9-F - 19 JAERI EVAL-JUL89 T.SUGI DIST-DEC21 20090828 ----JENDL-5 MATERIAL 925 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-10 (MF,MT)=(4,2),(4,51),(4,52) are replaced by preliminary results of R-matrix analysis with AMUR up to 1.0 MeV (S.Kunieda) 21-11 revised by O.Iwamoto (MF8/MT4,16,22,28,32,102-105,107) added 21-11 above 20 MeV, JENDL-4.0/HE merged by O.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto ****************************************************** * * * --- JENDL-5.0 --- * * * * Incident neutron data up to 200 MeV * * * ****************************************************** Data evaulation was performed with an R-matrix code AMUR/1,2/ up to 1.0 MeV MeV. Experimental data fitted are as follows. (n,tot) : Larson+ (1976)/3/, CS (n,n1),(n,n2) : Lashuk+ (1994)/4/, CS (n,n1+n2) : Broder+ (1969)/5/, CS (n,n0+n1+n2) : Elwyn+ (1964)/6/, DA (n,g) : Gabbard+ (1959)/7/, CS (n,g) : Egorov+ (2005)/8/ at 0.0280 eV, CS However, the analysis was still preliminary as it was difficult to reproduce some of the cross-section measurements. Therefore, S.K. decided to adopt only the angular distribution of (n,n0), (n,n1),(n,n2) which shows better agreements with Elwyn+ than those in the previous files. References 1) S.Kunieda+, Nucl. Data Sheets 118:250 (2014). 2) S.Kunieda+, Nucl. Data Sheets 123:159 (2015). 3) Larson+, ORNL Tech. Report 5612 (1976). 4) Lashuk+, taken from EXFOR (1994). 5) Broder+, Technical Report, Obninsk 155 (1969). 6) Elwyn+, Nucl. Phys. 59:113 (1964). 7) Gabbard+, Phys Rev. 114:201 (1959). 8) Egorov+, NIM A 545:296 (2005). ################################################## ### Descriptive texts of previous data ### ################################################## ****************************************************************** Descriptive data (E > 20 MeV) ****************************************************************** ****************************************************** --- JENDL-4.0/HE --- High-energy Evaluation up to 200 MeV ****************************************************** History 2015-03 Compiled by S.Kunieda Above 20 MeV : taken from JENDL High-energy File 2007 /1/. Below 20 MeV : taken from JENDL-4.0 /2/. References 1) Watanabe,Y. et al.: J. Korean Phys. Soc., 59, 1443 (2011). 2) Shibata,K. et al.: J. Nucl. Sci. Technol., 48, 1 (2011). ___________( Comments from JENDL High-energy File 2007 )__________ ************************************************** * * * JENDL-HE HIGH ENERGY FILE * * * ************************************************** NEUTRON EVALUATION UP TO 3 GEV USING GNASH-ECN AND JAM CODES K. Kosako __________________________________________________________________ In the evaluation of high-energy region, different theoretical model codes were used in accordance with incident energies: (I) intermediate energies up to 250 MeV, and (II) high energies above 150 MeV. A major code used in (I) was the GNASH code [1] based on statistical Hauser-Feshbach plus preequilibrium models. Optical model calculations were performed using the ECIS96 code [2], in which a spherical optical potential was used and the parameters were adjusted so as to reproduce experimental data. This code was also employed for DWBA calculation of direct inelastic scattering cross sections. Experimental data for both neutrons and protons were reproduced well by these calculations. Thus, the calculated results were adopted as the evaluated values of total cross sections, elastic and inelastic scattering cross sections, and total reaction cross sections up to 250 MeV. Transmission coefficients obtained by the optical model calculation were used in GNASH calculations of particle and gamma ray emission cross sections and isotope production cross sections up to 250 MeV. Elastic cross sections and angular distributions refered the result by the TOTELA code [3] based on systematics. In (II), the high energy nuclear reaction code JAM [4] plus statistical decay model (GEM) [5] was employed. Also, the TOTELA code was employed as a tool for evaluation of total, elastic, and proton reaction cross-sections. Gamma-ray energy spectra were calculated with ALICE-F code [6] and angular distributions were assumed to be isotropic. References [1] P.G. Young et al., LA-12343-MS, LANL (1992). [2] J. Raynal, IAEA SMR-9/8, p281 (1970). [3] T. Fukahori and K. Niita, INDC(NDS)-416. [4] Y. Nara, et al., Phys. Rev. C61, 024901 (1999). [5] S. Furihata, Nucl. Instr. and Meth. B171, p251 (2000). [6] T. Fukahori, JAERI-M 92-039, p114 (1992). __________________________________________________________________ ****************************************************************** Descriptive data (E < 20 MeV) ****************************************************************** ---------------------------------------- (MF,MT)=(4,2),(4,51),(4,52) were repalced by results of preliminar R-matrix analysis with AMUR up to 1 MeV 2021.10.06 S.Kunieda ---------------------------------------- =========================================================== The data were taken from JENDL-3.3. =========================================================== HISTORY 83-11 Evaluation for JENDL-2 was performed by Sugi and Nishimura (jaeri)/1/. 89-07 Resonance parameters and total cross section were re-evaluated for JENDL-3. 89-07 Compiled by T. Narita (jaeri). 94-06 JENDL-3.2. Gamma prodction data modified by T.Asami (Data Eng.). Other data were mainly adopted from JENDL fusion file. Compiled by T.Nakagawa (ndc/jaeri) ***** Modified parts for JENDL-3.2 ******************** (3,2), (3,4), (3,22), (3,28), (3,52-91), (3,104), (3,251) All angular distributions All energy distributions New evaluation fot gamma-ray production data *********************************************************** ------------------------------------------------------------- JENDL fusion file /2/ (as of Jun. 1994) Evaluated and compiled by S.Chiba (ndc/jaeri). The calculations have been carried out with the sincros-II code system (dwucky, egnash and casthy2y) /3/. the following set of omps were selected: n : Yamamuro (modified Walter-Guss) /3/ p : Perey and Walter-Guss combined /4/ d : Lohr-Haeberli /5/ t : Becchetti-Greenlees /6/ he-3 : Becchetti-Greenlees /6/ alpha : Lemos set modified by Arthur-Young /7/ The following values of level density parameters (1/MeV) were used to reproduce the ddx at 14 MeV: F-20 F-19 F-18 O-19 O-18 O-17 N-17 N-16 N-15 N-14 C-15 C-14 4.49 3.50 2.50 2.50 3.00 2.99 3.51 2.00 2.00 2.03 2.84 2.46 The data were taken from JENDL-3.1 except for the following: mf=3, mt= 2: adjusted to conserve the total c.s. mf=3, mt= 3: calculated as a sum of reaction c.s. mf=3, mt= 4: calcaulated as a sum of inelastic c.s. mf=3, mt=22, 28, 32, 91 : taken from the sincros-II calculation mf=3, mt=52: replaced by the sincros-II calculation above 2.5 mev mf=3, mt=53-60: replaced by the sincros-II calculation mf=3, mt=203,204,205,207: taken from the sincros-II calc. mf=4, mt= 2: repalced by the sincros-II calculation mf=6, mt=22, 28, 32, 91 : taken from the sincros-II calculation. Kumabe's systematics was used. mf=6, mt=203,204,205,207: taken from the sincros-II calculation. Kalbach's systematics was used. ------------------------------------------------------------- 00-10 JENDL-3.3 Compiled by K.Shibata (jaeri). ***** Modified parts for JENDL-3.3 ************************ (1,451) Updated. (3,203-207) Calculated. (3,251) Deleted. (4,2) Transformation matrix deleted. (4,16-28) Deleted. (5,16-28) Deleted. (6,16-28) Taken from JENDL fusion file. (6,203-207) Taken from JENDL fusion file. ************************************************************ mf=1 General information mt=451 Descriptive data and dictionary mf=2 Resonance parameters mt=151 Resolved resonance parameters : 1.0e-5 eV - 100 keV The multi-level Breit-Wigner formula was used. Res. energies and gam-n : The first two levels were based on Johnson et al. /8/. The 3rd and 4th levels were adjusted so as to fit to the experimental data of Larson et al./9/ Gam-g : The first three levels were based on Macklin and Winters /10/. The 4th level was adjusted so as to fit to the recommended thermal capture cross section of Mughabghab et al./11/. Scattering radius: 5.525 fm calculated 2200-m/s cross sections and res. integrals. 2200 m/s res. integ. elastic 3.643 b - capture 9.6 milli-b 19.5 milli-b total 3.652 b - mf=3 Neutron cross sections mt=1 Total cross section Below 100 keV: no background. Above 100 keV: based on the experimental data of Larson et al./9/ mt=2 Elastic scattering cross section Derived by subtracting the nonelastic cross section from the total cross section. mt=4 Total inelastic scattering cross section Sum of mt=51-60,91. mt=16 (n,2n) cross section Calculated by fitting the Pearlstein's function /12/ to the experimental data. mt=22 (n,n' alpha) and (n,alpha n') cross sections Calculated by the sincros-II code system. mt=28 (n,n' p) and (n,p n') cross sections Calculated by the sincros-II code system. mt=32 (n,n'd) cross secton Calculated by the sincros-II code system. mt=51-60 Inelastic scattering cross sections mt=51 (taken from JENDL-3.1) Up to 1 MeV : based on the experimental data of Broder et al. /13/. 1 MeV - 5.5 MeV : calculated with the Hauser-Feshbach method (eliese-3 /14/) taking into account (n,alpha) and (n,p) as competing processes. The level scheme of F-19, N-16 and O-19 was taken from Ajzenberg-Selove /15,16/. The optical potential parameters are : V = 51.56 - 1.492*E (MeV), Ws = 11.82 (MeV), Vso= 10.0 (MeV), r0 = rs = rso = 1.31 (fm), a = aso = 0.66 (fm), b = 0.47 (fm). The level density parameter of 3.609 (1/MeV)/17/ and pairing energy of 2.52 MeV /18/ were used. mt=52 Up to 2.5 MeV: taken from JENDL-3.1, which is based on the data of Broder et al. /13/. Above 2.5 MeV: calculated by the sincros-II code system. mt=53 - 60 Calculated by the sincros-II code system. The sincros-II calculation adopted the following discrete levels. The levels with L and Beta-L include the contribution of direct inelastic scattering, which was calculated assuming the weak-coupling model by the DWBA method: ---------------------------------------------- mt ex(MeV) spin-parity L beta-L ---------------------------------------------- 2 0.0 1/2+ 51 0.1099 1/2- 52 0.1972 5/2+ 2 0.4 53 1.3457 5/2- 54 1.4585 3/2- 55 1.5541 3/2+ 2 0.6 56 2.7798 9/2+ 4 0.4 57 3.9071 3/2+ 58 3.9985 7/2- 59 4.0325 9/2- 60 4.3777 7/2+ 4 0.4 ---------------------------------------------- mt=91 Inelastic to continuum Calculated with sincros-II code system. mt=102 Capture cross section Below 100 keV : no background. 100 keV - 1.87 MeV : based on the experimental data of Gabbard et al. /19/. 1.87 MeV - 20 MeV : assumed to decrease with 1/v law. mt=103 (n,p) cross section Up to 9 MeV : based on the experimental data of Bass et al. /20/. 9 MeV - 20 MeV : calculated with the statistical model by using Pearlstein' empirical formula. mt=104 (n,d) cross section Calculated by the sincros-II code system. mt=105 (n,t) cross section Calculated by the sincros-II code system. mt=107 (n,alpha) cross section Below 9 MeV, based on the following experimental data: Up to 4MeV Davis et al. /21/, 4MeV - 5.5MeV Smith et al. /22/, 5.5MeV - 9MeV Bass et al. /20/. Above 9 MeV, calculated with the Pearlstein's formula. mt=203 Total proton production Sum of mt=28 and 103. mt=204 Total deuteron production Sum of mt=32 and 104. mt=205 Total triton production Equal to mt=105. mt=207 Total alpha production Sum of mt=22 and 107. mf=4 Angular distributions of secondary neutrons mt=2 Calculated with optical model by the sincros-II code system. mt=51-60 Calculated by the sincros-II code system. mf=6 Energy-angle distributions of secondary particles mt=16,22,28,32,91 Calculated usingt the sincros-II code system and Kumabe's systematics /23/. mt=203,204,205,207 Based on Kalbach's systematics/24/. mf=12 Photon production multiplicities mt=51-60, 102, 103, 107 Calculated with the gnash code /7/. mf=13 Photon production cross sections mt=3 Calculated with the gnash code/7/. mf=14 Photon angular distributions mt=3,51-60,102,103,107 Isotropic mf=15 Photon energy distributions mt=3,102,103.107 Calculated with the gnash code/7/. References 1) Sugi T. and Nishimura K.: JAERI-M 7253 (1977), English trans- lation : ORNL-TR-4605. 2) Chiba, S. et al.: JAERI-M 92-027, p.35(1992). 3) Yamamuro, N.: JAERI-M 90-006 (1990). 4) Walter, R.L. and Guss, P.P.: Int. Conf. on Nucl. Data for Basic and Applied Science, Santa Fe, p.1079 (1986). 5) Lohr, J.M. and Haeberli, W.: Nucl. Phys. A232, 381 (1974). 6) Becchetti, F.D. and Greenlees, G.W.: "Polarization Phenomena in Nuclear Reactions", Univ. of Wisconsin Press, p.682 (1971). 7) Arthur, E.D. and Young, P.G.: LA-8626-MS (1980). 8) Johnson C.H. et al.: ORNL-5025 (1975). 9) Larson D.C. et al.: ORNL/TM-5612 (1976). 10) Macklin R.L. and Winters R.R.: Phys. Rev. C7, 1766 (1973). 11) Mughabghab S.F. et al.: Neutron Cross Sections, Vol.1, Part A, Z=1-60, Academic Press (1981). 12) Pearlstein S.: Nucl. Sci. Eng. 23, 238 (1965). 13) Broder et al.: 70 Helsinki Conf. 2, 295 (1970). 14) Igarasi S.: JAERI 1224 (1972). 15) Ajzenberg-Selove F.: Nucl. Phys. A166, 1 (1971). 16) Ajzenberg-Selove F.: Nucl. Phys. A190, 1 (1972). 17) Abdelmalek N.N. and Stavinsky V.S.: Nucl. Phys. 58, 601 (1964) 18) Newton T.D.: Can. J. Phys. 34, 804 (1956). 19) Gabbard F. et al.: Phys. Rev. 114, 201 (1959). 20) Bass R. et al.: EANDC(E) 66-64. 21) Davis E.A. et al.: Nucl. Phys. 27, 448 (1961). 22) Smith D.L. et al.: Phys. Rev. 117, 514 (1960). 23) Kumabe, I. et al.: Nucl. Sci. and Eng., 104, 280 (1990). 24) Kalbach C. : Phys. Rev. C37, 2350(1988).