39-Y-97
Spin
Level energy(keV) Spin & Parity
----------------------------------------
ground state (1/2-)
6.67500E+02 (9/2)+
3.52330E+03 (27/2-)
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)
96.918274106 ± 0.000007507 (amu) [mass excess = -76127.179 ± 6.993 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
6821.237 ± 6.707 (keV)
Strong Gamma-rays from Decay of Y- 97 (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
----------------------------------------------------------
161.2 72.49 B-
970.0 38.73 B-
1103.0 92.35 B-
----------------------------------------------------------
698.2 5.2 B-
840.1 5.2 B-
1103.1 3.95 B-
791.7 69.37 IT
911.4 71.29 IT
989.9 55.88 IT
----------------------------------------------------------
667.5 -- IT
----------------------------------------------------------
1996.6 7.42 B-
3287.6 18.1 B-
3401.3 14.12 B-
----------------------------------------------------------
*: 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- 1.17 S 3
B- 142 MS 8
B- 3.75 S 3
IT 1.17 S 3
IT 142 MS 8
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
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- 97 U-235 Thermal 5.895170e-03 3.772910e-03
Y- 97 U-235 Fast 5.075330e-03 3.248220e-03
Y- 97 U-235 High 3.302360e-03 2.113510e-03
Y- 97 U-238 Fast 4.232870e-03 2.709040e-03
Y- 97 U-238 High 2.927520e-03 1.873620e-03
Y- 97 Pu-239 Thermal 5.556510e-03 3.556170e-03
Y- 97 Pu-239 Fast 4.974170e-03 3.183460e-03
Y- 97 Pu-239 High 2.579290e-03 1.650750e-03
Y- 97 Pu-241 Thermal 5.133460e-03 3.285400e-03
Y- 97 Pu-241 Fast 4.023130e-03 2.574810e-03
-----------------------------------------------------------
Y- 97m U-235 Thermal 2.546210e-02 1.629580e-02
Y- 97m U-235 Fast 2.513500e-02 1.608640e-02
Y- 97m U-235 High 2.618300e-02 1.675710e-02
Y- 97m U-238 Fast 2.096280e-02 1.341620e-02
Y- 97m U-238 High 2.321100e-02 1.485510e-02
Y- 97m Pu-239 Thermal 2.399940e-02 1.535960e-02
Y- 97m Pu-239 Fast 2.463400e-02 1.576570e-02
Y- 97m Pu-239 High 2.045010e-02 1.308810e-02
Y- 97m Pu-241 Thermal 2.217220e-02 1.419010e-02
Y- 97m Pu-241 Fast 1.992410e-02 1.275140e-02
-----------------------------------------------------------
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- 97 U-235 Thermal 2.353570e-02 5.413200e-03
Y- 97 U-235 Fast 2.929760e-02 1.661140e-02
Y- 97 U-235 High 1.239010e-02 2.849730e-03
Y- 97 U-238 Fast 3.374980e-02 1.257230e-02
Y- 97 U-238 High 2.626770e-02 1.357070e-02
Y- 97 Pu-239 Thermal 1.364180e-02 2.182690e-03
Y- 97 Pu-239 Fast 1.377930e-02 3.169240e-03
Y- 97 Pu-239 High 7.874130e-03 1.811050e-03
Y- 97 Pu-241 Thermal 2.033100e-02 3.252960e-03
Y- 97 Pu-241 Fast 2.070850e-02 1.295430e-02
-----------------------------------------------------------
Y- 97m U-235 Thermal 2.548800e-02 1.631230e-02
Y- 97m U-235 Fast 2.516840e-02 1.610790e-02
Y- 97m U-235 High 2.619320e-02 1.673230e-02
Y- 97m U-238 Fast 2.103780e-02 1.341150e-02
Y- 97m U-238 High 2.324910e-02 1.483910e-02
Y- 97m Pu-239 Thermal 2.400990e-02 1.536190e-02
Y- 97m Pu-239 Fast 2.464240e-02 1.576800e-02
Y- 97m Pu-239 High 2.045550e-02 1.307960e-02
Y- 97m Pu-241 Thermal 2.219020e-02 1.418790e-02
Y- 97m Pu-241 Fast 1.994900e-02 1.276100e-02
-----------------------------------------------------------
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