ENTRY 14389 20140519 14001438900000001 SUBENT 14389001 20140519 14001438900100001 BIB 12 31 1438900100002 TITLE Effective Capture Cross Sections of 233Pa and 239Np 1438900100003 for Thermal Reactor Neutrons 1438900100004 AUTHOR (J.Halperin,R.W.Stoughton,D.E.Ferguson,C.V.Ellison, 1438900100005 D.C.Overholt,C.M.Stevens) 1438900100006 REFERENCE (C,55GENEVA,7,258,1955) 1438900100007 (J,NSE,1,108,1956) Same result for Np-239. 1438900100008 REL-REF (O,12301004,J.Halperin+,J,NSE,1,1,1956) 1438900100009 Data for Pa-233 (also reported in Geneva conf. paper) 1438900100010 INSTITUTE (1USAORL,1USAANL) 1438900100011 FACILITY (REAC,1USAORL) Low Intensity Test Reactor (LITR), and 1438900100012 a graphite reactor. 1438900100013 METHOD (EXTB,ACTIV) An activation cross section measurement 1438900100014 of the isotopes during the course of a neutron 1438900100015 irradiation. A uranium sample was used to measure Np 1438900100016 and Pu cross sections. Np and Pu were produced by 1438900100017 n-capture on U, 2 beta decays, capture again. The 1438900100018 competing channels are shown in the diagrams. 1438900100019 (MASSP) Further work involved one month cooling, 1438900100020 chemical processing, mass spectrographic analysis. 1438900100021 ANALYSIS The principal analyses required by this method are 1438900100022 the mass spectrographic determination of the 1438900100023 234U/233U and 240Pu/239Pu ratios, the analyses of the 1438900100024 233U and 239Pu produced in the 232Th and 238U 1438900100025 respectively, and the irradiation times. 1438900100026 ERR-ANALYS (DATA-ERR) A more realistic appraisal of the numerous 1438900100027 factors entering into such measurement suggest the 1438900100028 uncertainty of 10 to 20 percent. 1438900100029 MONITOR (27-CO-59(N,G)27-CO-60,,SIG) 1438900100030 HISTORY (20140519C) BP 1438900100031 DECAY-DATA (92-U-239,23.0MIN,B-) 1438900100032 (92-U-240,14.0HR,B-) 1438900100033 ENDBIB 31 0 1438900100034 COMMON 1 3 1438900100035 EN-DUMMY 1438900100036 EV 1438900100037 0.0253 1438900100038 ENDCOMMON 3 0 1438900100039 ENDSUBENT 38 0 1438900199999 SUBENT 14389002 20140519 14001438900200001 BIB 4 7 1438900200002 REACTION (94-PU-239(N,G)94-PU-240,,SIG,,SPA) 1438900200003 SAMPLE (92-U-238,ENR=0.9997) Uranium metal cylinders about 1438900200004 1.8 cm in diameter, 4.0 cm long, weighting about 190 1438900200005 grams and canned in aluminum. 1438900200006 DECAY-DATA (94-PU-239,24400.0YR,A) 1438900200007 (94-PU-240,6600.0YR,A) 1438900200008 STATUS (TABLE) page 259, C,55GENEVA,7,258,1955. 1438900200009 ENDBIB 7 0 1438900200010 NOCOMMON 0 0 1438900200011 DATA 2 1 1438900200012 DATA DATA-ERR 1438900200013 B B 1438900200014 400.0 40.0 1438900200015 ENDDATA 3 0 1438900200016 ENDSUBENT 15 0 1438900299999 SUBENT 14389003 20140519 14001438900300001 BIB 4 8 1438900300002 REACTION (93-NP-239(N,G)93-NP-240,,SIG,,SPA) 1438900300003 SAMPLE (92-U-238,ENR=0.9997) Uranium metal cylinders about 1438900300004 1.8 cm in diameter, 4.0 cm long, weighting about 190 1438900300005 grams and canned in aluminum. 1438900300006 DECAY-DATA (93-NP-239,56.0HR,B-) 1438900300007 (93-NP-240-M,7.0MIN,B-) 1438900300008 (93-NP-240-G,1.0HR,B-) 1438900300009 STATUS (TABLE) page 259, C,55GENEVA,7,258,1955. 1438900300010 ENDBIB 8 0 1438900300011 NOCOMMON 0 0 1438900300012 DATA 2 1 1438900300013 DATA DATA-ERR 1438900300014 B B 1438900300015 80.0 15.0 1438900300016 ENDDATA 3 0 1438900300017 ENDSUBENT 16 0 1438900399999 ENDENTRY 3 0 1438999999999