37-Rb-87
Spin
Level energy(keV) Spin & Parity
----------------------------------------
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)
86.909180531 ± 0.000000006 (amu) [mass excess = -84597.790 ± 0.006 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
282.243 ± 1.075 (keV)
Decay data(Chart of the Nuclides 2014)
Decay mode Half-life
B- 4.81E10 Y 9
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Rb-87.
Figures of cross sections, Rb-87: 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
Rb- 86 (Z= 37, A= 86), MT=102 (n,γ)
Rb- 87 (Z= 37, A= 87), MT= 2 (Elastic scattering)
Rb- 87 (Z= 37, A= 87), MT= 4 (Inelastic scattering)
Sr- 87 (Z= 38, A= 87), MT=103 (n,p)
Sr- 88 (Z= 38, A= 88), MT= 28 (n,np)
Sr- 88 (Z= 38, A= 88), MT=104 (n,d)
Sr- 89 (Z= 38, A= 89), MT= 32 (n,nd)
Sr- 89 (Z= 38, A= 89), MT=105 (n,t)
Y - 89 (Z= 39, A= 89), MT=106 (n,3He)
Y - 90 (Z= 39, A= 90), MT=107 (n,α)
Y - 91 (Z= 39, A= 91), 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)
-----------------------------------------------------------
Rb- 87 U-235 Thermal 2.498020e-05 1.598740e-05
Rb- 87 U-235 Fast 1.328260e-05 8.500850e-06
Rb- 87 U-235 High 2.043100e-04 1.307580e-04
Rb- 87 U-238 Fast 1.440540e-06 4.609720e-07
Rb- 87 U-238 High 1.897070e-05 1.214130e-05
Rb- 87 Pu-239 Thermal 1.465970e-04 9.382200e-05
Rb- 87 Pu-239 Fast 6.538940e-05 4.184930e-05
Rb- 87 Pu-239 High 2.739880e-04 1.753520e-04
Rb- 87 Pu-241 Thermal 1.468240e-05 9.396710e-06
Rb- 87 Pu-241 Fast 5.925540e-06 3.792350e-06
-----------------------------------------------------------
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)
-----------------------------------------------------------
Rb- 87 U-235 Thermal 2.591430e-02 3.382120e-04
Rb- 87 U-235 Fast 2.540520e-02 2.565100e-04
Rb- 87 U-235 High 2.456610e-02 9.821420e-04
Rb- 87 U-238 Fast 1.632320e-02 1.762000e-04
Rb- 87 U-238 High 1.693350e-02 3.443350e-04
Rb- 87 Pu-239 Thermal 1.003970e-02 5.020220e-05
Rb- 87 Pu-239 Fast 1.043460e-02 1.043410e-04
Rb- 87 Pu-239 High 1.313190e-02 5.248630e-04
Rb- 87 Pu-241 Thermal 7.533590e-03 1.506590e-04
Rb- 87 Pu-241 Fast 8.021290e-03 3.208000e-04
-----------------------------------------------------------
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