35-Br-84
Spin
Level energy(keV) Spin & Parity
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ground state 2-
3.20000E+02 (5-,6-)
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)
83.916496419 ± 0.000027622 (amu) [mass excess = -77783.084 ± 25.730 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
4656.251 ± 25.730 (keV)
Strong Gamma-rays from Decay of Br- 84 (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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881.6 41.6 B-
1897.6 14.56 B-
3927.5 6.78 B-
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424.0 100. B-
881.6 98. B-
1462.8 97. 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- 31.76 M 8
B- 6.0 M 2
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Kr- 84 (Z= 36, A= 84), MT=103 (n,p)
Kr- 85 (Z= 36, A= 85), MT= 28 (n,np)
Kr- 85 (Z= 36, A= 85), MT=104 (n,d)
Kr- 86 (Z= 36, A= 86), MT=105 (n,t)
Rb- 86 (Z= 37, A= 86), MT=106 (n,3He)
Rb- 87 (Z= 37, A= 87), MT=107 (n,α)
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- 84 U-235 Thermal 1.258460e-04 1.384300e-05
Br- 84 U-235 Fast 8.481250e-05 5.428000e-05
Br- 84 U-235 High 3.522350e-04 2.254300e-04
Br- 84 U-238 Fast 1.515430e-05 9.698780e-06
Br- 84 U-238 High 9.619290e-05 6.156350e-05
Br- 84 Pu-239 Thermal 2.706880e-04 1.732400e-04
Br- 84 Pu-239 Fast 1.642380e-04 1.051130e-04
Br- 84 Pu-239 High 2.509560e-04 1.606120e-04
Br- 84 Pu-241 Thermal 8.909660e-05 5.702190e-05
Br- 84 Pu-241 Fast 3.511280e-05 2.247220e-05
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Br- 84m U-235 Thermal 2.266630e-04 1.813310e-05
Br- 84m U-235 Fast 1.777650e-04 1.137700e-04
Br- 84m U-235 High 1.234410e-03 7.900220e-04
Br- 84m U-238 Fast 3.176310e-05 2.032840e-05
Br- 84m U-238 High 3.371080e-04 2.157490e-04
Br- 84m Pu-239 Thermal 4.875420e-04 3.120270e-04
Br- 84m Pu-239 Fast 3.442390e-04 2.203130e-04
Br- 84m Pu-239 High 8.794770e-04 5.628650e-04
Br- 84m Pu-241 Thermal 1.604740e-04 1.027030e-04
Br- 84m Pu-241 Fast 7.359550e-05 4.710110e-05
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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- 84 U-235 Thermal 9.665330e-03 1.845600e-04
Br- 84 U-235 Fast 1.010720e-02 4.055350e-04
Br- 84 U-235 High 1.383640e-02 3.177560e-03
Br- 84 U-238 Fast 8.221840e-03 2.302810e-04
Br- 84 U-238 High 1.090740e-02 6.539030e-04
Br- 84 Pu-239 Thermal 4.289330e-03 4.718480e-04
Br- 84 Pu-239 Fast 4.630310e-03 5.093520e-04
Br- 84 Pu-239 High 7.055970e-03 2.256420e-03
Br- 84 Pu-241 Thermal 3.351110e-03 2.010040e-04
Br- 84 Pu-241 Fast 3.491460e-03 1.397650e-04
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Br- 84m U-235 Thermal 2.266630e-04 1.816400e-05
Br- 84m U-235 Fast 1.777650e-04 1.137700e-04
Br- 84m U-235 High 1.234410e-03 7.888520e-04
Br- 84m U-238 Fast 3.176310e-05 2.032090e-05
Br- 84m U-238 High 3.371080e-04 2.155160e-04
Br- 84m Pu-239 Thermal 4.875420e-04 3.120270e-04
Br- 84m Pu-239 Fast 3.442390e-04 2.203130e-04
Br- 84m Pu-239 High 8.794770e-04 5.625010e-04
Br- 84m Pu-241 Thermal 1.604740e-04 1.026870e-04
Br- 84m Pu-241 Fast 7.359550e-05 4.710110e-05
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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