Open Access

Research on dose correction method of vehicle-borne environmental radiation measurement equipment


Cite

Fig. 1

NaI (Tl) detector model.
NaI (Tl) detector model.

Fig. 2

Simulation model of vehicle-borne radiation environmental measurement equipment.
Simulation model of vehicle-borne radiation environmental measurement equipment.

Fig. 3

Reference radiation field model: (a) early radiation field and (b) mid-late radiation field.
Reference radiation field model: (a) early radiation field and (b) mid-late radiation field.

Fig. 4

Trend of ambient dose rate with gamma energy in the single reference radiation field.
Trend of ambient dose rate with gamma energy in the single reference radiation field.

Fig. 5

Results of radionuclide activity over time: (a) early radiation field and (b) mid-late radiation field.
Results of radionuclide activity over time: (a) early radiation field and (b) mid-late radiation field.

Fig. 6

Ambient dose rates of the mixed-nuclide radiation field varying with time: (a) early radiation field and (b) mid-late radiation field.
Ambient dose rates of the mixed-nuclide radiation field varying with time: (a) early radiation field and (b) mid-late radiation field.

Representative nuclides in single-nuclide reference radiation field

Nuclides 60Co 132Te 137Cs 131I 133Xe
Half-life 5.27 a 76.80 h 30.07 a 8.02 d 5.25 d
Gamma energy (keV) 1173.24, 1332.50 228.16 661.66 364.49 81.00

Mass fraction percentage of main components of air and soil

Air

C N O Ar
0.02 75.50 23.20 1.28

Soil

H O Al Si Fe
6.67 48.33 18.00 22.50 4.50

Detector located at different locations of the dose CF

Central place Car (μGy/s) Air (μGy/s) CF Error
97.5, 160, 160 7.0442 × 10−3 7.8729 × 10−3 0.8947 0.8813 + 0.015
97.5, 195, 160 7.0905 × 10−3 7.9737 × 10−3 0.8892 0.8813 + 0.009
97.5, 230, 160 7.0965 × 10−3 8.1073 × 10−3 0.8753 0.8813 − 0.007
47.5, 240, 160 7.0088 × 10−3 8.0049 × 10−3 0.8756 0.8813 − 0.006
147.5, 240, 160 7.0541 × 10−3 8.0180 × 10−3 0.8798 0.8813 − 0.002
97.5, 265, 160 7.1126 × 10−3 8.1010 × 10−3 0.8780 0.8813 − 0.004
97.5, 300, 160 6.8867 × 10−3 7.8778 × 10−3 0.8742 0.8813 − 0.008
97.5, 335, 160 7.1724 × 10−3 8.2174 × 10−3 0.8728 0.8813 − 0.010
47.5, 370, 160 7.0047 × 10−3 7.9291 × 10−3 0.8834 0.8813 + 0.002
97.5, 370, 160 6.9351 × 10−3 7.8866 × 10−3 0.8794 0.8813 − 0.002
147.5, 370, 160 7.2050 × 10−3 8.1576 × 10−3 0.8832 0.8813 + 0.002
97.5, 405, 160 6.9543 × 10−3 7.8149 × 10−3 0.8899 0.8813 + 0.010

Environmental background composition of the reference radiation field

Distribution Aerosol Soil
Nuclides 7Be 40K 137Cs 210Pb 137Cs 226Ra
Energy (keV) 477.61 1460.83 661.66 46.54 661.66 186.21
Background (Bq) 5.66 × 101 2.36 × 100 1.37 × 10−2 2.84 × 101 3.91 × 105 2.98 × 104

Nuclide composition of the reference radiation field in the soil of middle and late stages of a nuclear accident

Nuclides 89Sr 131I 134Cs 136Cs 137Cs 238Pu 241Am
Energy (keV) 583.00 364.49 604.72 818.50 661.66 42.49 59.54
Concentration (Bq/kg) 1.31 × 102 3.44 × 104 8.63 × 104 1.11 × 103 8.53 × 104 2.40 × 10−3 1.21 × 10−3
Activity (Bq) 6.17 × 105 1.62 × 108 4.06 × 108 5.30 × 106 4.02 × 108 1.13 × 101 3.17 × 104

Dose rates measured at the height of 1 m above the ground and at the car roof of single-nuclide radiation field (μGy/s)

Nuclides Energy (keV) Car (μGy/s) Air (μGy/s)
133Xe 81.00 2.5149 × 10−5 2.8241 × 10−5
132Te 228.16 6.8513 × 10−4 7.8970 × 10−4
131I 364.49 2.4188 × 10−3 2.7888 × 10−3
137Cs 661.66 7.0965 × 10−3 8.1073 × 10−3
60Co 1173.24, 1332.50 1.5559 × 10−2 1.7436 × 10−2

Dose CF of mid-late mixed-nuclide reference radiation field

Time (d) 1 3 5 7 9 11 13 20 40 60 80 100
CF 0.669 0.669 0.670 0.670 0.670 0.671 0.671 0.672 0.672 0.672 0.672 0.673

Detailed information of the structure and materials of each component in the generalized model of vehicle-borne environmental radiation measurement equipment

Structure Material Component Density (g/cm3) Thickness (cm)
Vehicle chassis Alloy steel 3.45% C, 96.55% Fe 7.85 10.00
Vehicle tires Rubber 11.84% H, 88.16% C 0.92
Carriage Aluminium skin 100% Al 2.70 0.12
Polyurethane foam 54.4% C, 12.1% N, 33.5% O 0.04
Glass 46.0% O, 33.6% Si, 10.7% Ca, 9.7% Na 2.40 1.00
Aluminium alloy 97.43% Al, 1.55% C, 1.02% Cu 2.80 3.76
Detector crystal Sodium iodide 15.34% Na, 84.66% I 3.67
Magnesium oxide 39.7% O, 60.3% Mg 2.58 0.05
Aluminium 100% Al 2.70 0.20
Silicon dioxide 53.2% Si, 46.8% O 2.32 0.20

Dose CF of single-nuclide reference radiation field

Nuclides 133Xe 132Te 131I 137Cs 60Co
CF 0.8905 0.8676 0.8673 0.8753 0.8923

Dose CF of early mixed-nuclide reference radiation field

Time (h) 0 2 4 6 8 10 12 14 16 18 20 22 24
CF 0.883 0.883 0.883 0.884 0.884 0.884 0.884 0.884 0.884 0.884 0.884 0.883 0.883

Nuclide composition of the reference radiation field in the air of early stages of a nuclear accident

Nuclides 106Ru 129Te 131I 132Te 132I 133I 134Cs 136Cs 137Cs 144Ce
Energy (keV) 511.85 459.60 364.49 228.16 667.72 529.87 604.72 818.50 661.66 696.51
Concentration (Bq/m3) 1.24 × 102 1.30 × 103 3.23 × 103 3.22 × 102 1.23 × 103 3.80 × 101 3.55 × 101 5.00 × 100 3.75 × 101 5.00 × 103
Activity (Bq) 7.79 × 105 8.16 × 106 2.53 × 107 2.02 × 106 9.26 × 106 2.39 × 105 3.99 × 105 3.17 × 104 4.26 × 105 3.14 × 107
eISSN:
1508-5791
Language:
English
Publication timeframe:
4 times per year
Journal Subjects:
Chemistry, Nuclear Chemistry, Physics, Astronomy and Astrophysics, other