38-Sr-87
Spin
Level energy(keV) Spin & Parity
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ground state 9/2+
3.88533E+02 1/2-
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)
86.908877531 ± 0.000001154 (amu) [mass excess = -84880.033 ± 1.075 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-1861.690 ± 1.128 (keV)
Strong Gamma-rays from Decay of Sr- 87 (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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388.53 82.35 IT
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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
EC 2.815 H 12
IT 2.815 H 12
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Sr-87.
Figures of cross sections, Sr-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
Sr- 86 (Z= 38, A= 86), MT=102 (n,γ)
Sr- 87 (Z= 38, A= 87), MT= 2 (Elastic scattering)
Sr- 87 (Z= 38, A= 87), MT= 4 (Inelastic scattering)
Sr- 88 (Z= 38, A= 88), MT= 16 (n,2n)
Sr- 89 (Z= 38, A= 89), MT= 17 (n,3n)
Y - 89 (Z= 39, A= 89), MT= 32 (n,nd)
Y - 89 (Z= 39, A= 89), MT=105 (n,t)
Zr- 90 (Z= 40, A= 90), MT=107 (n,α)
Zr- 91 (Z= 40, 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)
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Sr- 87 U-235 Thermal 1.070940e-08 6.854070e-09
Sr- 87 U-235 Fast 4.781620e-09 3.060230e-09
Sr- 87 U-235 High 8.127460e-07 5.201580e-07
Sr- 87 U-238 Fast 1.334190e-10 8.538830e-11
Sr- 87 U-238 High 1.797500e-08 1.150390e-08
Sr- 87 Pu-239 Thermal 2.465660e-07 1.578020e-07
Sr- 87 Pu-239 Fast 1.142980e-07 7.315090e-08
Sr- 87 Pu-239 High 2.346730e-06 1.501910e-06
Sr- 87 Pu-241 Thermal 8.771010e-09 5.613460e-09
Sr- 87 Pu-241 Fast 2.383550e-09 1.525470e-09
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Sr- 87m U-235 Thermal 2.479520e-09 1.586900e-09
Sr- 87m U-235 Fast 9.655190e-10 6.179320e-10
Sr- 87m U-235 High 1.025090e-07 6.560520e-08
Sr- 87m U-238 Fast 2.694050e-11 1.724190e-11
Sr- 87m U-238 High 2.267110e-09 1.450960e-09
Sr- 87m Pu-239 Thermal 5.708660e-08 3.653540e-08
Sr- 87m Pu-239 Fast 2.307950e-08 1.477080e-08
Sr- 87m Pu-239 High 2.959840e-07 1.894300e-07
Sr- 87m Pu-241 Thermal 2.030730e-09 1.299670e-09
Sr- 87m Pu-241 Fast 4.812940e-10 3.080280e-10
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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- 87 U-235 Thermal 2.591430e-02 3.382250e-04
Sr- 87 U-235 Fast 2.540520e-02 2.565090e-04
Sr- 87 U-235 High 2.456700e-02 9.821800e-04
Sr- 87 U-238 Fast 1.632320e-02 1.762000e-04
Sr- 87 U-238 High 1.693350e-02 3.443390e-04
Sr- 87 Pu-239 Thermal 1.004000e-02 5.020370e-05
Sr- 87 Pu-239 Fast 1.043480e-02 1.043420e-04
Sr- 87 Pu-239 High 1.313460e-02 5.249690e-04
Sr- 87 Pu-241 Thermal 7.533600e-03 1.506590e-04
Sr- 87 Pu-241 Fast 8.021290e-03 1.604050e-04
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Sr- 87m U-235 Thermal 2.479530e-09 1.586900e-09
Sr- 87m U-235 Fast 9.655200e-10 6.179330e-10
Sr- 87m U-235 High 1.031530e-07 6.551270e-08
Sr- 87m U-238 Fast 2.694050e-11 1.723560e-11
Sr- 87m U-238 High 2.267130e-09 1.449380e-09
Sr- 87m Pu-239 Thermal 5.708760e-08 3.653600e-08
Sr- 87m Pu-239 Fast 2.307970e-08 1.477100e-08
Sr- 87m Pu-239 High 2.987570e-07 2.390340e-08
Sr- 87m Pu-241 Thermal 2.030730e-09 1.299450e-09
Sr- 87m Pu-241 Fast 4.812950e-10 3.080290e-10
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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