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|Program name||Package id||Status||Status date|
|Package ID||Orig. computer||Test computer|
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.
|Package ID||Status date||Status|
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
Keywords: Monte Carlo method, continuous energy, cross-sections, decay, fission yields.