last modified: 28-JAN-2010 | catalog | categories | new | search |

NEA-1854 ZZ-SERPENT117-ACELIB

ZZ SERPENT117-ACELIB, Continuous-energy X-sec lib., radioactive decay, fission yield data for SERPENT in ACE

top ]
1. NAME OR DESIGNATION

ZZ-SERPENT117-ACELIB

top ]
2. COMPUTERS
To submit a request, click below on the link of the version you wish to order. Only liaison officers are authorised to submit online requests. Rules for requesters are available here.
Program name Package id Status Status date
ZZ-SERPENT117-ACELIB NEA-1854/01 Arrived 28-JAN-2010

Machines used:

Package ID Orig. computer Test computer
NEA-1854/01 Many Computers
top ]
3. DESCRIPTION OF PROGRAM OR FUNCTION

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:

top ]
4. METHODS

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

top ]
8. RELATED OR AUXILIARY PROGRAMS

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

top ]
9. STATUS
Package ID Status date Status
NEA-1854/01 28-JAN-2010 Masterfiled Arrived
top ]
10. REFERENCES
  • 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

NEA-1854/01, included references:
Documentation included in the distribution package:

- Serpent 1.1.7 cross section library based on ENDF/B-VI.8
- Serpent 1.1.7 cross section library based on ENDF/B-VII
- Serpent 1.1.7 cross section library based on JEF-2.2
- Serpent 1.1.7 cross section library based on JEFF-3.1
- Serpent 1.1.7 cross section library based on JEFF-3.1.1
- Cross section libraries for Serpent 1.1.7, Documentation (October 27, 2009)
- Serpent 1.1.0 thermal scattering libraries based on JEF-2.2, JEFF3.1,
ENDF/B-VI.8 and ENDF/B-VII
top ]
12. PROGRAMMING LANGUAGE(S) USED
No specified programming language
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS

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

top ]
16. MATERIAL AVAILABLE
NEA-1854/01
xsdirconvert.pl utility script
Cross section, decay and fission yield libraries based on the JEF-2.2,
JEFF-3.1,JEFF-3.1.1, ENDF/B-VI.8 and ENDF/B-VII evaluated nuclear data files
Electronic documentation
top ]
17. CATEGORIES
  • Z. Data.

Keywords: Monte Carlo method, continuous energy, cross-sections, decay, fission yields.