient
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power Doppler coefficient
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power defect
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pressure coefficient
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void coefficient.
C
Evaluate the impact of decay heat generation on posttrip operations for varying facility
conditions.
C
Describe the bases for limits on power escalation and descent.
C
Calculate reactivity balance, critical rod position, shutdown margin, and inverse
count-rate ratios (1/m).
C
Determine the effect of poison concentration and loading on reactivity control and fuel
management for
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fission product poisons
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burnable poisons
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nonburnable poisons.
C
Determine the effect of each of the following on reactivity control and facility operations
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thermal-hydraulic limits
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linear heat generation rates
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minimum critical power ratio
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average planar linear heat generation rate
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peaking factors.
C
Evaluate the effect of the following on reactivity control and facility operations
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unbalanced core flow
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recirculation flow changes
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control rod movements
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natural circulation
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thermal-hydraulic instabilities
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main generator load changes
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inadvertent changes in burnable poison concentration
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xenon and samarium concentrations.
C
Discuss ways to prevent, identify, and mitigate operation with failed fuel.
14
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