ENTRY 23179 20220212 23102317900000001 SUBENT 23179001 20220212 23102317900100001 BIB 13 63 2317900100002 TITLE Mass and charge distributions in the very asymmetric 2317900100003 mass region of the neutron induced fission of 238-Np. 2317900100004 AUTHOR (I.Tsekhanovich,H.-O.Denschlag, M.Davi, Z.Bueyuekmumcu,2317900100005 F.Goennenwein, S.Oberstedt, H.R.Faust) 2317900100006 REFERENCE (J,NP/A,688,633,2001) Main reference. 2317900100007 ((S,AIP-447,239,1998)=(C,98SEYSS,,239,1998)) 2317900100008 Preliminary results. 2317900100009 First author M.Davi. 2317900100010 INSTITUTE (2FR ILL) I.Tsekhanovich,S.Oberstedt, H.R.Faust. 2317900100011 (4BLRPCB) I.Tsekhanovich. 2317900100012 (2GERMNZ) I.Tsekhanovich,H.-O.Denschlag,M.Davi. 2317900100013 (2TUKANK) Z.Bueyuekmumcu. 2317900100014 (2GERTUE) F.Goennenwein. 2317900100015 (2ZZZGEL) S.Oberstedt. 2317900100016 FACILITY (OLMS,2FR ILL) Recoil mass-separator Lohengrin of 2317900100017 Institute Laue-Langevin (ILL) Grenoble. 2317900100018 SAMPLE Prepared by electrodeposition of NpO2 on a rectangular 2317900100019 surface (5 mm x 40 mm) on a titanium backing. 2317900100020 Thickness of the NpO2-layer was about 110 microg/cm2. 2317900100021 Covered with thin nickel foils (first two targets) or 2317900100022 a tantalum foil (thickness of 0.25 microm and 0.084 2317900100023 microm, respectively). 2317900100024 The isotope undergoing the neutron induced fission 2317900100025 238-Np is formed on line from 237-Np in the high 2317900100026 neutron flux 5.4E+14 /cm**2/s at the target position 2317900100027 of Lohengrin. 2317900100028 EXP-YEAR (1995) 1995-1998, three runs. 2317900100029 DETECTOR (IOCH) Fission products from the reaction 2317900100030 237-Np(2nth,f) were detected in an ionization chamber. 2317900100031 METHOD The evolution of the target intensity as a function of 2317900100032 exposure time, was measured daily using reference 2317900100033 spectra (A/q = 88/22 at the kinetic energies of 85, 90,2317900100034 95, 100, 105 and 110 MeV). 2317900100035 In each mass chain at least 5 ionic charge states 2317900100036 (near the mean kinetic energy) and at least five 2317900100037 different kinetic energies (EL = 85, 90, 95, 100, 105 2317900100038 MeV) (near the mean ionic charge state) were measured. 2317900100039 An exception is the lightest mass (A = 74) where, due 2317900100040 to low count rates, only 4 ionic charge states 2317900100041 (q = 18-21) and only 4 kinetic energy settings (EL = 2317900100042 90, 95, 100, 105) could be measured. 2317900100043 CORRECTION Count rates obtained were corrected for the energy 2317900100044 dispersion of Lohengrin and for "burn-up" of targets. 2317900100045 ANALYSIS Mean energy loss for fragments from the targets covered2317900100046 with nickel was determined as 6.8 MeV (around 90% in 2317900100047 the covering nickel foil and approximately 10% in the 2317900100048 target itself); - in the target covered with tantalum 2317900100049 amounted to 2.3 MeV (70% in the foil and 30% in the 2317900100050 target material). Energy loss was calculated by the 2317900100051 computer code TRIM (Transport of Ions In Matter). 2317900100052 Corrected count rates of the single isotopes (excluding2317900100053 A=83) at various ionic charge states were fitted to 2317900100054 gaussian distributions. 2317900100055 Experimental values of the ionic charge and widths as 2317900100056 function of atomic mass and nuclear charge were fitted 2317900100057 to the systematics of Nikolaev+ (see REL-REF). 2317900100058 Absolute yields were normalized to the absolute yield 2317900100059 of mass 88 taken from REL-REF of G.Martinez+ 2317900100060 REL-REF (N,,V.S.Nikolaev+,J,PL/A,28,277,1968) 2317900100061 (R,22179001,G.Martinez+,J,NP/A,515,433,1990) 2317900100062 HISTORY (20120105C) M.M. 2317900100063 (20220212A) SD: Ref.C,98SEYSS aded. Correction in 2317900100064 Subent 004. 2317900100065 ENDBIB 63 0 2317900100066 COMMON 1 3 2317900100067 EN-DUMMY 2317900100068 EV 2317900100069 0.0253 2317900100070 ENDCOMMON 3 0 2317900100071 ENDSUBENT 70 0 2317900199999 SUBENT 23179002 20110103 22302317900200001 BIB 6 15 2317900200002 REACTION (93-NP-238(N,F)ELEM/MASS,,KE) 2317900200003 ANALYSIS Normal distributions were used for the description of 2317900200004 the kinetic energy distributions of fission products. 2317900200005 The mean kinetic energies were obtained by the fit of 2317900200006 the count rates of the individual masses at five 2317900200007 different kinetic energies after correction . 2317900200008 Reliable fit of the energy distribution of the isotope 2317900200009 34-Se-83 was not possible; the yield of 83Se was 2317900200010 obtained by subtracting the number of counts observed 2317900200011 for the isotopes with Z = 32,33 and 35 from the number 2317900200012 of counts observed for the total mass (A = 83). 2317900200013 CORRECTION For the energy loss in the targets and covering foils, 2317900200014 MISC-COL (MISC) Width of kinetic energy distribution. 2317900200015 ERR-ANALYS (DATA-ERR) One standard deviation. 2317900200016 STATUS (TABLE) Table 1 of J,NP/A,688,633,2001. 2317900200017 ENDBIB 15 0 2317900200018 NOCOMMON 0 0 2317900200019 DATA 6 43 2317900200020 MASS ELEMENT DATA DATA-ERR MISC MISC-ERR 2317900200021 NO-DIM NO-DIM MEV MEV MEV MEV 2317900200022 74. 29. 99.7 0.7 8.2 1.1 2317900200023 74. 30. 99.8 0.2 7.3 0.2 2317900200024 75. 29. 101.5 0.5 4.1 0.6 2317900200025 75. 30. 98.7 0.1 6.2 0.1 2317900200026 75. 31. 97.6 0.2 2.6 0.2 2317900200027 76. 29. 100.8 5.9 8.1 7.4 2317900200028 76. 30. 97.8 0.4 5.8 0.5 2317900200029 76. 31. 97.9 0.7 4.5 0.9 2317900200030 77. 30. 99.9 0.3 5.6 0.7 2317900200031 77. 31. 98.2 0.2 7.4 0.8 2317900200032 77. 32. 96.9 0.3 3.2 0.3 2317900200033 78. 30. 97.9 0.9 7.6 0.5 2317900200034 78. 31. 97.1 0.4 6.3 0.2 2317900200035 78. 32. 95.8 0.7 6.8 0.4 2317900200036 79. 31. 97.9 0.3 7.2 0.3 2317900200037 79. 32. 95.2 0.3 7.5 0.4 2317900200038 79. 33. 93.9 0.8 6.4 1.0 2317900200039 80. 31. 101.6 0.4 5.7 0.4 2317900200040 80. 32. 98.5 0.2 6.8 0.2 2317900200041 80. 33. 95.1 1.4 7.0 0.7 2317900200042 81. 31. 99.0 0.5 5.5 0.4 2317900200043 81. 32. 97.3 0.3 7.4 0.2 2317900200044 81. 33. 96.6 0.2 6.2 0.2 2317900200045 81. 34. 99.6 1.3 6.5 1.3 2317900200046 82. 32. 99.4 0.4 7.8 0.5 2317900200047 82. 33. 97.0 0.3 6.9 0.3 2317900200048 82. 34. 95.8 0.6 6.0 0.5 2317900200049 82. 35. 94.5 0.8 4.4 0.7 2317900200050 83. 32. 99.2 1.0 6.7 1.1 2317900200051 83. 33. 95.0 3.2 8.4 1.9 2317900200052 83. 35. 100.3 0.8 5.8 1.5 2317900200053 84. 32. 102.7 0.3 4.2 0.3 2317900200054 84. 33. 100.6 0.2 5.3 0.1 2317900200055 84. 34. 94.6 0.3 7.7 0.2 2317900200056 84. 35. 97.7 0.4 5.4 0.2 2317900200057 85. 33. 100.3 0.6 5.1 0.7 2317900200058 85. 34. 97.5 0.9 8.0 1.2 2317900200059 85. 35. 96.9 1.0 6.1 0.9 2317900200060 85. 36. 96.9 0.8 5.6 0.6 2317900200061 88. 34. 100.4 0.5 6.4 0.7 2317900200062 88. 35. 99.2 0.2 5.3 0.2 2317900200063 88. 36. 98.0 0.2 4.6 0.2 2317900200064 88. 37. 96.9 2.0 5.9 1.3 2317900200065 ENDDATA 45 0 2317900200066 ENDSUBENT 65 0 2317900299999 SUBENT 23179003 20110103 22302317900300001 BIB 3 4 2317900300002 REACTION (93-NP-238(N,F)MASS,CHN,FY) 2317900300003 Absolute mass yields . 2317900300004 ERR-ANALYS (DATA-ERR) One standard deviation. 2317900300005 STATUS (TABLE) Table 2 of J,NP/A,688,633,2001. 2317900300006 ENDBIB 4 0 2317900300007 NOCOMMON 0 0 2317900300008 DATA 3 12 2317900300009 MASS DATA DATA-ERR 2317900300010 NO-DIM PC/FIS PC/FIS 2317900300011 74. 0.00065 0.00016 2317900300012 75. 0.00154 0.00014 2317900300013 76. 0.00394 0.00042 2317900300014 77. 0.00944 0.00061 2317900300015 78. 0.0161 0.0011 2317900300016 79. 0.0379 0.0024 2317900300017 80. 0.0822 0.0050 2317900300018 81. 0.1351 0.0086 2317900300019 82. 0.206 0.014 2317900300020 83. 0.492 0.043 2317900300021 84. 0.459 0.027 2317900300022 85. 0.786 0.111 2317900300023 ENDDATA 14 0 2317900300024 ENDSUBENT 23 0 2317900399999 SUBENT 23179004 20220212 23102317900400001 BIB 5 12 2317900400002 REACTION (93-NP-238(N,F)ELEM/MASS,IND,FY,,FRC) 2317900400003 COMMENT Relative independent yields are given in % in Table, 2317900400004 divided by compiler by 100. 2317900400005 The data for A = 86 and 87 were taken from REL-REF of 2317900400006 G.Martinez+. 2317900400007 The absolute independent yields of the single nuclides2317900400008 could be obtained by multiplying the fractional 2317900400009 independent yields (Subent 004) by the chain yields 2317900400010 (Subent 003). 2317900400011 ERR-ANALYS (DATA-ERR) One sigma error. 2317900400012 STATUS (TABLE) Table 3 of Nucl.Phys.,A688(2001)633. 2317900400013 HISTORY (20220212A) SD: REACTION code uodated. 2317900400014 ENDBIB 12 0 2317900400015 NOCOMMON 0 0 2317900400016 DATA 4 51 2317900400017 MASS ELEMENT DATA DATA-ERR 2317900400018 NO-DIM NO-DIM NO-DIM NO-DIM 2317900400019 74. 29. 9.8E-2 7.6E-2 2317900400020 74. 30. 90.2E-2 34.3E-2 2317900400021 75. 29. 8.6E-2 3.1E-2 2317900400022 75. 30. 84.8E-2 13.0E-2 2317900400023 75. 31. 6.5E-2 2.4E-2 2317900400024 76. 29. 3.0E-2 3.0E-2 2317900400025 76. 30. 82.5E-2 13.7E-2 2317900400026 76. 31. 14.5E-2 4.3E-2 2317900400027 77. 30. 40.8E-2 4.2E-2 2317900400028 77. 31. 54.7E-2 4.4E-2 2317900400029 77. 32. 4.6E-2 0.9E-2 2317900400030 78. 30. 15.8E-2 1.8E-2 2317900400031 78. 31. 56.1E-2 4.9E-2 2317900400032 78. 32. 28.1E-2 3.1E-2 2317900400033 79. 31. 47.5E-2 4.2E-2 2317900400034 79. 32. 49.0E-2 4.7E-2 2317900400035 79. 33. 3.5E-2 0.9E-2 2317900400036 80. 31. 10.0E-2 1.2E-2 2317900400037 80. 32. 82.7E-2 6.0E-2 2317900400038 80. 33. 7.3E-2 1.0E-2 2317900400039 81. 31. 4.1E-2 0.6E-2 2317900400040 81. 32. 70.4E-2 5.6E-2 2317900400041 81. 33. 23.5E-2 2.0E-2 2317900400042 81. 34. 2.0E-2 0.4E-2 2317900400043 82. 32. 47.6E-2 5.4E-2 2317900400044 82. 33. 45.0E-2 4.7E-2 2317900400045 82. 34. 6.3E-2 0.9E-2 2317900400046 82. 35. 1.1E-2 0.2E-2 2317900400047 83. 32. 6.1E-2 1.5E-2 2317900400048 83. 33. 60.8E-2 15.8E-2 2317900400049 83. 34. 30.7E-2 16.7E-2 2317900400050 83. 35. 2.5E-2 1.1E-2 2317900400051 84. 32. 1.2E-2 0.1E-2 2317900400052 84. 33. 21.4E-2 2.2E-2 2317900400053 84. 34. 73.8E-2 7.6E-2 2317900400054 84. 35. 3.5E-2 0.4E-2 2317900400055 85. 33. 13.2E-2 3.2E-2 2317900400056 85. 34. 73.6E-2 16.2E-2 2317900400057 85. 35. 11.6E-2 2.8E-2 2317900400058 85. 36. 1.6E-2 0.4E-2 2317900400059 86. 33. 5.4E-2 0.5E-2 2317900400060 86. 34. 76.6E-2 5.2E-2 2317900400061 86. 35. 18.0E-2 1.4E-2 2317900400062 87. 33. 4.2E-2 0.4E-2 2317900400063 87. 34. 29.9E-2 2.2E-2 2317900400064 87. 35. 54.5E-2 3.8E-2 2317900400065 87. 36. 11.3E-2 0.9E-2 2317900400066 88. 34. 11.2E-2 1.3E-2 2317900400067 88. 35. 52.6E-2 2.1E-2 2317900400068 88. 36. 33.7E-2 1.5E-2 2317900400069 88. 37. 2.5E-2 0.6E-2 2317900400070 ENDDATA 53 0 2317900400071 ENDSUBENT 70 0 2317900499999 SUBENT 23179005 20110103 22302317900500001 BIB 5 7 2317900500002 REACTION (93-NP-238(N,F)MASS,,ZP) 2317900500003 Mean nuclear charges. 2317900500004 COMMENT The data for A = 86 and 87 were taken from REL-REF of 2317900500005 G.Martinez+. 2317900500006 MISC-COL (MISC) Width of charge distribution. 2317900500007 ERR-ANALYS (DATA-ERR) One sigma error. 2317900500008 STATUS (TABLE) Table 3 of J,NP/A,688,633,2001. 2317900500009 ENDBIB 7 0 2317900500010 NOCOMMON 0 0 2317900500011 DATA 5 15 2317900500012 MASS DATA DATA-ERR MISC MISC-ERR 2317900500013 NO-DIM NO-DIM NO-DIM NO-DIM NO-DIM 2317900500014 74. 29.840 0.024 0.385 0.018 2317900500015 75. 29.971 0.055 0.403 0.096 2317900500016 76. 30.155 0.070 0.445 0.046 2317900500017 77. 30.606 0.021 0.601 0.024 2317900500018 78. 31.147 0.024 0.714 0.030 2317900500019 79. 31.511 0.020 0.612 0.031 2317900500020 80. 31.966 0.008 0.470 0.009 2317900500021 81. 32.223 0.016 0.509 0.011 2317900500022 82. 32.396 0.086 0.793 0.063 2317900500023 83. 33.060 0.226 0.770 0.083 2317900500024 84. 33.783 0.008 0.490 0.006 2317900500025 85. 33.98 0.050 0.530 0.042 2317900500026 86. 34.147 0.006 0.494 0.008 2317900500027 87. 34.711 0.009 0.750 0.014 2317900500028 88. 35.272 0.014 0.700 0.019 2317900500029 ENDDATA 17 0 2317900500030 ENDSUBENT 29 0 2317900599999 SUBENT 23179006 20110103 22302317900600001 BIB 4 7 2317900600002 REACTION (93-NP-238(N,F)ELEM,CHG,FY) 2317900600003 Absolute yields of chemical elements.. 2317900600004 ANALYSIS Total independent yields of the chemical elements were 2317900600005 obtained by absolute isotopic yields fitting to normal 2317900600006 distribution and integration. 2317900600007 ERR-ANALYS (DATA-ERR) One standard deviation. 2317900600008 STATUS (TABLE) Table 4 of J,NP/A,688,633,2001. 2317900600009 ENDBIB 7 0 2317900600010 NOCOMMON 0 0 2317900600011 DATA 3 7 2317900600012 ELEMENT DATA DATA-ERR 2317900600013 NO-DIM PC/FIS PC/FIS 2317900600014 29. 0.00038 0.00035 2317900600015 30. 0.01218 0.00214 2317900600016 31. 0.04478 0.00324 2317900600017 32. 0.30026 0.01671 2317900600018 33. 0.7452 0.0348 2317900600019 34. 2.4758 0.1294 2317900600020 35. 2.9706 0.1715 2317900600021 ENDDATA 9 0 2317900600022 ENDSUBENT 21 0 2317900699999 SUBENT 23179007 20110103 22302317900700001 BIB 6 14 2317900700002 REACTION (93-NP-238(N,F)ELEM,PR,NU,,,DERIV) 2317900700003 Number of prompt neutrons. 2317900700004 ANALYSIS Number of prompt neutrons was estimated assuming that 2317900700005 an energy of 10 +- 5 MeV is required to boil off one 2317900700006 neutron, and using measured in this work kinetic 2317900700007 energy distributions of fission products. 2317900700008 ASSUMED (ASSUM,93-NP-238(N,F)0-NN-1,PR,KE) 2317900700009 MISC-COL (MISC) Increase in mean atomic mass 2317900700010 (deltaAm(Z)/deltaEkin), amu/MeV, with the kinetic 2317900700011 energy of the fragments for the various elements; 2317900700012 derived from a linear fit of the average mass of 2317900700013 various elements. 2317900700014 ERR-ANALYS (DATA-ERR) Not specified. 2317900700015 STATUS (TABLE) Table 6 of J,NP/A,688,633,2001. 2317900700016 ENDBIB 14 0 2317900700017 COMMON 2 3 2317900700018 ASSUM ASSUM-ERR 2317900700019 MEV MEV 2317900700020 10. 5. 2317900700021 ENDCOMMON 3 0 2317900700022 DATA 5 6 2317900700023 ELEMENT DATA DATA-ERR MISC MISC-ERR 2317900700024 NO-DIM PRT/FIS PRT/FIS SEE TEXT SEE TEXT 2317900700025 29. 0.12 0.08 0.012 0.005 2317900700026 30. 0.24 0.13 0.024 0.005 2317900700027 31. 0.51 0.31 0.051 0.017 2317900700028 32. 0.17 0.11 0.017 0.007 2317900700029 33. 0.16 0.10 0.016 0.006 2317900700030 34. 0.27 0.14 0.027 0.001 2317900700031 ENDDATA 8 0 2317900700032 ENDSUBENT 31 0 2317900799999 ENDENTRY 7 0 2317999999999