36-Kr-85
Spin
Level energy(keV) Spin & Parity
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ground state 9/2+
3.04870E+02 1/2-
Mass (The Ame2012 atomic mass evaluation (II) by M.Wang, G.Audi, A.H.Wapstra, F.G.Kondev, M.MacCormick, X.Xu, and B.Pfeiffer
Chinese Physics C36 p. 1603-2014, December 2012)
84.912527262 ± 0.000002147 (amu) [mass excess = -81480.330 ± 2.000 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
687.000 ± 2.000 (keV)
Strong Gamma-rays from Decay of Kr- 85 (Compiled from ENSDF as of March 2011)
[ Intensities before May 23th of 2013 were values when total intensity of the decay mode was 100(%) and a branching ratio of each decay mode was not multiplied. ]
γ-ray energy(keV) Intensity(%) Decay mode
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151.18 2.E-06 B-
362.81 2.E-06 B-
514.00 0.43 B-
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304.87 14.02 IT
129.81 0.3 B-
151.19 74.98 B-
451.0 0.01 B-
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*: relative, ~ approximate, ? calculated or estimatted
>: greater than or equal to, <: less than or equal to
[ Intensities; total intensity of the nuclide is 100(%). ]
Decay data(Chart of the Nuclides 2014)
Decay mode Half-life
B- 4.480 H 8
B- 10.756 Y 18
IT 4.480 H 8
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Kr-85.
Figures of cross sections, Kr-85: type-1: type-2: type-3.
type-1: total, elastic and inelastic scattering, capture and fision cross sections
type-2: same as type-1 but cross sections are averaged in 70 energy group intervals
type-3: threshold reaction cross sections
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Kr- 84 (Z= 36, A= 84), MT=102 (n,γ)
Kr- 85 (Z= 36, A= 85), MT= 2 (Elastic scattering)
Kr- 85 (Z= 36, A= 85), MT= 4 (Inelastic scattering)
Kr- 86 (Z= 36, A= 86), MT= 16 (n,2n)
Rb- 85 (Z= 37, A= 85), MT=103 (n,p)
Rb- 86 (Z= 37, A= 86), MT= 28 (n,np)
Rb- 86 (Z= 37, A= 86), MT=104 (n,d)
Rb- 87 (Z= 37, A= 87), MT= 32 (n,nd)
Rb- 87 (Z= 37, A= 87), MT=105 (n,t)
Sr- 87 (Z= 38, A= 87), MT=106 (n,3He)
Sr- 88 (Z= 38, A= 88), MT=107 (n,α)
Sr- 89 (Z= 38, A= 89), MT= 22 (n,nα)
Fission Yields for Fission Products in JENDL-4.0 Fission Yield Data
- Neutron-induced Fission Yields (from main actinide nuclides) - Independent Fission Yield -
Product Nuclide Energy Fission Yield Uncertainty(1σ)
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Kr- 85 U-235 Thermal 2.547730e-04 4.076370e-05
Kr- 85 U-235 Fast 3.095300e-05 1.980990e-05
Kr- 85 U-235 High 2.740750e-04 1.754080e-04
Kr- 85 U-238 Fast 1.995880e-06 1.277370e-06
Kr- 85 U-238 High 3.234060e-05 2.069800e-05
Kr- 85 Pu-239 Thermal 1.005260e-04 6.433660e-05
Kr- 85 Pu-239 Fast 9.493250e-05 6.075680e-05
Kr- 85 Pu-239 High 2.925810e-04 1.872520e-04
Kr- 85 Pu-241 Thermal 2.384420e-05 1.526030e-05
Kr- 85 Pu-241 Fast 1.023420e-05 6.549900e-06
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Kr- 85m U-235 Thermal 5.898700e-05 9.437910e-06
Kr- 85m U-235 Fast 6.250130e-06 4.000080e-06
Kr- 85m U-235 High 3.456800e-05 2.212350e-05
Kr- 85m U-238 Fast 4.030140e-07 2.579290e-07
Kr- 85m U-238 High 4.079000e-06 2.610560e-06
Kr- 85m Pu-239 Thermal 2.327450e-05 1.489570e-05
Kr- 85m Pu-239 Fast 1.916910e-05 1.226820e-05
Kr- 85m Pu-239 High 3.690220e-05 2.361740e-05
Kr- 85m Pu-241 Thermal 5.520570e-06 3.533170e-06
Kr- 85m Pu-241 Fast 2.066530e-06 1.322580e-06
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Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
- Neutron-induced Fission Yields (from main actinide nuclides) - Cumulative Fission Yield -
Product Nuclide Energy Fission Yield Uncertainty(1σ)
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Kr- 85 U-235 Thermal 3.061320e-03 2.276640e-04
Kr- 85 U-235 Fast 2.960730e-03 2.182300e-04
Kr- 85 U-235 High 3.815270e-03 3.422730e-04
Kr- 85 U-238 Fast 1.621570e-03 1.386380e-04
Kr- 85 U-238 High 2.207990e-03 1.770740e-04
Kr- 85 Pu-239 Thermal 1.315640e-03 8.872300e-05
Kr- 85 Pu-239 Fast 1.376330e-03 1.001120e-04
Kr- 85 Pu-239 High 2.313060e-03 3.774380e-04
Kr- 85 Pu-241 Thermal 8.956160e-04 6.849230e-05
Kr- 85 Pu-241 Fast 9.714650e-04 8.928970e-05
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Kr- 85m U-235 Thermal 1.300560e-02 1.082060e-04
Kr- 85m U-235 Fast 1.357620e-02 1.929440e-04
Kr- 85m U-235 High 1.640970e-02 6.558670e-04
Kr- 85m U-238 Fast 7.504870e-03 1.670230e-04
Kr- 85m U-238 High 1.008160e-02 2.077610e-04
Kr- 85m Pu-239 Thermal 5.630840e-03 4.044600e-05
Kr- 85m Pu-239 Fast 5.937980e-03 8.359910e-05
Kr- 85m Pu-239 High 9.362920e-03 2.620820e-04
Kr- 85m Pu-241 Thermal 4.039710e-03 1.131560e-04
Kr- 85m Pu-241 Fast 4.454220e-03 2.673190e-04
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Thermal=0.0253eV, Fast=500keV(Fast reactor spectrum), High=14MeV
→ Neutron-induced and Spontaneous Fission Yields of all nuclides in JENDL-4.0 Fission Yield Data