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15. Accident Analyses

AP1000 Design Control Document

Table 15A-3 (Sheet 1 of 2)

I-130

3.66x106

I-131

9.63x107

I-132

1.40x108

I-133

1.99x108

I-134

2.18x108

I-135

1.86x108

Cs-134

1.94x107

Cs-136

5.53x106

Cs-137

1.13x107

Cs-138

1.82x108

Rb-86

2.29x105

Te-127m

1.32x106

Te-127

1.02x107

Te-129m

4.50x106

Te-129

3.04x107

Te-131m

1.40x107

Te-132

1.38x108

Sb-127

1.03x107

Sb-129

3.10x107

Ru-103

1.45x108

Ru-105

9.83x107

Ru-106

4.77x107

Rh-105

9.00x107

Mo-99

1.84x108

Tc-99m

1.61x108

Note:

  • 1.

    The following assumptions apply:

    • Core thermal power of 3468 MWt (2 percent above the design core power of 3400 MWt)

    • Three-region equilibrium cycle core at end of life

REACTOR CORE SOURCE TERM(1)

Iodines

Cs Group

Te Group

Ru Group

Nuclide

Inventory (Ci)

Nuclide

Noble Gases

Sr & Ba

Ce Group

Kr-85m Kr-85 Kr-87 Kr-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-138 Sr-89 Sr-90 Sr-91 Sr-92 Ba-139 Ba-140 Ce-141 Ce-143 Ce-144 Pu-238 Pu-239 Pu-240 Pu-241 Np-239

Inventory (Ci)

    • 2.63

      x107

    • 1.06

      x106

    • 5.07

      x107

    • 7.14

      x107

    • 1.06

      x106

    • 5.84

      x106

    • 1.90

      x108

    • 3.87

      x107

    • 4.84

      x107

    • 1.65

      x108

    • 9.66

      x107

    • 8.31

      x106

    • 1.20

      x108

    • 1.29

      x108

    • 1.78

      x108

    • 1.71

      x108

    • 1.63

      x108

    • 1.52

      x108

    • 1.23

      x108

    • 3.83

      x105

    • 3.37

      x104

    • 4.94

      x104

    • 1.11

      x107

    • 1.93

      x109

Tier 2 Material

15A-8

Revision 12

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