38-Sr-86
Spin
Level energy(keV) Spin & Parity
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ground state 0+
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)
85.909260608 ± 0.000001154 (amu) [mass excess = -84523.199 ± 1.076 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-5240.000 ± 14.142 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sr-86.
Figures of cross sections, Sr-86: 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
Sr- 86 (Z= 38, A= 86), MT= 2 (Elastic scattering)
Sr- 86 (Z= 38, A= 86), MT= 4 (Inelastic scattering)
Sr- 87 (Z= 38, A= 87), MT= 16 (n,2n)
Zr- 90 (Z= 40, A= 90), 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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Sr- 86 U-235 Thermal 1.188110e-10 7.603890e-11
Sr- 86 U-235 Fast 6.726110e-11 4.304710e-11
Sr- 86 U-235 High 3.665030e-08 2.345610e-08
Sr- 86 U-238 Fast 1.370510e-12 8.771270e-13
Sr- 86 U-238 High 5.746250e-10 3.677610e-10
Sr- 86 Pu-239 Thermal 1.009840e-08 6.462980e-09
Sr- 86 Pu-239 Fast 3.579420e-09 2.290830e-09
Sr- 86 Pu-239 High 1.390900e-07 8.901770e-08
Sr- 86 Pu-241 Thermal 1.620260e-10 1.036970e-10
Sr- 86 Pu-241 Fast 3.707210e-11 2.372620e-11
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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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Sr- 86 U-235 Thermal 6.451300e-08 4.128840e-08
Sr- 86 U-235 Fast 4.371430e-07 2.797720e-07
Sr- 86 U-235 High 1.618740e-06 1.035990e-06
Sr- 86 U-238 Fast 2.801040e-08 1.792010e-08
Sr- 86 U-238 High 1.297090e-07 8.301340e-08
Sr- 86 Pu-239 Thermal 1.839720e-06 1.177420e-06
Sr- 86 Pu-239 Fast 4.732580e-06 3.028850e-06
Sr- 86 Pu-239 High 3.768160e-05 2.410240e-05
Sr- 86 Pu-241 Thermal 8.032520e-07 5.139200e-07
Sr- 86 Pu-241 Fast 2.178620e-07 1.394320e-07
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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