ENTRY 22950 20120614 22322295000000001 SUBENT 22950001 20120614 22322295000100001 BIB 8 43 2295000100002 TITLE Evidence for inelastic neutron acceleration by the 2295000100003 177Lu isomer 2295000100004 AUTHOR (O.Roig, G.Belier, V.Meot, D.Abt, J.Aupiais, 2295000100005 J.-M.Daugas, Ch.Jutier, G.Le Petit, A.Letourneau, 2295000100006 F.Marie, Ch.Veyssiere) 2295000100007 INSTITUTE (2FR BRC,2FR SAC) 2295000100008 REFERENCE (J,PR/C,74,054604,2006) burnup and INNA cross sections 2295000100009 #doi:10.1103/PhysRevC.74.054604 2295000100010 (C,2007NICE,1,463,2007) Another INNA cross sections 2295000100011 #doi:10.1051/ndata:07249 2295000100012 (J,NIM/A,521,5,2004) 2295000100013 Preliminary Lu-177-m burn-up x-section (590 b) 2295000100014 REL-REF (I,22924001,F.Marie+,J,NIM/A,556,547,2006) 2295000100015 Mini-INCA chamber description 2295000100016 (M,,O.Roig+,C,2005NOTRED,,593,2006) 2295000100017 Measurement of inelastic neutron acceleration reaction2295000100018 (O,22915001,G.Belier+,J,PR/C,74,054604,2006) 2295000100019 Maxwellian averaged capture cross sections 2295000100020 SAMPLE Lu-177m obtained by thermal neutron irradiation of 2295000100021 enriched (99.993%) Lu-176 sample (1.25 mg) at ILL 2295000100022 high flux reactor (HFR) and produced by mass 2295000100023 separator PARSIFAL. 2295000100024 Hf-177 (after beta-decay of Lu-177g) was chemically 2295000100025 removed. 2295000100026 ERR-ANALYS (DATA-ERR) Olivier Roig (2009-09-02): 2295000100027 These uncertainty values include counting statistics 2295000100028 errors and also all known systematic errors (half-life2295000100029 irradiations, counting and cooling time errors, 2295000100030 complete errors for the flux measurement including 2295000100031 calibrated sample uncertainties). 2295000100032 HISTORY (20070314C) S.M./M.M. 2295000100033 (20070322A) Last corrections have been done - SM 2295000100034 (20081228A) BIB-information updated. Correlation to 2295000100035 ENTRY 22915 established. Incident neutron energy 2295000100036 corrected. Subent 22950010 deleted as not relevant, 2295000100037 Subents 22950-005, -006, -007, -008, -009 corrected 2295000100038 - SM 2295000100039 (20100713U) M.M. J,NIM/A,556,547,2006 was moved in 2295000100040 REL-REFs. ndata07249 -> ndata:07249 in DOI 2295000100041 Ref. J,NIM/A,521,5,2004 was inserted. 2295000100042 (20120614C) On. Re-compiled with a letter from O.Roig 2295000100043 SUBENT 009 (ratio between two experimental works) was 2295000100044 deleted. 2295000100045 ENDBIB 43 0 2295000100046 NOCOMMON 0 0 2295000100047 ENDSUBENT 46 0 2295000199999 SUBENT 22950002 20120614 22322295000200001 BIB 11 23 2295000200002 REACTION (71-LU-177-M(N,NON),,SIG,,MXW/FCT) 2295000200003 Maxwellian averaged burnup cross section by the 2295000200004 Westcott convention multiplied by sqrt(pi)/2 2295000200005 FACILITY (REAC,2FR ILL) HFR/T4 (T=323 K) 2295000200006 INC-SPECT - Neutron flux=(1.24+/-0.05)e+13 n/cm2/s 2295000200007 - Epithermal/thermal-ratio=0.0005 2295000200008 DETECTOR (HPGE) High-purity-Ge detector setup 2295000200009 METHOD (ACTIV) Irradiated for 92 days, cooled for 110 days 2295000200010 SAMPLE Number of atoms: 2295000200011 Lu-177g: 5.25E+8, Lu-177m: (5.83+/-0.08)E+10, 2295000200012 Lu-176: ~1.E+8, Ta-181: ~1.E+11. 2295000200013 Diameter of Ti backing is 5 mm. 2295000200014 ANALYSIS Burnup cross section determined by measurement of 2295000200015 difference in Lu-177-m activity before and after 2295000200016 sample irradiation 2295000200017 DECAY-DATA (71-LU-177-M,160.44D,DG,112.9,, 2295000200018 DG,228.5,, 2295000200019 DG,378.5,, 2295000200020 DG,418.5) 2295000200021 MISC-COL (MISC) Epithermal/thermal neutron flux ratio 2295000200022 ERR-ANALYS (ERR-S,,0.5) Statistical error on gamma-ray counts 2295000200023 (ERR-1,,0.5) Solid angle 2295000200024 STATUS (TABLE) Table IV of Phys.Rev.C74(2006)054604 2295000200025 ENDBIB 23 0 2295000200026 NOCOMMON 0 0 2295000200027 DATA 4 1 2295000200028 KT-K DATA ERR-T MISC 2295000200029 K B B NO-DIM 2295000200030 323. 624. 93. 0.0005 2295000200031 ENDDATA 3 0 2295000200032 ENDSUBENT 31 0 2295000299999 SUBENT 22950003 20120614 22322295000300001 BIB 10 21 2295000300002 REACTION (71-LU-177-M(N,NON),,SIG,,MXW/FCT) 2295000300003 Maxwellian averaged burnup cross section by the 2295000300004 Westcott convention multiplied by sqrt(pi)/2 2295000300005 FACILITY (REAC,2FR ILL) HFR/H9 (T=323 K) 2295000300006 INC-SPECT - Neutron flux=(6.67+/-0.32)e+14 n/cm2/s 2295000300007 - Epithermal/thermal-ratio=0.015 2295000300008 SAMPLE Number of atoms: 2295000300009 Lu-177g: 2.07E+9, Lu-177m: (2.30+/-0.02)E+11, 2295000300010 Lu-176: ~1.E+8, Ta-181: ~1.3E+12. 2295000300011 Diameter of Ti backing is 19 mm. 2295000300012 DETECTOR (HPGE) High-purity-Ge detector setup in mini-INCA 2295000300013 METHOD (ACTIV) Irradiated for 3 days, cooled for 60 days 2295000300014 DECAY-DATA (71-LU-177-M,160.44D,DG,112.9,, 2295000300015 DG,208.4,, 2295000300016 DG,327.5,, 2295000300017 DG,378.5,, 2295000300018 DG,418.5) 2295000300019 MISC-COL (MISC) Epithermal/thermal neutron flux ratio 2295000300020 ERR-ANALYS (ERR-S,,0.5) Statistical error on gamma-ray counts 2295000300021 (ERR-1,,0.5) Solid angle 2295000300022 STATUS (TABLE) Table IV of Phys.Rev.C74(2006)054604 2295000300023 ENDBIB 21 0 2295000300024 NOCOMMON 0 0 2295000300025 DATA 4 1 2295000300026 KT-K DATA ERR-T MISC 2295000300027 K B B NO-DIM 2295000300028 323. 627. 51. 0.015 2295000300029 ENDDATA 3 0 2295000300030 ENDSUBENT 29 0 2295000399999 SUBENT 22950004 20120614 22322295000400001 BIB 3 7 2295000400002 REACTION (71-LU-177-M(N,NON),,SIG,,MXW/FCT) 2295000400003 Maxwellian averaged burnup cross section by the 2295000400004 Westcott convention multiplied by sqrt(pi)/2 2295000400005 ANALYSIS Average of two values from HFR/T4 and HFR/H9 2295000400006 STATUS (TABLE) Text (p054604-4) of Phys.Rev.C74(2006)054604 2295000400007 (DEP,22950002) Value from HFR/T4 (624 +/- 93 b) 2295000400008 (DEP,22950003) Value from HFR/H9 (627 +/- 51 b) 2295000400009 ENDBIB 7 0 2295000400010 NOCOMMON 0 0 2295000400011 DATA 3 1 2295000400012 KT-K DATA ERR-T 2295000400013 K B B 2295000400014 323. 626. 45. 2295000400015 ENDDATA 3 0 2295000400016 ENDSUBENT 15 0 2295000499999 SUBENT 22950005 20120614 22322295000500001 BIB 8 17 2295000500002 REACTION (71-LU-177-M(N,NON),,SIG,,SPA) 2295000500003 Spectrum averaged burnup cross section 2295000500004 FACILITY (REAC,2FR ILL) HFR/V4 2295000500005 INC-SPECT - Neutron flux=(1.53+/-0.04)e+14 n/cm2/s 2295000500006 - Epithermal/thermal-ratio is not given in the article 2295000500007 SAMPLE 0.31 +/- 0.03 mg, purity 99.993% 2295000500008 METHOD (ACTIV) Irradiated for 46 days 2295000500009 ASSUMED (ASSUM1,71-LU-176(N,G)71-LU-177-M,,SIG,,SPA) 2295000500010 Averaged EXFOR data with HFR/V4 flux from MCNP 2295000500011 (ASSUM2,71-LU-176(N,G)71-LU-177-G,,SIG,,SPA) 2295000500012 Averaged EXFOR data with HFR/V4 flux from MCNP 2295000500013 COMMENT By Olivier Roig (2009-09-02): 2295000500014 This port was very close to the nuclear fuel, and 2295000500015 therefore the neutron spectrum cannot be considered 2295000500016 as a Maxwellian flux. The temperature close to the 2295000500017 nuclear fuel is not well-known. 2295000500018 STATUS (TABLE) Text (p054604-4) of Phys.Rev.C74(2006)054604 2295000500019 ENDBIB 17 0 2295000500020 NOCOMMON 0 0 2295000500021 DATA 5 1 2295000500022 EN-DUMMY DATA ERR-T ASSUM1 ASSUM2 2295000500023 EV B B B B 2295000500024 0.0253 568. 79. 4.2 3153. 2295000500025 ENDDATA 3 0 2295000500026 ENDSUBENT 25 0 2295000599999 SUBENT 22950006 20120614 22322295000600001 BIB 5 10 2295000600002 REACTION (71-LU-177-M(N,INL)71-LU-177-G,,SIG,,MXW/FCT,DERIV) 2295000600003 Maxwellian averaged inelastic cross section in the 2295000600004 Westcott convention multiplied by sqrt(pi)/2 2295000600005 FACILITY (REAC,2FR ILL) HFR/T4 (burnup) 2295000600006 (REAC,2FR SAC) ORPHEE/p1 (capture) 2295000600007 ANALYSIS burnup cross section minus capture cross section 2295000600008 MISC-COL (MISC) Epithermal/thermal neutron flux ratio 2295000600009 STATUS (TABLE) Table V of Phys.Rev.C74(2006)054604 2295000600010 (DEP,22950002) burnup cross section (624 +/- 93 b) 2295000600011 (DEP,22915002) capture cross section (370 +/- 25 b) 2295000600012 ENDBIB 10 0 2295000600013 NOCOMMON 0 0 2295000600014 DATA 4 1 2295000600015 KT-K DATA DATA-ERR MISC 2295000600016 K B B NO-DIM 2295000600017 323. 254. 96. 0.0005 2295000600018 ENDDATA 3 0 2295000600019 ENDSUBENT 18 0 2295000699999 SUBENT 22950007 20120614 22322295000700001 BIB 5 9 2295000700002 REACTION (71-LU-177-M(N,INL)71-LU-177-G,,SIG,,MXW/FCT,DERIV) 2295000700003 Maxwellian averaged inelastic cross section in the 2295000700004 Westcott convention multiplied by sqrt(pi)/2 2295000700005 FACILITY (REAC,2FR ILL) HFR/H9 2295000700006 ANALYSIS burnup cross section minus capture cross section 2295000700007 MISC-COL (MISC) Epithermal/thermal neutron flux ratio 2295000700008 STATUS (TABLE) Table V of Phys.Rev.C74(2006)054604 2295000700009 (DEP,22950003) burnup cross section (627 +/- 51 b) 2295000700010 (DEP,22915005) capture cross section (366 +/- 53 b) 2295000700011 ENDBIB 9 0 2295000700012 NOCOMMON 0 0 2295000700013 DATA 4 1 2295000700014 KT-K DATA DATA-ERR MISC 2295000700015 K B B NO-DIM 2295000700016 323. 261. 73. 0.015 2295000700017 ENDDATA 3 0 2295000700018 ENDSUBENT 17 0 2295000799999 SUBENT 22950008 20120614 22322295000800001 BIB 5 22 2295000800002 REACTION 1(71-LU-177-M(N,INL)71-LU-177-G,,SIG,,MXW/FCT,DERIV) 2295000800003 Maxwellian averaged inelastic cross section by the 2295000800004 Westcott convention multiplied by sqrt(pi)/2 2295000800005 2(71-LU-177-M(N,INL)71-LU-177-G,,SIG,,MXW/FCT,DERIV) 2295000800006 Maxwellian averaged inelastic cross section by the 2295000800007 Westcott convention multiplied by sqrt(pi)/2 2295000800008 ANALYSIS 1Average of two values from HFR/T4+ORPHEE/p1 and HFR/H9 2295000800009 2Averaged burnup x-sect. minus averaged capture x-sect. 2295000800010 COMMENT 2By Olivier Roig (2009-09-02): 2295000800011 The 2007 value was derived with the Maxwellian 2295000800012 averaged capture cross section at kT=0.0253 eV 2295000800013 without conversion to 323 K by temperature factor 2295000800014 (203.6/323.). Therefore the latest value from the 2295000800015 experiment is the 2006 value (258 +/- 58 b). 2295000800016 STATUS 1(TABLE) Text (p054604-5) of Phys.Rev.C74(2006)054604 2295000800017 (DEP,22950006) from HFR/T4 and ORPHEE/p1 (254 +/- 96 b)2295000800018 (DEP,22950007) from HFR/H9 (261 +/- 73 b)2295000800019 2(TABLE) Text (p464) of ND2007 Conf. Proc.1(2007)463 2295000800020 (DEP,22950004) averaged burnup x-section (626 +/- 45 b)2295000800021 (DEP,22150006) averaged capture x-sect. (369 +/- 23 b)2295000800022 (SPSDD,22950008) temperature factor missing 2295000800023 HISTORY (20081031A) Data taken from main reference 2295000800024 ENDBIB 22 0 2295000800025 NOCOMMON 0 0 2295000800026 DATA 5 1 2295000800027 KT-K DATA 1ERR-T 2DATA 2ERR-T 2 2295000800028 K B B B B 2295000800029 323. 258. 58. 257. 50. 2295000800030 ENDDATA 3 0 2295000800031 ENDSUBENT 30 0 2295000899999 NOSUBENT 22950009 20120614 22322295000900001 NOSUBENT 22950010 20081228 22052295001000001 ENDENTRY 10 0 2295099999999