Question

Problem 12 A PWR nuclear power plant is operating at 1400MWe. The coolant water enters the reactor at 300°C (572°F) and leaves at 325°C (617°F). Assuming the water is at PWR conditions of 140 bar (2000 psia, pounds per square inch absolute) and 316°C, the specific heat is 6.06 kJ/(kg°C) and the density is 687 kg/m³. (a) At what rate must water flow through the system to cool the reactor (in kg/s)? (b) What rate of flow does this correspond to in terms of water volume (in L/min)? (c) Calculate the decay heat produced 1 day after shutdown of the reactor. (d) Qualitatively, how much can the flow rate of coolant water be reduced each day after shutdown? Conversion that may come in handy: • 1 eV = 1.602 × 10$^{-19}$ J • 1 amu = 931.49 MeV • $N_A$ = 6.022 × 10$^{23}$ atoms/mol • 1 tonne = 1000 kg • 1 Ci = 3.7 × 10$^{10}$ Bq • 1 Gy = 100 rad • 1 Sv = 100 rem Recoverable energy from 1 fission process: 190 MeV NRC occupational exposure limit: 5 rem/y. Potentially useful atomic masses Radiation Quality Factors Isotope Atomic mass (u) Proton 1.007276466879 Neutron 1.00866491585 H-1 1.00782503223 H-2 2.01410177812 He-4 4.00260325413 O-16 15.99491461957 U-235 235.043930131 U-238 238.050788423 Type of Radiation QF X-rays, gamma rays 1 beta particles 1 alpha particles 20 thermal neutrons (? 1 keV) 2 fast neutrons (? 1 MeV) 11

          Problem 12
A PWR nuclear power plant is operating at 1400MWe. The coolant water enters the reactor at 300°C (572°F) and leaves at 325°C (617°F). Assuming
the water is at PWR conditions of 140 bar (2000 psia, pounds per square inch absolute) and 316°C, the specific heat is 6.06 kJ/(kg°C) and the density
is 687 kg/m³.
(a) At what rate must water flow through the system to cool the reactor (in kg/s)?
(b) What rate of flow does this correspond to in terms of water volume (in L/min)?
(c) Calculate the decay heat produced 1 day after shutdown of the reactor.
(d) Qualitatively, how much can the flow rate of coolant water be reduced each day after shutdown?
Conversion that may come in handy:
• 1 eV = 1.602 × 10$^{-19}$ J
• 1 amu = 931.49 MeV
• $N_A$ = 6.022 × 10$^{23}$ atoms/mol
• 1 tonne = 1000 kg
• 1 Ci = 3.7 × 10$^{10}$ Bq
• 1 Gy = 100 rad
• 1 Sv = 100 rem
Recoverable energy from 1 fission process: 190 MeV
NRC occupational exposure limit: 5 rem/y.
Potentially useful atomic masses
Radiation Quality Factors
Isotope Atomic mass (u)
Proton 1.007276466879
Neutron 1.00866491585
H-1 1.00782503223
H-2 2.01410177812
He-4 4.00260325413
O-16 15.99491461957
U-235 235.043930131
U-238 238.050788423
Type of Radiation QF
X-rays, gamma rays 1
beta particles 1
alpha particles 20
thermal neutrons (? 1 keV) 2
fast neutrons (? 1 MeV) 11

Problem 12
A PWR nuclear power plant is operating at 1400MWe. The coolant water enters the reactor at 300°C (572°F) and leaves at 325°C (617°F). Assuming
the water is at PWR conditions of 140 bar (2000 psia, pounds per square inch absolute) and 316°C, the specific heat is 6.06 kJ/(kg°C) and the density
is 687 kg/m³.
(a) At what rate must water flow through the system to cool the reactor (in kg/s)?
(b) What rate of flow does this correspond to in terms of water volume (in L/min)?
(c) Calculate the decay heat produced 1 day after shutdown of the reactor.
(d) Qualitatively, how much can the flow rate of coolant water be reduced each day after shutdown?
Conversion that may come in handy:
• 1 eV = 1.602 × 10^-19 J
• 1 amu = 931.49 MeV
• NA = 6.022 × 10^23 atoms/mol
• 1 tonne = 1000 kg
• 1 Ci = 3.7 × 10^10 Bq
• 1 Gy = 100 rad
• 1 Sv = 100 rem
Recoverable energy from 1 fission process: 190 MeV
NRC occupational exposure limit: 5 rem/y.
Potentially useful atomic masses
Radiation Quality Factors
Isotope Atomic mass (u)
Proton 1.007276466879
Neutron 1.00866491585
H-1 1.00782503223
H-2 2.01410177812
He-4 4.00260325413
O-16 15.99491461957
U-235 235.043930131
U-238 238.050788423
Type of Radiation QF
X-rays, gamma rays 1
beta particles 1
alpha particles 20
thermal neutrons (? 1 keV) 2
fast neutrons (? 1 MeV) 11

Added by Vincent S.

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