ENTRY L0263 20201217 L045L026300000001 SUBENT L0263001 20201217 L045L026300100001 BIB 13 44 L026300100002 TITLE Neutron-neutron correlations in the photofission of L026300100003 238U L026300100004 AUTHOR (J.Burggraf,D.S.Dale,T.Forest,G.Warren,S.Stave, L026300100005 S.Behling,E.Church) L026300100006 INSTITUTE (1USAISU,1USABNW) L026300100007 REFERENCE (J,PR/C,102,014612,2020) L026300100008 REL-REF (O,14698001,J.Burggraf+,J,PR/C,102,014612,2020) L026300100009 Spontaneous fisson data compiled in REL-REF L026300100010 FACILITY (LINAC,1USAISU) Experiment was performed at the Idaho L026300100011 Accelerator Center, using short-pulsed L026300100012 L-band-frequency electron linear accelerator L026300100013 SAMPLE Depleted uranium target in the shape of a thin strip L026300100014 with dimensions of 4 x 2 x 0.05 cm3 and a mass of 7.6g L026300100015 Depleted uranium contains typically 0.22% of 235U. L026300100016 DETECTOR (SCIN) Measurements were made using array of 14 L026300100017 polyvinyltoluene scintillation detectors. Ten L026300100018 detectors had dimensions 76.2 x 15.2 x 3.8 cm and L026300100019 four were of 1/3 of the length, i.e. 25.4 cm. Long L026300100020 detectors were readout at both ends using L026300100021 photomultipliers. Short detectors were read out using L026300100022 single PMT. All detectors vere arranged in vertical L026300100023 position in a circle around the target at a distance L026300100024 of (125+-9) cm from the target. L026300100025 METHOD (TOF) Neutron energy was determined using L026300100026 time of flight L026300100027 (COINC) Coincidence of two fission neutrons L026300100028 was required L026300100029 INC-SOURCE (BRST) Bremsstrahlung photons were produced by 10.5 L026300100030 MeV electrons impinging on an Al radiator. A sweeping L026300100031 magnet was placed downstream from the bremsstrahlung L026300100032 radiator to remove charged particles from the photon L026300100033 beam. The photom beam then traveled through a series L026300100034 of polyethylene and lead collimators to define the L026300100035 photon beam. L026300100036 ANALYSIS To account for efficiency and acceptance of detector L026300100037 array, correlations were calculated as a ratio of L026300100038 correlated neutron distribution from the same fission L026300100039 event and uncorrelated neutron distribution from two L026300100040 independent events. L026300100041 ERR-ANALYS (DATA-ERR) Origin of uncertainties not described L026300100042 All uncertainties correspond to 68% confidence L026300100043 interval L026300100044 (ANG-ERR) Uncertainty in n-n correlation angle L026300100045 HISTORY (20201217C) Compiled by S.H. L026300100046 ENDBIB 44 0 L026300100047 COMMON 2 3 L026300100048 ANG-ERR EN-DUMMY L026300100049 ADEG MEV L026300100050 6. 10.5 L026300100051 ENDCOMMON 3 0 L026300100052 ENDSUBENT 51 0 L026300199999 SUBENT L0263002 20201217 L045L026300200001 BIB 3 8 L026300200002 REACTION (92-U-238(G,F),PAR,DA,N+N,REL) L026300200003 Ratio of correlated yield versus uncorrelated yield L026300200004 EN-SEC (E1,N) L026300200005 (E2,N) L026300200006 STATUS (CURVE) Data taken from figs.24 of the reference L026300200007 Waiting for data from author L026300200008 (COREL,L0263003) Angular distribution with maximum L026300200009 neutron energy cut L026300200010 ENDBIB 8 0 L026300200011 NOCOMMON 0 0 L026300200012 DATA 5 30 L026300200013 E1-MIN E2-MIN ANG-RL DATA DATA-ERR L026300200014 MEV MEV ADEG ARB-UNITS ARB-UNITS L026300200015 0.4 0.4 30.4 2.433 0.075 L026300200016 0.4 0.4 46.2 1.975 0.066 L026300200017 0.4 0.4 61.8 1.654 0.066 L026300200018 0.4 0.4 77.4 1.421 0.075 L026300200019 0.4 0.4 93.4 1.492 0.066 L026300200020 0.4 0.4 109.5 1.584 0.066 L026300200021 0.4 0.4 125.1 1.914 0.066 L026300200022 0.4 0.4 140.9 2.046 0.066 L026300200023 0.4 0.4 156.7 2.459 0.066 L026300200024 0.4 0.4 172.3 2.186 0.106 L026300200025 1.4 1.4 31.9 3.929 0.141 L026300200026 1.4 1.4 47.5 2.992 0.128 L026300200027 1.4 1.4 63. 1.962 0.11 L026300200028 1.4 1.4 78.4 1.646 0.101 L026300200029 1.4 1.4 94.3 1.624 0.11 L026300200030 1.4 1.4 109.9 1.998 0.114 L026300200031 1.4 1.4 125.5 2.948 0.119 L026300200032 1.4 1.4 141.2 2.974 0.123 L026300200033 1.4 1.4 156.6 3.586 0.132 L026300200034 1.4 1.4 172.3 3.08 0.198 L026300200035 2.4 2.4 32. 4.21 0.29 L026300200036 2.4 2.4 47.8 2.89 0.26 L026300200037 2.4 2.4 63.2 1.27 0.2 L026300200038 2.4 2.4 78.8 1.02 0.18 L026300200039 2.4 2.4 94.4 1.86 0.24 L026300200040 2.4 2.4 110. 1.69 0.22 L026300200041 2.4 2.4 125.7 2.28 0.23 L026300200042 2.4 2.4 141.3 2.64 0.23 L026300200043 2.4 2.4 156.9 3.11 0.26 L026300200044 2.4 2.4 172.5 2.69 0.39 L026300200045 ENDDATA 32 0 L026300200046 ENDSUBENT 45 0 L026300299999 SUBENT L0263003 20201217 L045L026300300001 BIB 3 8 L026300300002 REACTION (92-U-238(G,F),PAR,DA,N+N,REL) L026300300003 Ratio of correlated yield versus uncorrelated yields L026300300004 EN-SEC (E1,N) L026300300005 (E2,N) L026300300006 STATUS (CURVE) Data taken from fig.25 of the reference L026300300007 Waiting for data from author L026300300008 (COREL,L0263002) Angular distribution without L026300300009 maximum neutron energy cut L026300300010 ENDBIB 8 0 L026300300011 NOCOMMON 0 0 L026300300012 DATA 7 20 L026300300013 E1-MIN E1-MAX E2-MIN E2-MAX ANG-RL DATA L026300300014 DATA-ERR L026300300015 MEV MEV MEV MEV ADEG ARB-UNITS L026300300016 ARB-UNITS L026300300017 0.4 1.4 0.4 1.4 30.3 1.13 L026300300018 0.16 L026300300019 0.4 1.4 0.4 1.4 46.1 0.72 L026300300020 0.13 L026300300021 0.4 1.4 0.4 1.4 61.9 0.96 L026300300022 0.14 L026300300023 0.4 1.4 0.4 1.4 77.7 1.03 L026300300024 0.14 L026300300025 0.4 1.4 0.4 1.4 93.5 1.52 L026300300026 0.16 L026300300027 0.4 1.4 0.4 1.4 109.1 1. L026300300028 0.14 L026300300029 0.4 1.4 0.4 1.4 124.9 1.05 L026300300030 0.14 L026300300031 0.4 1.4 0.4 1.4 140.7 1.36 L026300300032 0.16 L026300300033 0.4 1.4 0.4 1.4 156.5 1.34 L026300300034 0.16 L026300300035 0.4 1.4 0.4 1.4 172.3 0.93 L026300300036 0.21 L026300300037 1.4 2.4 1.4 2.4 32. 3.74 L026300300038 0.28 L026300300039 1.4 2.4 1.4 2.4 47.6 3.65 L026300300040 0.26 L026300300041 1.4 2.4 1.4 2.4 63.2 2.53 L026300300042 0.23 L026300300043 1.4 2.4 1.4 2.4 78.6 1.5 L026300300044 0.2 L026300300045 1.4 2.4 1.4 2.4 94.2 1.86 L026300300046 0.22 L026300300047 1.4 2.4 1.4 2.4 109.8 1.45 L026300300048 0.19 L026300300049 1.4 2.4 1.4 2.4 125.5 3.43 L026300300050 0.24 L026300300051 1.4 2.4 1.4 2.4 140.9 3.62 L026300300052 0.25 L026300300053 1.4 2.4 1.4 2.4 156.5 3.19 L026300300054 0.24 L026300300055 1.4 2.4 1.4 2.4 172.3 2.96 L026300300056 0.37 L026300300057 ENDDATA 44 0 L026300300058 ENDSUBENT 57 0 L026300399999 ENDENTRY 3 0 L026399999999