NEA-1564 EASY-2010.
EASY-2010, European Neutron Activation System
NAME OR DESIGNATION OF PROGRAM, COMPUTER, DESCRIPTION OF PROGRAM OR FUNCTION, METHODS, STATUS, REFERENCES, REQUIREMENTS, LANGUAGE, OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS, NAME AND ESTABLISHMENT OF AUTHORS, MATERIAL, CATEGORIES
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| Program name | Package id | Status | Status date |
|---|---|---|---|
| EASY-2010 | NEA-1564/13 | Arrived | 16-DEC-2011 |
| EASY-2010 | NEA-1564/15 | Tested | 19-JUN-2012 |
Machines used:
| Package ID | Orig. computer | Test computer |
|---|---|---|
| NEA-1564/13 | Linux-based PC,UNIX W.S. | |
| NEA-1564/15 | PC Windows | PC Windows |
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3. DESCRIPTION OF PROGRAM OR FUNCTION
The EASY-2010 (European Activation System) consists of a wide range of codes, data and documentation all aimed at satisfying the objective of calculating the response of materials irradiated in a neutron flux. The main difference from the previous version is the upper energy limit, which has increased from 20 to 60 MeV. It is designed to investigate both fusion devices and accelerator based materials test facilities that will act as intense sources of high-energy neutrons causing significant activation of the surrounding materials. The very general nature of the calculational method and the data libraries means that it is applicable (with some reservations) to all situations (e.g. fission reactors or neutron sources) where materials are exposed to neutrons below 60 MeV.
EASY can be divided into two parts: data and code development tools and user tools and data. The former are required to develop the latter, but EASY users only need to be able to use the inventory code FISPACT and be aware of the contents of the EAF library (the data source). The complete EASY package contains the FISPACT-2007 inventory code, the EAF-2003, EAF-2005, EAF-2007 and EAF-2010 libraries, and the EASY User Interface for the Window version.
The activation package EASY-2010 is the result of significant development to extend the upper energy range from 20 to 60 MeV so that it is capable of being used for IFMIF calculations. The EAF-2010 library contains 66,256 reactions, almost five times more than in EAF-2003 (12,617).
Deuteron-induced and proton-induced cross section libraries are also included, and can be used with EASY to enable calculations of the activation due to deuterons and proton [2].
The EAF-2010/2007 data library covers:
- Cross section data for neutron-induced reactions
- Uncertainty data for neutron-induced reactions
- Decay data
- Fission yield data
- Biological hazard data
- Legal transport data
- Clearance data
- Charged particle ranges in materials
- Emitted particle spectral data (from neutron-induced reactions)
- Charged particle cross section data
- Gamma absorption data
The EAF-2010/2007 contains the following data libraries:
EAF_XS-2010 is the point-wise cross section library. Data on 66,256 cross sections on 816 targets are held in a modified ENDF/B format. The energy range 10e-5 eV - 60 MeV is covered. All nuclides with a half-life of greater than 0.5 day have cross section data, but in addition some short-lived nuclides are also treated as targets. The cross sections represent targets that are infinitely dilute, no self-shielding is included and the temperature for Doppler broadening is 294K. Reference 2 documents the EAF-2010 cross section library.
EAF_GXS-2010 is a set of multi-group libraries; the available group structures are: WIMS (69), GAM-II (100), XMAS (172), VITAMIN-J (175), VITAMIN-J+ (211), TRIPOLI (315) and TRIPOLI+ (351). Various choices of micro-flux weighting are available for particular applications..
EAF_UN-2010 contains uncertainty data for all cross sections. This library, in modified ENDF/B-6 format, contains error factor values (in 2 to 4 energy groups) for all reactions and is unique amongst activation libraries. This approach to uncertainties is less comprehensive than that found in general purpose evaluated files, but is of great value for fusion related inventory calculations.
EAF_DEC-2010 contains decay data information for 2233 nuclides, it is based primarily on the JEF-3.1.1 radioactive decay data library, with additional data from recent UK evaluations. It includes data on half-lives, decay modes and decay energies. Note that entries are included for all stable nuclides. Care has been taken to ensure that EAF_XS and EAF_DEC are compatible. This is especially important for the identification of isomeric states. All nuclides (including isomeric states) that can be formed from the various reactions in EAF_XS are included so long as their half-lives are greater than 1 second. Some nuclides with shorter half-lives are included where it is felt that they are of particular importance.
EAF_FIS-2007 is taken completely from the JEFF-3.1 fission yield library. It is a library of independent fission yields in ENDF/B-6 format. Only 19 of the 90 nuclides in EAF_XS which have fission cross-sections have any fission yield data in JEFF-3.1 at relevant energies. An inventory code using this data source will need a means of using a neighbouring fission yield for such nuclides.
EAF_HAZ-2007 is a library of values for each radionuclide describing the potential biological impact of that nuclide on human beings. The format is not ENDF/B-6, but is suitable for input by the FISPACT code. The values are Committed Effective Doses per unit uptake, which determine the dose received by a person over their lifetime (50 years) following the ingestion or inhalation of 1 Bq of activity of a particular radionuclide.
EAF_A2-2007 is a library of values relevant for the transport of radionuclides in shielded flasks. The format is not ENDF/B-6, but is suitable for input by the FISPACT code. Transport of radioactive material from place to place is governed by regulations set up by the IAEA. Using these values it is possible to work out how much of a particular mixture of radioactive materials can be packed into a type of container and safely transported. Data from this reference for the nuclides listed are transferred to EAF_A2, with the use of the default prescription given, for all radionuclides not explicitly listed.
EAF_CLEAR-2007 is a library of values relevant for the disposal of radioactive material. The format is not ENDF/B-6, but is suitable for input by the FISPACT code. This contains the clearance limit value for each radionuclide. This value can be used to decide if an amount of a radionuclide can be disposed of with no special precautions.
EAF_STOP-2007 contains new data compared to the previous versions. Due to the change of the upper energy limit from 20 to 60 MeV the data have been recalculated. It is required to enable the effect of sequential charged particle reactions (SCPR) to be investigated.. EAF_STOP contains the differential ranges for protons (p), deuterons (d), helions (h), tritons (t) and alpha particles in all the elements from H to U. The term differential range at a particular energy defines the distance travelled by the particle in the material in losing 1 MeV of energy. Data are given from 0 to 60 MeV.
EAF_SPEC-2007: EAF_XS contains the cross section data for (n,x) reactions, while EAF_SPEC describes the energy distribution of the charged particles emitted in these reactions. This is the second libraries required for SCPR. The data are calculated by a theoretical model code (TALYS) due to the lack of experimental data. Thirty-nine input neutron energies are used and the outgoing charged particles are in 1 MeV bins covering the energy range 0-60 MeV.
EAF_XN-2007 describes the cross sections of p, d, h, t and alpha particles on 775 targets. Ten reactions types are considered: (p,n), (d,n), (h,n), (t,n), (alpha,n), (p,2n), (d,2n), (h,2n), (t,2n) and (alpha,2n). This is the third of the libraries required for SCPR. The data are calculated by a theoretical model code (TALYS) due to the lack of experimental data. The data are given at 1 MeV intervals over the energy range 0-60 MeV.
EAF_ABS contains the photon mass energy attenuation coefficient for all the elements Z= 1 - 100 in increasing Z order. The attenuation coefficient and energy absorption coefficient for air are also listed. All data are stored in a 24 group energy structure.
The EASY-2010 (European Activation System) consists of a wide range of codes, data and documentation all aimed at satisfying the objective of calculating the response of materials irradiated in a neutron flux. The main difference from the previous version is the upper energy limit, which has increased from 20 to 60 MeV. It is designed to investigate both fusion devices and accelerator based materials test facilities that will act as intense sources of high-energy neutrons causing significant activation of the surrounding materials. The very general nature of the calculational method and the data libraries means that it is applicable (with some reservations) to all situations (e.g. fission reactors or neutron sources) where materials are exposed to neutrons below 60 MeV.
EASY can be divided into two parts: data and code development tools and user tools and data. The former are required to develop the latter, but EASY users only need to be able to use the inventory code FISPACT and be aware of the contents of the EAF library (the data source). The complete EASY package contains the FISPACT-2007 inventory code, the EAF-2003, EAF-2005, EAF-2007 and EAF-2010 libraries, and the EASY User Interface for the Window version.
The activation package EASY-2010 is the result of significant development to extend the upper energy range from 20 to 60 MeV so that it is capable of being used for IFMIF calculations. The EAF-2010 library contains 66,256 reactions, almost five times more than in EAF-2003 (12,617).
Deuteron-induced and proton-induced cross section libraries are also included, and can be used with EASY to enable calculations of the activation due to deuterons and proton [2].
The EAF-2010/2007 data library covers:
- Cross section data for neutron-induced reactions
- Uncertainty data for neutron-induced reactions
- Decay data
- Fission yield data
- Biological hazard data
- Legal transport data
- Clearance data
- Charged particle ranges in materials
- Emitted particle spectral data (from neutron-induced reactions)
- Charged particle cross section data
- Gamma absorption data
The EAF-2010/2007 contains the following data libraries:
EAF_XS-2010 is the point-wise cross section library. Data on 66,256 cross sections on 816 targets are held in a modified ENDF/B format. The energy range 10e-5 eV - 60 MeV is covered. All nuclides with a half-life of greater than 0.5 day have cross section data, but in addition some short-lived nuclides are also treated as targets. The cross sections represent targets that are infinitely dilute, no self-shielding is included and the temperature for Doppler broadening is 294K. Reference 2 documents the EAF-2010 cross section library.
EAF_GXS-2010 is a set of multi-group libraries; the available group structures are: WIMS (69), GAM-II (100), XMAS (172), VITAMIN-J (175), VITAMIN-J+ (211), TRIPOLI (315) and TRIPOLI+ (351). Various choices of micro-flux weighting are available for particular applications..
EAF_UN-2010 contains uncertainty data for all cross sections. This library, in modified ENDF/B-6 format, contains error factor values (in 2 to 4 energy groups) for all reactions and is unique amongst activation libraries. This approach to uncertainties is less comprehensive than that found in general purpose evaluated files, but is of great value for fusion related inventory calculations.
EAF_DEC-2010 contains decay data information for 2233 nuclides, it is based primarily on the JEF-3.1.1 radioactive decay data library, with additional data from recent UK evaluations. It includes data on half-lives, decay modes and decay energies. Note that entries are included for all stable nuclides. Care has been taken to ensure that EAF_XS and EAF_DEC are compatible. This is especially important for the identification of isomeric states. All nuclides (including isomeric states) that can be formed from the various reactions in EAF_XS are included so long as their half-lives are greater than 1 second. Some nuclides with shorter half-lives are included where it is felt that they are of particular importance.
EAF_FIS-2007 is taken completely from the JEFF-3.1 fission yield library. It is a library of independent fission yields in ENDF/B-6 format. Only 19 of the 90 nuclides in EAF_XS which have fission cross-sections have any fission yield data in JEFF-3.1 at relevant energies. An inventory code using this data source will need a means of using a neighbouring fission yield for such nuclides.
EAF_HAZ-2007 is a library of values for each radionuclide describing the potential biological impact of that nuclide on human beings. The format is not ENDF/B-6, but is suitable for input by the FISPACT code. The values are Committed Effective Doses per unit uptake, which determine the dose received by a person over their lifetime (50 years) following the ingestion or inhalation of 1 Bq of activity of a particular radionuclide.
EAF_A2-2007 is a library of values relevant for the transport of radionuclides in shielded flasks. The format is not ENDF/B-6, but is suitable for input by the FISPACT code. Transport of radioactive material from place to place is governed by regulations set up by the IAEA. Using these values it is possible to work out how much of a particular mixture of radioactive materials can be packed into a type of container and safely transported. Data from this reference for the nuclides listed are transferred to EAF_A2, with the use of the default prescription given, for all radionuclides not explicitly listed.
EAF_CLEAR-2007 is a library of values relevant for the disposal of radioactive material. The format is not ENDF/B-6, but is suitable for input by the FISPACT code. This contains the clearance limit value for each radionuclide. This value can be used to decide if an amount of a radionuclide can be disposed of with no special precautions.
EAF_STOP-2007 contains new data compared to the previous versions. Due to the change of the upper energy limit from 20 to 60 MeV the data have been recalculated. It is required to enable the effect of sequential charged particle reactions (SCPR) to be investigated.. EAF_STOP contains the differential ranges for protons (p), deuterons (d), helions (h), tritons (t) and alpha particles in all the elements from H to U. The term differential range at a particular energy defines the distance travelled by the particle in the material in losing 1 MeV of energy. Data are given from 0 to 60 MeV.
EAF_SPEC-2007: EAF_XS contains the cross section data for (n,x) reactions, while EAF_SPEC describes the energy distribution of the charged particles emitted in these reactions. This is the second libraries required for SCPR. The data are calculated by a theoretical model code (TALYS) due to the lack of experimental data. Thirty-nine input neutron energies are used and the outgoing charged particles are in 1 MeV bins covering the energy range 0-60 MeV.
EAF_XN-2007 describes the cross sections of p, d, h, t and alpha particles on 775 targets. Ten reactions types are considered: (p,n), (d,n), (h,n), (t,n), (alpha,n), (p,2n), (d,2n), (h,2n), (t,2n) and (alpha,2n). This is the third of the libraries required for SCPR. The data are calculated by a theoretical model code (TALYS) due to the lack of experimental data. The data are given at 1 MeV intervals over the energy range 0-60 MeV.
EAF_ABS contains the photon mass energy attenuation coefficient for all the elements Z= 1 - 100 in increasing Z order. The attenuation coefficient and energy absorption coefficient for air are also listed. All data are stored in a 24 group energy structure.
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4. METHODS
FISPACT is an inventory code that has been developed for neutron, proton and deuteron-induced activation calculations for materials in fusion devices. FISPACT-2007 uses external libraries of nuclear data for all relevant nuclides to calculate the number of atoms of each species at a specified time during the irradiation or after a decay time following shutdown. The various species are formed either by a direct reaction on a starting material, by a series of reactions some of which can be on radioactive targets or by a decay or series of decays. The accuracy of the calculated inventory is dependent on the quality of the input nuclear data - the cross sections and decay properties - the European Activation File (EAF), described in the next section, is the recommended source of data.
The generation of the European Activation File (EAF) is carried out using the SAFEPAQ-II application that is based on the SYMPAL and SAFEPAQ code systems. SAFEPAQ-II uses as input many world-wide sources of nuclear data. These evaluated files, calculations and experimental data are used to construct a collection of cross section data for neutron-induced reactions on a large set of stable and unstable target nuclides, a decay data file and other data libraries required by FISPACT.
FISPACT is an inventory code that has been developed for neutron, proton and deuteron-induced activation calculations for materials in fusion devices. FISPACT-2007 uses external libraries of nuclear data for all relevant nuclides to calculate the number of atoms of each species at a specified time during the irradiation or after a decay time following shutdown. The various species are formed either by a direct reaction on a starting material, by a series of reactions some of which can be on radioactive targets or by a decay or series of decays. The accuracy of the calculated inventory is dependent on the quality of the input nuclear data - the cross sections and decay properties - the European Activation File (EAF), described in the next section, is the recommended source of data.
The generation of the European Activation File (EAF) is carried out using the SAFEPAQ-II application that is based on the SYMPAL and SAFEPAQ code systems. SAFEPAQ-II uses as input many world-wide sources of nuclear data. These evaluated files, calculations and experimental data are used to construct a collection of cross section data for neutron-induced reactions on a large set of stable and unstable target nuclides, a decay data file and other data libraries required by FISPACT.
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| Package ID | Status date | Status |
|---|---|---|
| NEA-1564/13 | 16-DEC-2011 | Masterfiled Arrived |
| NEA-1564/15 | 19-JUN-2012 | Tested at NEADB |
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10. REFERENCES
- J.A. Simpson and J-Ch Sublet, SYMPAL: Utilities guide, UKAEA FUS 357, 1997
- R.A. Forrest and J.A. Simpson, SAFEPAQ: User manual, UKAEA FUS 355, 1997
- Regulations for the safe transport of radioactive material, 1985 edition, (and supplement 1988), Safety Series No 6, IAEA, Vienna
- S. Cierjacks, P. Oblozinsky and B. Rzehorz, Nuclear data libraries for the treatment of sequential (x,n) reactions in fusion materials activation calculations, KfK 4867, 991
- J.A. Simpson and J-Ch Sublet, SYMPAL: Utilities guide, UKAEA FUS 357, 1997
- R.A. Forrest and J.A. Simpson, SAFEPAQ: User manual, UKAEA FUS 355, 1997
- Regulations for the safe transport of radioactive material, 1985 edition, (and supplement 1988), Safety Series No 6, IAEA, Vienna
- S. Cierjacks, P. Oblozinsky and B. Rzehorz, Nuclear data libraries for the treatment of sequential (x,n) reactions in fusion materials activation calculations, KfK 4867, 991
NEA-1564/13, included references:
- R.A. Forrest:The European Activation File: EAF-2007 deuteron- and proton-induced cross
section libraries, UKAEA FUS 536
- L. W. Packer and J-Ch. Sublet:
The European Activation File: EAF-2010 decay data library, CCFE-R (10)02 (March
2010)
- L. W. Packer and J-Ch. Sublet:
The European Activation File: EAF-2010 biological, clearance and transport
libraries, CCFE-R (10)04 (March 2010)
- J.-Ch. Sublet, L. W. Packer, J. Kopecky, R. A. Forrest, A. J. Koning and
D. A. Rochman:
The European Activation File: EAF-2010 neutron-induced cross section library
CCFE-R (10)05
- R. A. Forrest:
FISPACT-2007: User manual, UKAEA FUS 534
- L. W. Packer and R. A. Forrest:
SAFEPAQ-II: User manual, CCFE-R-(10)03
- Online EAF-2010 Documentation: http://www.ccfe.ac.uk/EASY.aspx
NEA-1564/15, included references:
- R.A. Forrest:The European Activation File: EAF-2007 deuteron- and proton-induced cross
section libraries, UKAEA FUS 536
- R.A. Forrest:
The European Activation System: EASY-2007 overview, UKAEA FUS 533
- L. W. Packer and J-Ch. Sublet:
The European Activation File: EAF-2010 decay data library, CCFE-R (10)02 (March
2010)
- L. W. Packer and J-Ch. Sublet:
The European Activation File: EAF-2010 biological, clearance and transport
libraries, CCFE-R (10)04 (March 2010)
- J.-Ch. Sublet, L. W. Packer, J. Kopecky, R. A. Forrest, A. J. Koning and
D. A. Rochman:
The European Activation File: EAF-2010 neutron-induced cross section library
CCFE-R (10)05
- R. A. Forrest:
FISPACT-2007: User manual, UKAEA FUS 534
- L. W. Packer and R. A. Forrest:
SAFEPAQ-II: User manual, CCFE-R-(10)03
- Online EAF-2010 Documentation: http://www.ccfe.ac.uk/EASY.aspx
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NEA-1564/13
UNIX workstations (IBM AIX, Oracle Sparc & Intel, Ubuntu LINUX, Dec ALPHA and MacIntosh).NEA-1564/15
This version was tested at CCFE on Win98 (Second Edition), NT4 (Service Pack 5), Windows 2000, Windows XP and Windows Vista.Tested at the NEA Databank on Dell INTEL Duo E6550, 2.33 GHz (for Windows).
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| Package ID | Computer language |
|---|---|
| NEA-1564/13 | FORTRAN |
| NEA-1564/15 | FORTRAN |
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NEA-1564/13
READMEs.txt Readme file/eaf2010
eaf_dec_20100.001 to 010 The Decay data sub-libraries for EAF-2010
eaf_a2_20100 The A2 data for EAF-2010
eaf_haz_20100 The biological hazard data for EAF-2010
eaf_n_asscfy_20070 List of fissionable nuclides with fission yield data used
eaf_d_asscfy_20070 List of fissionable nuclides with fission yield data used
eaf_p_asscfy_20070 List of fissionable nuclides with fission yield data used
eaf_n_fis_20100 The JEF-3.1.1 fission yield data
eaf_d_fis_20100 The Deuteron fission yield data
eaf_p_fis_20100 The Proton fission yield data
eaf_un_20100 The uncertainty file for the cross section data
eaf_abs_20070 The Gamma-ray attenuation coefficients data
eaf_clear_20100 The clearance index
eaf_n_gxs_066_fis_20100 The 66 groups CINDER version of EAF-2010, fission
eaf_n_gxs_066_flt_20100 The 66 groups CINDER version of EAF-2010, flat
eaf_n_gxs_069_fis_20100 The 69 groups WIMS version of EAF-2010, fission
eaf_n_gxs_100_fus_20100 The 100 groups GAM-II version of EAF-2010, fusion
eaf_n_gxs_175_fus_20100 The 175 groups Vitamin-J version of EAF-2010,fusion
eaf_n_gxs_175_flt_20100 The 175 groups Vitamin-J version of EAF-2010, flat
eaf_n_gxs_172_fis_20100 The 172 groups Xmas version of EAF-2010, fission
eaf_n_gxs_172_flt_20100 The 172 groups Xmas version of EAF-2010, flat
eaf_n_gxs_315_fis_20100 The 315 groups tripoli version of EAF-2010, fission
eaf_n_gxs_315_fus_20100 The 315 groups tripoli version of EAF-2010, fusion
eaf_n_gxs_315_flt_20100 The 315 groups tripoli version of EAF-2010, flat
eaf_n_gxs_211_flt_20100 211 groups Vitamin-J+ 60 MeV version of EAF-2010, flat
eaf_n_gxs_351_flt_20100 351 groups tripoli+ 60 MeV version of EAF-2010, flat
eaf_d_gxs_211_flt_20070 211 groups Vitamin-J+ 60 MeV Deuteron-induced library
eaf_p_gxs_211_flt_20070 The 211 groups Vitamin-J+ 60 MeV Proton-induced lib.
eaf_index_20100 index of nuclides used for all cross section libraries
eaf_spec_pt1_20070 Particle emission spectra
eaf_spec_pt2_20070 Particle emission spectra
eaf_spec_pt3_20070 Particle emission spectra
eaf_spec_pt4_20070 Particle emission spectra
eaf_spec_pt5_20070 Particle emission spectra
eaf_stop_alp_20070 Stopping power for Alpha particle
eaf_stop_deu_20070 Stopping power for Deuteron particle
eaf_stop_he3_20070 Stopping power for Helium-3 particle
eaf_stop_pro_20070 Stopping power for Proton particle
eaf_stop_tri_20070 Stopping power for Triton particle
eaf_xn_an_20070 Alpha,n cross section library
eaf_xn_a2n_20070 Alpha,2n cross section library
eaf_xn_d2n_20070 Deuteron,2n cross section library
eaf_xn_dn_20070 Deuteron,n cross section library
eaf_xn_hn_20070 Helium-3,n cross section library
eaf_xn_h2n_20070 Helium-3,2n cross section library
eaf_xn_pn_20070 Proton,n cross section library
eaf_xn_p2n_20070 Proton,2n cross section library
eaf_xn_t2n_20070 Triton,2n cross section library
eaf_xn_tn_20070 Triton,n cross section library
FILES The list of files to be connected to streams
FILES_d The list of files to be connected to streams, deuteron
FILES_p The list of files to be connected to streams, proton
fisplink Unix script file to link the necessary files in the
working directory (NEEDS TO BE MODIFIED)
fisplib Unix script file to create one-group averaged cross section library
/fispact2010 The FISPACT code directory
Fisp_Unix_2010.f FISPACT source code OsX, Sol, Ubuntu system dependent sub-dir
fisp10 FISPACT executable, system dependent
Makefile File needed to compile FISPACT and create the executable fisp10
Makeliste c-shell make (>&) output
/fispQA Directory containing test cases
runtest Unix script to run all test cases
Tst_100 Test cases GAM-II library (fusion)
Tst_175 Test cases Vitamin-J library (fusion)
Tst_069 Test cases WIMS library (fission)
Tst_172v Test cases Xmas library (fission)
Tst_172w Test cases Xmas library (flat)
Tst_315 Test cases Tripoli library (fusion)
Tst_burn Test cases
Tst_spec Test cases
Tst_211 Test cases Vitamin-j+ 60 MeV library (flat)
Tst_351 Test cases Tripoli+ 60 MeV library (flat)
Tst_deut Test cases Vitamin-j+ 60 MeV Deuteron library
Tst_ptot Test cases Vitamin-j+ 60 MeV Proton library
/Docs Documentation and User Manuals in Acrobat PDF format
SAFEPAQ-II_User_manual.pdf
FISPACT_User_manual_2007.pdf
EAF_n_Cross_sections_2010.pdf
EAF_Hazards_2010.pdf
EAF_Decay_2010.pdf
EAF_Charged_Particles_2007.pdf
/util Utility codes for printing and graphical output.
/archive Archive directory
NEA-1564/15
readme fileGettingStartedNEA.doc Getting Started document which contains the EASY 2007
GUI installation user name and password
\eaf_data\ The complete EAF-2007 data library
\archive\data\eaf_20051\ The EAF-2005.1 data library different from EAF-2005
\archive\data\eaf_2005\ The complete EAF-2005 data library
\archive\data\eaf_2003\ The complete EAF-2003 data library
\archive\data\fendl2\ The FENDL-2 data library
\archive\data\jeff-30A\ The JEFF-3.0/A data library
\easy07ui\ The EASY-2007 User Interface, a Windows application
to make the use of the inventory code FISPACT easier on a PC. EAF-2007 nuclear
data can also be displayed
\Install_EASY\ The Install EASY application to copy all EAF-2007 data
files and install FISPACT-2007 on your PC
\fispact\ FISPACT-2007. The version of FISPACT for a PC plus
files for getting FISPACT working and tested
\testcases\ The set of inputs for the Test Cases for FISPACT-2007
\testcases_UKAEA\ The set of inputs and outputs for the Test Cases for
FISPACT-2007 run at UKAEA
Electronic documentation
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- B. Spectrum Calculations, Generation of Group Constants and Cell Problems
- Z. Data.
Keywords: cross sections, data.