Nuclear Data Evaluation for Actinoid Nuclides. T.Nakagawa, O.Iwamoto, N.Otuka, S.Chiba Japan Atomic Energy Agency
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1 Nuclear Data Evaluation for Actinoid Nuclides T.Nakagawa, O.Iwamoto, N.Otuka, S.Chiba Japan Atomic Energy Agency 1
2 Nuclear Data Evaluation For JENDL Actinoid File (JENDL/AC) Nuclides 79 nuclides: Ac-225 to Fm nuclides: data were revised. 17 nuclides: additional nuclides for JENDL/AC. Their half-lives are longer than 1day. Neutron energy range 1.0e-5 ev to 20 MeV 2
3 Resolved Resonance Parameters SAMMY analyses Th-232, U-233, U-238, Pu-241: ENDF/B-VII.0 was adopted. U-235: was adopted up to 500 ev Pu-239:. New analysis has been done by Derrien. Pu-240: was slightly modified. Np-236: New evaluation was done by Furutaka (JAEA). Other nuclides Parameters of Multi-Level Breit-Wigner formula were modified to reproduce experimental data. Thermal fission and capture cross sections Evaluated from experimental data if available. 3
4 Cm-244 U-234 U-235 U-236 U-238 Np-237 Pu-238 Pu-239 Pu-240 Pu-241 Pu-242 Am-241 Am-242m (AC-J33)/J33[%] Am-243 Cm-242 Cm-243 Cm-245 Thermal Cross Sections Changes from. capture fission
5 241 Am Capture Cross Section Thermal cross section (b) Kalebin (1976) 624 ± 20 Shinohara+ (1997) 854 ± 58 Fioni+ (2001) 696 ± 48 Bringer+ (2006) 714 ± 23 Present LANL (2007) about 660 ± 25 Large thermal capture cross section is inconsistent with measured total cross sections Am total Ju.V.Adamchuk+ ('55) Ju.V.Adamchuk+ ('55) Ju.V.Adamchuk+ ('55) G.G.Slaughter+ ('61) H.Derrien+ ('75) S.M.Kalebin+ ('76) Present
6 Modification of Resonance Parameters Cm fission M.G.Silbert ('76) present
7 235 U Capture Cross Section U capture 500eV~2.25 kev; pointwise data were given present F.D.Brooks+ ('66) G.de Saussure+ ('66) G.de Saussure+ ('66) R.B.Perez+ ('73) R.B.Perez+ ('73) F.Corvi+ ('75) V.N.Kononov+ ('75) R.Gwin+ ('76) G.V.Muradyan+ ('77) F.Corvi+ ('82)
8 Unresolved Resonance Parameters Option LSSF=1 Unresolved resonance parameters are used only for selfshielding calculations. Cross sections are given in MF=3. Upper boundary energies Selected to be high enough to avoid discontinuity of selfshielded cross sections. Code for URP evaluation ASREP code 8
9 Theoretical Calculation CCONE code Developed by O. Iwamoto (Nuclear Data Center, JAEA). Based on coupled channel optical model, DWBA, preequilibrium exciton model, statistical model. Fission cross section can be calculated. Programming language: C++ 9
10 Fission Cross Sections calculated with CCONE Code 242m Am fission present CCONE P.A.Seeger+ ('67) C.D.Bowman+ ('68) E.F.Fomushkin+ ('81) E.F.Fomushkin+ ('81) E.F.Fomushkin+ ('81) J.W.T.Dabbs+ ('83) J.W.T.Dabbs+ ('83) J.C.Browne+ ('84) J.C.Browne+ ('84) J.C.Browne+ ('84) V.F.Gerasimov+ ('87) V.A.Shigin+ ('91) B.I.Fursov+ ('97) B.I.Fursov+ ('97) V.F.Gerasimov+ ('97) T.Kai+ ('01)
11 238 U(n,2n) Cross Section 238 U (n,2n) Frehaut+ (befor correction) L.R. Veeser + ('78) H.Karius+ ('79) J.Frehaut+ ('80) J.Frehaut+ ('80) N.V.Kornilov+ (' 80) P.Raics+ ('80) T.B.Ryves+ ('80) R.Pepelnik+ ( '85) V.Ya.Golovnya+ ('87) V.Ya.Golovnya+ ('87) C.Konno+ ('93) A.A.Filatenkov+ ('99) A.A.Filatenkov+ ('99) 0 CCONE (= present) ENDF/B-VII Neutron Energy (MeV) 11
12 237 Np Capture Cross Section 237 Np capture 10 1 present (=CCONE) ENDF/B-VII D.C.Stupegia+ ('67) M.Lindner+ ('76) L.W.Weston+ ('81) Ju.N.Trofimov+ ('83) N.N.Buleeva+ ('88) N.N.Buleeva+ ('88) N.N.Buleeva+ ('88) Katsuhei Kobayashi+ ('02) Katsuhei Kobayashi+ ('02) E.I.Esch+ ('05)
13 241 Am Capture Cross Section 241 Am capture G.N.Flerov+ ('67) D.B.Gayther+ ('77) K.Wisshak+ ('80) K.Wisshak+ ('80) K.Wisshak+ ('80) K.Wisshak+ ('80) K.Wisshak+ ('80) K.Wisshak+ ('82) G.Vanpraet+ ('85) present (=CCONE) ENDF/B-VII
14 Isomeric Ratio of 241 Am Capture Cross Section Isomeric ratio (ground state) Am capture present ENDF/B-VII JEFF-3.1 Bringer et al. ('06) Fioni et al. ('01) Shinohara et al. ('97) Wisshak et al. ('82) Dovbenko et al. ('71) Gavrilov et al. ('75) Harbour et al. ('73) Bak et al. ('67) present IR FBR PWR BWR
15 Fission Cross Sections Evaluated with GMA code and experimental data GMA is a least-squares fitting code developed by Poenitz, and improved by S.Chiba et al. Simultaneous Evaluation for important nuclides 15
16 243 Am Fission Cross Section 243 Am fission K.Wisshak+ ('83) K.Wisshak+ ('83) K.Wisshak+ ('83) K.Wisshak+ ('83) E.F.Fomushkin+ ('84) B.I.Fursov+ ('85) K.Kanda+ ('87) H.Knitter+ ('88) K.Kobayashi+ ('99) V.Ya.Golovnya+ ('99) A.Laptev+ ('04) Baba+ ('07) present. ENDF/B-VII
17 243 Cm Fission Cross Section 243 Cm fission 10 1 Present R.R.Fullwood+ ('70) M.G.Silbert ('76) E.F.Fomushkin+ ('87) E.F.Fomushkin+ ('90) E.F.Fomushkin+ ('91) B.I.Fursov+ ('97) B.I.Fursov+ ('97)
18 235 U Fission Cross Section 235 U fission A.D.Carlson ('83) I.D.Alkhazov+ ('83) A.D.Carlson+ ('84) L.W.Weston+ ('84) C.M.Herbach+ ('85) C.M.Herbach+ ('85) R.Arlt+ ('85) R.Arlt+ ('85) I.D.Alkhazov+ ('86) Li Jingwen+ ('86) J.Rapaport+ ('87) I.D.Alkhazov+ ('88) I.D.Alkhazov+ ('88) N.N.Buleeva+ ('88) R.G.Johnson+ ('88) T.Iwasaki+ ('88) K.Merla+ ('91) K.Merla+ ('91) R.G.Johnson+ ('91) V.A.Kalinin+ ('91) D.Rochman+ ('05)
19 235 U Fission Cross Section U fission A.D.Carlson ('83) I.D.Alkhazov+ ('83) A.D.Carlson+ ('84) L.W.Weston+ ('84) C.M.Herbach+ ('85) C.M.Herbach+ ('85) R.Arlt+ ('85) R.Arlt+ ('85) I.D.Alkhazov+ ('86) Li Jingwen+ ('86) J.Rapaport+ ('87) I.D.Alkhazov+ ('88) I.D.Alkhazov+ ('88) N.N.Buleeva+ ('88) R.G.Johnson+ ('88) T.Iwasaki+ ('88) K.Merla+ ('91) K.Merla+ ('91) R.G.Johnson+ ('91) V.A.Kalinin+ ('91) D.Rochman+ ('05) present ENDF/B-VII
20 Simultaneous Evaluation of Fission Cross Sections Nuclides U-233, U-235, U-238, Pu-239, Pu-240, Pu-241 Neutron energy range 10 kev to 20 MeV Code used for the evaluation SOK code developed by T. Kawano (LANL) 20
21 Simultaneous Evaluation of Fission Cross Sections U fission 2 1 JENDL/AC previous SOK 239 Pu fission JENDL/AC previous SOK
22 Adjustment of Model Parameters to Integral Data Integral data are also experimental data. Model parameters used in the CCONE calculation for important nuclides will be adjusted to integral data. Integral data: k-eff of FBR and small cores at LANL, etc. Preliminary adjustment was successfully done. Cross-section changes were small and reasonable. C/E values were considerably improved. 22
23 Summary JENDL/AC is under development. Evaluated data are given to 79 nuclides from Ac to Fm. Results of theoretical calculation with CCONE code are widely adopted. The present evaluation is based on experimental data as much as possible. Integral data are considered as experimental data, and model parameters of CCONE code will be adjusted to them. JENDL/AC will be released in FY2007. Covariance data will be provided for important nuclides in FY
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