41-Nb-93
Spin
Level energy(keV) Spin & Parity
----------------------------------------
ground state 9/2+
3.07700E+01 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)
92.906373004 ± 0.000001958 (amu) [mass excess = -87212.984 ± 1.824 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-406.665 ± 1.934 (keV)
Strong Gamma-rays from Decay of Nb- 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
----------------------------------------------------------
30.77 6.E-04 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
IT 16.13 Y 14
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Nb-93.
Figures of cross sections, Nb-93: 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
Nb- 93 (Z= 41, A= 93), MT= 2 (Elastic scattering)
Nb- 93 (Z= 41, A= 93), MT= 4 (Inelastic scattering)
Nb- 94 (Z= 41, A= 94), MT= 16 (n,2n)
Nb- 95 (Z= 41, A= 95), MT= 17 (n,3n)
Mo- 94 (Z= 42, A= 94), MT= 28 (n,np)
Mo- 94 (Z= 42, A= 94), MT=104 (n,d)
Mo- 95 (Z= 42, A= 95), MT= 32 (n,nd)
Mo- 95 (Z= 42, A= 95), MT=105 (n,t)
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)
-----------------------------------------------------------
Nb- 93 U-235 Thermal 3.623050e-11 2.318760e-11
Nb- 93 U-235 Fast 1.031210e-11 6.599770e-12
Nb- 93 U-235 High 4.505670e-08 2.883630e-08
Nb- 93 U-238 Fast 3.399990e-13 2.175990e-13
Nb- 93 U-238 High 1.597480e-10 1.022380e-10
Nb- 93 Pu-239 Thermal 4.229040e-09 2.706590e-09
Nb- 93 Pu-239 Fast 2.345030e-09 1.500810e-09
Nb- 93 Pu-239 High 3.324160e-07 2.127460e-07
Nb- 93 Pu-241 Thermal 3.178680e-11 2.034360e-11
Nb- 93 Pu-241 Fast 1.763350e-11 1.128540e-11
-----------------------------------------------------------
Nb- 93m U-235 Thermal 8.388360e-12 5.368550e-12
Nb- 93m U-235 Fast 2.082260e-12 1.332650e-12
Nb- 93m U-235 High 5.682830e-09 3.637010e-09
Nb- 93m U-238 Fast 6.865350e-14 4.393830e-14
Nb- 93m U-238 High 2.014840e-11 1.289500e-11
Nb- 93m Pu-239 Thermal 9.791380e-10 6.266480e-10
Nb- 93m Pu-239 Fast 4.735160e-10 3.030500e-10
Nb- 93m Pu-239 High 4.192640e-08 2.683290e-08
Nb- 93m Pu-241 Thermal 7.359510e-12 4.710090e-12
Nb- 93m Pu-241 Fast 3.560600e-12 2.278790e-12
-----------------------------------------------------------
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)
-----------------------------------------------------------
Nb- 93 U-235 Thermal 6.339730e-02 4.490650e-04
Nb- 93 U-235 Fast 6.239500e-02 4.611580e-04
Nb- 93 U-235 High 5.203520e-02 3.117620e-03
Nb- 93 U-238 Fast 4.918390e-02 9.839790e-04
Nb- 93 U-238 High 4.538910e-02 1.271920e-03
Nb- 93 Pu-239 Thermal 3.797780e-02 2.658390e-04
Nb- 93 Pu-239 Fast 3.826360e-02 2.678870e-04
Nb- 93 Pu-239 High 3.232140e-02 3.551940e-03
Nb- 93 Pu-241 Thermal 2.980460e-02 4.176260e-04
Nb- 93 Pu-241 Fast 2.981070e-02 5.962000e-04
-----------------------------------------------------------
Nb- 93m U-235 Thermal 6.022740e-02 4.266190e-04
Nb- 93m U-235 Fast 5.927530e-02 4.380990e-04
Nb- 93m U-235 High 4.943340e-02 2.961740e-03
Nb- 93m U-238 Fast 4.672470e-02 9.347820e-04
Nb- 93m U-238 High 4.311960e-02 1.208320e-03
Nb- 93m Pu-239 Thermal 3.607890e-02 2.525480e-04
Nb- 93m Pu-239 Fast 3.635040e-02 2.544940e-04
Nb- 93m Pu-239 High 3.070500e-02 3.374300e-03
Nb- 93m Pu-241 Thermal 2.831440e-02 3.967430e-04
Nb- 93m Pu-241 Fast 2.832010e-02 1.132780e-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