ENTRY 14574 20191020 14761457400000001 SUBENT 14574001 20191020 14761457400100001 BIB 10 32 1457400100002 TITLE High resolution measurement of tagged two-neutron 1457400100003 energy and angle correlations in 252Cf (sf) 1457400100004 AUTHOR (P.F.Schuster,M.J.Marcath,S.Marin,S.D.Clarke,M.Devlin, 1457400100005 R.C.Haight,R.Vogt,P.Talou,I.Stetcu,T.Kawano,J.Randrup, 1457400100006 S.A.Pozzi) 1457400100007 INSTITUTE (1USAMHG,1USALAS,1USALRL,1USADAV,1USABRK) 1457400100008 REFERENCE (J,PR/C,100,014605,2019) 1457400100009 FACILITY Measurements of spontaneous fission events were 1457400100010 performed using Chi-Nu array at LANSCE, Los Alamos 1457400100011 DETECTOR (FISCH) The 252Cf fission source was deposited over 1457400100012 a hemispherical fission chamber. One or two fission 1457400100013 fragments may have triggered the fission chamber. 1457400100014 Fixed threshold was applied to exclude alpha-particle 1457400100015 interactions. 1457400100016 (SCIN) A Chi-Nu detector array consisting of 54 EJ309 1457400100017 liquid scintillator detectors mounted at 15deg 1457400100018 intervals along six arcs to form a hemispherical 1457400100019 distribution of detectors was used for neutron 1457400100020 detection. Each EJ309 detector was cylindrical, 17.78 1457400100021 cm in diameter and 5.08 cm thick, coupled to a 1457400100022 12.7-cm-diam photomultiplier tube Hamamatsu R4144. 1457400100023 Only 42 detectors were used in the present experiment 1457400100024 forming altogether 861 pairs of detectors at angles 1457400100025 from 15deg to 180deg. The fission chamber with 252Cf 1457400100026 source was placed in the center of the array. 1457400100027 METHOD (TOF,PSD) Time of flight between fission fragment and 1457400100028 neutron detection was used for neutron energy 1457400100029 determination. 1457400100030 INC-SOURCE (CF252) The 252Cf spontaneous fission count rate 1457400100031 was 2.98E+5 fissions/sec. 1457400100032 ERR-ANALYS (DATA-ERR) Origin of uncertainties not described 1457400100033 HISTORY (20191020C) Compiled by S.H. 1457400100034 ENDBIB 32 0 1457400100035 NOCOMMON 0 0 1457400100036 ENDSUBENT 35 0 1457400199999 SUBENT 14574002 20191020 14761457400200001 BIB 2 6 1457400200002 REACTION (98-CF-252(0,F),PR/PAR,NU/DA,,MSC) 1457400200003 Bicorrelation neutron count rate normalized by integral1457400200004 as a function of relative angle. Neutron energy is in 1457400200005 Interval 1-4 MeV 1457400200006 STATUS (TABLE) Data presented in fig. 6a sent by 1457400200007 author P.F.Sch. 1457400200008 ENDBIB 6 0 1457400200009 COMMON 2 3 1457400200010 E-MIN E-MAX 1457400200011 MEV MEV 1457400200012 1. 4. 1457400200013 ENDCOMMON 3 0 1457400200014 DATA 4 15 1457400200015 ANG-MIN ANG-MAX DATA DATA-ERR 1457400200016 ADEG ADEG ARB-UNITS ARB-UNITS 1457400200017 20. 30. 0.068208 0.00282 1457400200018 30. 40. 0.064216 0.002008 1457400200019 40. 50. 0.06021 0.001518 1457400200020 50. 60. 0.055947 0.001668 1457400200021 60. 70. 0.053399 0.001932 1457400200022 80. 90. 0.051531 0.001145 1457400200023 90. 100. 0.052084 0.001308 1457400200024 100. 110. 0.054075 0.00234 1457400200025 110. 120. 0.056117 0.002245 1457400200026 120. 130. 0.061026 0.002006 1457400200027 130. 140. 0.065777 0.001667 1457400200028 140. 150. 0.070823 0.001608 1457400200029 150. 160. 0.074807 0.002159 1457400200030 160. 170. 0.078655 0.000876 1457400200031 170. 180. 0.080747 0.001409 1457400200032 ENDDATA 17 0 1457400200033 ENDSUBENT 32 0 1457400299999 SUBENT 14574003 20191020 14761457400300001 BIB 2 4 1457400300002 REACTION ((98-CF-252(0,F),PR/PAR,NU/DA)// 1457400300003 (98-CF-252(0,F),PR/PAR,NU/DA)) 1457400300004 STATUS (TABLE) Data presented in fig. 7a sent by 1457400300005 author P.F.Sch. 1457400300006 ENDBIB 4 0 1457400300007 COMMON 2 3 1457400300008 ANG-NM ANG-DN 1457400300009 ADEG ADEG 1457400300010 175.0 85.0 1457400300011 ENDCOMMON 3 0 1457400300012 DATA 3 14 1457400300013 E-MIN DATA DATA-ERR 1457400300014 MEV NO-DIM NO-DIM 1457400300015 1.2 1.590742 0.045185 1457400300016 1.4 1.628029 0.050823 1457400300017 1.6 1.671889 0.058901 1457400300018 1.8 1.725056 0.064493 1457400300019 2. 1.77464 0.071873 1457400300020 2.2 1.809143 0.082497 1457400300021 2.4 1.870117 0.08742 1457400300022 2.6 1.931472 0.114994 1457400300023 2.8 2.007181 0.143094 1457400300024 3. 2.059003 0.200745 1457400300025 3.2 2.12013 0.258779 1457400300026 3.4 2.094623 0.372404 1457400300027 3.6 2.035816 0.558271 1457400300028 3.8 1.936426 1.146925 1457400300029 ENDDATA 16 0 1457400300030 ENDSUBENT 29 0 1457400399999 SUBENT 14574004 20191020 14761457400400001 BIB 2 5 1457400400002 REACTION (98-CF-252(0,F)0-NN-1,PR/PAR,KE,,MSC) 1457400400003 Average neutron energy as a function of neutron 1457400400004 correlation angle in energy range of 1 to 4 MeV. 1457400400005 STATUS (TABLE) Data taken from fig. 8a, waiting for data 1457400400006 from author. 1457400400007 ENDBIB 5 0 1457400400008 COMMON 2 3 1457400400009 E-MIN E-MAX 1457400400010 MEV MEV 1457400400011 1. 4. 1457400400012 ENDCOMMON 3 0 1457400400013 DATA 4 17 1457400400014 ANG-MIN ANG-MAX DATA DATA-ERR 1457400400015 ADEG ADEG MEV MEV 1457400400016 10. 20. 2.40 0.01 1457400400017 20. 30. 2.36 0.01 1457400400018 30. 40. 2.35 0.01 1457400400019 40. 50. 2.34 0.01 1457400400020 50. 60. 2.32 0.01 1457400400021 60. 70. 2.31 0.01 1457400400022 70. 80. 2.31 0.01 1457400400023 80. 90. 2.30 0.01 1457400400024 90. 100. 2.30 0.01 1457400400025 100. 110. 2.30 0.01 1457400400026 110. 120. 2.31 0.01 1457400400027 120. 130. 2.32 0.01 1457400400028 130. 140. 2.34 0.01 1457400400029 140. 150. 2.35 0.01 1457400400030 150. 160. 2.36 0.01 1457400400031 160. 170. 2.37 0.01 1457400400032 170. 180. 2.38 0.02 1457400400033 ENDDATA 19 0 1457400400034 ENDSUBENT 33 0 1457400499999 ENDENTRY 4 0 1457499999999