8-O - 16 JAEA EVAL-DEC19 S.Kunieda DIST-DEC21 20200323 ----JENDL-5 MATERIAL 825 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 19-12 Data are taken from R-matrix analysis with AMUR up to 6 MeV (S.Kunieda & O.Iwamoto) 21-11 revised by O.Iwamoto (MF8/MT4,16,22,28,102-104,107) 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 are taken from R-matrix analysis with AMUR up to 6 MeV/1,2/. New data are the total, elastic scattering and (n,alpha) cross- sections with covariance. They are compiled in (MF,MT)= (3,1),(3,2),(3,107) : Cross sections (4,2) : Angular distribution (33,1),(33,2),(33,107) : Covariance data for cross sections note: (n,alpha) cross-sections are larger than those in the previous library by ~35% due to the unitarity constraint from the R-matrix theory. References 1) S.Kunieda+, Nucl. Data Sheets 118:250 (2014). 2) S.Kunieda+, Nucl. Data Sheets 123:159 (2015). ################################################## ### 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 mEXIFON, ALICE-F, AND JAM CODES T. Murata HISTORY 2003-05 New evaluation was made by T.Murata (AITEL). 2003-10 Compilation was made by T.Fukahori (JAERI) and K.Kosako (SAEI) 2005-05 The DDX of particle production was modified between 20- 150 MeV by T.Murata (AITEL). 2005-06 Compilation was made by K.Kosako (Shimizu Corp.) and T.Fukahori (JAERI). MF=1 General Information MT=451 Description data and dictionary MF=3 Neutron Cross Sections MT=1 Total cross section Total cross section was calculated with ELIESE-3 code/1/ using potential given by Wilmore-Hodgeson/2/ in the incident neutron energy region below 65 MeV, and adjusted to connect smoothly to the cross section of JENDL-3.3 below 20MeV. between 65 MeV and 150 MeV, the cross section was calculeted with JLM model code developed by Chiba/3/. Above 150 MeV,the results of NMTC/ JAM code/4/ calculation were adopted. Calculated cross sections were modified a little to reproduce experimantal cross sections/5/. MT=2 Elastic scattering cross section, MT=3 and MT=5 Non-elastic cross section Elastic scattering cross section and Non-elastic cross section were obtained in the calculations of total cross section men- tioned above. And modified a little to connect smoothly between each energy region. MT=201: Neutron production cross section MT=202: Gamma-ray production cross section MT=203: Proton production cross section MT=204: Deuteron production cross section MT=205: Triton production cross section MT=206: He-3 production cross section MT=207: He-4 production cross section These cross sections were evaluated on the calculated results with a modified EXIFON(mEXIFON)/6/,DWUCK-4/7/ and NMTC/JAM codes and adjusted to reproduce experimental cross sections/8/ and also to connect smoothly to the cross section of JENDL-3.3 at 20 MeV. For some reactions smoothly connection to JENDL-3.3 values was abandoned because of contradiction with the experi- mental data in the present energy region. Gamma-ray production cross section was calculated with ALICE-F code/9/. MF=4 Angular Distributions MT=2: Elastic Scattering Optical model and NMTC/JAM calculations described above,were made for angular distribution of elastic scattering. MF=6 Product Energy-Angle Distributions MT= 5: Isotope Production Cross Section Ratios Production cross section of radio-nuclides, of which half lives are longer than 1 second; Be-7,Be-10,Be-11,C-10,C-11, C-14,N-13,N-16,O-14 and O-15 were evaluated on the calculated results with the above mentioned codes and normalized or adjusted to reproduce experimental data/10/. If no experimen- tal data were available, calculated results were adopted. The ratios of these cross sections to non-elastic cross section (MF=3,MT=5) are given in the file. For emission of neutron,photon,proton,deuteron,triton.He-3 and alpha particle, their energy-angle distributions are given in the laboratory system. Below 150 MeV, continuum energy spectrum of emitted particle in the cm system and ratios of precompoud process were calcu- lated with mEXIFON code and converted to the laboratory system with the systematics of Kalbach/11/. Angular distributions of the particles emitted by the follow- ing direct reaction were calculated with DWUCK-4 code, with parameters determined to reproduce experimental DDX/12/. O16(n,d)N15(Ex=0.0MeV,1/2-) O16(n,d)N15(Ex=6.324MeV,3/2-) O16(n,t)N14(Ex=3.948MeV,1+) These peaks were superimposed on continuum DDX. In the higher energy region, the DDX were calculated with NMTC/JAM code directly. Gamma-ray energy spectrum were calculated with ALICE-F code and angular distributions were assumed to be isotropic. Additional isotope production cross sections below 20 MeV, which were evaluated presently and not included in JENDL-3.3 are given in the following. O16+n, C14 production (eV,barn); 5 incident energy points 1.5539E+07 0.0000E+00 1.7000E+07 0.0000E+00 1.8000E+07 2.4420E-06 1.9000E+07 3.1835E-05 2.0000E+07 1.8380E-04 O16+n, N16 production (eV,barn); 30 incident energy points 1.0244E+07 0.0000E+00 1.1000E+07 0.0000E+00 1.1250E+07 1.6900E-02 1.1500E+07 3.4700E-02 1.1750E+07 7.9400E-02 1.1880E+07 7.9400E-02 1.2000E+07 5.2700E-02 1.2250E+07 2.5100E-02 1.2500E+07 2.4100E-02 1.2750E+07 2.6300E-02 1.3000E+07 3.1900E-02 1.3250E+07 4.0500E-02 1.3500E+07 4.6000E-02 1.3750E+07 4.6000E-02 1.4000E+07 4.3700E-02 1.4250E+07 4.0200E-02 1.4500E+07 3.6900E-02 1.4750E+07 3.5300E-02 1.5000E+07 3.5300E-02 1.5250E+07 3.5000E-02 1.5500E+07 3.3000E-02 1.5750E+07 3.1600E-02 1.6000E+07 3.0800E-02 1.6250E+07 3.0300E-02 1.6500E+07 2.9000E-02 1.7000E+07 2.6400E-02 1.7500E+07 2.5600E-02 1.8000E+07 2.4300E-02 1.9000E+07 2.2700E-02 2.0000E+07 2.2300E-02 O16+n, O15 production (eV,barn); 8 incident energy points 1.6652E+07 0.0000E+00 1.7000E+07 1.5500E-04 1.7500E+07 2.7200E-04 1.8000E+07 4.5000E-04 1.8500E+07 7.1100E-04 1.9000E+07 1.0500E-03 1.9500E+07 1.4900E-03 2.0000E+07 2.1000E-03 References /1/ Igarasi,S.: JAERI 1224 (1972) /2/ Wilmore,D,Hodgson,P.E.: Nucl.Physics.55,673(1964) /3/ Chiba,S.: Private communication /4/ Niita,K.: JAERI-Conf 2000-005(2000),p.98 /5/ Auman,M.et al.: Phys.Rev.C5,1(1972) Measday,D.F.,Palmieri,J.N.: Nucl.Physics.85,129,(1966) /6/ Murata,T.: JAERI-Conf 97-005 (1997),p.286 Kalka,H.: Z.Phys.A341,289(1992) /7/ Kunz,P.D.: Private communication. /8/ Proton; Benck,S.et al.: AD&ND Tables 72,1(1999), Deuteron; Benck,S.et al.: ibid., Triton; Benck,S.et al.: ibid., Shibata,S.et al.: INS-REP.1115(1995), He-3; Nakamura,T.et al.:Proc.ND for Sci.Tech.(Julich),p.714 Alpha; Benck,S.et al.: ibid., Baba,M.et al.: Private communication /9/ Fukahori,T.: JAERI-M 92-039(1992),p.114 /10/ C-14; Imamura,M. et al.: Nucl.Instr.Method B52,595(1990) N-16; DeJuren,J.A. et al.: Phys.Rev.127,1229(1962) O-15; Brill,O.D. et al.: DOC,136(1),55(1981) /11/ Kalbach,C.: Phys.Rev.C37(1988)2350 /12/ Subramanian,T.S. et al.: Phys.Rev.C34,1580(1986), ****************************************************************** Descriptive data (E < 20 MeV) ****************************************************************** HISTORY 83-12 New evaluation for JENDL-3 Sub-working group on evaluation of O-16, Working group on nuclear data for fusion, Japanese Nuclear Data Committee In charge sig-t Y.Nakajima K.Shibata(jaeri) sig-el T.Murata(naig) sig-in S.Tanaka(jaeri) capture T.Asami(jaeri) (n,2n),(n,p),(n,d),(n,alpha) Y.Kanda(kyu) Compilation Evaluated data were compiled by K.Shibata. 84-07 Data of mf=4 (mt=16,91) were revised. Comment was also modified. 87-01 Data of mf=3 (mt=51-64,67), mf=4 (mt=51-55) and mf=5(mt=16) were modified (S.Chiba, jaeri). Comment was also modified. 90-10 mf=5 (except mt=91), mf=12, mt=102 modified. 93-12 Capture and gamma production cross sections were modified. 08-07 Total and elastics scattering cross sections were modified below 3 MeV. The elastic angular distributions were replaced with new R-matrix calculations between 100 keV and 3 MeV. 09-04 The (n,a) cross sections was modified. 09-06 The interpolation of MF/MT=12/102 was changed to 2. ***** modified parts for JENDL-3.2 ****************************** (3,102) Reevaluated by K. Shibata. (3,2),(3,3) Recalculated (12,102) Modified due to energy conservation (12,51;57;62) 510 keV gammas incorporated (13,3) Reevaluated by T. Asami (de) ****************************************************************** ***** modified parts for JENDL Fusion File 96/1/26 ************* (3,102) Calculated by A. Mengoni (enea) (3,2),(3,3) Recalculated ****************************************************************** 2002-1 Compiled by K.Shibata (jaeri) for JENDL-3.3. ***** modified parts for JENDL-3.3 2001/5/23 ******************* (1,451) Modified. (3,1),(3,2) Recalculated (3,16) Corrected The JENDL-3.2 data were ten times larger than the measurement /2/ by mistake. (3,3) Deleted (3,251) Deleted (4,2) Transformation matrices were deleted. (5,22),(5,28) Distributions at threshold were modified. Interpolation was changed to 22. (12,51-107) Calculated. (13,3) Deleted. (14,51-107) Prepared. (15,3) Deleted. (15,51-107) Calculated. (33,1-107) Taken from JENDL-3.2 covariance file except for mt=16. The covariance for mt=16 was revised on the basis of experimental data. (34,2) Taken from JENDL-3.2 covariance file. ****************************************************************** 2009-04 Compiled by K.Shibata (jaea) for JENDL-4 ***** modifications for JENDL-4 2008/07/02 ********************* (1,451) Modified (3,2) R-matrix calculations below 3 MeV (3,1) Re-calculated from partial cross sections (4,2) R-matrix calculations between 100 keV and 3 MeV (3,107) The data were replaced with those of ENDF/B-VII.0 below 6.5 MeV. ****************************************************************** mf=1 General information mt=451 Descriptive data mf=2 Resonance parameters mt=151 Scattering radius only. mf=3 Cross sections Thermal cross sections and resonance integrals at 300 K ---------------------------------------------------------- 0.0253 eV res. integ. (*) (barns) (barns) ---------------------------------------------------------- Total 3.9624E+00 Elastic 3.9646E+00 n,gamma 1.8988E-04 6.7337E-04 ---------------------------------------------------------- (*) Integrated from 0.5 eV to 10 MeV. mt=1 Sig-t Below 3 MeV, the total cross section was calculated with the R-matrix theory. Above 3 MeV, based on the experimental data of Cierjacks et al./1/. ********************************************************* For JENDL-4, data were modified below 3 MeV. See above. ********************************************************* mt=2 Sig-el Below 3 MeV, calculated with the R-matrix theory. Above 3 MeV, the elastic scattering cross section was obtained by subtracting the reaction cross sections from the total cross section. ********************************************************* For JENDL-4, data were modified below 3 MeV. See above. ********************************************************* mt=4 Total inelastic Sum of mt=51 to 91. mt=16 (n,2n) Based on experimental data/2/. mt=51-79,91 Sig-in Shape of the excitation functions was calculated with the statistical model. The optical potential parameters are the following: V = 48.25-0.053E, Ws = 3.0 + 0.25E, Vso = 5.5 (MeV) r = 1.255 , rs = 1.352 , rso = 1.15 (fm) a = 0.536 , b = 0.205 , aso = 0.50 (fm). Level scheme no Energy(MeV) Spin-parity g.s. 0.0 0+ 1 6.0490 0+ 2 6.1300 3- 3 6.9170 2+ 4 7.1169 1- 5 8.8720 2- 6 9.6300 1- 7 9.8470 2+ 8 10.360 4+ 9 10.960 0- 10 11.080 3+ 11 11.100 4+ 12 11.520 2+ 13 11.600 3- 14 12.050 0+ 15 12.440 1- 16 12.530 2- 17 12.800 0- 18 12.970 2- 19 13.020 2+ 20 13.090 1- 21 13.120 3- 22 13.260 3- 23 13.660 1+ 24 13.870 4+ 25 13.980 2- 26 14.030 0+ 27 14.100 3- 28 14.300 4+ 29 14.400 5+ Continuum levels were assumed above 14.4 MeV. Constant temperature of 3.4 MeV was used. For the inelastic scattering to the second and third levels, the (n,n')gamma data of Nordborg et al./3/ and Lundberg et al./4/ below 10 MeV. For mt=51 to 55, the 14 MeV cross sections were normalized to the experimental data/5/-/8/. Cross sections for mt=56-64 and 67 were normalized to reproduce the ddx data at 14 MeV/8/,/9/. mt=102 Capture 1/v curve normalized to the recommended value in the 4th edition of BNL-325 /10/ at 0.0253 eV. Between 1 eV and 1 MeV, model calculations (direct capture and resonance) were performed by A. Mengoni (enea)/28/. Above 1 MeV, a value of 0.1 mb was assumed by considering inverse reaction data. mt=103 (n,p) Based on experimental data/11/-/14/. mt=104 (n,d) Based on the evaluation of Foster, Jr. and Young /15/. mt=107 (n,alpha) Based on experimental data/3/,/16/-/21/. For JENDL-4, the measured (n,a) cross sections, which were coverted from the inverse-reaction data/18,21,32/, were compared with the existing libraries. As a result, it was found that the ENDF/B-VII.0 data reproduce the experimental data fairly well below 6.5 MeV. Therefore, we decided to replace the (n,a) data with those of ENDF/B-VII.0 below 6.5 MeV. Above 6.5 MeV, the cross sections remain unchanged from JENDL-3.3. mf=4 Angular distributions of secondary neutrons mt=2 10e-5 eV to 3 MeV R-matrix calculation 3 MeV to 5 MeV Based on the experimental data of Lister and Sayres /22/. 5 MeV to 9 MeV Multi-level formula/23/. 9 MeV to 15 MeV Based on the experimental data of Glendinning et al./24/ 15 MeV to 20 MeV Calculated with the spherical optical model. The potential parameters are the same as those given in Sig-in. ********************************************************* For JENDL-4, data were modified between 100 keV and 3 MeV. See above. ********************************************************* mt=16 Assumed to be isotropic in the laboratory system. mt=51-79 Calculated with the statistical model. For mt=51, 52 and 55, experimental data/8/ at 14.2 MeV. For mt=53 and 54 ENDF/B-IV was adopted. mt=91 Isotropic distributions in the center of mass system were transformed into the ones in the laboratory system. The formula is given in ref./25/. mf=5 Energy distribution for secondary neutrons mt=16 Evaporation spectrum was assumed. Constant temperature was deduced from the experimental data of Chiba et al. /26/ for Li-7 according to the Sqrt(E/a) law. mt=22,28 Calcualted by GNASH /27/. mt=91 Evaporation spectrum was assumed. Constant temperature of 3.4 MeV was determined from the stair case plotting. mf=12 Photon production multiplicities mt=22,51-55,59,61,63,66-68,103,107 Calculated with GNASH/27/. mt=102 Calculated with CASTHY/29/. Below 280 keV, based on the data measured by Igashira et al./30/ mf=14 Photon angular distributions mt=22,51-55,59,61,63,66-68,102,103,107 Isotropic mf=15 Photon energy distributions mt=22,103,107 Calculated with GNASH/27/. mt=102 Calculated with CASTHY/29/. mf=33 Covariances of cross sections (ref. 31) mt=1 Based on experimental data. A chi-value was 6.53. mt=2 Constructed from mt=1, 16, 22, 28, 51-91, 102, 103, 104, and 107. mt=4 Constructed from mt=51-91. mt=16 Based on experimental data. mt=22 Based on systematics. mt=28 Based on systematics. mt=51-91 The covariances were estimated by using kalman system. A chi-value was 2.45. For mt=52,53, based on experimental data between 7 and 11 MeV. mt=102 Based on experimental data. mt=103 Based on experimental data. mt=104 Based on experimental data. mt=107 Based on experimental data. mf=34 Covariances of angular distributions mt=2 Based on experimental data and model calculations. References 1) Cierjacks,S. et al.: Nucl. Instr. Meth., 169, 185 (1980). 2) Brill,O.D. et al.: Soviet Phys. Doklady, 6, 24 (1961). 3) Nordborg,C. et al.: Nucl. Sci. Eng., 66, 75 (1978). 4) Lundberg,B. et al.: Phys. Scr. 2, 273 (1970). 5) Bauer,R.W. et al.: Nucl. Phys., 47, 241 (1963). 6) McDonald,W.J. et al.: Nucl. Phys., 75, 353 (1966). 7) Meier,D. et al.: EXFOR 20907,007 (1969). 8) Baba,M. et al.: "Nucl. Data for Basic and Applied Science", Santa Fe, 1985, p223. 9) Takahashi,A. et al.: Oktavian report. 10)Mughabghab,S.F. et al.: Neutron Cross Sections Vol.1, Academic Press, 1981. 11)Bormann,N. et al.: First IAEA Conf. Nuclear Data for Reactors, 1 (1967) 225. 12)De Juren,J.A. et al.: Phys. Rev., 127, 1229 (1962). 13)Seeman,K.W. et al.: Bull. Am. Phys. Soc., 6, 237 (1961). 14)Martin,H.C. et al.: Phys. Rev., 93, 498 (1954). 15)Foster,Jr. D.G. and Young P.G.: LA-4780 (1972). 16)Davis,E.A. et al.: Nucl. Phys., 48, 169 (1963). 17)Sick,I. et al.: Helv. Phys. Acta, 41, 573 (1968). 18)Divatita,A.S. et al.: First IAEA Conf. Nuclear Data for Reactors, 1 (1967) 233. 19)Dickens,J.K. et al: Nucl. Sci. Eng., 40, 283 (1970). 20)Oorphan,V.J. et al.: Nucl. Sci. Eng., 42, 352 (1970). 21)Bair,J.K. and Haas,F.X. : Phys. Rev., C7, 1356 (1973). 22)Lister,D. and Sayres A.: Phys. Rev., 143, 745 (1966). 23)Murata,T.: Proc. Int. Conf. Nuclear Data for Science and Technology, Mito, 1988, p.557, (1988). 24)Glendinning, S.G. et al.: Nucl. Sci. Eng., 82, 393 (1982). 25)Nakagawa,T: JAERI-M 84-103 (1984). 26)Chiba, S. et al.: J. Nucl. Sci. Technol., 22, 771 (1985). 27)Young,P.G. and Arthur,E.D.: LA-6947 (1977). 28)Mengoni A.: Private communication (1995). 29)Igarasi S. and Fukahori T.: JAERI 1321 (1991). 30)Igashira M. et al.: private communication (1993). 31)Shibata,K. et al.: JAERI-Research 97-074 (1997). 32)Harissopulos,S. et al.: Phys. Rev., C72, 062801 (2005).