3-Li-7
Spin
Level energy(keV) Spin & Parity
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ground state 3/2-
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)
7.01600343659 ± 0.00000000454 (amu) [mass excess = 14907.10520 ± 0.00423 (keV) ]
Beta-decay energy (calculated as M(A,Z)-M(A,Z+1), taken from Ame2012)
-861.893 ± 0.071 (keV)
Cross Sections (taken from JENDL-4.0)
Table of cross sections, Li-7.
Figures of cross sections, Li-7: 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
Li- 6 (Z= 3, A= 6), MT=102 (n,γ)
Li- 7 (Z= 3, A= 7), MT= 2 (Elastic scattering)
Li- 7 (Z= 3, A= 7), MT= 4 (Inelastic scattering)
Be- 9 (Z= 4, A= 9), MT=105 (n,t)
B - 10 (Z= 5, A= 10), MT=107 (n,α)
B - 11 (Z= 5, A= 11), MT= 22 (n,nα)
N - 14 (Z= 7, A= 14), MT=108 (n,2α)
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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Li- 7 U-235 Thermal 7.010570e-07 1.325000e-07
Li- 7 U-235 Fast 1.051590e-06 1.987500e-07
Li- 7 U-235 High 8.179000e-07 1.545830e-07
Li- 7 U-238 Fast 9.347430e-07 1.766660e-07
Li- 7 U-238 High 7.010570e-07 1.325000e-07
Li- 7 Pu-239 Thermal 1.285270e-06 2.429160e-07
Li- 7 Pu-239 Fast 1.168430e-06 2.208330e-07
Li- 7 Pu-239 High 1.460540e-06 2.760410e-07
Li- 7 Pu-241 Thermal 1.285270e-06 2.429160e-07
Li- 7 Pu-241 Fast 1.226850e-06 2.318750e-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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Li- 7 U-235 Thermal 7.824150e-07 1.340270e-07
Li- 7 U-235 Fast 1.123220e-06 1.995420e-07
Li- 7 U-235 High 8.735880e-07 1.551990e-07
Li- 7 U-238 Fast 9.984990e-07 1.773730e-07
Li- 7 U-238 High 7.491720e-07 1.330360e-07
Li- 7 Pu-239 Thermal 1.374240e-06 2.439160e-07
Li- 7 Pu-239 Fast 1.248440e-06 2.217230e-07
Li- 7 Pu-239 High 1.558450e-06 2.771070e-07
Li- 7 Pu-241 Thermal 1.372210e-06 2.438710e-07
Li- 7 Pu-241 Fast 1.310990e-06 2.328120e-07
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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