ENTRY 14414 20150401 14061441400000001 SUBENT 14414001 20150401 14061441400100001 BIB 11 29 1441400100002 TITLE First fission yield measurements at the National 1441400100003 Ignition Facility: 14-MeV neutron fission of 238U 1441400100004 AUTHOR (N.Gharibyan,K.J.Moody,J.D.Despotopulos,P.M.Grant, 1441400100005 D.A.Shaughnessy) 1441400100006 INSTITUTE (1USALRL) 1441400100007 REFERENCE (J,JRN,303,1335,2015) 1441400100008 FACILITY (FNS,1USALRL) Experiment performed at the National 1441400100009 Ignition Facility located at the Lawrence Livermore 1441400100010 National Laboratory 1441400100011 SAMPLE (92-U-238,ENR=0.9996) 1441400100012 (92-U-235,ENR=0.00039) 1441400100013 (92-U-234,ENR=0.000003) 1441400100014 Ultra-depleted uranium disc with diameter of 28 mm and 1441400100015 thickness of 239mg/cm2 was loaded inside the Target 1441400100016 Option Activation Device (TOAD) assembly along with 1441400100017 front-back catcher foil (Al, 99.999 %, thickness 1441400100018 6.75 mg/cm2) and flux monitor foil (Au, 99.95 %, 1441400100019 483 mg/cm2). Two individual U-TOAD assemblies 1441400100020 were used. 1441400100021 DETECTOR (HPGE) 1441400100022 METHOD (CHSEP,GSPEC) One TOAD assembly was chemically 1441400100023 separated and selectively analysed using HPGe 1441400100024 detector, second TOAD assembly was analysed without 1441400100025 chemical separation. 1441400100026 INC-SOURCE (D-T) Inertial-confinement fusion (ICF) process 1441400100027 inducing thermonuclear burn in a deuterium-tritium 1441400100028 filled capsule 1441400100029 ERR-ANALYS (DATA-ERR) No information given 1441400100030 HISTORY (20150401C) Compiled by S.H. 1441400100031 ENDBIB 29 0 1441400100032 NOCOMMON 0 0 1441400100033 ENDSUBENT 32 0 1441400199999 SUBENT 14414002 20150401 14061441400200001 BIB 2 3 1441400200002 REACTION (92-U-238(N,F)MASS,CHN,FY) 1441400200003 STATUS (TABLE) Data shown in fig.3 of the reference 1441400200004 sent by author (N.G.) 1441400200005 ENDBIB 3 0 1441400200006 COMMON 1 3 1441400200007 EN 1441400200008 MEV 1441400200009 14.0 1441400200010 ENDCOMMON 3 0 1441400200011 DATA 3 32 1441400200012 MASS DATA DATA-ERR 1441400200013 NO-DIM PC/FIS PC/FIS 1441400200014 72. 6.30E-02 3.59E-02 1441400200015 85. 1.09E+00 1.93E-01 1441400200016 87. 2.20E+00 9.72E-01 1441400200017 88. 2.28E+00 7.85E-01 1441400200018 91. 2.72E+00 1.22E-01 1441400200019 92. 3.50E+00 2.56E-01 1441400200020 93. 5.07E+00 1.32E+00 1441400200021 95. 4.79E+00 5.07E-01 1441400200022 97. 6.58E+00 1.96E-01 1441400200023 99. 5.98E+00 3.96E-01 1441400200024 103. 4.31E+00 3.31E-01 1441400200025 105. 3.15E+00 1.50E-01 1441400200026 112. 1.40E+00 2.93E-01 1441400200027 115. 6.16E-01 3.66E-01 1441400200028 117. 3.88E-01 9.32E-02 1441400200029 127. 1.12E+00 3.57E-01 1441400200030 128. 4.61E-01 1.66E-01 1441400200031 129. 1.64E+00 1.63E-01 1441400200032 131. 3.59E+00 6.48E-01 1441400200033 132. 5.17E+00 2.08E-01 1441400200034 133. 5.99E+00 2.19E-01 1441400200035 134. 7.03E+00 3.79E-01 1441400200036 135. 5.14E+00 1.54E-01 1441400200037 139. 5.58E+00 1.41E+00 1441400200038 140. 5.09E+00 2.33E-01 1441400200039 141. 5.21E+00 8.70E-01 1441400200040 142. 4.71E+00 4.07E-01 1441400200041 143. 4.47E+00 2.92E-01 1441400200042 147. 1.44E+00 9.53E-02 1441400200043 149. 1.05E+00 3.43E-01 1441400200044 151. 4.53E-01 8.37E-02 1441400200045 153. 2.98E-01 3.60E-02 1441400200046 ENDDATA 34 0 1441400200047 ENDSUBENT 46 0 1441400299999 ENDENTRY 2 0 1441499999999