DLC-0055 ZZ-RECOIL/B.

1. NAME OR DESIGNATION OF PROGRAM:  ZZ-RECOIL/B.
Primary Recoil Spectra, Displacement Rates, and Gas-Production Rates

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)

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.

5. RESTRICTIONS ON THE COMPLEXITY OF THE PROBLEM:

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.

7. UNUSUAL FEATURES OF THE PROGRAM:

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.

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).

- 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)

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.

13. OPERATING SYSTEM UNDER WHICH PROGRAM IS EXECUTED:  MVS/SE.

14. OTHER PROGRAMMING OR OPERATING INFORMATION OR RESTRICTIONS:

15. NAME AND ESTABLISHMENT OF AUTHOR:
T.A. Gabriel, J.D. Amburgey, N.M. Greene
ORNL

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