ENTRY 30950 20010420 00003095000000001 SUBENT 30950001 20010420 00003095000100001 BIB 12 39 3095000100002 INSTITUTE (3INDTRM) 3095000100003 REFERENCE (J,JIN,30,2305,1968) 3095000100004 AUTHOR (M.N.Namboodiri,N.Ravindran,M.Rajagopalan, 3095000100005 M.V.Ramaniah) 3095000100006 TITLE Mass distribution in the reactor neutron fission of 3095000100007 231Pa and 237Np 3095000100008 FACILITY (REAC,3INDTRM) Swimming pool reactor "Apsara" 3095000100009 INC-SPECT Reactor pile spectrum, but the samples were covered 3095000100010 with cadmium foils thick enough to cut off the thermal 3095000100011 neutron flux almost completely. 3095000100012 Irradiation times varied from 6 to 24 hrs. 3095000100013 METHOD (RCHEM).using standard procedures 3095000100014 (RVAL).relative to U-235 thermal fission with Ba-140 as3095000100015 internal standard. Absolute yields were obtained by 3095000100016 normalization of the mass yield distribution to 200%, 3095000100017 which was generated by drawing a smooth curve through 3095000100018 the measured points and extrapolating it at the light 3095000100019 and heavy mass wing of the distribution. 3095000100020 The measured R-values are not given. 3095000100021 DETECTOR (PROPC) Sugarman type methane flow proportional counter3095000100022 ANALYSIS The values given are averages of all determinations. 3095000100023 ERR-ANALYS The errors given are the mean quare deviations of the 3095000100024 respective number of determinations. 3095000100025 Compiler's comments: 3095000100026 - Apparantly only statistical errors are given as one 3095000100027 standard deviation. 3095000100028 - A general statement is made that probably refers to 3095000100029 the estimated maximum overall error: "The maximum 3095000100030 expected error in the values in the region of high 3095000100031 yields is about 10% and in the region of low yields 3095000100032 about 20%." 3095000100033 HISTORY (19881017T) Automatic conversion from Rider file, 3095000100034 Reference 68NAM1. 3095000100035 (20010421A) ML:additions from publication,corrections: 3095000100036 - all reactions: modifier changed from 'FIS' to 'SPA' 3095000100037 - subentry 3 (for A=125 chain yield) deleted and 3095000100038 Sn-125 added to subentry 2 with the same yield value3095000100039 (as given in the publication). 3095000100040 STATUS All data from Table 1 of J.Inorg.Nucl.Chem.30(1968)23053095000100041 ENDBIB 39 0 3095000100042 NOCOMMON 0 0 3095000100043 ENDSUBENT 42 0 3095000199999 SUBENT 30950002 20010420 00003095000200001 BIB 5 15 3095000200002 REACTION (93-NP-237(N,F)ELEM/MASS,CUM,FY,,SPA) 3095000200003 MONITOR (93-NP-237(N,F)56-BA-140,CUM,FY,,SPA) internal standard3095000200004 Compiler's comment: the reference U-235 thermal fission3095000200005 yields are not given. They were taken from 3 sources: 3095000200006 S.Katcoff, Nucleonics 18, no.11, p.201 (1960) 3095000200007 H.Farrar, R.H.Tomlinson, Nucl. Phys. 34, 367 (1962) 3095000200008 H.Farrar, et al., Can. J. Phys. 40, 1017 (1962) 3095000200009 Hence the actual values used cannot be determined. 3095000200010 SAMPLE About 1 mg of Np-237 as nitrate solution, evaporated on3095000200011 pure aluminum foils which were sealed in quartz tubes. 3095000200012 Reference sample: 50 microgram of U-235 3095000200013 MISC-COL (MISC) Number of determinations 3095000200014 ADD-RES The peak positions of the mass distribution are around 3095000200015 A=99 and 137. 3095000200016 The peak-to-valley ratio is 180. 3095000200017 ENDBIB 15 0 3095000200018 COMMON 2 3 3095000200019 EN-DUMMY MONIT 3095000200020 MEV PC/FIS 3095000200021 1.0 5.3 3095000200022 ENDCOMMON 3 0 3095000200023 DATA 6 22 3095000200024 ELEMENT MASS ISOMER DATA DATA-ERR MISC 3095000200025 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3095000200026 35. 83. 0.265 0.009 2. 3095000200027 38. 89. 2.040 0.080 5. 3095000200028 38. 91. 4.040 0.103 2. 3095000200029 40. 97. 6.950 0.165 2. 3095000200030 42. 99. 6.980 0.004 2. 3095000200031 44. 103. 0. 4.040 0.270 2. 3095000200032 44. 106. 1.560 0.020 2. 3095000200033 45. 105. 0. 2.750 0.164 3. 3095000200034 46. 109. 0. 0.299 0.003 2. 3095000200035 46. 112. 0.072 0.003 2. 3095000200036 47. 111. 0. 0.085 0.0012 2. 3095000200037 47. 113. 0. 0.045 0.003 2. 3095000200038 48. 115. 0. 0.041 0.001 3. 3095000200039 50. 121. 0. 0.047 0.0013 2. 3095000200040 50. 125. 0. 0.126 0.003 2. 3095000200041 51. 127. 0.916 0.040 2. 3095000200042 52. 129. 0. 2.600 1. 3095000200043 52. 132. 6.330 0.036 3. 3095000200044 58. 141. 4.970 0.234 2. 3095000200045 58. 144. 4.310 0.158 3. 3095000200046 60. 147. 2.350 0.013 3. 3095000200047 63. 156. 0.090 0.0012 2. 3095000200048 ENDDATA 24 0 3095000200049 ENDSUBENT 48 0 3095000299999 NOSUBENT 30950003 20010420 00003095000300001 SUBENT 30950004 20010420 00003095000400001 BIB 5 15 3095000400002 REACTION (91-PA-231(N,F)ELEM/MASS,CUM,FY,,SPA) 3095000400003 MONITOR (91-PA-231(N,F)56-BA-140,CUM,FY,,SPA) Internal standard3095000400004 Compiler's comment: the reference U-235 thermal fission3095000400005 yields are not given. They were taken from 3 sources: 3095000400006 S.Katcoff, Nucleonics 18, no.11, p.201 (1960) 3095000400007 H.Farrar, R.H.Tomlinson, Nucl. Phys. 34, 367 (1962) 3095000400008 H.Farrar, et al., Can. J. Phys. 40, 1017 (1962) 3095000400009 Hence the actual values used cannot be determined. 3095000400010 SAMPLE About 1 mg of Pa-231 as nitrate solution, evaporated on3095000400011 pure aluminum foils which were sealed in quartz tubes. 3095000400012 Reference sample: 50 microgram of U-235 3095000400013 MISC-COL (MISC) Number of determinations 3095000400014 ADD-RES The peak positions of the mass distribution are around 3095000400015 A=91 and 140. 3095000400016 The peak-to-valley ratio is 106. 3095000400017 ENDBIB 15 0 3095000400018 COMMON 2 3 3095000400019 EN-DUMMY MONIT 3095000400020 MEV PC/FIS 3095000400021 1.0 6.96 3095000400022 ENDCOMMON 3 0 3095000400023 DATA 6 20 3095000400024 ELEMENT MASS ISOMER DATA DATA-ERR MISC 3095000400025 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 3095000400026 35. 83. 2.270 0.140 2. 3095000400027 38. 89. 7.260 0.144 7. 3095000400028 38. 91. 7.340 0.290 2. 3095000400029 40. 97. 4.500 0.020 2. 3095000400030 42. 99. 2.590 0.150 3. 3095000400031 44. 103. 0. 0.328 0.035 3. 3095000400032 44. 106. 0.108 0.010 2. 3095000400033 45. 105. 0. 0.154 0.024 4. 3095000400034 46. 109. 0. 0.083 0.0028 3. 3095000400035 46. 112. 0.061 0.002 5. 3095000400036 47. 111. 0. 0.099 0.0049 3. 3095000400037 47. 113. 0. 0.077 0.0057 2. 3095000400038 48. 115. 0. 0.080 0.0045 2. 3095000400039 50. 121. 0. 0.076 0.0081 2. 3095000400040 51. 127. 0.080 0.0045 2. 3095000400041 52. 129. 0. 1.180 0.065 3. 3095000400042 52. 132. 3.420 0.360 3. 3095000400043 58. 143. 6.120 0.340 2. 3095000400044 60. 147. 2.450 0.0710 3. 3095000400045 62. 153. 0.079 0.0025 2. 3095000400046 ENDDATA 22 0 3095000400047 ENDSUBENT 46 0 3095000499999 ENDENTRY 4 0 3095099999999