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92-U -233 SAEI+ Eval-MAR00 T.Mutsunobu, T.Kawano DIST-JAN09 20090105 ----JEFF-311 MATERIAL 9222 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT *************************** JEFF-3.1.1 ************************* ** ** ** Original data taken from: JEFF-3.1 Updated ** ** Modification: 4th time group corrected ** ****************************************************************** ***************************** JEFF-3.1 ************************* Original data taken from: JENDL 3.3 + ENDF/B-VI.4 (MF 12-15 From ENDF/B-VI.4) MT=458(ENERGY RELEASE IN FISSION) evaluation from ENDF/B-VI.4 25/05/05 (NEA/OECD)the 4th time group has been corrected: from 1.330420-2 to 1.330420-1 05/01 NEA/OECD (Rugama) 8 delayed neutron groups Jefdoc-976(Spriggs,Campbel and Piksaikin,Prg Nucl Eng 41,223(2002) **************************** JENDL 3.3 *************************** HISTORY 82-06 Evaluation for JENDL-2 was made by N. Asano (SAEI), H. Matsunobu (SAEI) and Y.Kikuchi(JAERI). 87-03 Re-evaluation for JENDL-3 was made by H.Matsunobu (SAEI) Main part of revision was the cross sections above 10 keV and angular and energy distributions of neutrons. Data were compiled by T. Nakagawa (JAERI). 94-04 JENDL-3.2. Resonance parameters reevaluated by H.Derrien (JAERI)/1/ Cross sections reevaluated by H.Matsunobu(SAEI) Fission spectrum reevaluated by T.Ohsawa(Kinki univ.) Compiled by T.Nakagawa (NDC/JAERI) ***** Modified parts for JENDL-3.2 ******************** (2,151); New analysis with SAMMY MF=3 ; all data except fission cross section below 6.75 MeV and total cross section MF=4 ; for inelastic scattering (5,18) *********************************************************** 00-02 JENDL-3.3. Evaluation was made by H. Matsunobu (SAEI) and T.Kawano(Kyushu Univ.) and compiled by O.Iwamoto (NDC/JAERI). ***** Modified parts for JENDL-3.3 ******************** (1,452), (1,455), (1,456) (2,151) unresolved resonance region (3,2), (3,16), (3,17), (3,18), (3,102) (5,16), (5,17), (5,91), (5,455) *********************************************************** 02-01 Covariances were taken from JENDL-3.2 covariance file except for MF/MT=31/455, 31/456/, 33/18, and 33/102, which were evaluated by Matsunobu./8/ MF=2 Resonance Parameters MT=151 2200-m/s cross sections and calculated res. integrals 2200 m/s Res. Integ. total 588.38 b - elastic 11.97 b - fission 531.16 b 773 b capture 45.25 b 138 b MF=3 Neutron Cross Sections Smooth part (above 30 keV) MT=18 Fission Results of recent simultaneous evaluation of fission cross sections /2/ were adopted. MF=5 Energy Distributions of Secondary Neutrons MT=16,17,91 Calculated with pre-compound and multi-step evaporation theory code EGNASH /3,4/. MT=455 Delayed neutron spectrum. Summation calculation made by Brady and England /5/ was adopted. MF=31 Covariances of Average Number of Neutrons per Fission MT=452 Constructed from MT=455 and 456. MT=455 Based on experimental data. A chi-value was 0.13. MT=456 Based on experimental data. A chi-value was 0.96. MF=32 Covariances of Resonance Paremeters (ref.6) MT=151 Resolved resonance Based on the SAMMY analysis by Derrien /1/. Unresolved resonance The covariances were obtained by using kalman. MF=33 Covariances of Cross Sections (ref.6) MT=1 Based on experimental data. A chi-value was 0.244. MT=2 Constructed from mt=1, 4, 16, 17, 18, and 102. MT=4 Based on experimental data. A chi-value was 0.151. MT=16 Based on experimental data. MT=17 Taken from mt=16 MT=18 The covariances were obtained by the simultaneous evaluation. /2/ MT=102 Based on experimental data on alpha values. A chi-value was 0.186. MF=34 Covariances of Angular Distributions (ref.6) MT=2 The covariances of p1 coefficients were obtained by using kalman. A chi-value was 1.474. MF=35 Covariances of Energy Distributions MT=18 The covariances were obtained by using kalman./7/ References 1) Derrien H.: J. Nucl. Sci. Technol., 31, 379 (1994) 2) Kawano T. et al.: JAERI-Research 2000-004 (2000). 3) Yamamuro N.: JAERI-M 90-006 (1990). 4) Young P.G. and Arthur E.D.: LA-6947 (1977). 5) Brady M.C. and England T.R.: Nucl. Sci. Eng., 103, 129(1989). 6) Shibata K. and Hasegawa A.: JNC TJ9400 2000-004 (2000) [in Japanese]. 7) Kawano T. et al.: JAERI-Research 99-009 (1999) [in Japanese]. 8) Matsunobu H.: Private communication (2001). ******************** JEDL-3.2 ************************************ 92-U -233 SAEI+ Eval-Mar87 H.Matsunobu,Y.Kikuchi,T.Nakagawa Dist-Sep89 Rev2-Apr94 History 82-06 Evaluation for JENDL-2 was made by N. Asano (SAEI), H. Matsunobu (SAEI) and Y.Kikuchi(JAERI). 87-03 Re-evaluation for JENDL-3 was made by H.Matsunobu (SAEI) Main part of revision was the cross sections above 10 keV and angular and energy distributions of neutrons. Data were compiled by T. Nakagawa (JAERI). 94-04 JENDL-3.2. Resonance parameters reevaluated by H.Derrien (JAERI)/1/ Cross sections reevaluated by H.Matsunobu(SAEI) Fission spectrum reevaluated by T.Ohsawa(Kinki univ.) Compiled by T.Nakagawa (NDC/JAERI) ***** Modified parts for JENDL-3.2 ******************** (2,151); New analysis with SAMMY MF=3 ; all data except fission cross section below 6.75 MeV and total cross section MF=4 ; for inelastic scattering (5,18) *********************************************************** MF=1 General Information MT=451 Comments and dictionary MT=452 Nu-total Sum of Nu-d and Nu-p MT=455 Nu-d Below 4 MeV Nu-d = 0.0075094 + 4.627E-5*ln(E(MeV)) Between 4 and 20 MeV Based on the data of Masters et al. /2/ and Evans et al. /3/. MT=456 Nu-p Renormalization was made to 3.756 of Cf-252. Below 1 MeV Nu-p = 2.486 + 0.1121*(E-DE), where DE is difference of average fragment kinetic energy between incident and thermal neutron energies. It was taken from data of Boldeman et al. /4/. Between 1 and 2.73 MeV Nu-p = 2.436 + 0.1279*E Between 2.73 and 7.47 MeV Nu-p = 2.327 + 0.1678*E Above 7.47 MeV Nu-p = 2.857 + 0.09689*E MF=2 Resonance Parameters MT=151 a) Resolved resonance region ( 1 eV to 150 eV) Resolved resonance parameters for the Reich-Moore formula were obtained by using SAMMY/5/. Details are given in Appendix. b) Unresolved resonance region ( 0.15 keV to 30 keV) Parameters were deduced with ASREP code /6/ so as to reproduce the evaluated cross sections in this energy region. 2200-m/s cross sections and calculated res. integrals 2200 m/s Res. Integ. total 588.38 b - elastic 11.97 b - fission 531.16 b 774 b capture 45.25 b 138 b MF=3 Neutron Cross Sections Smooth part (above 30 keV) MT=1 Total Based on the data of Poenitz /7,8/. Between 10 and 48 keV, cross-section curve calculated with the statistical- model code CASTHY /9/ and the coupled-channel theory code ECIS /10/ was normalized at 48 keV. MT=2 Elastic Obtained by subtracting non-elastic scattering cross section from the total cross section. MT=4 and 51-64,91 Inelastic scattering Calculated with CASTHY /9/ and ECIS /10/. Coupled levels were first three levels. Deformed OMP recommended by Haouat et al. /11/, was slightly modified so as to reproduce the experimental data of Smith et al. /12/, and spherical OMP was the same as that used for JENDL-2. In the energy range above 8.25 MeV, the cross section was approximated by using an extponential-type fuction, because the cross section curve obtained by CASTHY and ECIS showed large fluctuation. Deformed OMP V =46.4-0.3*E , Ws=3.5 +0.4*E , Vso=6.2 (MeV) r0=1.26 , rs=1.26 , rso=1.12 (fm) a0=0.63 , b =0.52 , aso=0.47 (fm) Beta-2=0.20, Beta-4=0.074 Spherical OMP V =41.8-0.20*E+0.008*E**2, Ws=6.50-0.15*E, Vso=6.0 (MeV) r0=1.31 , rs=1.36 , rso=1.32 (fm) a0=0.57 , b =0.44 , aso=0.50 (fm) (dir. W.S.) Level scheme was taken from Ref. /13/. No. Energy(MeV) Spin-Parity g.s. 0.0 5/2 + * 1 0.04035 7/2 + * 2 0.0922 9/2 + * 3 0.1551 11/2 + * 4 0.29882 5/2 - 5 0.31191 3/2 + 6 0.3208 7/2 - 7 0.34047 5/2 + 8 0.3537 9/2 - 9 0.397 11/2 - 10 0.39849 1/2 + 11 0.41576 3/2 + 12 0.5039 7/2 - 13 0.5467 5/2 + 14 0.5971 7/2 + Above 0.6 MeV, assumed to be overlapped. Levels with asterisk were coupled in the ECIS calculation. MT=16,17 (n,2n) and (n,3n) Calculated by using the EGNASH-2 code /14/. The (n,2n) cross section was normalized to fission-spectrum-averaged value of 0.00408 b measured by Kobayashi et al./15/. The same normalization factor was also applied to the (n,3n) cross section. MT=18 Fission Based on the experimental data of Gwin et al. /16/, Carlson et al. /17/, Manabe et al. /18/, Kanda et al. /19/, Iwasaki et al. /20/, Meadows /21/, Lisowski et al./22/ and the fission cross section of U-235 obtained by the simultaneous evaluation /23/ and measured by Carlson et al./24/ between 13.25 and 20 MeV. MT=102 Capture In the energy range from 30 keV to 1 MeV, the alpha values measured by Hopkins and Diven /25/ were multiplied by the fission cross section. In the high energy region, values calculated with CASTHY and ECIS were normalized to 0.0578 b at 1 MeV. MT=251 Mu-bar Calculated with CASTHY and ECIS. MF=4 Angular Distributions of Secondary Neutrons MT=2, 51-64 and 91 Calculated with CASTHY and ECIS. MT=16,17 and 18 Assumed to be isotropic in the Lab system. MF=5 Energy Distributions of Secondary Neutrons MT=16,17,91 Calculated with PEGASUS /26/. MT=18 Fission spectrum Distributions were calculated with the modified Madland-Nix model/27,28/. The compound nucleus formation cross sections for fission fragments (FF) were calculated using Becchetti- Greenlees potential/29/. Up to 4th-chance-fission were considered at high incident neuttron energies. The Ignatyuk formula/30/ were used to generate the level density parameters. Parameters adopted: Total average FF kinetic energy = 172.311-0.0212*E(MeV) Average energy release = 188.438 MeV Average mass number of light FF = 95 Average mass number of heavy FF = 139 Level density of the light FF = 9.999- 10.094 Level density of the heavy FF = 11.89 - 12.20 Note that the parameters vary with the incident energy within the indicated range. MT=455 Delayed neutrons Recommendation by Saphier et al. /31/ was adopted. References 1) Derrien H.: to be published in J. Nucl. Sci. Technol. (1994) 2) Master C.F. et al.: Nucl. Sci. Eng., 36, 202 (1969). 3) Evans A.E. et al.: Nucl. Sci. Eng., 50, 80 (1973). 4) Boldeman J.W. et al.: Nucl. Phys., A265, 337 (1976). 5) Larson N.: ORNL/TM-9179/R1 (1985). 6) Kikuchi Y.: to be published. 7) Poenitz W.P. et al.: Nucl. Sci. Eng., 78, 333 (1981). 8) Poenitz W.P. et al.: ANL/NDM-80 (1983). 9) Igarasi S. and Fukahori T.: JAERI 1321 (1991). 10) Raynal J.: ECIS. 11) Haouat G., et al.: Nucl. Sci. Eng., 81, 491 (1982). 12) Smith A.B. et al.: 1982 Antwerp, p.039 (1982). 13) Lederer D.G. and Shirley V.S.: Table of Isotopes, 7th Ed. (1978). 14) Yamamuro N.: JAERI-M 90-006 (1990). 15) Kobayashi K.: J. Nucl. Sci. Technol., 10, 668 (1973). 16) Gwin R. et al.: Nucl. Sci. Eng., 59, 79 (1976). 17) Carlson G.W. and Behrens J.W.: Nucl. Sci. Eng., 66, 205 (1978) 18) Manabe F., et al. : 1987 Annual Meeting of Atomic Energy Society of Japan, Nagoya, p.167 (1987) in Japanese. 19) Kanda K., et al.: 1985 Santa-Fe, p.569 (1985). 20) Iwasaki T., et al.: private communication (1987). 21) Meadows J.W.: Nucl. Sci. Eng., 54, 317 (1974). 22) Lisowski P.W.: 1991 Juelich, p.732 (1992). 23) Kanda Y. et al.: 1985 Santa Fe, 2, 1567 (1986). 24) Carlson A.D. et al.: 1991 Juelich, p.518 (1992). 25) Hopkins J.C. and Diven B.C.: Nucl. Sci. Eng., 12, 169 (1962). 26) Iijima S, et al.: JAERI-M 87-025, p.337 (1987). 27) Madland D.G. and Nix J.R.: Nucl. Sci. Eng., 81, 213 (1982). 28) Ohsawa T. and Shibata T.: 1991 Juelich Conf., 965 (1992). 29) Becchetti Jr.F.D. and Greenlees G.W.: Phys. Rev., 182, 1190 (1969). 30) Ignatyuk A.V.: Sov. J. Nucl. Phys., 29, 450 (1979). 31) Saphier D., et al.: Nucl. Sci. Eng., 62, 660 (1977). ***************************************************************** Appendix RESONANCE DATA ,JAERI DECEMBRE 1992 ***************************************************************** The Reich-Moore R-matrix resonance parameters were obtained from sequencial Bayesian fits of selected experimental total, fis- sion and capture cross sections performed with the computing code SAMMY. The selected experimental data were the following: 1) total cross sections measured by Pattenden/1/, Moore/2/, Kolar/3/, Harvey/4/; 2) fission cross sections measured by Weston/5,6/, Blons/7/, Deruyter/8/, Wagemans/9/. 3) capture cross sections measured by Weston/5,6/. In the low energy range the data of Pattenden,Moore,Harvey, Kolar, Weston, Deruyter and Wagemans were considered.In the energy range from 15 eV to 150 eV, only the data from Kolar, Blons and Weston could be analysed owing to the poor resolution of the other data. Some of the data were renormalized to the Axton standard /10/ at 0.0253 eV. The fission cross section measurement of Weston /5/ available in the energy range above 1 eV was renormalised to the data of Wagemans/9/ over the energy range from 1 eV to 20 eV, resulting in an increase of the cross section by 2.4% compared to the original EXFOR file. The fission cross section measurement of Blons available in the energy range above 15 eV was renormalized to the the data of Weston over the energy range from 15 eV to 150 eV, resulting in an increase of the cross section by 2.9% compared to the data in the original EXFOR file. The total cross section of Kolar needed a background correction of (2.3-0.038E) barn, E in eV, in the energy range from 77 eV to 150 eV, corresponding to 0 to 1.5% of the measured transmission. These renormalizations and background corrections were performed after preliminary fits of the data available from the EXFOR file in order to realize a consistency of +-2% among the cross section of the experimental data base. The final SAMMY fits were performed without renormali- zation and background correction parameters The transmission data of Pattenden, Moore, Harvey and Kolar are not available from the EXFOR file and were not requested from the authors. The SAMMY fits were performed on the experimental ef- fective total cross sections using the sample thicknesses and the experimental resolution to calculate the theoritical effective cross sections. Enough informations were found in the publications by the authors to ensure the accuracy of the calculations. Due to the high resolution of the transmission measurements of Kolar(100 m flight path) and of the fission measurements of Blons (50 m flight path and sample cooled down at liquid nitrogen tempe- rature) the analysis could be performed up to 150 ev neutron ener- gy. The high resolution fission cross section of Cao/11/ were not included in the experimental data base owing to a severe problem of the renormalization of the data. The capture cross sections of Weston were included in the fits below 30 eV only. Above 30 eV the statistical accuracy of the data was too poor and the try and error method was used in a prelimina- ry work to obtain the capture width of some strong capture reson- ances. The capture width of the other resonances was kept at a constant value of 41 meV close to the average value obtained by fitting the energy range below 30 eV. Some resonances not pertain- ing to 233U were disclosed in the experimental data and were iden- tified as 195Pt resonances. The experimental data of Table 2 were roughly corrected for these resonances. The values of the cross sections obtained by Axton at 0.0253 eV were included in all the experimental data available in the thermal range with the small error bars obtained by Axton, in order to ensure the best agreement between the calculated and the evaluated thermal values. The values calculated from the resonance parameters are the followings: Calculation Axton (RESENDD 0.1% 300 K) Evaluation Fission 531.29 b 530.70+-1.34 b Capture 45.27 b 45.62+-0.70 b Scattering 11.99 b 12.19+-0.67 b Tables 1 and 2 show the average cross sections calculated from the resonance parameters compared with the average experimen- tal data and with average JENDL-3, ENDF/B-VI and JEF-2 data. Table 1 Fission Cross Sections ------------------------------------------------------------- Energy Wagem Deruy Westo Blons Calcu JENDL ENDF6 JEF2 Range(eV) ------------------------------------------------------------- 0.021-0.031 525.6 526.7 526.8 526.5 528.8 523.9 520.6 0.031-0.082 362.9 363.5 363.9 361.7 363.9 361.9 359.7 0.082-1.000 151.3 150.9 150.6 150.1 149.4 149.0 148.6 1.000-2.100 388.8 387.7 391.7 387.9 383.0 378.9 382.1 2.100-2.750 204.4 204.6 207.5 204.6 205.9 198.1 198.8 2.750-3.000 50.1 53.4 51.9 50.2 52.9 50.6 50.8 3.000-15.00 106.2 105.6 104.9 104.3 103.6 101.2 101.5 0.021-15.00 134.2 133.5 133.5 132.5 131.7 129.1 129.5 15.00-30.00 95.03 94.60 95.51 96.49 91.80 92.69 30.00-50.00 40.13 40.30 40.27 40.19 38.85 39.16 50.00-75.00 40.66 40.49 40.53 40.79 35.80 39.90 75.00-100.0 35.57 36.70 36.03 36.58 33.36 32.74 100.0-125.0 36.84 36.89 36.97 31.78 29.94 28.94 125.0-150.0 21.29 20.29 20.78 16.30 22.10 26.25 15.00-150.0 41.39 41.48 41.45 39.91 38.49 40.05 -------------------------------------------------------------- Table 2 Capture Cross Sections ------------------------------------------------------------- Energy Weston Calcul JENDL3 ENDF6 JEF2.2 Range(eV) ------------------------------------------------------------- 0.021-0.031 45.17 44.90 44.82 45.40 45.54 0.031-0.082 32.51 32.57 32.45 32.58 32.68 0.082-1.000 14.06 14.44 13.99 13.24 13.13 1.000-2.100 66.83 66.54 70.54 67.46 67.31 2.100-2.750 111.83 110.67 106.25 112.04 110.80 2.750-3.000 7.50 8.25 8.85 7.53 5.74 3.000-15.00 17.43 17.61 19.51 17.66 17.02 0.021-15.00 24.85 24.97 26.57 24.22 24.43 15.00-30.00 13.25 13.97 11.92 13.27 12.67 30.00-50.00 5.21 5.81 4.85 5.47 5.00 50.00-75.00 4.91 5.38 4.42 3.80 5.25 75.00-100.0 8.71 9.07 5.39 4.30 5.33 100.0-125.0 5.37 6.01 3.55 3.88 4.63 125.0-150.0 3.38 3.78 2.12 3.54 4.12 15.00-150.0 6.39 6.90 4.91 5.16 5.73 -------------------------------------------------------------- The experimental capture data of Weston was increased by a background correction according to the evaluation of Reynolds et al./12/ and renormalized to the original value of Weston in the energy range 1.0 eV to 2.75 eV. RESONANCE INTEGRAL FISSION Energy range this work JENDL-3 ENDF/B-6 JEF-2 ------------------------------------------------------ 0.5 eV-150 eV 710.34 710.53 691.08 697.18 150 eV-20 MeV 64.25 63.34 65.29 0.5 eV-20 MeV 774.79 754.43 762.47 ------------------------------------------------------ RESONANCE INTEGRAL CAPTURE Energy range this work JENDL-3 ENDF/B-6 JEF-2 ------------------------------------------------------ 0.5 eV-150 eV 131.92 131.77 128.79 127.51 150 eV-20 MeV 6.65 7.58 7.24 0.5 eV-20 MeV 138.42 136.37 134.75 ------------------------------------------------------ References of Appendix 1) PATTENDEN et al.: Nucl. Sci. Eng., 17, 404 (1963) 2) MOORE et al.: Phys. Rev., 118, 714 (1960) 3) KOLAR et al.: 1970 Helsinki, Vol.I, 387 (1970) 4) HARVEY et al.: 1979 Knoxville, p.690 (1979) 5) WESTON et al.: Nucl. Sci. Eng., 34, 1 (1968) 6) WESTON et al.: Nucl. Sci. Eng., 42, 143 (1970) 7) BLONS et al.: Nucl. Sci. Eng., 51, 130 (1973) 8) DERUYTER et al.: Nucl. Sci. Eng., 54, 423 (1974) 9) WAGEMANS et al.: 1988 Mito, 91 (1988) 10) AXTON et al.: BCMN Report, GE/PH/01/86 (1986) 11) CAO et al.: 1970 Helsinki. Vol.I, 419 (1970) 12) REYNOLDS et al.: KAPL-M-7323 (1973)Back |