35-Br-81
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)
80.916289690 ± 0.000001375 (amu) [mass excess = -77975.651 ± 1.281 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-280.837 ± 0.483 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Br-81.
Figures of cross sections, Br-81: 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
Br- 81 (Z= 35, A= 81), MT= 2 (Elastic scattering)
Br- 81 (Z= 35, A= 81), MT= 4 (Inelastic scattering)
Kr- 82 (Z= 36, A= 82), MT= 28 (n,np)
Kr- 82 (Z= 36, A= 82), MT=104 (n,d)
Kr- 83 (Z= 36, A= 83), MT= 32 (n,nd)
Kr- 83 (Z= 36, A= 83), MT=105 (n,t)
Rb- 85 (Z= 37, A= 85), 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- 81 U-235 Thermal 8.845910e-08 5.661390e-08
Br- 81 U-235 Fast 5.857910e-08 3.749060e-08
Br- 81 U-235 High 2.883950e-06 1.845730e-06
Br- 81 U-238 Fast 2.540950e-09 1.626210e-09
Br- 81 U-238 High 3.714050e-07 2.376990e-07
Br- 81 Pu-239 Thermal 2.669580e-06 1.708530e-06
Br- 81 Pu-239 Fast 8.338650e-07 5.336740e-07
Br- 81 Pu-239 High 6.354120e-06 4.066640e-06
Br- 81 Pu-241 Thermal 1.310210e-07 8.385350e-08
Br- 81 Pu-241 Fast 5.575810e-08 3.568520e-08
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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- 81 U-235 Thermal 1.900650e-03 1.474810e-04
Br- 81 U-235 Fast 2.145340e-03 2.846540e-04
Br- 81 U-235 High 3.296180e-03 3.938410e-04
Br- 81 U-238 Fast 7.955030e-04 2.091610e-04
Br- 81 U-238 High 3.150240e-03 4.080320e-04
Br- 81 Pu-239 Thermal 1.766000e-03 3.021430e-04
Br- 81 Pu-239 Fast 1.352580e-03 1.694760e-04
Br- 81 Pu-239 High 2.618470e-03 4.469070e-04
Br- 81 Pu-241 Thermal 5.823190e-04 1.067310e-04
Br- 81 Pu-241 Fast 8.653470e-04 1.172010e-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