41-Nb-97
Spin
Level energy(keV) Spin & Parity
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ground state 9/2+
7.43400E+02 1/2-
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)
96.908095932 ± 0.000001892 (amu) [mass excess = -85608.088 ± 1.762 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
1935.471 ± 1.721 (keV)
Strong Gamma-rays from Decay of Nb- 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
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657.94 98.23 B-
1024.4 1.09 B-
1268.62 0.15 B-
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743.36 97.9 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- 72.1 M 7
IT 58.7 S 18
Evaluated Data Libraries
Links to the libraries.
Parent Nuclides by Reactions in JENDL-4.0
Mo- 97 (Z= 42, A= 97), MT=103 (n,p)
Mo- 98 (Z= 42, A= 98), MT= 28 (n,np)
Mo- 98 (Z= 42, A= 98), MT=104 (n,d)
Mo- 99 (Z= 42, A= 99), MT= 32 (n,nd)
Mo- 99 (Z= 42, A= 99), MT=105 (n,t)
Tc- 99 (Z= 43, A= 99), 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)
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Nb- 97 U-235 Thermal 1.070380e-04 1.712610e-05
Nb- 97 U-235 Fast 2.169540e-05 1.388510e-05
Nb- 97 U-235 High 3.359880e-03 2.150320e-03
Nb- 97 U-238 Fast 1.945940e-06 1.245410e-06
Nb- 97 U-238 High 3.508750e-05 2.245610e-05
Nb- 97 Pu-239 Thermal 6.521520e-04 2.086880e-04
Nb- 97 Pu-239 Fast 2.599660e-04 1.663780e-04
Nb- 97 Pu-239 High 1.425440e-03 9.122790e-04
Nb- 97 Pu-241 Thermal 3.535210e-05 2.262530e-05
Nb- 97 Pu-241 Fast 2.446740e-05 1.565910e-05
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Nb- 97m U-235 Thermal 2.478210e-05 5.699880e-06
Nb- 97m U-235 Fast 4.380790e-06 2.803710e-06
Nb- 97m U-235 High 4.237690e-04 2.712120e-04
Nb- 97m U-238 Fast 3.929300e-07 2.514750e-07
Nb- 97m U-238 High 4.425450e-06 2.832290e-06
Nb- 97m Pu-239 Thermal 1.509910e-04 4.831710e-05
Nb- 97m Pu-239 Fast 5.249310e-05 3.359560e-05
Nb- 97m Pu-239 High 1.797850e-04 1.150620e-04
Nb- 97m Pu-241 Thermal 8.184960e-06 5.238380e-06
Nb- 97m Pu-241 Fast 4.940520e-06 3.161940e-06
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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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Nb- 97 U-235 Thermal 6.044670e-02 7.675570e-04
Nb- 97 U-235 Fast 6.063670e-02 7.391190e-04
Nb- 97 U-235 High 5.592790e-02 4.476920e-03
Nb- 97 U-238 Fast 5.648640e-02 1.025360e-03
Nb- 97 U-238 High 5.374520e-02 1.199690e-03
Nb- 97 Pu-239 Thermal 5.473140e-02 9.607540e-04
Nb- 97 Pu-239 Fast 5.349910e-02 7.473870e-04
Nb- 97 Pu-239 High 4.610120e-02 1.887450e-03
Nb- 97 Pu-241 Thermal 4.874670e-02 1.205560e-03
Nb- 97 Pu-241 Fast 4.521480e-02 1.397540e-03
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Nb- 97m U-235 Thermal 5.732400e-02 1.541430e-03
Nb- 97m U-235 Fast 5.758450e-02 1.305840e-03
Nb- 97m U-235 High 4.996080e-02 1.823180e-03
Nb- 97m U-238 Fast 5.366020e-02 1.470610e-03
Nb- 97m U-238 High 5.102480e-02 1.585330e-03
Nb- 97m Pu-239 Thermal 5.138280e-02 1.487380e-03
Nb- 97m Pu-239 Fast 5.057980e-02 1.240260e-03
Nb- 97m Pu-239 High 4.245100e-02 1.467710e-03
Nb- 97m Pu-241 Thermal 4.627620e-02 1.723030e-03
Nb- 97m Pu-241 Fast 4.293110e-02 1.973290e-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