Japan Charged-Particle Nuclear Reaction Data Group (JCPRG)
PENDL : Plotter for Evaluated Nuclear Data Libraries
PENDL is a data plotter for evaluated nuclear data libraries compiled in ENDF (Evaluated Nuclear Data File) format.
Tabulated data is generated by the ENDF-B Pre-processing codes, PREPRO, written by Dermott E. Cullen (LLNL).
Target
Mass Element Isomer Temp. K
Quantity (MF)
1. NU 2+3. SIG 4. DA
Reaction (MT)
1.(n,tot) 2.(n,el) 4.(n,inl) 16.(n,2n) 17.(n,3n) 18.(n,f)
51.(n,n1) 52.(n,n2) 53.(n,n3) 54.(n,n4) 55.(n,n5) 91.(n,nc)
102.(n,γ) 103.(n,p) 104.(n,d) 105.(n,t) 106.(n,3He) 107.(n,α)
202.(n,γ+X) 203.(n,p+X) 204.(n,d+X) 205.(n,t+X) 206.(n,3He+X) 207.(n,α+X)
452.total fission (ν-bar) 455.delayed fission (ν-bar) 456.prompt fission (ν-bar)
Library
JENDL-4.0 JENDL-3.3 JENDL-3.2 ENDF/B-VII.1 ENDF/B-VII.0 ENDF/B-VI.8
JEFF-3.2 JEFF-3.1 JEFF-3.0 CENDL-3.1 CENDL-2 BROND-2.2
IRDFF-1.05 IAEA Standard 06
Energy range
Emin Emax Unit (Einc)
Plot option
x-axis y-axis z-axis Unit (sigma)
Allowable error
Resonance % Non-resonance % Doppler broaden % Ang. dist. %
Cross section for 235U(n,tot), (n,el) Angular distribution for 56Fe(n,el) (3D)
Angular distribution for 56Fe(n,el) (2D)