35-Br-82
Spin
Level energy(keV) Spin & Parity
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ground state 5-
4.59492E+01 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)
81.916803246 ± 0.000001370 (amu) [mass excess = -77497.277 ± 1.277 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
3093.041 ± 0.973 (keV)
Strong Gamma-rays from Decay of Br- 82 (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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698.37 0.03 B-
776.52 0.26 B-
1474.88 0.02 B-
45.95 -- IT
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554.35 71.06 B-
619.11 43.53 B-
776.52 83.4 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- 35.282 H 7
B- 6.13 M 5
IT 6.13 M 5
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Br- 81 (Z= 35, A= 81), MT=102 (n,γ)
Kr- 82 (Z= 36, A= 82), MT=103 (n,p)
Kr- 83 (Z= 36, A= 83), MT= 28 (n,np)
Kr- 83 (Z= 36, A= 83), MT=104 (n,d)
Kr- 84 (Z= 36, A= 84), MT=105 (n,t)
Rb- 85 (Z= 37, A= 85), MT=107 (n,α)
Rb- 86 (Z= 37, A= 86), 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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Br- 82 U-235 Thermal 3.821370e-07 2.445680e-07
Br- 82 U-235 Fast 1.040950e-06 6.662090e-07
Br- 82 U-235 High 3.808660e-05 2.285190e-06
Br- 82 U-238 Fast 8.970350e-08 5.741020e-08
Br- 82 U-238 High 1.419230e-06 9.083100e-07
Br- 82 Pu-239 Thermal 8.999420e-06 5.759630e-06
Br- 82 Pu-239 Fast 8.248310e-06 5.278920e-06
Br- 82 Pu-239 High 3.557590e-05 2.276860e-05
Br- 82 Pu-241 Thermal 2.263190e-06 1.448440e-06
Br- 82 Pu-241 Fast 7.394960e-07 4.732770e-07
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Br- 82m U-235 Thermal 1.629940e-07 1.043170e-07
Br- 82m U-235 Fast 3.811130e-07 2.439120e-07
Br- 82m U-235 High 8.417180e-06 5.050310e-07
Br- 82m U-238 Fast 3.284220e-08 2.101900e-08
Br- 82m U-238 High 3.136520e-07 2.007380e-07
Br- 82m Pu-239 Thermal 3.838550e-06 2.456680e-06
Br- 82m Pu-239 Fast 3.019870e-06 1.932720e-06
Br- 82m Pu-239 High 7.862310e-06 5.031880e-06
Br- 82m Pu-241 Thermal 9.653280e-07 6.178110e-07
Br- 82m Pu-241 Fast 2.707440e-07 1.732760e-07
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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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Br- 82 U-235 Thermal 5.412200e-07 3.463800e-07
Br- 82 U-235 Fast 1.412920e-06 9.042650e-07
Br- 82 U-235 High 4.630170e-05 1.851230e-06
Br- 82 U-238 Fast 1.217570e-07 7.792470e-08
Br- 82 U-238 High 1.725360e-06 1.104220e-06
Br- 82 Pu-239 Thermal 1.274590e-05 5.106420e-07
Br- 82 Pu-239 Fast 1.119570e-05 7.165250e-06
Br- 82 Pu-239 High 4.324950e-05 2.763070e-05
Br- 82 Pu-241 Thermal 3.205350e-06 2.049810e-06
Br- 82 Pu-241 Fast 1.003740e-06 6.413150e-07
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Br- 82m U-235 Thermal 1.629940e-07 1.043170e-07
Br- 82m U-235 Fast 3.811130e-07 2.439120e-07
Br- 82m U-235 High 8.417180e-06 5.044360e-07
Br- 82m U-238 Fast 3.284220e-08 2.101130e-08
Br- 82m U-238 High 3.136520e-07 2.005200e-07
Br- 82m Pu-239 Thermal 3.838550e-06 2.456680e-06
Br- 82m Pu-239 Fast 3.019870e-06 1.932720e-06
Br- 82m Pu-239 High 7.862310e-06 5.028620e-06
Br- 82m Pu-241 Thermal 9.653280e-07 6.177110e-07
Br- 82m Pu-241 Fast 2.707440e-07 1.732760e-07
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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