35-Br-87
Spin
Level energy(keV) Spin & Parity
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ground state 3/2-
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)
86.920674018 ± 0.000003404 (amu) [mass excess = -73891.676 ± 3.171 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
6817.845 ± 3.181 (keV)
Strong Gamma-rays from Decay of Br- 87 (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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1419.71 22. B-
1476.06 7.9 B-
1577.60 6. 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- 55.65 S 13
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
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- 87 U-235 Thermal 1.269840e-02 3.555540e-04
Br- 87 U-235 Fast 1.422480e-02 8.534850e-04
Br- 87 U-235 High 1.137890e-02 3.641230e-03
Br- 87 U-238 Fast 6.577160e-03 2.104690e-03
Br- 87 U-238 High 9.127980e-03 2.920960e-03
Br- 87 Pu-239 Thermal 5.530270e-03 3.318160e-04
Br- 87 Pu-239 Fast 6.233080e-03 1.433610e-03
Br- 87 Pu-239 High 7.026560e-03 4.497000e-03
Br- 87 Pu-241 Thermal 4.368970e-03 6.990340e-04
Br- 87 Pu-241 Fast 4.144770e-03 1.865150e-03
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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- 87 U-235 Thermal 2.069150e-02 5.343810e-04
Br- 87 U-235 Fast 2.109410e-02 1.268160e-03
Br- 87 U-235 High 1.623180e-02 2.590810e-03
Br- 87 U-238 Fast 1.543740e-02 9.246340e-04
Br- 87 U-238 High 1.554470e-02 9.310490e-04
Br- 87 Pu-239 Thermal 6.907680e-03 4.144850e-04
Br- 87 Pu-239 Fast 8.050770e-03 6.440660e-04
Br- 87 Pu-239 High 9.135710e-03 4.105540e-03
Br- 87 Pu-241 Thermal 6.249640e-03 3.748270e-04
Br- 87 Pu-241 Fast 6.939170e-03 5.551790e-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