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IAEA1364 ZZ-FENDL-2.

ZZ FENDL-2, Evaluated Nuclear Data Library for Fusion Neutronics Applications

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1. NAME OR DESIGNATION:  ZZ-FENDL-2.
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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-FENDL-2.0 IAEA1364/02 Arrived 22-JAN-2002
ZZ-FENDL-2.1 IAEA1364/03 Arrived 18-MAR-2005

Machines used:

Package ID Orig. computer Test computer
IAEA1364/02 Many Computers
IAEA1364/03 Many Computers
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3. DESCRIPTION

FENDL: Fusion Evaluated Nuclear Data Library
MATERIALS/NUCLIDES: H-1, H-2, H-3, He-3, He-4, Li-6, Li-7, Be-9, B-10, B-11, C-12, N-14, N-15, O-16, F-19, Na-23, Mg-nat, Al-27, Si-28, Si-29, Si-30, P-31, S-nat, Cl-35, Cl-37, K-nat, Ca-nat, Ti-46, Ti-47, Ti-48, Ti-49, Ti-50, V-nat, Cr-50, Cr-52, Cr-53, Cr-54, Mn-55, Fe-54, Fe-56, Fe-57, Fe-58, Co-59, Ni-58, Ni-60, Ni-61, Ni-62, Ni-64, Cu-63, Cu-65, Ga-nat, Zr-nat, Nb-93, Mo-92, Mo-94, Mo-95, Mo-96, Mo-97, Mo-98, Mo-100, Sn-nat, Ta-181, W-182, W-183, W-184, W-186, Au-197, Pb-206, Pb-207, Pb-208, Bi-209
Photo-atomic data
IAEA1364/02
FENDL version 2.0 consists of the following sublibraries:

- ACTIVATION (FENDL/A-2.0)- neutron activation cross sections for 13006 reactions on 739 targets ranging from 1-H up to 248-Cm at incident energies up to 20 MeV. Pointwise and processed data in different formats are included. Plots are available!
  
- DECAY (FENDL/D-2.0) - decay properties (decay type, decay energy, and half life) for 1867 nuclides and isomers. FENDL/D-2.0 sublibrary is complementary to the activation sublibrary. Pointwise and processed data are included.
  
- DOSIMETRY (FENDL/DS-2.0) - neutron cross sections to be used for reactor neutron dosimetry by foil activation, radiation damage cross-sections, and benchmark neutron spectra. This sublibrary is identical to the International Reactor Dosimetry File (IRDF-90). Pointwise and processed data are included.
  
- FUSION (FENDL/C-2.0) - charged-particle cross sections for the following fusion reactions: 1-H-2(d,n)2-He-3, 1-H-2(d,p)1-H-3, 2-He-3(d,p)2-He-4, 1-H-3(t,2n)2-He-4, and 1-H-3(d,n)2-He-4. Pointwise and processed data are included.
  
- TRANSPORT - validated basic nuclear data (neutron-nucleus interaction including photon production, and photon-atom interaction cross sections) for 57 nuclides relevant for fusion. In addition to the pointwise data (FENDL/E-2.0), the sublibrary also contains processed data FENDL/MG-2.0 and FENDL/MC-2.0 to be used in the discrete-ordinates and Monte Carlo transport calculations respectively.
  
- BENCHMARKS - collection of benchmarks for FENDL-2.0 validation.

IAEA1364/03
FENDL-2.1 includes:
- FENDL/E-2.1: Contains selected evaluated nuclear data files in ENDF-6 format. Temperature: 300K.
- FENDL/MC-2.1: Contains pointwise continuous-energy cross section data in ACE format for MCNP calculations; also includes probability tables (PT) in the unresolved resonance range. Temperature: 300K.
- FENDL/MG-2.1: Contains multigroup cross section data in the 175n/42g Vitamin J energy structure for multigroup transport codes in two formats: MATXS format processed with MATXSR NJOY module and GENDF format processed with GROUPR and GAMINR NJOY modules. Temperature: 300K.
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4. METHODS
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM
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6. TYPICAL RUNNING TIME
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7. UNUSUAL FEATURES
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8. RELATED OR AUXILIARY PROGRAMS
IAEA1364/03
The existing FENDL/DS-2.0 sublibrary for dosimetry was not updated; the use of IRDF-2002 is recommended instead.
FENDL/A-2.0 sublibrary for activation and FENDL/D-2.0 decay data sublibrary were not updated - use of EAF-2003 (JEFF-3.0/A) is recommended.
No changes are recommended to the FENDL/C-2.0 charged-particle sublibrary.
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9. STATUS
Package ID Status date Status
IAEA1364/02 22-JAN-2002 Masterfiled Arrived
IAEA1364/03 18-MAR-2005 Masterfiled Arrived
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10. REFERENCES
IAEA1364/02, included references:
- A.B. Pashchenko, H. Wienke, J. Kopecky,J.-Ch. Sublet and R.A. Forrest:
FENDL/A-2.0 Neutron Activation Cross Section Data Library for Fusion
Applications, Released on March 14, 1997,(IAEA-NDS-173  Rev. 1, October 1998)
- A.B. Pashchenko and H. Wienke:
FENDL2/A-MCNP, FENDL2/A-VITJ_E and FENDL2/A-VITJ_FLAT
The processed FENDL-2 neutron activation cross-section data files,
summary documentation (IAEA-NDS-174 March 1997)
- A.B. Pashchenko and H. Wienke:
FENDL/E-2.0 Evaluated nuclear data library of neutron-nucleus interaction cross
sections and photon production cross sections and photon-atom interaction cross
sections for fusion applications
Released on May 15, 1998 (IAEA-NDS-175, Rev. 3, October 1998)
- H. Wienke and M. Herman:
FENDL/MG-2.0 and FENDL/MC-2.0 The processed cross-section libraries for neutron
photon transport calculations
Version 1, March 1997 (IAEA-NDS-176, Rev. 1, 98/10)
- A.B. Pashchenko and H. Wienke:
FENDL/C-2.0 Charged-Particle Reaction Data Library for Fusion Applications
Version 1 of March 1997, (IAEA-NDS-177 March 1997)
- A.B. Pashchenko, H. Wienke:
FENDL/D-2. Decay Data Library for Fusion Applications, Released on March 14,1997
(IAEA-NDS-178 Rev.0, March 1997)
- R. Forrest and A. Trkov:
Maintain FENDL Library for Fusion Applications
FENDL-2 Library for Fusion Applications - Status and Future Developments
Summary Report of an IAEA Consultant's Meeting, IAEA Vienna 10-12 November 2003
INDC(NDS)-451 (November 2003)
IAEA1364/03, included references:
- R. Forrest and A.Trkov:
'Maintain FENDL Library for Fusion Applications'
FENDL-2 Library for Fusion Applications - Status and Future Developments
Summary Report of an IAEA Consultants' Meeting, IAEA Vienna 10-12 November 2003
INDC(NDS)451 (November 2003)
- D. Lopez Aldama and A. Trkov:
FENDL-2.1 Update of an Evaluated Nuclear Data Library for Fusion Applications
INDC(NDS)-467 (December 2004)
- Robin Forrest and Alberto Mengoni:
IAEA Technical Meeting on Nuclear Data Library for Advanced Systems - Fusion
Devices, International Atomic Energy Agency Vienna, Austria 31 October - 2
November 2007 (INDC(NDS)-0525, April 2008)
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11. HARDWARE REQUIREMENTS
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12. PROGRAMMING LANGUAGE(S) USED

No item found

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13. SOFTWARE REQUIREMENTS
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS
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15. NAME AND ESTABLISHMENT OF AUTHORS

IAEA
Nuclear Data Section
Wagramer Strasse 5
P.O.Box 100
A-1400 Vienna
Austria
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16. MATERIAL AVAILABLE
IAEA1364/02
ACTIVATION  neutron activation cross sections
DECAY  decay properties
DOSIMETRY  N  X-sec to be used for reactor neutron dosimetry by foil activation
FUSION  charged-particle cross sections for several fusion reactions
TRANSPORT Validated basic nuclear data
BENCHMARKS Collection of benchmarks for FENDL-2.0 validation

IAEA1364/03
FENDL/E-2.1: selected evaluated nuclear data files in ENDF-6 format
FENDL/MC-2.1: pointwise continuous-energy cross section data in ACE format for
MCNP calculations
FENDL/MG-2.1: multigroup cross section data in the 175n/42g Vitamin J energy
structure for multigroup transport codes in MATXS and GENDF formats
SIGACE package for Doppler broadening of ACE-formatted file (for generating
ACE-formatted files at temperatures higher than 300K)
NJOY inputs to generate ACE, MATXS and GENDF files
NJOY-99.90 local updates
Auxiliary programs and WINDOWS batch files used to update and verify the
FENDL-2.1 transport sublibraries
INDC(NDS)-451 document
INDC(NDS)-467 document
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17. CATEGORIES
  • X. Magnetic Fusion Research
  • Z. Data.

Keywords: cross sections, evaluated data, fusion reactions, group constants.