ENTRY 14286 20220822 15001428600000001 SUBENT 14286001 20220822 15001428600100001 BIB 8 22 1428600100002 TITLE Gamma-ray multiplicity measurement of the spontaneous 1428600100003 fission of 252Cf in a segmented HPGe/BGO detector 1428600100004 array 1428600100005 AUTHOR (D.L.Bleuel,L.A.Bernstein,J.T.Burke,J.Gibelin, 1428600100006 M.D.Heffner,J.Mintz,E.B.Norman,L.Phair,N.D.Scielzo, 1428600100007 S.A.Sheets,N.J.Snyderman,M.A.Stoyer,M.Wiedeking) 1428600100008 INSTITUTE (1USALRL,1USABRK) 1428600100009 REFERENCE (J,NIM/A,624,691,2010) 1428600100010 SAMPLE Cf-252 source, 1.5E6 fission/minutes, on a nickel foil 1428600100011 backing, 90 microg/cm2 1428600100012 METHOD (COINC) Coincidence of gamma rays from fission 1428600100013 fragments 1428600100014 DETECTOR (HPGE) The experiment was performed using six EURISYS 1428600100015 high-purity germanium (HPGe) Clover detectors of the 1428600100016 Livermore-Berkeley Array for Collaborative Experiments1428600100017 Each Clover consists of four HPGe crystals in a shared1428600100018 cryostat surrounded by 16 SCIONIX bismuth-germanate 1428600100019 detectors. The system had high degree of segmentation 1428600100020 with 19 HPGe and 94 BGO detectors and good solid 1428600100021 angle coverage. 1428600100022 HISTORY (20110201) Compiled by S.H. 1428600100023 (20220730A) OS. REACTION in subs.4,5 modified 1428600100024 ENDBIB 22 0 1428600100025 NOCOMMON 0 0 1428600100026 ENDSUBENT 25 0 1428600199999 SUBENT 14286002 20120330 13791428600200001 BIB 3 5 1428600200002 REACTION (98-CF-252(0,F)0-G-0,NUM,FY,,REL) 1428600200003 Overall gamma ray multiplicity spectra 1428600200004 ERR-ANALYS (ERR-S) Statistical uncertainty 1428600200005 STATUS (TABLE ) Data presented in Fig. 6 of the reference 1428600200006 sent by author (D.L.B.) 1428600200007 ENDBIB 5 0 1428600200008 NOCOMMON 0 0 1428600200009 DATA 3 36 1428600200010 PART-OUT DATA ERR-S 1428600200011 NO-DIM ARB-UNITS ARB-UNITS 1428600200012 0.0 292.8E+5 124.8E+2 1428600200013 1.0 453.2E+6 580.1E+2 1428600200014 2.0 340.1E+6 340.2E+2 1428600200015 3.0 190.7E+6 196.4E+2 1428600200016 4.0 102.3E+6 119.5E+2 1428600200017 5.0 653.3E+5 880.6E+1 1428600200018 6.0 532.8E+5 777.9E+1 1428600200019 7.0 491.4E+5 735.4E+1 1428600200020 8.0 455.4E+5 701.3E+1 1428600200021 9.0 405.0E+5 657.8E+1 1428600200022 10.0 342.2E+5 602.3E+1 1428600200023 11.0 275.1E+5 538.7E+1 1428600200024 12.0 211.0E+5 471.1E+1 1428600200025 13.0 154.9E+5 403.5E+1 1428600200026 14.0 109.1E+5 338.7E+1 1428600200027 15.0 740.0E+4 279.5E+1 1428600200028 16.0 484.3E+4 226.8E+1 1428600200029 17.0 306.2E+4 181.4E+1 1428600200030 18.0 187.5E+4 143.3E+1 1428600200031 19.0 111.2E+4 111.9E+1 1428600200032 20.0 642.2E+3 869.5E+0 1428600200033 21.0 360.5E+3 672.9E+0 1428600200034 22.0 197.2E+3 522.7E+0 1428600200035 23.0 105.9E+3 411.2E+0 1428600200036 24.0 554.3E+2 330.6E+0 1428600200037 25.0 284.2E+2 273.7E+0 1428600200038 26.0 143.0E+2 233.5E+0 1428600200039 27.0 727.1E+1 204.1E+0 1428600200040 28.0 360.2E+1 181.9E+0 1428600200041 29.0 195.4E+1 166.5E+0 1428600200042 30.0 941.2E+0 153.7E+0 1428600200043 31.0 608.8E+0 144.3E+0 1428600200044 32.0 330.4E+0 133.7E+0 1428600200045 33.0 437.6E+0 127.4E+0 1428600200046 34.0 167.0E+0 121.2E+0 1428600200047 35.0 157.0E+0 111.3E+0 1428600200048 ENDDATA 38 0 1428600200049 ENDSUBENT 48 0 1428600299999 SUBENT 14286003 20120330 13791428600300001 BIB 4 7 1428600300002 REACTION 1(98-CF-252(0,F)42-MO-106,NUM,FY,G) 1428600300003 2(98-CF-252(0,F)46-PD-108,NUM,FY,G) 1428600300004 ANALYSIS Gamma ray multiplicities in both channels are 1428600300005 normalized to sum to unity. 1428600300006 ERR-ANALYS (ERR-S) Statistical uncertainty 1428600300007 STATUS (TABLE) Data presented in fig. 7 of the reference 1428600300008 sent by author (D.L.B.) 1428600300009 ENDBIB 7 0 1428600300010 NOCOMMON 0 0 1428600300011 DATA 5 28 1428600300012 PART-OUT DATA 1ERR-S 1DATA 2ERR-S 2 1428600300013 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 1428600300014 1.0 -4.96E-02 2.24E-03 5.64E-01 1.62E-03 1428600300015 2.0 8.18E-02 2.40E-03 2.65E-01 1.73E-03 1428600300016 5.0 9.65E-02 1.25E-03 7.59E-03 7.95E-04 1428600300017 6.0 1.07E-01 1.16E-03 2.24E-03 7.28E-04 1428600300018 7.0 1.11E-01 1.15E-03 1.95E-03 7.22E-04 1428600300019 8.0 1.07E-01 1.13E-03 1.21E-03 7.14E-04 1428600300020 9.0 9.85E-02 1.08E-03 2.19E-03 6.94E-04 1428600300021 10.0 8.23E-02 1.01E-03 1.71E-03 6.50E-04 1428600300022 11.0 6.39E-02 9.16E-04 1.11E-03 5.93E-04 1428600300023 12.0 4.76E-02 8.06E-04 1.78E-03 5.22E-04 1428600300024 13.0 3.54E-02 6.95E-04 2.16E-04 4.54E-04 1428600300025 14.0 2.29E-02 5.84E-04 1.51E-03 3.83E-04 1428600300026 15.0 1.50E-02 4.81E-04 6.28E-04 3.18E-04 1428600300027 16.0 1.04E-02 3.89E-04 2.86E-04 2.58E-04 1428600300028 17.0 6.26E-03 3.09E-04 3.94E-04 2.05E-04 1428600300029 18.0 3.17E-03 2.45E-04 1.82E-04 1.62E-04 1428600300030 19.0 2.29E-03 1.88E-04 2.30E-04 1.24E-04 1428600300031 20.0 8.80E-04 1.43E-04 2.32E-05 9.54E-05 1428600300032 21.0 7.29E-04 1.08E-04 -3.48E-05 7.12E-05 1428600300033 22.0 3.78E-04 8.01E-05 2.32E-05 5.44E-05 1428600300034 23.0 8.97E-05 6.04E-05 -2.13E-05 4.14E-05 1428600300035 24.0 1.11E-04 4.36E-05 -3.28E-05 2.99E-05 1428600300036 25.0 5.71E-05 3.21E-05 9.66E-06 2.23E-05 1428600300037 26.0 1.63E-05 2.61E-05 7.73E-06 1.68E-05 1428600300038 27.0 4.89E-06 1.85E-05 1.16E-05 1.22E-05 1428600300039 28.0 -1.63E-05 1.53E-05 -1.35E-05 1.21E-05 1428600300040 29.0 -1.63E-05 1.34E-05 -5.80E-06 9.27E-06 1428600300041 30.0 -9.78E-06 1.08E-05 1.93E-06 6.97E-06 1428600300042 ENDDATA 30 0 1428600300043 ENDSUBENT 42 0 1428600399999 SUBENT 14286004 20220822 15001428600400001 BIB 5 15 1428600400002 REACTION (98-CF-252(0,F)ELEM/MASS,NUM,FY,G,MSC) 1428600400003 ANALYSIS Number of emitted neutrons in various fission channels 1428600400004 was determined from correlated discrete gamma rays of 1428600400005 fission products 1428600400006 2n channel 106Mo x 144Ba 1428600400007 4n channel 106Mo x 142Ba 1428600400008 Multiplicities in both channels are normalized 1428600400009 to sum to unity. 1428600400010 This table contains the gamma ray multiplicity of event1428600400011 with 2 neutrons emitted. For the 4n channel see 1428600400012 subentry 5. 1428600400013 ERR-ANALYS (ERR-S) Statistical uncertainty 1428600400014 STATUS (TABLE) Data presented in fig. 12 of the reference 1428600400015 sent by author (D.L.B.) 1428600400016 HISTORY (20220730A) Added MSC to REACTION SF8 1428600400017 ENDBIB 15 0 1428600400018 COMMON 4 3 1428600400019 ELEM1 MASS1 ELEM2 MASS2 1428600400020 NO-DIM NO-DIM NO-DIM NO-DIM 1428600400021 42. 106. 56. 144. 1428600400022 ENDCOMMON 3 0 1428600400023 DATA 3 29 1428600400024 PART-OUT DATA ERR-S 1428600400025 NO-DIM NO-DIM NO-DIM 1428600400026 2.0 1.59E-02 6.31E-03 1428600400027 3.0 1.20E-02 9.35E-03 1428600400028 4.0 1.15E-02 1.10E-02 1428600400029 5.0 6.37E-02 1.20E-02 1428600400030 6.0 8.74E-02 1.34E-02 1428600400031 7.0 7.78E-02 1.52E-02 1428600400032 8.0 1.10E-01 1.71E-02 1428600400033 9.0 1.13E-01 1.85E-02 1428600400034 10.0 1.11E-01 1.93E-02 1428600400035 11.0 1.08E-01 1.92E-02 1428600400036 12.0 4.49E-02 1.87E-02 1428600400037 13.0 8.84E-02 1.76E-02 1428600400038 14.0 5.03E-02 1.60E-02 1428600400039 15.0 3.20E-02 1.42E-02 1428600400040 16.0 1.84E-02 1.22E-02 1428600400041 17.0 2.31E-02 1.04E-02 1428600400042 18.0 1.62E-02 8.62E-03 1428600400043 19.0 7.09E-03 7.14E-03 1428600400044 20.0 4.51E-03 5.54E-03 1428600400045 21.0 9.02E-04 4.44E-03 1428600400046 22.0 -1.16E-03 3.38E-03 1428600400047 23.0 4.90E-03 2.64E-03 1428600400048 24.0 1.29E-04 2.09E-03 1428600400049 25.0 2.58E-04 1.42E-03 1428600400050 26.0 -6.44E-04 9.73E-04 1428600400051 27.0 1.16E-03 7.62E-04 1428600400052 28.0 -1.80E-03 7.06E-04 1428600400053 29.0 -2.58E-04 5.16E-04 1428600400054 30.0 5.16E-04 2.58E-04 1428600400055 ENDDATA 31 0 1428600400056 ENDSUBENT 55 0 1428600499999 SUBENT 14286005 20220822 15001428600500001 BIB 5 15 1428600500002 REACTION (98-CF-252(0,F)ELEM/MASS,NUM,FY,G,MSC) 1428600500003 ANALYSIS Number of emitted neutrons in various fission channels 1428600500004 was determined from correlated discrete gamma rays of 1428600500005 fission products 1428600500006 2n channel 106Mo x 144Ba 1428600500007 4n channel 106Mo x 142Ba 1428600500008 Multiplicities in both channels are normalized 1428600500009 to sum to unity. 1428600500010 This table contains the gamma ray multiplicity of event1428600500011 with 4 neutrons emitted. For the 2n channel see 1428600500012 subentry 4. 1428600500013 ERR-ANALYS (ERR-S) Statistical uncertainty 1428600500014 STATUS (TABLE) Data presented in fig. 12 of the reference 1428600500015 sent by author (D.L.B.) 1428600500016 HISTORY (20220730A) Added MSC to REACTION SF8 1428600500017 ENDBIB 15 0 1428600500018 COMMON 4 3 1428600500019 ELEM1 MASS1 ELEM2 MASS2 1428600500020 NO-DIM NO-DIM NO-DIM NO-DIM 1428600500021 42. 106. 56. 142. 1428600500022 ENDCOMMON 3 0 1428600500023 DATA 3 29 1428600500024 PART-OUT DATA ERR-S 1428600500025 NO-DIM NO-DIM NO-DIM 1428600500026 2.0 2.06E-02 4.42E-03 1428600500027 3.0 3.48E-02 6.60E-03 1428600500028 4.0 2.22E-02 7.63E-03 1428600500029 5.0 4.79E-02 8.06E-03 1428600500030 6.0 4.68E-02 9.16E-03 1428600500031 7.0 5.94E-02 1.04E-02 1428600500032 8.0 1.18E-01 1.18E-02 1428600500033 9.0 1.09E-01 1.28E-02 1428600500034 10.0 1.18E-01 1.35E-02 1428600500035 11.0 1.13E-01 1.35E-02 1428600500036 12.0 8.01E-02 1.31E-02 1428600500037 13.0 6.92E-02 1.23E-02 1428600500038 14.0 5.53E-02 1.13E-02 1428600500039 15.0 3.62E-02 1.00E-02 1428600500040 16.0 3.00E-02 8.73E-03 1428600500041 17.0 1.76E-02 7.40E-03 1428600500042 18.0 8.19E-03 6.16E-03 1428600500043 19.0 8.19E-03 5.15E-03 1428600500044 20.0 -3.75E-03 4.04E-03 1428600500045 21.0 5.50E-03 3.19E-03 1428600500046 22.0 -2.34E-03 2.45E-03 1428600500047 23.0 2.46E-03 1.88E-03 1428600500048 24.0 4.68E-03 1.43E-03 1428600500049 25.0 -3.51E-04 1.15E-03 1428600500050 26.0 -7.02E-04 7.22E-04 1428600500051 27.0 1.17E-04 5.85E-04 1428600500052 28.0 9.37E-04 4.68E-04 1428600500053 29.0 4.68E-04 3.70E-04 1428600500054 30.0 1.17E-04 2.62E-04 1428600500055 ENDDATA 31 0 1428600500056 ENDSUBENT 55 0 1428600599999 ENDENTRY 5 0 1428699999999