ENTRY 33037 20120723 31573303700000001 SUBENT 33037001 20120723 31573303700100001 BIB 12 49 3303700100002 TITLE Measurement of neutron-induced reaction cross 3303700100003 sections in zirconium isotopes at thermal, 2.45 MeV 3303700100004 and 9.85 MeV energies 3303700100005 AUTHOR (P.M.Prajapati, S.Mukherjee, H.Naik, A.Goswami, 3303700100006 S.V.Suryanarayana, S.C.Sharma, B.S.Shivashankar, 3303700100007 V.K.Mulik, K.C.Jagdeesan, S.V.Thakre, S.Bisnoi, 3303700100008 T.Patel, K.K.Rasheed, S.Ganesan) 3303700100009 INSTITUTE (3INDBDA,3INDTRM,3INDIND,3INDPOO) 3303700100010 3INDIND-Manipal University-576104 3303700100011 REFERENCE (J,NSE,171,78,2012) 3303700100012 SAMPLE Thermal: 3303700100013 0.3268 g and ~1 mm thick natural Zr metal foil, and 3303700100014 0.0215 g Au metal foil (neutron flux monitor) wrapped 3303700100015 separately with 0.025 mm thick aluminium foil in 3303700100016 alkathene bags. 3303700100017 2.45 MeV: 3303700100018 Two samples, 0.0952 g, 1 mm thick natural Zr metal 3303700100019 foil and 0.057 g of In metal foil (neutron flux 3303700100020 monitor) wrapped separately with 0.025 mm thick Al 3303700100021 foil in alkathene bags. 3303700100022 9.85 MeV: 3303700100023 0.1694 g natural Zr metal foil and 1 mm thick of In 3303700100024 metal foil (neutron flux monitor) wrapped separately 3303700100025 with 0.025 mm thick Al foil in alkathene bags. 3303700100026 DETECTOR (HPGE) 80 cm3 HPGe detector coupled to a personal 3303700100027 computer-based 4 K multichannel analyzer. 3303700100028 The efficiency of the detector was 20% with energy 3303700100029 resolution of 2.0 keV FWHM at 1332.0 KeV. 3303700100030 ANALYSIS The observed photo-peak activity of gamma-lines was 3303700100031 obtained using PHAST peak fitting programme. 3303700100032 MONIT-REF (,,3,IRDF-2002,,2005) Values not given in the article 3303700100033 ERR-ANALYS (ERR-T) The overall uncertainty represents the 3303700100034 contribution from both random and systematic errors: 3303700100035 (ERR-S,10.,15.) Counting statistics (~10-15%) 3303700100036 (ERR-1) Neutron flux estimation (~4%) 3303700100037 (ERR-2) Irradiation time (~2%) 3303700100038 (ERR-3) Detection efficiency calibration (~3%) 3303700100039 (ERR-4) Half-life and gamma-ray abundances (~2%) 3303700100040 (ERR-SYS) The total systematic error (~4%) 3303700100041 CRITIQUE Naohiko Otsuka (2012-07-23): 3303700100042 The flux uncertainty 4% is coded as the common 3303700100043 uncertainty applicable to all cross section data 3303700100044 by the corresponding author (PrajapatI) in this 3303700100045 entry. It could be applicable only to 9.85 MeV data. 3303700100046 STATUS (APRVD) Entry approved by Mr. P.M. Prajapati 3303700100047 (TABLE) Table II of Nucl.Sci.Eng.171(2012)78 3303700100048 HISTORY (20120416C) Ms.Kajal Kapadia, Mr.P.M.Prajapati and 3303700100049 Dr.S.Mukherjee of M.S.University of Baroda, Vadodara 3303700100050 (20120723U) BL+On. Finalized 3303700100051 ENDBIB 49 0 3303700100052 COMMON 5 3 3303700100053 ERR-1 ERR-2 ERR-3 ERR-4 ERR-SYS 3303700100054 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 3303700100055 4. 2. 3. 2. 4. 3303700100056 ENDCOMMON 3 0 3303700100057 ENDSUBENT 56 0 3303700199999 SUBENT 33037002 20120723 31573303700200001 BIB 9 13 3303700200002 REACTION (40-ZR-94(N,G)40-ZR-95,,SIG,,SPA) 3303700200003 Not effective cross section in Westcott's convention 3303700200004 FACILITY (REAC,3INDTRM) APSARA Reactor, BARC 3303700200005 SAMPLE (40-ZR-94,NAT=0.1738) 3303700200006 INC-SOURCE (REAC) APSARA reactor 3303700200007 METHOD (ACTIV) Irradiated for 6 h 30 min 3303700200008 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 3303700200009 Monitored neutron flux was 1.105 x 10**8 n/cm2/s. 3303700200010 DECAY-MON (79-AU-198,2.272D,DG,411.80,0.9562) 3303700200011 DECAY-DATA (40-ZR-95,64.03D,DG,724.19,0.4427, 3303700200012 DG,756.72,0.5438) 3303700200013 CRITIQUE Shoji Nakamura (2012-07-12): 3303700200014 Monitored by Au foil only. No thermal flux determined.3303700200015 ENDBIB 13 0 3303700200016 NOCOMMON 0 0 3303700200017 DATA 3 1 3303700200018 EN-DUMMY DATA ERR-T 3303700200019 EV MB MB 3303700200020 0.0253 51.25 7.68 3303700200021 ENDDATA 3 0 3303700200022 ENDSUBENT 21 0 3303700299999 SUBENT 33037003 20120723 31573303700300001 BIB 9 12 3303700300002 REACTION (40-ZR-96(N,G)40-ZR-97,,SIG,,SPA) 3303700300003 Not effective cross section in Westcott's convention 3303700300004 FACILITY (REAC,3INDTRM) APSARA Reactor, BARC 3303700300005 SAMPLE (40-ZR-96,NAT=0.028) 3303700300006 INC-SOURCE (REAC) APSARA reactor, 3303700300007 METHOD (ACTIV,GSPEC) Irradiated for 6 h 30 min 3303700300008 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 3303700300009 Monitored neutron flux was 1.105 x 10**8 n/cm2/s. 3303700300010 DECAY-MON (79-AU-198,2.272D,DG,411.80,0.9562) 3303700300011 DECAY-DATA (40-ZR-97,16.74HR,DG,743.36,0.9369) 3303700300012 CRITIQUE Shoji Nakamura (2012-07-12): 3303700300013 Monitored by Au foil only. No thermal flux determined.3303700300014 ENDBIB 12 0 3303700300015 NOCOMMON 0 0 3303700300016 DATA 3 1 3303700300017 EN-DUMMY DATA ERR-T 3303700300018 EV MB MB 3303700300019 0.0253 24.30 3.88 3303700300020 ENDDATA 3 0 3303700300021 ENDSUBENT 20 0 3303700399999 SUBENT 33037004 20120723 31573303700400001 BIB 8 10 3303700400002 REACTION (40-ZR-94(N,G)40-ZR-95,,SIG) 3303700400003 FACILITY (CCW,3INDTRM) Purnima D-D Neutron Generator 3303700400004 SAMPLE (40-ZR-94,NAT=0.1738) 3303700400005 INC-SOURCE (D-D) Purnima Neutron Generator 3303700400006 METHOD (ACTIV,GSPEC) Irradiated for 2 h 30 min 3303700400007 MONITOR (49-IN-115(N,INL)49-IN-115-M,,SIG) 3303700400008 Monitored neutron flux was 2.1 x 10**5 n/cm2/s. 3303700400009 DECAY-MON (49-IN-115-M,4.486HR,DG,336.24,0.4580) 3303700400010 DECAY-DATA (40-ZR-95,64.03D,DG,724.19,0.4427, 3303700400011 DG,756.72,0.5438) 3303700400012 ENDBIB 10 0 3303700400013 NOCOMMON 0 0 3303700400014 DATA 3 1 3303700400015 EN DATA ERR-T 3303700400016 MEV MB MB 3303700400017 2.45 5.41 0.59 3303700400018 ENDDATA 3 0 3303700400019 ENDSUBENT 18 0 3303700499999 SUBENT 33037005 20120723 31573303700500001 BIB 8 10 3303700500002 REACTION (40-ZR-90(N,P)39-Y-90-M,,SIG) 3303700500003 FACILITY (VDGT,3INDTRM) 14 UD Pelletron Accelerator 3303700500004 SAMPLE No information on isotopic abundance for data reduction3303700500005 INC-SOURCE (P-LI7) Pelletron Accelerator 3303700500006 METHOD (ACTIV,GSPEC) Irradiated for 4 h and cooled for 2 h 3303700500007 MONITOR (49-IN-115(N,INL)49-IN-115-M,,SIG) 3303700500008 Monitored neutron flux was ~(1.3+/-0.05)x10**7 n/cm2/s.3303700500009 DECAY-MON (49-IN-115-M,4.486HR,DG,336.24,0.4580) 3303700500010 DECAY-DATA (39-Y-90-M,3.19HR,DG,202.53,0.9730, 3303700500011 DG,479.51,0.9074) 3303700500012 ENDBIB 10 0 3303700500013 NOCOMMON 0 0 3303700500014 DATA 4 1 3303700500015 EN EN-RSL DATA ERR-T 3303700500016 MEV MEV MB MB 3303700500017 9.85 0.38 3.1 0.45 3303700500018 ENDDATA 3 0 3303700500019 ENDSUBENT 18 0 3303700599999 ENDENTRY 5 0 3303799999999