ENTRY 22924 20160726 22522292400000001 SUBENT 22924001 20160726 22522292400100001 BIB 16 58 2292400100002 TITLE Thermal neutron capture cross-section measurements of 2292400100003 243-Am and 242-Pu using the mini-INCA alpha- and 2292400100004 gamma-spectroscopy station 2292400100005 AUTHOR (F.Marie,A.Letourneau,G.Fioni,O.Deruelle,Ch.Veyssiere, 2292400100006 H.Faust,P.Mutti,I.AlMahamid,B.Muhammad) 2292400100007 INSTITUTE (2FR SAC) -Marie,Letourneau,Fioni,Deruelle,Veyssiere 2292400100008 (2FR ILL) -Faust,Mutti 2292400100009 (1USABRK) -Almahamid,Muhammad 2292400100010 REFERENCE (J,NIM/A,556,547,2006) 2292400100011 (W,LETOURNEAU,2003) Internal Report DAPNIA-03-243, 2292400100012 2003. Experimental and analysis details 2292400100013 FACILITY (REAC,2FR ILL) High flux reactor of Laue-Langevin Inst.2292400100014 in Grenoble, 2292400100015 Mini-INCA (INcineration of Actinides) set-up. 2292400100016 Mini-INCA chamber was housed inside a casemate 2292400100017 composed by layer B4-C blanket surrounded by 5 cm 2292400100018 borated polyethylene layer protected by 5cm lead layer2292400100019 H9 beam channel for short-time irradiated samples. 2292400100020 INC-SOURCE (REAC) Flux intensity Of 6.1E+14 n/cm2/sec. 2292400100021 INC-SPECT Thermal neutrons of H9 beam channel. 2292400100022 Epithermal component- 2% of neutrons with energy >12292400100023 METHOD (ACTIV) Irradiation time for Am-243 - 3h 28 min, 2292400100024 for Pu-242 - 2 days. 2292400100025 (ASPEC,GSPEC) Off-line alpha- and gamma- spectroscopies2292400100026 of irradiated samples. 2292400100027 (STTA) Monitor irradiated with actinide samples 2292400100028 MONITOR ((MONIT)27-CO-59(N,G)27-CO-60,,SIG,,MXW) Averaged in 2292400100029 H9 flux,for flux intensity determination. 2292400100030 MONIT-REF (,R.B.Firestone,B,FIRESTONE,,1996) Table of Isotopes 2292400100031 SAMPLE 6 mm diameter Al foil doped with 0.1% 59-Co,irradiated2292400100032 together with actinide samples. Homogeneity of 59-Co 2292400100033 inside Al foil - 2%.,weigheted masses of monitors were2292400100034 7.43+-0.05 mg. 2292400100035 PART-DET (A) 2292400100036 (G) 2292400100037 DETECTOR (SIBAR) Passivated Implanted Planar Silicon alpha- 2292400100038 detector of 300 micron thickness and 1.13 cm diameter. 2292400100039 3mm Al plate collimator. Typical resolution 17 keV for 2292400100040 241-Am alpha-particles. Detector was calibrated in 2292400100041 energy with standard sources of 241-Am and 244-Cu. 2292400100042 (HPGE) High-purity coaxial germanium GX1518 gamma- 2292400100043 detector of 4 cm thickness and 5.15 cm diameter, with 2292400100044 500 microm carbon-epoxy entrance window. 7cm lead 2292400100045 collimator. 2292400100046 Typical resolution 1.8 keV at 1.173 MeV. Detector was 2292400100047 calibrated in energy with standard sources of 154-Eu, 2292400100048 241-Am, 60-Co. Efficiency 0.098+-0.002 at 1.17 MeV. 2292400100049 ERR-ANALYS (DATA-ERR) Error of data 2292400100050 (ERR-1) Uncertainty of neutron flux 2292400100051 (ERR-2) Uncertainty of alpha- detection 2292400100052 (ERR-3) Uncertainty of gamma-detection(maximal) 2292400100053 COMMENT E-mail of of corresponding author: 2292400100054 aletourneau@cea.fr 2292400100055 HISTORY (20060416C) M.M./S.M. 2292400100056 (20061113A) Corrected by S.M. 2292400100057 (20160726U) SD: Entry was re-transmitted to exclude 2292400100058 difference between trans.2181 and Master file. 2292400100059 Small additional corrections. ERR-ANALYS update. 2292400100060 ENDBIB 58 0 2292400100061 COMMON 5 3 2292400100062 ERR-1 ERR-2 ERR-3 MONIT MONIT-ERR 2292400100063 PER-CENT PER-CENT PER-CENT B B 2292400100064 3.8 3. 2. 31.1 0.19 2292400100065 ENDCOMMON 3 0 2292400100066 ENDSUBENT 65 0 2292400199999 SUBENT 22924002 20160726 22522292400200001 BIB 8 15 2292400200002 REACTION (95-AM-243(N,G)95-AM-244,,SIG,,MXW) Averaged over 2292400200003 neutron spectrum similar to Maxwellian, 2292400200004 ANALYSIS .Data obtained by measurement of Cm-244 alpha activity 2292400200005 INC-SPECT .Thermal neutron spectrum similar to Maxwell. 2292400200006 2% epithermal part 2292400200007 SAMPLE 11.7 microgram of pure Am-243. Isotopic concentration 2292400200008 before irradiation: Am-243 - 99.987%, Am-242 - 0.002%,2292400200009 Am-241 - 0.011%. 2292400200010 DECAY-DATA (96-CM-244,18.1YR,A,5804.8,0.764, 2292400200011 A,5762.7,0.236) 2292400200012 ERR-ANALYS (ERR-4) Error of intensity values, given in DECAY-DATA 2292400200013 STATUS (TABLE) Text on p.552 of NIM/A,556,547,2006 2292400200014 HISTORY (20061113A) SF5 'CUM' added,SF4 changed 2292400200015 (20160726U) SD: SF5=(CUM) deleted from REACTION code 2292400200016 (as it is given in Master file). 2292400200017 ENDBIB 15 0 2292400200018 COMMON 1 3 2292400200019 ERR-4 2292400200020 PER-CENT 2292400200021 0.2 2292400200022 ENDCOMMON 3 0 2292400200023 DATA 3 1 2292400200024 EN-DUMMY DATA DATA-ERR 2292400200025 EV B B 2292400200026 0.025 74.1 3.3 2292400200027 ENDDATA 3 0 2292400200028 ENDSUBENT 27 0 2292400299999 SUBENT 22924003 20160726 22522292400300001 BIB 4 9 2292400300002 REACTION (95-AM-243(N,G)95-AM-244,,SIG,,,DERIV) Derived 2292400300003 experimental c-s using corrections 2292400300004 ANALYSIS .Contribution of non-thermal neutrons was taken into 2292400300005 account by correction factor 0.905. 2292400300006 STATUS (DEP,22924002) 2292400300007 (TABLE) Table 2 of NIM/A,556,547,2006 2292400300008 HISTORY (20061113A) SF5 'CUM' added, SF4 changed 2292400300009 (20160726U) SD: SF5=(CUM) deleted from REACTION code 2292400300010 (as it is given in Master file). 2292400300011 ENDBIB 9 0 2292400300012 NOCOMMON 0 0 2292400300013 DATA 3 1 2292400300014 EN DATA DATA-ERR 2292400300015 EV B B 2292400300016 0.025 81.8 3.6 2292400300017 ENDDATA 3 0 2292400300018 ENDSUBENT 17 0 2292400399999 SUBENT 22924004 20160726 22522292400400001 BIB 7 15 2292400400002 REACTION (95-AM-243(N,G)95-AM-244-G,,SIG,,MXW) Averaged over 2292400400003 Thermal neutron spectrum 2292400400004 INC-SPECT .Thermal neutron spectrum similar to Maxwell. 2292400400005 DECAY-DATA (95-AM-244-G,10.1HR,DG,744.,0.66, 2292400400006 DG,898.,0.28) 2292400400007 SAMPLE 11.7 microgram of pure Am-243.Isotopic concentration 2292400400008 before irradiation: Am-243 - 99.987%, Am-242 - 0.002%,2292400400009 Am-241 - 0.011%. 2292400400010 ERR-ANALYS (ERR-4) Error of intensity value of 744.keV gamma-line 2292400400011 given in DECAY-DATA 2292400400012 (ERR-5) Error of intensity value of 898.keV gamma-line 2292400400013 given in DECAY-DATA 2292400400014 ANALYSIS Fitting gamma-photopeak with Gaussian function added 2292400400015 to linear background 2292400400016 STATUS (TABLE) Text on p.553 of NIM/A,556,547,2006 2292400400017 ENDBIB 15 0 2292400400018 COMMON 2 3 2292400400019 ERR-4 ERR-5 2292400400020 PER-CENT PER-CENT 2292400400021 18. 8. 2292400400022 ENDCOMMON 3 0 2292400400023 DATA 3 1 2292400400024 EN-DUMMY DATA DATA-ERR 2292400400025 EV B B 2292400400026 0.025 4.7 1.4 2292400400027 ENDDATA 3 0 2292400400028 ENDSUBENT 27 0 2292400499999 SUBENT 22924005 20160726 22522292400500001 BIB 3 6 2292400500002 REACTION (95-AM-243(N,G)95-AM-244-G,,SIG,,,DERIV) Derived 2292400500003 experimental cross-section 2292400500004 ANALYSIS .Contribution of non-thermal neutrons was taken into 2292400500005 account by correction factor 0.905. 2292400500006 STATUS (DEP,22924004) 2292400500007 (TABLE) Text on p.553 of NIM/A,556,547,2006 2292400500008 ENDBIB 6 0 2292400500009 NOCOMMON 0 0 2292400500010 DATA 3 1 2292400500011 EN DATA DATA-ERR 2292400500012 EV B B 2292400500013 0.025 5.2 1.56 2292400500014 ENDDATA 3 0 2292400500015 ENDSUBENT 14 0 2292400599999 SUBENT 22924006 20160726 22522292400600001 BIB 5 9 2292400600002 REACTION (94-PU-242(N,G)94-PU-243,,SIG,,MXW) Averaged over 2292400600003 Thermal neutron spectrum 2292400600004 INC-SPECT .Thermal neutron spectrum similar to Maxwell. 2292400600005 SAMPLE .10.5 microgram of Pu-242.Isotopic composition before 2292400600006 irradiation: Pu-242 - 99.932%, Pu-238 - 0.004%, 2292400600007 Pu-239 - 0.005%, Pu-240 - 0.022%, Pu-241 - 0.035%, 2292400600008 Pu-244 - 0.002%. 2292400600009 DECAY-DATA (95-AM-243,7370.YR,A) 2292400600010 STATUS (TABLE) Text on p.554 of NIM/A,556,547,2006 2292400600011 ENDBIB 9 0 2292400600012 NOCOMMON 0 0 2292400600013 DATA 3 1 2292400600014 EN-DUMMY DATA DATA-ERR 2292400600015 EV B B 2292400600016 0.025 22.5 1.1 2292400600017 ENDDATA 3 0 2292400600018 ENDSUBENT 17 0 2292400699999 SUBENT 22924007 20160726 22522292400700001 BIB 3 6 2292400700002 REACTION (94-PU-242(N,G)94-PU-243,,SIG,,,DERIV) Derived 2292400700003 from experimental cross section 2292400700004 ANALYSIS .Contribution of non-thermal neutrons was taken into 2292400700005 account by correction factor 1.0 2292400700006 STATUS (DEP,22924006) 2292400700007 (TABLE) Text on p.554 of NIM/A,556,547,2006 2292400700008 ENDBIB 6 0 2292400700009 NOCOMMON 0 0 2292400700010 DATA 3 1 2292400700011 EN DATA DATA-ERR 2292400700012 EV B B 2292400700013 0.025 22.5 1.1 2292400700014 ENDDATA 3 0 2292400700015 ENDSUBENT 14 0 2292400799999 ENDENTRY 7 0 2292499999999