NEA-1854 ZZ-SERPENT117-ACELIB

ZZ-SERPENT117-ACELIB

Continuous-energy cross section libraries and radioactive decay and fission yield data for the Serpent Monte Carlo reactor physics burnup calculation code. This data contains unresolved resonance probability tables (when available) and replaces the data libraries distributed with the Serpent 1.1.0 installation package (NEA-1840). The cross section libraries can also be used with MCNP.

FORMAT: ACE, ENDF

NUMBER OF GROUPS: Continuous-energy

NUCLIDES: H1, H2, H3, He-nat,He3, He4, Li6, Li7, Be7, Be9, B10, B11, C-nat, C12, N14, N15, O16, O17, F19, Na22, Na23, Mg-nat, Mg24, Mg25, Mg26, Al27, Si-nat, Si28, Si29, Si30, P31, S-nat, S32, S33, S34, S36, Cl-nat, Cl35, Cl37, Ar36, Ar38, Ar40, K-nat, K39, K40, K41, Ca-nat, Ca40, Ca42, Ca43, Ca44, Ca46, Ca48, Sc45, Ti-nat, Ti46, Ti47, Ti48, Ti49, Ti50, V-nat, V51, Cr-nat, Cr50, Cr52, Cr53, Cr54, Mn55, Fe-nat, Fe54, Fe56, Fe57, Fe58, Co58, Co59, Co158m, Ni-nat, Ni58, Ni59, Ni60, Ni61, Ni62, Ni64, Cu-nat, Cu63, Cu65, Zn-nat, Zn64, Ga-nat, Ga69, Ga71, Ge-nat, Ge70, Ge72, Ge73, Ge74, Ge76, As74, As75, Se74, Se76, Se77, Se78, Se79, Se80, Se82, Br79, Br81, Kr78, Kr80, Kr82, Kr83, Kr84, Kr85, Kr86, Rb85, Rb86, Rb87, Sr84, Sr86, Sr87, Sr88, Sr89, Sr90, Y89, Y90, Y91, Zr-nat, Zr90, Zr91, Zr92, Zr93, Zr94, Zr95, Zr96, Nb93, Nb94, Nb95, Mo-nat, Mo92, Mo94, Mo95, Mo96, Mo97, Mo98, Mo99, Mo100, Tc99, Ru96, Ru98, Ru99, Ru100, Ru101, Ru102, Ru103, Ru104, Ru105, Ru106, Rh103, Rh105, Pd102, Pd104, Pd105, Pd106, Pd107, Pd108, Pd110, Ag-nat, Ag107, Ag109, Ag111, Ag110m, Cd-nat, Cd106, Cd108, Cd110, Cd111, Cd112, Cd113, Cd114, Cd116, Cd115m, In-nat, In113, In115, Sn-nat, Sn112, Sn113, Sn114, Sn115, Sn116, Sn117, Sn118, Sn119, Sn120, Sn122, Sn123, Sn124, Sn125, Sn126, Sb-nat, Sb121, Sb123, Sb124, Sb125, Sb126, Te120, Te122, Te123, Te124, Te125, Te126, Te128, Te130, Te132, Te127m, Te129m, I127, I129, I130, I131, I135, Xe123, Xe124, Xe126, Xe128, Xe129, Xe130, Xe131, Xe132, Xe133, Xe134, Xe135, Xe136, Cs133, Cs134, Cs135, Cs136, Cs137, Ba130, Ba132, Ba133, Ba134, Ba135, Ba136, Ba137, Ba138, Ba140, La138, La139, La140, Ce136, Ce138, Ce139, Ce140, Ce141, Ce142, Ce143, Ce144, Pr141, Pr142, Pr143, Nd142, Nd143, Nd144, Nd145, Nd146, Nd147, Nd148, Nd150, Pm147, Pm148, Pm149, Pm151, Pm148m, Sm-nat, Sm144, Sm147, Sm148, Sm149, Sm150, Sm151, Sm152, Sm153, Sm154, Eu-nat, Eu151, Eu152, Eu153, Eu154, Eu155, Eu156, Eu157, Gd-nat, Gd152, Gd153, Gd154, Gd155, Gd156, Gd157, Gd158, Gd160, Tb159, Tb160, Dy156, Dy158, Dy160, Dy161, Dy162, Dy163, Dy164, Ho165, Ho166m, Er162, Er164, Er166, Er167, Er168, Er170, Lu-nat, Lu175, Lu176, Hf-nat, Hf174, Hf176, Hf177, Hf178, Hf179, Hf180, Ta181, Ta182, W-nat, W182, W183, W184, W186, Re-nat, Re185, Re187, Os-nat, Ir-nat, Ir191, Ir193, Pt-nat, Au197, Hg-nat, Hg196, Hg198, Hg199, Hg200, Hg201, Hg202, Hg204, Tl-nat, Pb-nat, Pb204, Pb206, Pb207, Pb208, Bi209, Ra223, Ra224, Ra225, Ra226, Ac225, Ac226, Ac227, Th227, Th228, Th229, Th230, Th232, Th233, Th234, Pa231, Pa232, Pa233, U232, U233, U234, U235, U236, U237, U238, U239, U240, U241, Np235, Np236, Np237, Np238, Np239, Pu236, Pu237, Pu238, Pu239, Pu240, Pu241, Pu242, Pu243, Pu244, Pu246, Am241, Am242, Am243, Am244, Am242m, Am244m, Cm240, Cm241, Cm242, Cm243, Cm244, Cm245, Cm246, Cm247, Cm248, Cm249, Cm250, Bk247, Bk249, Bk250, Cf249, Cf250, Cf251, Cf252, Cf253, Cf254, Es253, Es254, Es255, Fm255, thermal scattering data for light water, heavy water and graphite

TEMPERATURES: 300K, 600K, 900K, 1200K, 1500K and 1800K

ORIGIN: Separate libraries for JEF-2.2, JEFF-3.1, JEFF-3.1.1, ENDF/B-VI.8 and ENDF/B-VII. Each library contains ACE format cross section data for 432 nuclides with missing data complemented from other evaluations. Radioactive decay and fission yield data is in standard ENDF format.

WEIGHTING SPECTRUM:

The library was generated using the NJOY processing code. Documentation is included.

xsdirconvert.pl, a utility script for converting MCNP xsdir files to Serpent directory file format.

• T. Viitanen and J. Leppanen: "Cross Section Libraries for Serpent 1.1.7"

• Complete and up-to-date description of the Serpent project can be found at website: http://montecarlo.vtt.fi

Helsinki university of Technology
Department of Applied Physics
P.O. Box 4100
FI-02015 TKK, Espoo
Finland

VTT Technical Research Centre of Finland
Nuclear Energy
P.O. Box 1000
FI-02044 VTT, Espoo
Finland