39-Y-90
Spin
Level energy(keV) Spin & Parity
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ground state 2-
6.82040E+02 7+
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)
89.907143942 ± 0.000002397 (amu) [mass excess = -86494.860 ± 2.233 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
2278.698 ± 1.647 (keV)
Strong Gamma-rays from Decay of Y- 90 (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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202.53 97.25 IT
479.51 90.74 IT
681.8 0.32 IT
2318.97 2.E-03 B-
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1760.70 -- B-
2186.24 1.E-06 B-
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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
B- 3.19 H 1
B- 64.00 H 21
IT 3.19 H 6
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Y-90.
Figures of cross sections, Y-90: 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
Y - 89 (Z= 39, A= 89), MT=102 (n,γ)
Y - 90 (Z= 39, A= 90), MT= 2 (Elastic scattering)
Y - 90 (Z= 39, A= 90), MT= 4 (Inelastic scattering)
Y - 91 (Z= 39, A= 91), MT= 16 (n,2n)
Zr- 90 (Z= 40, A= 90), MT=103 (n,p)
Zr- 91 (Z= 40, A= 91), MT= 28 (n,np)
Zr- 91 (Z= 40, A= 91), MT=104 (n,d)
Zr- 92 (Z= 40, A= 92), MT= 32 (n,nd)
Zr- 92 (Z= 40, A= 92), MT=105 (n,t)
Nb- 93 (Z= 41, A= 93), MT=107 (n,α)
Nb- 94 (Z= 41, A= 94), 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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Y- 90 U-235 Thermal 3.698720e-08 2.367180e-08
Y- 90 U-235 Fast 1.713120e-08 1.096400e-08
Y- 90 U-235 High 2.629870e-06 1.683110e-06
Y- 90 U-238 Fast 9.091610e-10 5.818620e-10
Y- 90 U-238 High 3.889230e-08 2.489110e-08
Y- 90 Pu-239 Thermal 7.969640e-07 5.100570e-07
Y- 90 Pu-239 Fast 3.642170e-07 2.330990e-07
Y- 90 Pu-239 High 5.344050e-06 3.420190e-06
Y- 90 Pu-241 Thermal 2.879080e-08 1.842610e-08
Y- 90 Pu-241 Fast 1.083790e-08 6.936220e-09
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Y- 90m U-235 Thermal 5.257020e-08 3.364500e-08
Y- 90m U-235 Fast 2.867420e-08 1.835150e-08
Y- 90m U-235 High 7.524060e-06 4.815390e-06
Y- 90m U-238 Fast 1.521750e-09 9.739180e-10
Y- 90m U-238 High 1.112710e-07 7.121350e-08
Y- 90m Pu-239 Thermal 1.132730e-06 7.249480e-07
Y- 90m Pu-239 Fast 6.096250e-07 3.901610e-07
Y- 90m Pu-239 High 1.528930e-05 9.785170e-06
Y- 90m Pu-241 Thermal 4.092050e-08 2.618910e-08
Y- 90m Pu-241 Fast 1.814040e-08 1.160980e-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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Y- 90 U-235 Thermal 5.772090e-02 5.865150e-04
Y- 90 U-235 Fast 5.452160e-02 4.035280e-04
Y- 90 U-235 High 4.599230e-02 1.838290e-03
Y- 90 U-238 Fast 3.246620e-02 4.545850e-04
Y- 90 U-238 High 3.191430e-02 1.275970e-03
Y- 90 Pu-239 Thermal 2.103390e-02 4.209390e-04
Y- 90 Pu-239 Fast 2.047910e-02 1.434940e-04
Y- 90 Pu-239 High 2.103750e-02 3.363640e-03
Y- 90 Pu-241 Thermal 1.535540e-02 2.150330e-04
Y- 90 Pu-241 Fast 1.549330e-02 6.205710e-04
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Y- 90m U-235 Thermal 5.257020e-08 3.364500e-08
Y- 90m U-235 Fast 2.867420e-08 1.835150e-08
Y- 90m U-235 High 7.524060e-06 4.808260e-06
Y- 90m U-238 Fast 1.521750e-09 9.735620e-10
Y- 90m U-238 High 1.112710e-07 7.113640e-08
Y- 90m Pu-239 Thermal 1.132730e-06 7.249480e-07
Y- 90m Pu-239 Fast 6.096250e-07 3.901610e-07
Y- 90m Pu-239 High 1.528930e-05 9.778830e-06
Y- 90m Pu-241 Thermal 4.092050e-08 2.618490e-08
Y- 90m Pu-241 Fast 1.814040e-08 1.160980e-08
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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