ENTRY 10723 20090911 13551072300000001 SUBENT 10723001 20090911 13551072300100001 BIB 12 36 1072300100002 INSTITUTE (1USAINL) 1072300100003 REFERENCE (R,ICP-1050,(III),197709) 1072300100004 (C,77NBS,,146,1977) 1072300100005 AUTHOR (W.J.Maeck,W.A.Emel,A.L.Erikson,J.E.Delmore,J.W.Meteer)1072300100006 TITLE Fast reactor fission yields for Np-237 1072300100007 FACILITY (REAC,1USAINL) Experimental Breeder Reactor (EBR-II). 1072300100008 SAMPLE Oxide powder, greater than 99.9% 237Np, mixed with 1072300100009 high purity nickel powder and weld-sealed in nickel 1072300100010 capsules. 1072300100011 DETECTOR Mass spectrometer to determine fission products. 1072300100012 (GELI) for gamma detection of non-fissionable spectrum 1072300100013 monitors. 1072300100014 MONITOR Monitors used include wires of cobalt,iron,nickel, 1072300100015 titanium,and copper, scandium powder, U-235, U-235, 1072300100016 and Np-237 oxide. 1072300100017 METHOD (ASEP) Isotope dilution mass spectroscopy used. 1072300100018 Fissionable monitors analyzed using gamma counting of 1072300100019 137Cs. Neutron spectra determined from monitor data 1072300100020 using the fitting code SPECTRA. Absolute number of 1072300100021 fissions determined using summation technique. 1072300100022 ERR-ANALYS (DATA-ERR) Quoted error is standard deviation including1072300100023 allowances for known systematic errors. Determined by:1072300100024 .approximating functions used to calculate the fission1072300100025 yields, 1072300100026 .using the linear terms of a Taylor series expansion, 1072300100027 .calculating the standard deviation of the linear sum 1072300100028 of random variables. 1072300100029 STATUS (APRVD) Approved by W.J.Maeck, 1980/3/10. 1072300100030 (TABLE) Data taken from tables in report. 1072300100031 HISTORY (19791220C) 1072300100032 (19800820U) BIB correction. 1072300100033 (19801028A) Reactions and data corrected. 1072300100034 Bib corrections. 1072300100035 (19840917A) Bib correction. 1072300100036 (20090908A) VM:Updated to new date formats,lower case. 1072300100037 BIB updates. 1072300100038 ENDBIB 36 0 1072300100039 NOCOMMON 0 0 1072300100040 ENDSUBENT 39 0 1072300199999 SUBENT 10723002 20090911 13551072300200001 BIB 2 4 1072300200002 REACTION (93-NP-237(N,F)MASS,CHN,FY,,FIS) 1072300200003 INC-SPECT Fission spectrum average. 238U/235U reactor spectral 1072300200004 index is 0.005. Location 23 cm above reactor 1072300200005 mid-plane. 1072300200006 ENDBIB 4 0 1072300200007 COMMON 1 3 1072300200008 EN-MEAN 1072300200009 KEV 1072300200010 250. 1072300200011 ENDCOMMON 3 0 1072300200012 DATA 3 43 1072300200013 MASS DATA DATA-ERR 1072300200014 NO-DIM PC/FIS PC/FIS 1072300200015 83. 0.480 0.009 1072300200016 84. 0.762 0.011 1072300200017 85. 0.953 0.007 1072300200018 86. 1.296 0.019 1072300200019 87. 1.728 0.012 1072300200020 88. 2.211 0.028 1072300200021 90. 3.366 0.052 1072300200022 91. 3.924 0.054 1072300200023 92. 4.449 0.064 1072300200024 93. 5.135 0.068 1072300200025 94. 5.097 0.066 1072300200026 95. 5.676 0.057 1072300200027 96. 5.473 0.076 1072300200028 97. 6.131 0.057 1072300200029 98. 6.144 0.057 1072300200030 100. 6.591 0.065 1072300200031 101. 6.226 0.053 1072300200032 102. 5.926 0.049 1072300200033 104. 4.231 0.037 1072300200034 106. 2.313 0.260 1072300200035 125. 0.080 0.009 1072300200036 131. 3.680 0.061 1072300200037 132. 5.034 0.036 1072300200038 133. 6.726 0.057 1072300200039 134. 7.494 0.051 1072300200040 135. 7.624 0.061 1072300200041 136. 6.835 0.051 1072300200042 137. 6.429 0.051 1072300200043 138. 6.209 0.046 1072300200044 139. 5.545 0.185 1072300200045 140. 5.473 0.042 1072300200046 142. 4.927 0.038 1072300200047 143. 4.730 0.036 1072300200048 144. 4.189 0.030 1072300200049 145. 3.506 0.025 1072300200050 146. 2.816 0.021 1072300200051 147. 2.222 0.018 1072300200052 148. 1.740 0.015 1072300200053 149. 1.270 0.009 1072300200054 150. 0.983 0.010 1072300200055 151. 0.707 0.006 1072300200056 152. 0.453 0.004 1072300200057 154. 0.183 0.002 1072300200058 ENDDATA 45 0 1072300200059 ENDSUBENT 58 0 1072300299999 SUBENT 10723003 20090911 13551072300300001 BIB 3 5 1072300300002 REACTION (93-NP-237(N,F)MASS,CHN,FY,,FIS) 1072300300003 INC-SPECT Fission spectrum average. 238U/235U reactor 1072300300004 spectral index is 0.022. Location is 2 cm below 1072300300005 reactor mid-plane. 1072300300006 HISTORY (19810309A) Mass corrected. 1072300300007 ENDBIB 5 0 1072300300008 COMMON 1 3 1072300300009 EN-MEAN 1072300300010 KEV 1072300300011 485. 1072300300012 ENDCOMMON 3 0 1072300300013 DATA 3 43 1072300300014 MASS DATA DATA-ERR 1072300300015 NO-DIM PC/FIS PC/FIS 1072300300016 83. 0.492 0.009 1072300300017 84. 0.776 0.011 1072300300018 85. 0.948 0.006 1072300300019 86. 1.317 0.019 1072300300020 87. 1.727 0.012 1072300300021 88. 2.189 0.028 1072300300022 90. 3.298 0.052 1072300300023 91. 3.895 0.083 1072300300024 92. 4.502 0.091 1072300300025 93. 5.107 0.100 1072300300026 94. 5.145 0.101 1072300300027 95. 5.632 0.058 1072300300028 96. 5.593 0.119 1072300300029 97. 6.078 0.056 1072300300030 98. 6.091 0.056 1072300300031 100. 6.515 0.064 1072300300032 101. 6.118 0.155 1072300300033 102. 5.826 0.148 1072300300034 104. 4.162 0.106 1072300300035 106. 2.625 0.166 1072300300036 125. 0.092 0.010 1072300300037 131. 3.759 0.061 1072300300038 132. 5.062 0.035 1072300300039 133. 6.682 0.056 1072300300040 134. 7.495 0.050 1072300300041 135. 7.546 0.059 1072300300042 136. 6.845 0.050 1072300300043 137. 6.362 0.050 1072300300044 138. 6.242 0.045 1072300300045 139. 5.816 0.193 1072300300046 140. 5.501 0.037 1072300300047 142. 4.915 0.033 1072300300048 143. 4.700 0.035 1072300300049 144. 4.159 0.029 1072300300050 145. 3.484 0.024 1072300300051 146. 2.800 0.020 1072300300052 147. 2.214 0.018 1072300300053 148. 1.740 0.014 1072300300054 149. 1.279 0.009 1072300300055 150. 0.990 0.010 1072300300056 151. 0.717 0.006 1072300300057 152. 0.462 0.004 1072300300058 154. 0.188 0.002 1072300300059 ENDDATA 45 0 1072300300060 ENDSUBENT 59 0 1072300399999 SUBENT 10723004 20090911 13551072300400001 BIB 5 8 1072300400002 REACTION (93-NP-237(N,F)MASS,CHN,FY,,FIS) 1072300400003 INC-SPECT Fission spectrum average. 238U/235U spectral index 1072300400004 of reactor is 0.005. Located 23 cm above reactor 1072300400005 mid-plane. 1072300400006 ANALYSIS Values obtained by interpolation and extrapolation 1072300400007 using measured mass data. 1072300400008 STATUS (DEP,10723002) 1072300400009 HISTORY (19801028A) Bib, data corrections. 1072300400010 ENDBIB 8 0 1072300400011 COMMON 1 3 1072300400012 EN-MEAN 1072300400013 KEV 1072300400014 250. 1072300400015 ENDCOMMON 3 0 1072300400016 DATA 5 22 1072300400017 MASS MASS-MIN MASS-MAX DATA DATA-ERR 1072300400018 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 1072300400019 75. 80. 0.40 0.10 1072300400020 81. 0.23 0.02 1072300400021 82. 0.32 0.03 1072300400022 89. 2.789 0.146 1072300400023 99. 6.367 0.331 1072300400024 103. 5.078 0.361 1072300400025 105. 3.272 0.233 1072300400026 107. 1.61 0.32 1072300400027 108. 0.97 0.19 1072300400028 109. 0.48 0.10 1072300400029 110. 0.22 0.04 1072300400030 111. 0.10 0.02 1072300400031 112. 117. 0.18 0.07 1072300400032 118. 124. 0.25 0.10 1072300400033 126. 0.18 0.03 1072300400034 127. 0.39 0.07 1072300400035 128. 0.79 0.13 1072300400036 129. 1.37 0.20 1072300400037 130. 2.42 0.36 1072300400038 141. 5.200 0.254 1072300400039 153. 0.318 0.016 1072300400040 155. 160. 0.24 0.06 1072300400041 ENDDATA 24 0 1072300400042 ENDSUBENT 41 0 1072300499999 SUBENT 10723005 20090911 13551072300500001 BIB 5 8 1072300500002 REACTION (93-NP-237(N,F)MASS,CHN,FY,,FIS) 1072300500003 INC-SPECT Fission spectrum average. 238U/235U spectral index 1072300500004 of reactor is 0.022. Location is 2 cm below 1072300500005 reactor mid-plane. 1072300500006 ANALYSIS Values obtained by interpolation and extrapolation 1072300500007 using measured mass data. 1072300500008 STATUS (DEP,10723003) 1072300500009 HISTORY (19801028A) Bib, data corrections. 1072300500010 ENDBIB 8 0 1072300500011 COMMON 1 3 1072300500012 EN-MEAN 1072300500013 KEV 1072300500014 485. 1072300500015 ENDCOMMON 3 0 1072300500016 DATA 5 22 1072300500017 MASS MASS-MIN MASS-MAX DATA DATA-ERR 1072300500018 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 1072300500019 75. 80. 0.51 0.13 1072300500020 81. 0.25 0.03 1072300500021 82. 0.36 0.04 1072300500022 89. 2.742 0.144 1072300500023 99. 6.303 0.328 1072300500024 103. 4.995 0.376 1072300500025 105. 3.394 0.256 1072300500026 107. 1.67 0.34 1072300500027 108. 0.83 0.17 1072300500028 109. 0.41 0.08 1072300500029 110. 0.19 0.04 1072300500030 111. 0.10 0.02 1072300500031 112. 117. 0.21 0.08 1072300500032 118. 124. 0.25 0.10 1072300500033 126. 0.18 0.03 1072300500034 127. 0.35 0.07 1072300500035 128. 0.69 0.12 1072300500036 129. 1.31 0.20 1072300500037 130. 2.39 0.35 1072300500038 141. 5.208 0.253 1072300500039 153. 0.325 0.017 1072300500040 155. 160. 0.25 0.06 1072300500041 ENDDATA 24 0 1072300500042 ENDSUBENT 41 0 1072300599999 ENDENTRY 5 0 1072399999999