39-Y-93
Spin
Level energy(keV) Spin & Parity
----------------------------------------
ground state 1/2-
7.58721E+02 7/2+
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)
92.909577886 ± 0.000011351 (amu) [mass excess = -84227.656 ± 10.574 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
2895.027 ± 10.491 (keV)
Strong Gamma-rays from Decay of Y- 93 (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
----------------------------------------------------------
266.9 7.32 B-
947.1 2.09 B-
1917.8 1.54 B-
----------------------------------------------------------
168.50 51.28 IT
590.24 99.8 IT
----------------------------------------------------------
*: 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- 10.18 H 8
IT 0.82 S 4
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Zr- 93 (Z= 40, A= 93), MT=103 (n,p)
Zr- 94 (Z= 40, A= 94), MT= 28 (n,np)
Zr- 94 (Z= 40, A= 94), MT=104 (n,d)
Zr- 95 (Z= 40, A= 95), MT= 32 (n,nd)
Zr- 95 (Z= 40, A= 95), MT=105 (n,t)
Nb- 95 (Z= 41, A= 95), MT=106 (n,3He)
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)
-----------------------------------------------------------
Y- 93 U-235 Thermal 9.407240e-04 6.020630e-04
Y- 93 U-235 Fast 1.820250e-03 1.164960e-03
Y- 93 U-235 High 2.733290e-03 1.749310e-03
Y- 93 U-238 Fast 3.495780e-05 2.237310e-05
Y- 93 U-238 High 2.830790e-04 1.811700e-04
Y- 93 Pu-239 Thermal 1.508830e-03 9.656490e-04
Y- 93 Pu-239 Fast 1.328660e-03 8.503420e-04
Y- 93 Pu-239 High 3.139530e-03 2.009290e-03
Y- 93 Pu-241 Thermal 2.671310e-04 1.709640e-04
Y- 93 Pu-241 Fast 1.919460e-04 1.228460e-04
-----------------------------------------------------------
Y- 93m U-235 Thermal 1.443090e-04 9.235800e-05
Y- 93m U-235 Fast 2.435260e-04 1.558570e-04
Y- 93m U-235 High 2.280210e-04 1.459340e-04
Y- 93m U-238 Fast 4.676900e-06 2.993220e-06
Y- 93m U-238 High 2.361550e-05 1.511390e-05
Y- 93m Pu-239 Thermal 2.314580e-04 1.481330e-04
Y- 93m Pu-239 Fast 1.777570e-04 1.137650e-04
Y- 93m Pu-239 High 2.619110e-04 1.676220e-04
Y- 93m Pu-241 Thermal 4.097860e-05 2.622630e-05
Y- 93m Pu-241 Fast 2.567990e-05 1.643510e-05
-----------------------------------------------------------
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)
-----------------------------------------------------------
Y- 93 U-235 Thermal 6.339590e-02 6.446890e-04
Y- 93 U-235 Fast 6.239450e-02 1.034810e-03
Y- 93 U-235 High 5.199660e-02 3.388820e-03
Y- 93 U-238 Fast 4.918390e-02 9.836150e-04
Y- 93 U-238 High 4.538820e-02 1.272160e-03
Y- 93 Pu-239 Thermal 3.796100e-02 6.912050e-04
Y- 93 Pu-239 Fast 3.825210e-02 6.301340e-04
Y- 93 Pu-239 High 3.221800e-02 3.956670e-03
Y- 93 Pu-241 Thermal 2.980390e-02 4.278420e-04
Y- 93 Pu-241 Fast 2.981020e-02 6.875840e-03
-----------------------------------------------------------
Y- 93m U-235 Thermal 2.164160e-02 1.385050e-02
Y- 93m U-235 Fast 2.105760e-02 1.347690e-02
Y- 93m U-235 High 1.714520e-02 1.097300e-02
Y- 93m U-238 Fast 1.695950e-02 1.085400e-02
Y- 93m U-238 High 1.557670e-02 9.969090e-03
Y- 93m Pu-239 Thermal 1.272760e-02 8.145630e-03
Y- 93m Pu-239 Fast 1.285500e-02 8.227230e-03
Y- 93m Pu-239 High 1.020360e-02 6.530330e-03
Y- 93m Pu-241 Thermal 1.021700e-02 6.538880e-03
Y- 93m Pu-241 Fast 1.023510e-02 6.550450e-03
-----------------------------------------------------------
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