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| Program name | Package id | Status | Status date |
|---|---|---|---|
| ZZ-MCB-JENDL-3.2 | NEA-1670/04 | Tested | 20-DEC-2004 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1670/04 | Linux-based PC,UNIX W.S. | Linux-based PC |
MCB-JENDL-3.2 is a continuous-energy cross section libraries in ACE format suitable for the MCB-1C and MCNP codes. Libraries for various materials were generated at six different temperatures, and cover the energy range up to 20 MeV.
FORMAT: ACE
NUMBER OF GROUPS: Continuous energy
NUCLIDES: Library includes elements with the following atomic numbers:
Z= 1-9, 11-29, 31-65, 72-74, 82-83, 88-100 (i.e.: H, He, Li, Be, B, C, N, O, F, Na, Mg, Al, Si, P, S, Cl, Ar, K, Ca, Sc, Ti, V, Cr, Mn, Fe, Co, Ni, Cu, Ga, Ge, As, Se, Br, Kr, Rb, Sr, Y, Zr, Nb, Mo, Tc, Ru, Rh, Pd, Pd, Ag, Cd, In, Sn, Sb, Te, I, Xe, Cs, Ba, La, Ce, Pr, Nd, Pm, Sm, Eu, Gd, Tb, Hf, Ta, W, Pb, Bi, Ra, Ac, Th, Pa, U, Np, Pu, Am, Cm, Bk, Cf, Es, Fm).
TEMPERATURES: 300 K, 600 K, 900 K, 1200 K, 1500 K, and 1800 K.
ORIGIN: JENDL-3.2
WEIGHTING SPECTRUM:
J. Cetnar, W. Gudowski and J. Wallenius, "MONTE-CARLO CONTINUOUS ENERGY BURNUP (MCB1C) - THE CODE DESCRIPTION, METHODS AND BENCHMARKS" in preparation for NSE.
J. Cetnar, W. Gudowski and J. Wallenius, "MCB: A continuous energy Monte Carlo Burnup simulation code", In "Actinide and Fission Product Partitioning and Transmutation", EUR 18898 EN, OECD/NEA (1999) 523.
J. F. Briesmeister, Ed.
"MCNP - A General Monte Carlo N-Particle Transport Code, Version 4C," LA-13709-M (April 2000).
Keywords: Monte Carlo method, cross sections, data library, fission products, neutrons, reaction.
