39-Y-89
Spin
Level energy(keV) Spin & Parity
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ground state 1/2-
9.08960E+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)
88.905840348 ± 0.000002397 (amu) [mass excess = -87709.151 ± 2.233 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-2832.760 ± 2.776 (keV)
Strong Gamma-rays from Decay of Y- 89 (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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908.96 99.16 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
IT 15.663 S 5
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Y-89.
Figures of cross sections, Y-89: 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= 2 (Elastic scattering)
Y - 89 (Z= 39, A= 89), MT= 4 (Inelastic scattering)
Y - 90 (Z= 39, A= 90), MT= 16 (n,2n)
Y - 91 (Z= 39, A= 91), MT= 17 (n,3n)
Zr- 90 (Z= 40, A= 90), MT= 28 (n,np)
Zr- 90 (Z= 40, A= 90), MT=104 (n,d)
Zr- 91 (Z= 40, A= 91), MT= 32 (n,nd)
Zr- 91 (Z= 40, A= 91), MT=105 (n,t)
Zr- 92 (Z= 40, A= 92), MT= 33 (n,nt)
Nb- 93 (Z= 41, A= 93), 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- 89 U-235 Thermal 4.354670e-10 2.786990e-10
Y- 89 U-235 Fast 1.361350e-10 8.712620e-11
Y- 89 U-235 High 5.834240e-08 3.733920e-08
Y- 89 U-238 Fast 5.426750e-12 3.473110e-12
Y- 89 U-238 High 6.110650e-10 3.910820e-10
Y- 89 Pu-239 Thermal 1.612790e-08 1.032190e-08
Y- 89 Pu-239 Fast 6.293950e-09 4.028130e-09
Y- 89 Pu-239 High 2.177570e-07 1.393650e-07
Y- 89 Pu-241 Thermal 3.087460e-10 1.975970e-10
Y- 89 Pu-241 Fast 1.116360e-10 7.144710e-11
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Y- 89m U-235 Thermal 1.880850e-09 1.203740e-09
Y- 89m U-235 Fast 6.741920e-10 4.314830e-10
Y- 89m U-235 High 4.625720e-07 2.960450e-07
Y- 89m U-238 Fast 2.687530e-11 1.720020e-11
Y- 89m U-238 High 4.844880e-09 3.100720e-09
Y- 89m Pu-239 Thermal 6.965860e-08 4.458160e-08
Y- 89m Pu-239 Fast 3.117000e-08 1.994870e-08
Y- 89m Pu-239 High 1.726500e-06 1.104960e-06
Y- 89m Pu-241 Thermal 1.333520e-09 8.534520e-10
Y- 89m Pu-241 Fast 5.528640e-10 3.538330e-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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Y- 89 U-235 Thermal 4.725010e-02 4.795440e-04
Y- 89 U-235 Fast 4.363980e-02 6.199340e-04
Y- 89 U-235 High 4.127890e-02 1.155530e-03
Y- 89 U-238 Fast 2.761730e-02 3.866050e-04
Y- 89 U-238 High 2.924200e-02 5.849970e-04
Y- 89 Pu-239 Thermal 1.722490e-02 3.445740e-04
Y- 89 Pu-239 Fast 1.724760e-02 3.451100e-04
Y- 89 Pu-239 High 2.069450e-02 8.274640e-04
Y- 89 Pu-241 Thermal 1.233130e-02 3.452600e-04
Y- 89 Pu-241 Fast 1.280870e-02 7.694140e-04
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Y- 89m U-235 Thermal 7.089400e-06 2.360200e-06
Y- 89m U-235 Fast 6.546640e-06 2.177540e-06
Y- 89m U-235 High 6.654440e-06 2.126780e-06
Y- 89m U-238 Fast 4.142620e-06 1.383140e-06
Y- 89m U-238 High 4.391140e-06 1.463440e-06
Y- 89m Pu-239 Thermal 2.653390e-06 8.698960e-07
Y- 89m Pu-239 Fast 2.618300e-06 8.596670e-07
Y- 89m Pu-239 High 4.831880e-06 1.997830e-06
Y- 89m Pu-241 Thermal 1.851030e-06 6.229700e-07
Y- 89m Pu-241 Fast 1.921850e-06 7.614080e-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