ENTRY 31614 20120405 31553161400000001 SUBENT 31614001 20120405 31553161400100001 BIB 12 42 3161400100002 TITLE Differential Cross-Section Measurement for the 3161400100003 64Zn(n,a) 61Ni Reaction at 5.03 and 5.95 MeV 3161400100004 AUTHOR (Guohui Zhang,Rongtai Cao,Jinxiang Chen,Guoyou Tang, 3161400100005 Yu.M.Gledenov, M.Sedysheva,G.Khuukhenkhuu) 3161400100006 INSTITUTE (3CPRBJG,4ZZZDUB) 3161400100007 REFERENCE (J,NSE,156,115,2007) 3161400100008 ((S,ISINN-14,223,2007)=(S,JINR-E3-2007-23,223,2007)) 3161400100009 Same (n,a) cross section given 3161400100010 ((S,ISINN-18,143,2011)=(S,JINR-E3-2011-26,143,2011)) 3161400100011 Same (n,a) cross section given 3161400100012 FACILITY (VDG,3CPRBJG) The 4.5-MV Van de Graaff accelerator of 3161400100013 the Institute of Heavy Ion Physics, Peking University.3161400100014 SAMPLE (30-ZN-64,ENR=0.994) 3161400100015 Two 64Zn samples (mass 4.05 +/- 0.05 mg and thickness 3161400100016 266.3 mg/cm2 each) attached back-to-back to the 3161400100017 common cathode were used for simultaneous alpha event 3161400100018 measurements of forward (0 to 90 deg) and backward 3161400100019 (90 to 180 deg) angles. 3161400100020 The isotopic abundance of the 64Zn samples was 99.4%. 3161400100021 Each sample was vacuumevaporated on a tantalum 3161400100022 backing 4.8 cm in diameter and 50 mm in thickness. 3161400100023 DETECTOR (IOCH) Twin-gridded ionization chamber. 3161400100024 The working gas of the ionization chamber was 3161400100025 Kr + 2.68%CO2. The pressures of the working gas were 3161400100026 1.40, and 1.65 atm for the 5.03, and 5.95 MeV 3161400100027 measurements, respectively. 3161400100028 (BF3) A BF3 long counter as a neutron flux monitor. 3161400100029 MONITOR (92-U-238(N,F),,SIG) 3161400100030 The absolute neutron flux was determined by measuring 3161400100031 the fission rate with a 238Ufoil (diam. 4.50 cm, 3161400100032 mass 7.85 +/- 0.10 mg, and abundance 99.999%) placed 3161400100033 at the third position of the sample changer. 3161400100034 MONIT-REF (,,3,ENDF/B-VII.0,,2006) 3161400100035 INC-SOURCE (D-D) Monoenergetic neutrons were produced through the 3161400100036 D(d,n)3He reaction with a deuterium gas target, 3161400100037 2.0 cm in length and 3.2 to 3.5 atm in pressure. 3161400100038 The gas cell was separated from the vacuum tube by a 3161400100039 molybdenum film 5 um in thickness. 3161400100040 STATUS (TABLE) Table 1-3 of Nucl.Sci.Eng.156(2007)115 3161400100041 (APRVD) Entry approved by Dr. Guohui Zhang 3161400100042 HISTORY (20080718C) 3161400100043 (20120405U) On. REFERENCE: ISINN-14 and -18 added 3161400100044 ENDBIB 42 0 3161400100045 COMMON 2 3 3161400100046 EN-NRM MONIT 3161400100047 MEV MB 3161400100048 5.03 540.7 3161400100049 ENDCOMMON 3 0 3161400100050 ENDSUBENT 49 0 3161400199999 SUBENT 31614002 20080718 31293161400200001 BIB 5 9 3161400200002 REACTION (30-ZN-64(N,A)28-NI-61,PAR,SIG) tbl. 3 3161400200003 ANALYSIS (INTAD) Angle-integrated cross sections are derived 3161400200004 from the differential data through the second-order 3161400200005 polynomial fitting. 3161400200006 EN-SEC (E-LVL-MIN,28-NI-61) 3161400200007 (E-LVL-MAX,28-NI-61) 3161400200008 ERR-ANALYS (ERR-T) Total error 3161400200009 STATUS (DEP,31614004) 3161400200010 (DEP,31614005) 3161400200011 ENDBIB 9 0 3161400200012 NOCOMMON 0 0 3161400200013 DATA 5 4 3161400200014 EN E-LVL-MIN E-LVL-MAX DATA ERR-T 3161400200015 MEV MEV MEV MB MB 3161400200016 5.03 0.0 0.283 41.3 2.5 3161400200017 5.03 0.656 37.8 2.8 3161400200018 5.95 0.0 0.283 26.5 1.7 3161400200019 5.95 0.656 49.3 3.8 3161400200020 ENDDATA 6 0 3161400200021 ENDSUBENT 20 0 3161400299999 SUBENT 31614003 20080718 31293161400300001 BIB 4 7 3161400300002 REACTION (30-ZN-64(N,A)28-NI-61,,SIG) tbl. 3 3161400300003 ANALYSIS (INTAD) Angle-integrated cross sections are derived 3161400300004 from the differential data through the second-order 3161400300005 polynomial fitting. 3161400300006 ERR-ANALYS (ERR-T) Total error 3161400300007 STATUS (DEP,31614004) 3161400300008 (DEP,31614005) 3161400300009 ENDBIB 7 0 3161400300010 NOCOMMON 0 0 3161400300011 DATA 3 2 3161400300012 EN DATA ERR-T 3161400300013 MEV MB MB 3161400300014 5.03 79.1 5.3 3161400300015 5.95 75.8 5.5 3161400300016 ENDDATA 4 0 3161400300017 ENDSUBENT 16 0 3161400399999 SUBENT 31614004 20080718 31293161400400001 BIB 3 15 3161400400002 REACTION (30-ZN-64(N,A)28-NI-61,PAR,DA) tbl.1,2 3161400400003 EN-SEC (E-LVL-MIN,28-NI-61) 3161400400004 (E-LVL-MAX,28-NI-61) 3161400400005 ERR-ANALYS (ERR-SYS) The scale errors for the differential data 3161400400006 come from: 3161400400007 * the uncertainty of neutron flux determination is 3161400400008 3.6% (including the uncertainty of the fission 3161400400009 counts is 2.2%, the error of the reference cross 3161400400010 section at 5.03 MeV is 2.6%, the 238U atom number 3161400400011 error is 1.3% 3161400400012 * the error of the 64Zn atom number (1.2%). 3161400400013 (DATA-ERR) The errors in include: 3161400400014 * statistical errors (3 - 6%), 3161400400015 * background subtraction errors (4 - 6%), 3161400400016 * 90-deg line determination uncertainties (2 - 4%). 3161400400017 ENDBIB 15 0 3161400400018 COMMON 2 3 3161400400019 EN ERR-SYS 3161400400020 MEV PER-CENT 3161400400021 5.03 3.8 3161400400022 ENDCOMMON 3 0 3161400400023 DATA 5 32 3161400400024 E-LVL-MIN E-LVL-MAX COS-CM DATA-CM DATA-ERR 3161400400025 MEV MEV NO-DIM MB/SR PER-CENT 3161400400026 0. 0.283 -0.952 3.67 7.2 3161400400027 0. 0.283 -0.857 4.03 7.2 3161400400028 0. 0.283 -0.761 3.66 6.2 3161400400029 0. 0.283 -0.664 3.37 6.2 3161400400030 0. 0.283 -0.567 3.25 6.2 3161400400031 0. 0.283 -0.469 2.85 6.7 3161400400032 0. 0.283 -0.371 2.86 6.7 3161400400033 0. 0.283 -0.273 2.46 7.7 3161400400034 0. 0.283 0.227 2.64 7.5 3161400400035 0. 0.283 0.329 3.09 6.5 3161400400036 0. 0.283 0.43 3.34 6.5 3161400400037 0. 0.283 0.533 3.51 6. 3161400400038 0. 0.283 0.636 3.68 6. 3161400400039 0. 0.283 0.739 4.19 6. 3161400400040 0. 0.283 0.843 4.34 7. 3161400400041 0. 0.283 0.948 4.85 7. 3161400400042 0.656 -0.952 3.24 8.6 3161400400043 0.656 -0.857 3. 8.6 3161400400044 0.656 -0.761 3.29 7.8 3161400400045 0.656 -0.665 2.96 7.8 3161400400046 0.656 -0.568 3.26 7.8 3161400400047 0.656 -0.47 3.3 7.8 3161400400048 0.656 -0.372 2.96 8. 3161400400049 0.656 -0.274 2.75 8.8 3161400400050 0.656 0.226 2.76 8.6 3161400400051 0.656 0.327 2.88 8. 3161400400052 0.656 0.429 3.13 7.8 3161400400053 0.656 0.532 3.2 7.8 3161400400054 0.656 0.635 3.37 7.8 3161400400055 0.656 0.739 3.3 7.8 3161400400056 0.656 0.843 3.27 8.5 3161400400057 0.656 0.947 3.13 8.5 3161400400058 ENDDATA 34 0 3161400400059 ENDSUBENT 58 0 3161400499999 SUBENT 31614005 20080718 31293161400500001 BIB 3 16 3161400500002 REACTION (30-ZN-64(N,A)28-NI-61,PAR,DA) tbl.1,2 3161400500003 EN-SEC (E-LVL-MIN,28-NI-61) 3161400500004 (E-LVL-MAX,28-NI-61) 3161400500005 ERR-ANALYS (ERR-SYS) The scale errors for the differential data 3161400500006 come from: 3161400500007 * the uncertainty of neutron flux determination is 3161400500008 4.2% (including the uncertainty of the fission 3161400500009 counts is 2.2%, the error of the reference cross 3161400500010 section at 5.03 MeV is 2.6%, the 238U atom number 3161400500011 error is 1.3%, and the BF3 relative efficiency 3161400500012 shape error in the 5.0- to 6.0- MeV range is 2.0%).3161400500013 * the error of the 64Zn atom number (1.2%). 3161400500014 (DATA-ERR) The errors in include: 3161400500015 * statistical errors (3 - 6%), 3161400500016 * background subtraction errors (4 - 6%), 3161400500017 * 90-deg line determination uncertainties (2 - 4%). 3161400500018 ENDBIB 16 0 3161400500019 COMMON 2 3 3161400500020 EN ERR-SYS 3161400500021 MEV PER-CENT 3161400500022 5.95 4.4 3161400500023 ENDCOMMON 3 0 3161400500024 DATA 5 32 3161400500025 E-LVL-MIN E-LVL-MAX COS-CM DATA-CM DATA-ERR 3161400500026 MEV MEV NO-DIM MB/SR PER-CENT 3161400500027 0. 0.283 -0.952 2.72 7.6 3161400500028 0. 0.283 -0.857 2.65 7.6 3161400500029 0. 0.283 -0.761 2.51 7. 3161400500030 0. 0.283 -0.664 2.36 7. 3161400500031 0. 0.283 -0.567 2.03 7.3 3161400500032 0. 0.283 -0.47 1.72 7.6 3161400500033 0. 0.283 -0.372 1.78 7.6 3161400500034 0. 0.283 -0.274 1.61 8.5 3161400500035 0. 0.283 0.226 1.82 8.5 3161400500036 0. 0.283 0.328 1.82 7.7 3161400500037 0. 0.283 0.43 2.17 7.3 3161400500038 0. 0.283 0.532 2.45 7. 3161400500039 0. 0.283 0.635 2.53 7. 3161400500040 0. 0.283 0.739 2.64 7. 3161400500041 0. 0.283 0.843 2.62 7.8 3161400500042 0. 0.283 0.948 2.36 7.8 3161400500043 0.656 -0.953 3.86 8.3 3161400500044 0.656 -0.857 3.74 8.3 3161400500045 0.656 -0.761 3.47 7.7 3161400500046 0.656 -0.665 3.71 7.7 3161400500047 0.656 -0.568 3.39 7.7 3161400500048 0.656 -0.471 3.58 7.7 3161400500049 0.656 -0.373 3.5 7.7 3161400500050 0.656 -0.275 3.31 8.4 3161400500051 0.656 0.225 4.21 8.3 3161400500052 0.656 0.327 4.25 7.5 3161400500053 0.656 0.429 4.22 7.5 3161400500054 0.656 0.531 4.26 7.5 3161400500055 0.656 0.635 4.43 7.5 3161400500056 0.656 0.738 4.79 7.5 3161400500057 0.656 0.843 4.51 8.2 3161400500058 0.656 0.947 4.12 8.3 3161400500059 ENDDATA 34 0 3161400500060 ENDSUBENT 59 0 3161400599999 ENDENTRY 5 0 3161499999999