last modified: 25-APR-1997 | catalog | categories | new | search |

NEA-1544 ZZ-GEFF-2-MATXS.

ZZ GEFF-2-MATXS, Coupled Neutron-Gamma Fusion Neutronics Library in MATXS Format

top ]
1. NAME OR DESIGNATION OF PROGRAM:  ZZ-GEFF-2-MATXS.
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-GEFF-2-MATXS NEA-1544/01 Tested 25-APR-1997

Machines used:

Package ID Orig. computer Test computer
NEA-1544/01 DEC ALPHA W.S.
top ]
3. DESCRIPTION OF PROGRAM OR FUNCTION

This library for fusion neutronics calculations, to be used in conjunction with the TRANSX code, is the MATXS format version of ZZ-GEFF-2-GENDF from which it has been derived by means of the MATXSR NJOY module. It has a 175 neutron, 42 photon VITAMIN-J group structure with the standard weighting function: Maxwellian (at the temperature to which the material is referenced) + 1/E + fission spectrum + 1/E + fusion peak + 1/E. It includes 93 materials from 1-H-1 to Bi-209 - almost all from EFF-2 basic data; but Ag-107, Ag-109, natural Cd, the 6 Hf isotopes and the 4 W isotopes have been taken from JEF-2.2 - at 3
temperatures and 6 dilution cross section values; 10 thermal groups  are provided below 3 eV. Neutron cross sections and diffusion matrices, photon and gas production, kerma and DPA are given. The library includes H in H2O, metallic Be and Graphite for which an accurate treatment with S(alpha,beta) matrices has been provided for the thermal scattering region, while all remaining materials have been treated with the 'free gas' approximation.
Photon interaction data are taken from GEPDL - which is included in  ZZ-GEFF-2-GENDF - a 42 group photon interaction P8 library based upon EPDL-90; in order to couple this photon section - GEPDL - which is P8, with the neutron part - GEFF-2 - which is P5, the latter has  been filled with zeroes for the contribution P6 to P8.
top ]
4. METHOD OF SOLUTION

NJOY has been used to process both GEFF-2 and GEPDL; since the processing activities lasted over a couple of years, less important materials were processed with the 91.13 version of the code and the 91.38 has been used to process all the remaining materials, including the whole GEPDL. Some very important  modifications have been introduced in the code as far as the kerma computation is concerned, in order to solve problems due to physical inconsistencies of the data and non-standard formats of some materials, e.g. the lump reaction MT 10 - neutron diffusion in the continuum energy region - was not properly treated by the kerma module HEATR.  The libraries have been produced both in GENDF -
ZZ-GEFF-2-GENDF - and in MATXS format - the current one; the size of this library in card image format is about 500MB.
top ]
5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
top ]
6. TYPICAL RUNNING TIME:
top ]
7. UNUSUAL FEATURES OF THE PROGRAM:
top ]
8. RELATED AND AUXILIARY PROGRAMS:  NJOY, BBC, TRANSX.
top ]
9. STATUS
Package ID Status date Status
NEA-1544/01 25-APR-1997 Tested at NEADB
top ]
10. REFERENCES

- G.C.Panini:
  Preliminary Report on Group Transport Libraries GEFF-2
  RFL-2 from EFF 2.2 & JEF 2.2 at June, 22, 1992 - PART B Graphs -
  EFF-DOC-154(92)
NEA-1544/01, included references:
- P.Peerani:
  Contribution of radioactive decay to kerma and dpa
  EFF-DOC-55(90)
- E.Cuccoli, G.C.Panini, P.Peerani:
  A Library of Response Functions in Vitamin-J Structure
  EFF-DOC-72(90)
- G.C.Panini, P.Peerani:
  RFL-1 : A Library of Nuclear Response Functions in Vitamin-J
  Structure
  EFF-DOC-130(92)
- G.C.Panini:
  Preliminary Report on Group Transport Libraries GEFF-2 &
  RFL-2 from EFF 2.2 & JEF 2.2 at June, 22, 1992 - PART A
  EFF-DOC-153(92)
- M.Frisoni, G.C.Panini:
  Neutron Heating in EFF-2.2 and JEF 2.2
  EFF-DOC-155(92)/JEF-DOC-374(92)
- M.Frisoni, G.C.Panini, P.Peerani:
  Status Report on the Computation of Kerma and Photon Production
  Data for RFL-2
  EFF-DOC-177(92)
- G.C.Panini:
  Status Report on Group Transport Library GEFF-2 from EFF2.2 & JEF
  2.2 at December, 1992
  EFF-DOC-178(92)
- M.Frisoni, G.C.Panini, P.Peerani:
  Check on the Importance of Radioactive Decay on Kerma and Photon
  Production Data
  EFF-DOC-17
- M.Frisoni, G.C.Panini:
  Status Report on Nuclear Data Processing for the European
  Programme for Fusion
  EFF-DOC-250(93)
- M.Frisoni, G.C.Panini:
  Group Nuclear Data Libraries for the European Programme for fusion
  EFF-DOC-367(94)
top ]
11. MACHINE REQUIREMENTS:
top ]
12. PROGRAMMING LANGUAGE(S) USED

No item found

top ]
13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:
top ]
14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS

The
SIZE of the library in card image ASCII format is about 500MB. The list of the materials includes the values of temperature and of dilution at which each material is given.
top ]
15. NAME AND ESTABLISHMENT OF AUTHORS: , ENEA, Bologna, ITALY
top ]
16. MATERIAL AVAILABLE
NEA-1544/01
File name File description Records
NEA1544_01.001 Information file 137
NEA1544_01.002 List of materials 254
NEA1544_01.003 AG107 6674
NEA1544_01.004 AG109 9474
NEA1544_01.005 AL27 110077
NEA1544_01.006 AR36 32232
NEA1544_01.007 AR38 31559
NEA1544_01.008 AR40 35592
NEA1544_01.009 B10 80965
NEA1544_01.010 B11 62234
NEA1544_01.011 BA130 16196
NEA1544_01.012 BA134 5718
NEA1544_01.013 BA135 7029
NEA1544_01.014 BA136 6455
NEA1544_01.015 BA137 6197
NEA1544_01.016 BA138 4896
NEA1544_01.017 BE9 38970
NEA1544_01.018 BE9M 40582
NEA1544_01.019 BI209 61276
NEA1544_01.020 CAnat 103817
NEA1544_01.021 CDnat 21885
NEA1544_01.022 CLnat 25194
NEA1544_01.023 Cnat 27205
NEA1544_01.024 CO59 15334
NEA1544_01.025 CR50 54008
NEA1544_01.026 CR52 73642
NEA1544_01.027 CR53 63514
NEA1544_01.028 CR54 49457
NEA1544_01.029 CU63 147356
NEA1544_01.030 CU65 121929
NEA1544_01.031 F19 158349
NEA1544_01.032 FE54 38804
NEA1544_01.033 FE56 96667
NEA1544_01.034 FE57 54885
NEA1544_01.035 FE58 50790
NEA1544_01.036 GRAPHITE 27304
NEA1544_01.037 H1 67235
NEA1544_01.038 H1-BOUND 67158
NEA1544_01.039 H2 47589
NEA1544_01.040 H3 29452
NEA1544_01.041 HE3 18369
NEA1544_01.042 HE4 14997
NEA1544_01.043 HF174 54920
NEA1544_01.044 HF176 58412
NEA1544_01.045 HF177 58798
NEA1544_01.046 HF178 57441
NEA1544_01.047 HF179 53549
NEA1544_01.048 HF180 56949
NEA1544_01.049 IN113 76304
NEA1544_01.050 IN115 65609
NEA1544_01.051 K-nat 28581
NEA1544_01.052 LI6 126598
NEA1544_01.053 LI7 81874
NEA1544_01.054 MG-nat 84798
NEA1544_01.055 MN55 141975
NEA1544_01.056 MO100 103072
NEA1544_01.057 MO92 94963
NEA1544_01.058 MO94 107612
NEA1544_01.059 MO95 134106
NEA1544_01.060 MO96 106949
NEA1544_01.061 MO97 133377
NEA1544_01.062 MO98 108397
NEA1544_01.063 N14 80993
NEA1544_01.064 N15 26157
NEA1544_01.065 NA23 73038
NEA1544_01.066 NB93 61184
NEA1544_01.067 NI58 68768
NEA1544_01.068 NI60 77234
NEA1544_01.069 NI61 118428
NEA1544_01.070 NI62 95234
NEA1544_01.071 NI64 85635
NEA1544_01.072 O16 56505
NEA1544_01.073 P31 5632
NEA1544_01.074 PB-nat 87150
NEA1544_01.075 RE185 22660
NEA1544_01.076 RE187 31582
NEA1544_01.077 SI28 85147
NEA1544_01.078 SN112 19255
NEA1544_01.079 SN114 20227
NEA1544_01.080 SN115 19177
NEA1544_01.081 SN116 15192
NEA1544_01.082 SN117 18136
NEA1544_01.083 SN118 14493
NEA1544_01.084 SN119 21413
NEA1544_01.085 SN120 16819
NEA1544_01.086 SN122 14433
NEA1544_01.087 SN124 17902
NEA1544_01.088 S-nat 24670
NEA1544_01.089 TA181 55286
NEA1544_01.090 TI-nat 90076
NEA1544_01.091 V-nat 47210
NEA1544_01.092 W182 32638
NEA1544_01.093 W183 36353
NEA1544_01.094 W184 33596
NEA1544_01.095 W186 33727
NEA1544_01.096 W-nat 105269
NEA1544_01.097 ZR-nat 28226
top ]
17. CATEGORIES
  • J. Gamma Heating and Shield Design
  • X. Magnetic Fusion Research
  • Z. Data.

Keywords: data library, fusion reactors, group constants, neutron cross sections, nuclear damage.