29-Cu- 65 LANL,ORNL EVAL-FEB98 A.KONING,M.CHADWICK,HETRICK Ch98,Ch99 DIST-NOV 1 REV4- 20011108 ----ENDF/B-VI MATERIAL 2931 REVISION 4 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT Oct 22,2004, Holly Trellue remade mf6mt5 using corrected gnash code, to fix an earlier bug. Impact is reduced sec. particle prod. for new ENDF/B-VII release **************************************************************** ENDF/B-VI MOD 5 Revision, May 2000, S.C. Frankle, R.C. Reedy, P.G. Young (LANL) The secondary gamma-ray spectrum for radiative capture (MF 12, MT 102) has been updated for new experimental data at incident neutron energies up to 1 keV. The MF=12, MT=102 yields above 1 keV were adjusted slightly to force energy conservation. The Q-value for radiative capture was also updated in File 3. Details of these changes are described in Frankel et al. [Fr01]. **************************************************************** ENDF/B-VI MOD 4 Evaluation, February 1998, A.J. Koning (ECN), M.B. Chadwick, P.G. Young (LANL) Los Alamos LA150 Library, produced with FKK/GNASH/GSCAN code in cooperation with ECN Petten. This evaluation provides a complete representation of the nuclear data needed for transport, damage, heating, radioactivity, and shielding applications over the incident neutron energy range from 1.0E-11 to 150 MeV. The discussion here is divided into the region below and above 20 MeV. INCIDENT NEUTRON ENERGIES < 20 MeV Below 20 MeV the evaluation is based completely on the ENDF/B- VI (Release 2) evaluation by D. Hetrick, C.Y. Fu, and D. Larson. INCIDENT NEUTRON ENERGIES > 20 MeV The ENDF/B-VI Release 2 evaluation extends to 20 MeV and includes cross sections and energy-angle data for all significant reactions. The present evaluation utilizes a more compact composite reaction spectrum representation above 20 MeV in order to reduce the length of the file. No essential data for applications is lost with this representation. The evaluation above 20 MeV utilizes MF=6, MT=5 to represent all reaction data. Production cross sections and emission spectra are given for neutrons, protons, deuterons, tritons, alpha particles, gamma rays, and all residual nuclides produced (A>5) in the reaction chains. To summarize, the ENDF sections with non-zero data above En = 20 MeV are: MF=3 MT= 1 Total Cross Section MT= 2 Elastic Scattering Cross Section MT= 3 Nonelastic Cross Section MT= 5 Sum of Binary (n,n') and (n,x) Reactions MF=4 MT= 2 Elastic Angular Distributions MF=6 MT= 5 Production Cross Sections and Energy-Angle Distributions for Emission Neutrons, Protons, Deuterons, Tritons, and Alphas; and Angle- Integrated Spectra for Gamma Rays and Residual Nuclei That Are Stable Against Particle Emission The evaluation is based on nuclear model calculations that have been benchmarked to experimental data, especially for n + Cu65 and p + Cu65 reactions (Ch98). We use the GNASH code system (Yo92), which utilizes Hauser-Feshbach statistical, preequilib- rium and direct-reaction theories. Spherical optical model calculations are used to obtain particle transmission coefficients for the Hauser-Feshbach calculations, as well as for the elastic neutron angular distributions. Cross sections and spectra for producing individual residual nuclei are included for reactions. The energy-angle-correlations for all outgoing particles are based on Kalbach systematics (Ka88). A model was developed to calculate the energy distributions of all recoil nuclei in the GNASH calculations (Ch96a). The recoil energy distributions are represented in the laboratory system in MT=5, MF=6, and are given as isotropic in the lab system. All other data in MT=5,MF=6 are given in the center-of-mass system. This method of representation utilizes the LCT=3 option approved at the November, 1996, CSEWG meeting. Preequilibrium corrections were performed in the course of the GNASH calculations using the exciton model of Kalbach (Ka77, Ka85), validated by comparison with calculations using Feshbach, Kerman, Koonin (FKK) theory [Ch93]. Discrete level data from nuclear data sheets were matched to continuum level densities using the formulation of Ignatyuk et al. (Ig75) and pairing and shell parameters from the Cook (Co67) analysis. Neutron and charged- particle transmission coefficients were obtained from the optical potentials, as discussed below. Gamma-ray transmission coefficients were calculated using the Kopecky-Uhl model (Ko90). SPECIFIC INFORMATION CONCERNING THE 65Cu EVALUATION This evaluation is documented in some detail in Ref. (Ko98b). The neutron total cross section above 20 MeV was obtained by evaluating experimental data, with a particular emphasis on the Finlay (Fi93) elemental data. This resulted in an evaluated elemental Cu total cross section; to obtain an isotopic 65Cu total cross section, it was assumed that 63Cu and 65Cu have total cross sections in an A**2/3 ratio to one another. The total neutron nonelastic cross section was obtained directly from an optical model calculation (see below), after verifying that it was in good agreement with the experimental data (Ko98b). To obtain the neutron optical potential we used total cross section data from 1.2 to 4.5 MeV (Gu86) and from 5.3 to 600 MeV (Fi93), and elastic scattering angular distribution data from 1.6 to 96 MeV (Br50, Sa60, Ki74, El82, Gu86). The optical potential parameters were obtained using a combination of a grid search code and the interactive optical model viewer ECISVIEW [Ko97], both built around the coupled channels code ECIS96 [Ra94]. The energy dependence of the optical model parameters is as described in [Ko98]. This optical potential was used for the calculation, with ECIS96, of neutron transmission coefficients and DWBA cross sections for the entire energy region above 20 MeV. Due to the lack of proton elastic scattering data in numerical form, we used a combination of global optical models for the proton channel. The Becchetti-Greenlees potential [Be69]was adopted below 47 MeV, and the non-relativistic version of the Madland potential [Ma88] above 47 MeV. At this particular energy point the two potentials join smoothly. For deuterons, the Lohr-Haeberli global potential [Lo74] was used; for alpha particles the Moyen potential (MacFadden-Satchler [Ma66]) was used; and for tritons the Becchetti-Greenlees potential [Be71] was used. The He-3 channel was ignored, due to its small importance. Following Delaroche et al. [De82], we adopted the weak-coupling model for direct collective inelastic scattering for Cu-65, using Ni-64 as a basis. For the calculation of the cross sections, ECIS96 was used in DWBA mode. We used the following direct transitions for Cu-65 (ground state 3/2- ) : Jpi Ex(MeV) Deformation length (Delta) or parameter (Beta) 0.5- 0.771 Beta(2)=0.0566 2.5- 1.116 Beta(2)=0.0980 3.5- 1.481 Beta(2)=0.1132 1.5- 1.743 Beta(2)=0.0800 1.5- 3.185 Delta(3)=0.3167 2.5- 3.435 Delta(3)=0.3879 3.5- 3.685 Delta(3)=0.4479 4.5- 3.935 Delta(3)=0.5008 Only one measurement exists for neutron-induced emission spectra above 20 MeV for 65Cu: the 25.7 MeV (n,xn) data by Marcinkowski et al (Ma83). Without adjusting any of the level density or pre- equilibrium parameters the GNASH calculation was in good agreement with these data (Ko98b). Hence we adopted these parameters for the whole energy region. **************************************************************** REFERENCES [Ab93] W. Abfalterer, R.W. Finlay, S.M. Grimes, and V. Mishra, Phys.Rev. C47, 1033 (1993) [Al83] R. Alarcon and J. Rapaport, Nucl.Phys. A458, 502 (1986) [Ar80] E.D. Arthur and P.G. Young, 'Evaluation of Neutron Cross Sections to 40 MeV for 54,56Fe," Proc. Sym. on Neutron Cross Sections from 10 to 50 MeV, 12-14 May 1980, Brookhaven National Laboratory [Eds. M. R. Bhat and S. Pearlstein, BNL-NCS- 51245, 1980] p. 731. [Be69] F.D. Becchetti, Jr., and G.W. Greenlees, Phys.Rev. 182, 1190 (1969) [Be71] F.D. Becchetti, Jr., and G.W. Greenlees in "Polarization Phenomena in Nuclear Reactions," (Ed: H.H. Barschall and W. Haeberli, The University of Wisconsin Press, 1971) p.682. [Be92] O. Bersillon, "SCAT2 - A Spherical Optical Model Code," in Proc. ICTP Workshop on Computation and Analysis of Nuclear data Relevant to Nuclear Energy and Safety, February-March, 1999 Trieste, Italy, to be published in World Scientific Press, and Progress Report of the Nuclear Physics Division, Bruyeres- le-Chatel 1977, CEA-N-2037 (1978) p.111 [Br50] S. Bratenahl, S. Fernbach, R.H. Hildebrand et al., Phys.Rev. 77, 597 (1950) [Ch93] M.B. Chadwick and P.G. Young, Phys.Rev. C 47, 2255 (1993) [Ch96] M.B. Chadwick, P.G. Young, R.E. MacFarlane, and A.J. Koning, "High-Energy Nuclear Data Libraries for Accelerator- Driven Technologies: Calculational Method for Heavy Recoils," Proc. of 2nd Int. Conf. on Accelerator Driven Transmutation Technology and Applications, Kalmar, Sweden, 3-7 June 1996 [Ch98] M.B. Chadwick and P.G. Young, "GNASH Calculations of n,p + Cu isotopes and Benchmarking of Results" in APT PROGRESS REPORT: 1 February - 1 March 1998, internal Los Alamos National Laboratory memo, 6 Mar.1998 from R.E. MacFarlane to L. Waters. [Ch99] M.B. Chadwick, P G. Young, G. M. Hale, et al., Los Alamos National Laboratory report, LA-UR-99-1222 (1999) [Co67] J.L. Cook, H. Ferguson, and A.R. DeL Musgrove, Aust.J. Phys. 20, 477 (1967) [De82] J.P. Delaroche, S.M. El-Kadi, P.P. Guss, C.E. Floyd and R.L. Walter, Nucl. Phys. A390, 541 (1982). [El82] S.M. El-Kadi, C.E. Nelson, F.O. Purser et al., Nucl.Phys. A390, 509 (1982) [Fi93] R. W. Finlay, W. P. Abfalterer, G. Fink et al., Phys. Rev C 47, 237 (1993) [Fr01] S.C. Frankle, R.C. Reedy, and P.G. Young, Los ALamos National Laboratory Report, LA-13812 (2001). [Gu86] P. Guenther, D.L. Smith, A.B. Smith, J.F. Whalen, Nucl. Phys. A448, 280 (1986) [Ig75] A.V. Ignatyuk, G.N. Smirenkin, and A.S. Tishin, Sov.J. Nucl.Phys. 21, 255 (1975); translation of Yad.Fiz. 21, 485 (1975) [Ka77] C. Kalbach, Z.Phys.A 283, 401 (1977) [Ka85] C. Kalbach, Los Alamos National Laboratory report LA-10248-MS (1985) [Ka88] C. Kalbach, Phys.Rev.C 37, 2350 (1988); see also C. Kalbach and F. M. Mann, Phys.Rev.C 23, 112 (1981) [Ki74] W.E. Kinney, F.G. Perey, report ORNL-4908 (1974) [Ko90] J. Kopecky and M. Uhl, Phys.Rev.C 41, 1941 (1990) [Ko97] A.J. Koning, J.J. van Wijk and J.-P. Delaroche, "ECISVIEW: A Graphical Interface for ECIS95", Proceedings of the NEA Specialists' Meeting on the Nucleon Nucleus Optical Model up to 200 MeV, Bruyeres-le-Chatel, November 13-15 1996. Available at http://db.nea.fr/html/science/om200/. [Ko98] A.J. Koning, J.-P. Delaroche and O. Bersillon, "Nuclear Data for Accelerator-Driven Systems: Nuclear models, Experiments and Data Libraries", to appear in Mucl. Instr. Meth. A (1998). [Ko98b] A.J. Koning, M.B. Chadwick, and P.G. Young, "ENDF/B-VI neutron and proton datafiles up to 150 MeV for 63Cu and 65Cu", Los Alamos National Laboratory report LAUR- (1998); ECN lab and JEFF report (1998). [Lo74] J.M. Lohr and W. Haeberli, Nucl.Phys. A232, 381 (1974) [Ma66] Macfadden and Satchler, Nuc.Phys. 84, 177 (1966) [Ma83] A. Marcinkowski, R.W. Finlay, G. Randers-Pehrson et al., Nucl.Phys. A402, 220 (1983) [Ma88] D.G. Madland, "Recent Results in the Development of a Global Medium-Energy Nucleon-Nucleus Optical-Model Potential, "Proc. OECD/NEANDC Specialist's Mtg. on Preequilibrium Nuclear Reactions, Semmering, Austria, 10-12 Feb. 1988, NEANDC-245 'U' (1988). [Pe63] C.M. Perey and F.G. Perey, Phys.Rev. 132, 755 (1963) [Ra94] J. Raynal, Notes on ECIS94, CEA Saclay Report CEA-N-2772 (1994) [Sa60] G.L. Salmon, Nucl.Phys. 21, 15 (1960) [Yo92] P.G. Young, E.D. Arthur, and M.B. Chadwick, report LA-12343-MS (1992) **************************************************************** ENDF/B-VI MOD 3 Revision, March 1991, ORNL MOD 3 changes 1) Corrections to MF=6, MT=63 at 17.5 MeV to prevent negative values in the angular distribution. **************************************************************** * Note there was no MOD 2 released. **************************************************************** ENDF/B-VI MOD 1 Evaluation, November 1989, D. Hetrick, F.Y. Fu, D. Larson (ORNL) This work employed several nuclear model codes including the optical-model code GENOA [1], the Distorted Wave Born Approximation (DWBA) program DWUCK [2], and the Hauser-Feshbach code TNG [3,4]. The TNG code provides energy and angular distributions of particles emitted in the compound and pre- compound reactions, ensures consistency among all reactions, and maintains energy balance. Details pertinent to the contents of this evaluation and extensive comparisons of calculations with experimental data can be found in reference [5]. ----- DESCRIPTION OF FILES (MF-MT) 1-451 GENERAL INFORMATION, REFERENCES, AND DEFINITIONS. 2-151 RESONANCE PARAMETERS WERE TAKEN FROM MUGHABGHAB [6]. POINT WISE RECONSTRUCTION COMPARED WITH DATA [7] SHOWED POORER FIT ABOVE 100 KEV, SO THE RESONANCE REGION WAS CUT OFF AT 99.5 KEV. REICH-MOORE PARAMETERS ARE GIVEN. AGREEMENT WITH DATA COULD BE IMPROVED WITH ADDITION OF A BACKGROUND FILE IN 3/1, BUT THIS IN GENERAL GIVES TOO LARGE AN AVERAGE CROSS SECTION, WHEN BINNED IN 10 KEV BINS AND COMPARED WITH THE BINNED DATA. THIS IS PROBABLY DUE TO TOO LARGE AN ESTIMATE OF NEUTRON WIDTHS FOR RESONANCES SEEN ONLY IN CAPTURE AND NOT IN TRANSMISSION. NOTE THAT THE FLAG HAS BEEN SET TO ALLOW USER CALCULATION OF THE ANGULAR DISTRIBUTIONS FROM THE R-M RESONANCE PARAMETERS, IF THE USER WANTS ANGULAR DISTRIBUTIONS ON A FINER ENERGY GRID THAN GIVEN IN 4/2. 3-1 THE TOTAL CROSS SECTION IS GIVEN BY RESONANCE PARAMETERS FROM 1.E-5 EV TO 99.5 KEV. THE THERMAL CROSS SECTION (16.3B) IS REPRODUCED. A SMALL CONTRIBUTION FROM 3/102 IS REQUIRED FROM 60 TO 99.5 KEV, WHICH WHEN ADDED TO 2/151 REPRODUCES THE CAPTURE DATA. FROM 99.5 KEV TO 1.12 MEV CU65 DATA FROM [7] IS USED, AFTER APPROPRIATE AVERAGING. ABOVE THIS, NO ISOTOPIC DATA IS AVAILABLE. FROM 1.12 TO 4.0 MEV, NAT CU DATA OF PEREY [8] USED IN V5 IS RETAINED. FROM 4.0 TO 20 MEV, NAT CU DATA OF LARSON ET.AL [9] IS AVERAGED AND USED. COMPARISONS FROM 1.2 TO 4.5 MEV WITH AVERAGED ARGONNE DATA FOR NAT CU [10] SHOW 1% AGREEMENT. LARSON'S DATA ABOVE 10 MEV WERE ADJUSTED SLIGHTLY (<2 %) TO FIT 65CU DATA OF DYUMIN ET AL. [11]. 3-2 ELASTIC SCATTERING CROSS SECTIONS WERE OBTAINED BY SUBTRACTING THE NONELASTIC FROM THE TOTAL. THE THERMAL VALUE OF 14.1B IS REPRODUCED. 3-3 NONELASTIC CROSS SECTION; SUM OF 3-4, 3-16, 3-22, 3-28, 3-102, 3-103, 3-104, 3-105, 3-106, AND 3-107. 3-4 TOTAL INELASTIC CROSS SECTION; SUM OF 3-51, 3-52, .. .., 3-63, AND 3-91 3-16 (N,2N) CROSS SECTIONS WERE TAKEN FROM THE GLUCS [12] CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS SECTIONS [13]. 3-22 (N,NA) CROSS SECTIONS WERE CALCULATED BY THE TNG CODE [3,4,5] WHICH AGREES WELL WITH AVAILABLE DATA [5]. 3-28 (N,NP) CROSS SECTIONS WERE CALCULATED BY THE TNG CODE [3,4,5]. DATA ARE SCARCE FOR THIS REACTION [5]. 3-51 TO 3-63 INELASTIC SCATTERING EXCITING LEVELS; RESULTS ARE FROM TNG [3,4,5] WHICH INCLUDES DIRECT INTERACTION CROSS SECTIONS FROM DWUCK [2] CALCULATIONS. EXTENSIVE COMPARISONS WITH EXPERIMENTAL DATA USED IN THE EVALUATION PROCESS ARE SHOWN IN [5]. 3-91 INELASTIC SCATTERING EXCITING THE CONTINUUM (TNG CALCULATED). GUIDANCE FROM (N,XN) EMISSION DATA [5]. 3-102 (N,G) CAPTURE CROSS SECTION IS OBTAINED FROM RESONANCE PARAMETERS FROM 1.E-5 EV TO 99.5 KEV. A SMALL BACKGROUND IS GIVEN HERE, WHICH WHEN ADDED TO THE RESONANCE CONTRIBUTION REPRODUCES EXPERIMENTAL DATA, INCLUDING THE THERMAL VALUE OF 2.17B. FROM 99.5 KEV TO 20 MEV, DATA FROM THE CSISRS LIBRARY [14] WERE USED TO CONSTRUCT AN AVERAGE CURVE THROUGH THE DATA; RESULTS ARE SIMILAR TO EYE GUIDE IN REF [15]. 3-103 (N,P) CROSS SECTIONS WERE CALCULATED BY THE TNG CODE [3,4,5] WHICH AGREES WELL WITH MEASURED DATA [5]. 3-104 (N,D) CROSS SECTION - SHAPE OF (N,P) CROSS SECTION USED NORMALIZED TO AVAILABLE DATA [5]. 3-105 (N,T) CROSS SECTION - SHAPE OF (N,P) CROSS SECTION USED NORMALIZED TO SYSTEMATICS OF QAIM AND STOCKLIN [16] AT 14.6 MEV. 3-106 (N,3HE) CROSS SECTION - SHAPE OF (N,A) CROSS SECTION USED NORMALIZED TO AVAILABLE DATA [17]. 3-107 (N,A) CROSS SECTIONS WERE CALCULATED BY THE TNG CODE [3,4,5]. DATA ARE SCARCE AND DISCREPANT FOR THIS REACTION [5]. 4-2 ANGULAR DISTRIBUTIONS OF SECONDARY NEUTRONS GIVEN FOR ELASTIC SCATTERING ARE RESULTS OF FITTING DATA WITH GENOA. IF DESIRED, ANGULAR DISTRIBUTIONS CAN BE CALCULATED BY THE USER ON A FINER ENERGY GRID FROM THE R-M RESONANCE PARAMETERS IN 2/151. 6-16 (N,2N) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 64CU RESIDUAL, AND ENERGY DEPENDENT YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR THE OUTGOING NEUTRON). (N,XN) AND (N,XG) D-D EMISSION DATA HEAVILY USED TO BENCHMARK THE TNG CALCULATIONS [5]. 6-22 (N,NA) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON, ALPHA, AND 61CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR THE OUTGOING NEUTRON). (N,XA) AND (N,XG) D-D EMISSION DATA HEAVILY USED TO BENCHMARK THE TNG CALCULATIONS [5]. 6-28 (N,NP) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 64NI RESIDUAL, AND ENERGY DEPENDENT YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH PRODUCT (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR THE OUTGOING NEUTRON). (N,XP) AND (N,XG) D-D EMISSION DATA USED TO BENCHMARK THE TNG CALCULATIONS [5]. 6-51 THROUGH 6-63 INELASTIC SCATTERING EXCITING LEVELS; EACH SECTION INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 65CU RESIDUAL; ANGULAR DISTRIBUTIONS ARE GIVEN FOR THE OUTGOING NEUTRON (LEGENDRE COEFFICIENTS COMPUTED BY DWUCK [2] AND TNG [3,4,5]). COMPARISONS WITH ANGULAR DISTRIBUTION DATA ARE GIVEN IN [5]. 6-91 INELASTIC SCATTERING EXCITING THE CONTINUUM; INCLUDES SIMPLE CONSTANT YIELDS FOR THE NEUTRON AND 65CU RESIDUAL AND ENERGY DEPENDENT YIELD BASED ON TNG CALCULATED GAMMA-RAY SPECTRA FOR THE GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH (ANGULAR DISTRIBUTIONS ARE GIVEN ONLY FOR THE OUTGOING NEUTRON). (N,XN) AND (N,XG) D-D EMISSION DATA RELIED UPON TO BENCHMARK THE TNG CALCULATIONS [5]. 6-103 (N,P) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR P AND 65NI RESIDUAL, AND ENERGY DEPENDENT YIELD BASED ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH PRODUCT. (N,XP) AND (N,XG) D-D EMISSION DATA USED TO BENCHMARK THE TNG CALCULATIONS [5]. 6-107 (N,A) REACTION; INCLUDES SIMPLE CONSTANT YIELDS FOR A AND 62CO RESIDUAL, AND ENERGY DEPENDENT YIELD BASED ON CALCULATED GAMMA-RAY SPECTRA FOR GAMMA RAY; CALCULATED NORMALIZED DISTRIBUTIONS ARE GIVEN FOR EACH PRODUCT. (N,XA) AND (N,XG) D-D EMISSION DATA USED TO BENCHMARK THE TNG CALCULATIONS [5]. 12-51 THROUGH 12-63 BRANCHING RATIOS FOR THE LEVELS, COMPILED BY HETRICK ET AL. [5] ARE GIVEN. 12-102 (N,G) CAPTURE; THERMAL VALUES TAKEN FROM DELFINI ET AL. [18]. HIGHER-ENERGY VALUES BASED ON TNG CALCULATIONS USING PRIMARY BRANCHING RATIOS OF DELFINI ET AL. FOR S-WAVES 14-51 THROUGH 14-63 GAMMA RAY ANGULAR DISTRIBUTIONS ASSUMED TO BE ISOTROPIC. 14-102 (N,G) CAPTURE; ISOTROPIC DISTRIBUTIONS ASSUMED 15-102 (N,G) CAPTURE; AS IN 12-102 -------------------------------------------------------------- UNCERTAINTY FILES ALL NON-DERIVED FILES CONTAIN AN LB=8 COMPONENT, AS REQUIRED BY ENDF/B-VI FORMATS 33-1 TOTAL UNCERTAINTIES GIVEN AS DERIVED FROM 1E-5 TO 200 EV EXPLICIT FROM 200 EV TO 20 MEV, USING LB=0,1 AND 8. 33-2 EXPLICIT FROM 1E-5 T0 200 EV, DERIVED FROM 200EV TO 20 MEV 33-3 DERIVED FROM 1.E-5 TO 99.5 KEV, EXPLICIT USING LB=1,8 FROM 99.5 KEV TO 20 MEV. 33-4 DERIVED FROM THRESHOLD TO 20 MEV. 33-16 (N,2N) COVARIANCES WERE TAKEN FROM THE GLUCS [12] CALCULATION IN WHICH THIS REACTION WAS STUDIED SIMUL- TANEOUSLY WITH 12 OTHER DOSIMETRY REACTION CROSS SECTIONS [13]. 33-22 (N,NA) UNCERTAINTIES ESTIMATED FROM TNG AND DATA. 33-28 (N,NP) COVARIANCES ESTIMATED FROM TNG AND DATA. 33-51-91 INELASTIC SCATTERING UNCERTAINTIES ESTIMATED FROM DATA AND CALCULATIONS. 33-102 CAPTURE UNCERTAINTIES ESTIMATED FROM THERMAL VALUE AT LOW ENERGIES, BINNED DATA IN THE RESONANCE REGION, AND CSISRS DATA [5,14,15] FROM 99.5 KEV TO 20 MEV. 33-103 (N,P) COVARIANCES - ESTIMATED USING CSISRS DATA AS GUIDE. 33-104 (N,D) COVARIANCES - ESTIMATED, BASED ON DATA. 33-105 (N,T) COVARIANCES - ESTIMATED. 33-106 (N,3HE) COVARIANCES - ESTIMATED, BASED ON DATA. 33-107 (N,A) COVARIANCES WERE ESTIMATED BASED ON TNG AND DATA. **************************************************************** REFERENCES: [1] F.G. Perey, computer code GENOA, ORNL, unpublished (1967) [2] P.D. Kunz, "Distorted Wave Code DWUCK72," Univ. of Colorado, unpublished (1972) [3] C.Y. Fu, report ORNL/TM-7042 (1980); also, C.Y Fu, Symp. on Neutron Cross Sections from 10 to 50 MeV, Upton, NY, May 1980, Brookhaven National Lab. report BNL-NCS-51245 (1980) p.675 [4] K. Shibata and C.Y. Fu, report ORNL/TM-10093 (1986) [5] D.M. Hetrick, C.Y. Fu, and D.C. Larson, Oak Ridge report ORNL/TM-9083 [ENDF-337] (1984) [6] S.F. Mughabghab, M. Divadeenam, and N.E. Holden, "Neutron Cross Sections, Vol. 1, Neutron Resonance Parameters and Thermal Cross Sections, Part A, Z=1-60," (Academic Press, 1981) [7] M.S. Pandey, J.B. Garg and J.A. Harvey, Phys.Rev. C 15, 600 (1977), and private communication. [8] F.G. Perey, private communication (1977) [9] D.C. Larson, Symp. on Neutron Cross Sections from 10 to 50 MeV, Upton, NY, May 1980, Brookhaven National Lab. report BNL-NCS-51245 (1980) p.277 [10] P. Guenther, D.L. Smith, A.B. Smith and J.F. Whalen, Nucl. Phys. A, 448, 280 (1986) [CSISRS data set 12869/002], and W.P. Poenitz and J.F. Whalen, Argonne report ANL/NDM-80 (1983) [CSISRS data set 12853] [11] A.I. Dyumin, D.M. Kaminker, G.N. Popova, and V.A. Smolin, Izv.Akad.Nauk SSSR, Ser.Fiz. 36, 852 (1972) [12] D.M. Hetrick and C.Y. Fu, Oak Ridge report ORNL/TM-7341 [ENDF-303] (1980) [13] C.Y. Fu and D.M. Hetrick, Proc. Fourth ASTM-Euratom Symp. on Reactor Dosimetry, Gaithersburg, Maryland, March 22-26, 1982 (U.S. National Bureau of Standards) p.877 [14] CSISRS Library, National Nuclear Data Center, Brookhaven National Laboratory, Upton, N.Y. 11973. [15] V. McLane, C.L. Dunford and P.F. Rose, "Neutron Cross Sections, Vol. 2, Neutron Cross Section Curves" (Academic Press, 1988) [16] S.M. Qaim and G. Stoecklin, Nucl.Phys. A257, 233 (1976) [17] S.M. Qaim, Radiochimica Acta, 25, 13 (1978) [18] M.G. Delfini, J. Kopecky, R.E. Chrien et al., Nucl.Phys. A404, 250 (1983) ************************ C O N T E N T S *********************** 1 451 596 5 2 151 184 1 3 1 1018 4 3 2 1017 4 3 3 82 4 3 4 19 1 3 5 55 4 3 16 11 1 3 22 7 1 3 28 8 1 3 51 15 1 3 52 14 1 3 53 13 1 3 54 13 1 3 55 13 1 3 56 13 1 3 57 13 1 3 58 13 1 3 59 12 1 3 60 12 1 3 61 12 1 3 62 12 1 3 63 12 1 3 91 12 1 3 102 12 5 3 103 13 1 3 104 8 1 3 105 7 1 3 106 7 1 3 107 11 1 4 2 891 4 6 5 13168 4 6 16 415 1 6 22 435 1 6 28 534 1 6 51 47 1 6 52 44 1 6 53 44 1 6 54 44 1 6 55 7 1 6 56 7 1 6 57 7 1 6 58 7 1 6 59 7 1 6 60 7 1 6 61 7 1 6 62 7 1 6 63 41 3 6 91 1547 1 6 103 934 1 6 107 782 1 12 51 3 1 12 52 3 1 12 53 3 1 12 54 3 1 12 55 3 1 12 56 3 1 12 57 4 1 12 58 3 1 12 59 3 1 12 60 3 1 12 61 3 1 12 62 3 1 12 63 3 1 12 102 1709 5 14 51 1 1 14 52 1 1 14 53 1 1 14 54 1 1 14 55 1 1 14 56 1 1 14 57 1 1 14 58 1 1 14 59 1 1 14 60 1 1 14 61 1 1 14 62 1 1 14 63 1 1 14 102 1 5 15 102 88 1 33 1 20 1 33 2 14 1 33 3 18 1 33 4 10 1 33 16 63 1 33 22 14 1 33 28 14 1 33 51 12 1 33 52 12 1 33 53 12 1 33 54 12 1 33 55 12 1 33 56 12 1 33 57 12 1 33 58 12 1 33 59 12 1 33 60 12 1 33 61 12 1 33 62 12 1 33 63 12 1 33 91 12 1 33 102 17 1 33 103 14 1 33 104 12 1 33 105 10 1 33 106 10 1 33 107 18 1