39-Y-91
Spin
Level energy(keV) Spin & Parity
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ground state 1/2-
5.55570E+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)
90.907297442 ± 0.000002761 (amu) [mass excess = -86351.877 ± 2.572 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
1544.281 ± 1.841 (keV)
Strong Gamma-rays from Decay of Y- 91 (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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1204.77 0.26 B-
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555.57 95. 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
B- 58.51 D 6
IT 49.71 M 4
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Y-91.
Figures of cross sections, Y-91: 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 - 90 (Z= 39, A= 90), MT=102 (n,γ)
Y - 91 (Z= 39, A= 91), MT= 2 (Elastic scattering)
Y - 91 (Z= 39, A= 91), MT= 4 (Inelastic scattering)
Zr- 91 (Z= 40, A= 91), MT=103 (n,p)
Zr- 92 (Z= 40, A= 92), MT= 28 (n,np)
Zr- 92 (Z= 40, A= 92), MT=104 (n,d)
Zr- 93 (Z= 40, A= 93), MT= 32 (n,nd)
Zr- 93 (Z= 40, A= 93), MT=105 (n,t)
Nb- 94 (Z= 41, A= 94), MT=107 (n,α)
Nb- 95 (Z= 41, A= 95), 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- 91 U-235 Thermal 6.194120e-07 3.964260e-07
Y- 91 U-235 Fast 2.883650e-07 1.845530e-07
Y- 91 U-235 High 1.017460e-05 6.511730e-06
Y- 91 U-238 Fast 1.492400e-08 9.551340e-09
Y- 91 U-238 High 3.475790e-07 2.224500e-07
Y- 91 Pu-239 Thermal 4.661650e-06 2.983470e-06
Y- 91 Pu-239 Fast 3.307390e-06 2.116730e-06
Y- 91 Pu-239 High 1.686920e-05 1.079630e-05
Y- 91 Pu-241 Thermal 3.422150e-07 2.190180e-07
Y- 91 Pu-241 Fast 1.695520e-07 1.085140e-07
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Y- 91m U-235 Thermal 2.675330e-06 1.712230e-06
Y- 91m U-235 Fast 1.428090e-06 9.139780e-07
Y- 91m U-235 High 8.067000e-05 5.162870e-05
Y- 91m U-238 Fast 7.390920e-08 4.730190e-08
Y- 91m U-238 High 2.755810e-06 1.763710e-06
Y- 91m Pu-239 Thermal 2.013440e-05 1.288600e-05
Y- 91m Pu-239 Fast 1.637940e-05 1.048280e-05
Y- 91m Pu-239 High 1.337490e-04 8.559900e-05
Y- 91m Pu-241 Thermal 1.478080e-06 9.459710e-07
Y- 91m Pu-241 Fast 8.396890e-07 5.374010e-07
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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- 91 U-235 Thermal 5.815650e-02 4.254350e-04
Y- 91 U-235 Fast 5.719140e-02 8.151830e-04
Y- 91 U-235 High 4.826340e-02 1.929000e-03
Y- 91 U-238 Fast 4.014450e-02 8.458160e-04
Y- 91 U-238 High 3.856620e-02 7.810950e-04
Y- 91 Pu-239 Thermal 2.485830e-02 3.480000e-04
Y- 91 Pu-239 Fast 2.515540e-02 5.031760e-04
Y- 91 Pu-239 High 2.237470e-02 2.455280e-03
Y- 91 Pu-241 Thermal 1.862980e-02 3.729750e-04
Y- 91 Pu-241 Fast 1.925050e-02 7.724260e-04
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Y- 91m U-235 Thermal 5.175910e-02 2.811490e-02
Y- 91m U-235 Fast 5.090020e-02 2.764660e-02
Y- 91m U-235 High 4.295430e-02 2.334010e-02
Y- 91m U-238 Fast 3.572860e-02 1.939370e-02
Y- 91m U-238 High 3.432390e-02 1.864190e-02
Y- 91m Pu-239 Thermal 2.212200e-02 1.201940e-02
Y- 91m Pu-239 Fast 2.238720e-02 1.216340e-02
Y- 91m Pu-239 High 1.991310e-02 1.081410e-02
Y- 91m Pu-241 Thermal 1.658040e-02 9.008630e-03
Y- 91m Pu-241 Fast 1.713290e-02 9.306660e-03
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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