last modified: 19-SEP-1983 | catalog | categories | new | search |

DLC-0055 ZZ-RECOIL/B.

ZZ RECOIL/B, Heavy Charged Particle Recoil Spectra Library for Radiation Damage Calculation

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1. NAME OR DESIGNATION OF PROGRAM:  ZZ-RECOIL/B.
Primary Recoil Spectra, Displacement Rates, and Gas-Production Rates
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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-RECOIL/B DLC-0055/01 Tested 19-SEP-1983

Machines used:

Package ID Orig. computer Test computer
DLC-0055/01 IBM 3081 IBM 3081
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3. DESCRIPTION OF PROBLEM OR FUNCTION



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  FORMAT: GAM-II group structure



  NUMBER OF GROUPS: 104 neutron and Recoil-energy groups



NUCLIDES: Elements Included in Charged-Particle Recoil Data Base: Al, W, Ti, Pb, V, Mg, Cr, Be, Mn, C, Fe, Au, Co, Si, Ni, B-10, Cu, B-11, Zr, N, Nb, Li-6, Mo, Li-7, Ta (Data for Ta-181,Ta-182), O,



  ORIGIN: ENDF/B-IV cross-section data



  WEIGHTING SPECTRUM:



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A heavy charged-particle recoil data base (primary knock-on atom (PKA) spectra) and an analysis program have been created to assist experimentalists in studying, evaluating, and correlating radiation-damage effects in different neutron environments. Since experimentally obtained controlled thermo-nuclear-reactor-type neutron spectra are not presently available, the data base can be extremely useful in relating currently obtainable radiation damage to that which is anticipated in future fusion devices. However, the usefulness of the data base is not restricted to just CTR needs. Most of the elements of interest to the radiation-damage community and all neutron reactions of any significance for these elements have been processed, using available ENDF/B-IV cross-section data, and are included in the data base. Calculated data such as primary recoil spectra, displacement rates, and gas-production rates, obtained with the data base, for different radiation environments are presented and compared with previous calculations. Primary neutrons with energies up to 20 MeV have been considered. The elements included in the  data base are  listed  in Table I.

All neutron reactions of significance for these elements (i.e., elastic, inelastic, (n,2n), (n,3n), (n,p), (n,sigma), (n,gamma), etc.,) which have cross sections available from ENDF/B-IV have been  processed and placed in the data base.



      TABLE I



  Elements Included in Charged-Particle Recoil Data Base



              Al                         W

              Ti                         Pb

              V                          Mg

              Cr                         Be

              Mn                         C

              Fe                         Au

              Co                         Si

              Ni                        10B

              Cu                        11B

              Zr                         N

              Nb                        6Li

              Mo                        7Li

              Ta (Data for              O

                  Ta181,Ta182)
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4. METHOD OF SOLUTION

The neutron group structure up to 14.91 MeV is  the same as the GAM-II group structure. (1) The recoil group structure used is based on equal lethargy intervals from 20 eV to 10 MeV.
For elastic, inelastic, (n,2n), (n,3n), (n,np), and (n,sigma) reactions, a modified version of the XLACS module from the AMPX code system (1) was used to calculate the heavy charged-particle recoil spectra. For elastic and inelastic resolved reactions, where angular distributions are usually available, the recoil spectra were obtained in the form of a neutron-group- (gn) to-recoil group (gr) transfer matrix.
For the remaining reactions given above, the recoil spectra were obtained by using a one-neutron emission model(2) and the secondary- neutron spectra (assumed to be applicable at all angles in the center-of-mass system) given in ENDF/B-IV.
For neutron absorption reactions, such as (n,p), (n,sigma), etc., the methods of Doran, (2) Jenkins, (3) and Parkin and Goland (4) were used.
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5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:
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6. TYPICAL RUNNING TIME

NEA-DB executed test cases of the various processing codes distributed with the data library. The following CPU times were required:
     Data conversion program:        3 seconds
     Group boundary conversion:      1 second
     RECOIL:                         7 seconds.
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7. UNUSUAL FEATURES OF THE PROGRAM:
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8. RELATED AND AUXILIARY PROGRAMS

The following processing programs are included with the data base:
1) A Group Boundary Conversion Program.
2) RECOIL: BCD to binary conversion program.
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9. STATUS
Package ID Status date Status
DLC-0055/01 19-SEP-1983 Tested at NEADB
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10. REFERENCES

- N.M. Greene et al.,
  AMPX: A Modular Code System for Generating Coupled Multigroup
  Neutron-Gamma Libraries from ENDF/B,
  ORNL-TM-37-6, Oak Ridge National Laboratory (to be published).
- J.D. Jenkins,
  Nucl. Sci. Eng. 41, 155 (1970).
- D.G. Doran,
  Nucl. Sci. Eng. 49, 130 (1972).
- D.M. Parkin and A.N. Goland,
  A Computational Method for the Evaluation of Radiation Effects
  Producted by CTR-Related Neutron Spectra,
  Brookhaven National Laboratory Report (1974).
- J. Lindhard et al.,
  Mat. Fys. Medd. Dan. Vid. Selsk 33, 1 (1963).
- M.T. Robinson,
  Nuclear Fusion Reactors, Proc. British Nuclear Energy Society
  Conference, Culham Laboratory,
  September 1969, p. 364.
- D.M. Parkin and A.N. Goland,
Analysis of Radiation Damage in Fusion Simulation Neutron Spectra,   presented at the International Conference on Radiation Effects and    Tritium Technology for Fusion Reactors,
  October 1-3, 1975, Gatlinburg, Tennessee (to be published in the
  proceedings).
- R.T. Santoro,
Neutronics Calculations for the Tokamak Experimental Power Reactor    Reference Design,
  ORNL-TM-5033, Oak Ridge National Laboratory (1975).
- G.L. Kulcinski, D.G. Doran, and M.A. Abdou,
  Comparison of Displacement and Gas Production Rates in Current
  Fission and Future Fusion Reactors,
  UWFDM-15, University of Wisconsin (1974).
- Proposal for an Accelerator-Based Neutron Generator,
  BNL-20159, Brookhaven National Laboratory (1975).
DLC-0055/01, included references:
- T.A. Gabriel, J.D. Amburgey and N.M. Greene
  RADIATION-DAMAGE CALCULATIONS: Primary Recoil Spectra,
  Displacement Rates, and Gas-Production Rates.
  ORNL/TM-5160 (March 1976)
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11. MACHINE REQUIREMENTS

Main storage requirements for the various processing codes are as follows:
     Data conversion program:     150K bytes
     Group boundary conversion:    150K bytes
      RECOIL:                       400K bytes.
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12. PROGRAMMING LANGUAGE(S) USED
Package ID Computer language
DLC-0055/01 FORTRAN-IV
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13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  MVS/SE.
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14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:
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15. NAME AND ESTABLISHMENT OF AUTHOR:
T.A. Gabriel, J.D. Amburgey, N.M. Greene
ORNL
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16. MATERIAL AVAILABLE
DLC-0055/01
File name File description Records
DLC0055_01.003 ZZ-RECOIL/B INFORMATION FILE 81
DLC0055_01.004 W1128 (NOV 77) DATA 10065
DLC0055_01.005 B1160 (AUG 77) DATA 3308
DLC0055_01.006 NB1189 (NOV 77) DATA 8866
DLC0055_01.007 NI1190 (NOV 77) DATA 10961
DLC0055_01.008 CR1190 (NOV 77) DATA 20029
DLC0055_01.009 FE1192 (NOV 77) DATA 14714
DLC0055_01.010 AL1193 (NOV 77) DATA 13000
DLC0055_01.011 SI1194 (NOV 77) DATA 11863
DLC0055_01.012 V1196 (NOV 77) DATA 7511
DLC0055_01.013 MN1197 (NOV 77) DATA 7532
DLC0055_01.014 CO1199 (NOV 77) DATA 7755
DLC0055_01.015 LI1271 (AUG 75) DATA 6955
DLC0055_01.016 LI1272 (AUG 75) DATA 3536
DLC0055_01.017 B1273 (AUG 75) DATA 12034
DLC0055_01.018 C1274 (AUG 75) DATA 2699
DLC0055_01.019 N1275 (AUG 75) DATA 13232
DLC0055_01.020 MG1280 (NOV 77) DATA 17303
DLC0055_01.021 AU1283 (NOV 77) DATA 11673
DLC0055_01.022 ZR1284 (NOV 77) DATA 6811
DLC0055_01.023 TA1285 (NOV 77) DATA 11714
DLC0055_01.024 TI1286 (NOV 77) DATA 5525
DLC0055_01.025 NO1287 (NOV 77) DATA 5236
DLC0055_01.026 PB1288 (NOV 77) DATA 14635
DLC0055_01.027 BE1289 (NOV 77) DATA 6644
DLC0055_01.028 CU1295 (NOV 77) DATA 11080
DLC0055_01.029 O1276 (NOV 77) DATA 6617
DLC0055_01.030 RECOIL SOURCE (FORTRAN-4) 1783
DLC0055_01.031 GROUP BOUNDARIES CONVERSION PGM (FORTRAN-4) 16
DLC0055_01.032 RECOIL DATA CONVERSION PGM (FORTRAN-4) 45
DLC0055_01.033 ENERGY GROUP BOUNDARIES 33
DLC0055_01.034 JCL FOR RECOIL AND DATA 46
DLC0055_01.035 ORIGINAL JCL FOR RECOIL 124
DLC0055_01.036 JCL FOR DATA CONVERSION 15
DLC0055_01.037 JCL FOR GROUP BOUNDARIES CONVERSION 11
DLC0055_01.038 OUTPUT FROM GROUP BOUNDARIES CONVERSION 1
DLC0055_01.039 OUTPUT FROM DATA CONVERSION 1391
DLC0055_01.040 RECOIL PRINTED OUTPUT 3420
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17. CATEGORIES
  • G. Radiological Safety, Hazard and Accident Analysis
  • X. Magnetic Fusion Research
  • Z. Data.

Keywords: CTR, data, fusion reactors, kerma factors, multigroup, neutron reactions, neutron recoil, radiation effects, recoil spectra.