Research Article

Source Term Study on Tritium in HTR-PM: Theoretical Calculations and Experimental Design

Table 1

Main parameters used in the calculation of H-3 in HTR-PM.

ParameterDesign value

Rated thermal power for each module of HTR-PM250 MW
Average thermal neutron fluence rate in the reactor core7.10 + 13 cm−2⋅s−1
Average thermal neutron fluence rate in graphite reflectors2.70 + 13 cm−2⋅s−1
Average fast fluence rate in graphite reflectors4.10 + 12 cm−2⋅s−1
Average thermal neutron fluence rate in control rods2.45 + 13 cm−2⋅s−1
Average fast neutron fluence rate in control rods4.10 + 12 cm−2⋅s−1
Average thermal neutron fluence rate in absorber balls2.49 + 10 cm−2⋅s−1
Average fast neutron fluence rate in absorber balls2.10 + 8 cm−2⋅s−1
Average thermal neutron fluence rate in carbon bricks4.87 + 10 cm−2⋅s−1
Average fast neutron fluence rate in carbon bricks5.86 + 8 cm−2⋅s−1
Sum of the breakage rate and free uranium fraction2.61E − 4
Fission fraction of U-2350.655
Fission fraction of Pu-2390.271
Fission fraction of Pu-2410.070
Average yield of H-3 production per fission of U-2358.00E − 5
Average yield of H-3 production per fission of Pu-2391.80E − 4
Average yield of H-3 production per fission of Pu-2411.50E − 4
Helium volume in the primary loop15,690 Nm3
He-3 abundance in the primary helium1.40E − 7
Mass of matrix graphite of each fuel element0.186 kg
Li abundance in matrix graphite, graphite reflectors, and carbon bricks0.05 ppm
Mass of graphite reflectors252,000 kg
Mass of carbon bricks128,000 kg
Mass of B4C in absorber balls231 kg
Mass of B4C in control rods1,877 kg
Content of B4C in carbon bricks5%
Fractional leakage rate of the primary coolant0.5%/d
Fractional purification rate of HPS5%/h
Fractional permeation rate of H-3 to the secondary loop0.365%/h
Mass of water in the secondary loop100,000 kg
Fractional leakage rate of the secondary coolant5%/h