35-Br-79
Spin
Level energy(keV) Spin & Parity
----------------------------------------
ground state 3/2-
2.07580E+02 9/2+
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)
78.918337579 ± 0.000001387 (amu) [mass excess = -76068.055 ± 1.292 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1625.778 ± 3.333 (keV)
Strong Gamma-rays from Decay of Br- 79 (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
----------------------------------------------------------
207.2 76.3 IT
----------------------------------------------------------
*: 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
IT 4.864 S 35
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Br-79.
Figures of cross sections, Br-79: 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- 79 (Z= 35, A= 79), MT= 2 (Elastic scattering)
Br- 79 (Z= 35, A= 79), MT= 4 (Inelastic scattering)
Br- 81 (Z= 35, A= 81), MT= 17 (n,3n)
Kr- 80 (Z= 36, A= 80), MT= 28 (n,np)
Kr- 80 (Z= 36, A= 80), MT=104 (n,d)
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)
-----------------------------------------------------------
Br- 79 U-235 Thermal 3.156320e-12 2.020050e-12
Br- 79 U-235 Fast 3.143140e-12 2.011610e-12
Br- 79 U-235 High 1.084300e-09 6.939480e-10
Br- 79 U-238 Fast 1.352730e-13 8.657490e-14
Br- 79 U-238 High 5.792880e-11 3.707450e-11
Br- 79 Pu-239 Thermal 5.799950e-10 3.711980e-10
Br- 79 Pu-239 Fast 2.559830e-10 1.638300e-10
Br- 79 Pu-239 High 4.236690e-09 2.711480e-09
Br- 79 Pu-241 Thermal 1.790390e-11 1.145850e-11
Br- 79 Pu-241 Fast 6.791570e-12 4.346610e-12
-----------------------------------------------------------
Br- 79m U-235 Thermal 1.033220e-11 6.612610e-12
Br- 79m U-235 Fast 1.189580e-11 7.613310e-12
Br- 79m U-235 High 6.716400e-09 4.298490e-09
Br- 79m U-238 Fast 5.119680e-13 3.276590e-13
Br- 79m U-238 High 3.588250e-10 2.296480e-10
Br- 79m Pu-239 Thermal 1.898620e-09 1.215110e-09
Br- 79m Pu-239 Fast 9.688180e-10 6.200430e-10
Br- 79m Pu-239 High 2.624310e-08 1.679560e-08
Br- 79m Pu-241 Thermal 5.860850e-11 3.750940e-11
Br- 79m Pu-241 Fast 2.570400e-11 1.645060e-11
-----------------------------------------------------------
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)
-----------------------------------------------------------
Br- 79 U-235 Thermal 4.467130e-04 2.684350e-05
Br- 79 U-235 Fast 9.069400e-04 9.995500e-05
Br- 79 U-235 High 1.682380e-03 1.847520e-04
Br- 79 U-238 Fast 3.272080e-04 7.514990e-05
Br- 79 U-238 High 1.335150e-03 2.132660e-04
Br- 79 Pu-239 Thermal 4.364550e-04 8.730230e-06
Br- 79 Pu-239 Fast 6.076550e-04 4.861590e-05
Br- 79 Pu-239 High 8.636770e-04 9.491810e-05
Br- 79 Pu-241 Thermal 1.496190e-04 2.393440e-05
Br- 79 Pu-241 Fast 3.584450e-04 5.738270e-05
-----------------------------------------------------------
Br- 79m U-235 Thermal 1.033220e-11 6.612610e-12
Br- 79m U-235 Fast 1.189580e-11 7.613310e-12
Br- 79m U-235 High 6.716400e-09 4.292120e-09
Br- 79m U-238 Fast 5.119680e-13 3.275390e-13
Br- 79m U-238 High 3.588250e-10 2.293990e-10
Br- 79m Pu-239 Thermal 1.898620e-09 1.215110e-09
Br- 79m Pu-239 Fast 9.688180e-10 6.200430e-10
Br- 79m Pu-239 High 2.624310e-08 1.678470e-08
Br- 79m Pu-241 Thermal 5.860850e-11 3.750340e-11
Br- 79m Pu-241 Fast 2.570400e-11 1.645060e-11
-----------------------------------------------------------
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