ENTRY 21208 20201210 22962120800000001 SUBENT 21208001 20201210 22962120800100001 BIB 8 15 2120800100002 TITLE Cross-sections for the (n,2n) reactions of 232Th, 2120800100003 238U and 237Np with 14 MeV neutrons 2120800100004 AUTHOR (J.L.Perkin,R.F.Coleman) 2120800100005 REFERENCE (J,JNE/AB,14,69,1961) 2120800100006 INSTITUTE (2UK ALD) AWRE Aldermaston. 2120800100007 FACILITY (ACCEL,2UK ALD) No information, probably Van de Graaf. 2120800100008 INC-SOURCE (D-T) 160 keV or 500 keV deuterons incident on a 2120800100009 tritiated zirconium target. 2120800100010 METHOD (ACTIV) 2120800100011 HISTORY (19791211T) NEUDADA 2120800100012 (19800110E) 2120800100013 (20060809A) Date and reference code corrected 2120800100014 (20201210U) SD:Updated to new date formats, lower case.2120800100015 Ref.AERE-NP/R-2033 deleted (another experiment and 2120800100016 authors). Corrections in all Subents. 2120800100017 ENDBIB 15 0 2120800100018 NOCOMMON 0 0 2120800100019 ENDSUBENT 18 0 2120800199999 SUBENT 21208002 20201210 22962120800200001 BIB 9 27 2120800200002 REACTION (90-TH-232(N,2N)90-TH-231,,SIG) 2120800200003 SAMPLE Oxide sample, ground to a fine powder and dusted on 2120800200004 sellotape. Two areas placed face to face, sandwiching 2120800200005 the Al monitor foil, used in the irradiation. Weight 2120800200006 of oxide measured as 16.7 mg by ashing the sample and 2120800200007 weighing the residue. 2120800200008 Thorium oxide sample was stripped of natural 2120800200009 daughters by chemical processing prior to irradiation.2120800200010 Th-231 calibration samples extracted from uranium 2120800200011 metal by similar chemical separation. 2120800200012 DETECTOR (NAICR) 2.25 X 2.25 inch sodium iodide crystal. 2120800200013 Counter efficiency, calibrated using a known quantity 2120800200014 of Th-231, was obtained from uranium metal where it was2120800200015 in equilibrium with U-235. 2120800200016 DECAY-DATA (90-TH-231,25.6HR,DG,58.5,,DG,85.) 2120800200017 MONITOR (13-AL-27(N,A)11-NA-24-G,,SIG) 2120800200018 STATUS (TABLE) Text on p.71 of J.Nucl.En.,A/B,14(1961)69 2120800200019 CORRECTION 3% correction for growth of gamma activity in 2120800200020 Ra-224 and its daughters, observed in separate 2120800200021 experiment. 2120800200022 ERR-ANALYS (ERR-T) Total uncertainty includes: 2120800200023 (ERR-1) Uncertainty in neutron flux...............3%. 2120800200024 (ERR-2) Uncertainty in weight of thorium..........1%. 2120800200025 (ERR-3) Uncertainty in counter efficiency.........3%. 2120800200026 (ERR-S) Counting statistics.......................1%. 2120800200027 HISTORY (19791210T) 2120800200028 (20201210U) SD: ERR-ANALYS updated. DATA-ERR -> ERR-T. 2120800200029 ENDBIB 27 0 2120800200030 NOCOMMON 0 0 2120800200031 DATA 8 1 2120800200032 EN EN-ERR DATA ERR-T ERR-S ERR-1 2120800200033 ERR-2 ERR-3 2120800200034 MEV MEV B B PER-CENT PER-CENT 2120800200035 PER-CENT PER-CENT 2120800200036 14.1 0.3 1.20 0.05 1. 3.2120800200037 1. 3. 2120800200038 ENDDATA 6 0 2120800200039 ENDSUBENT 38 0 2120800299999 SUBENT 21208003 20201210 22962120800300001 BIB 9 20 2120800300002 REACTION (92-U-238(N,2N)92-U-237,,SIG) 2120800300003 SAMPLE 275 mg of uranium-oxide. No chemical separation of 2120800300004 fission products was made. 2120800300005 DETECTOR (NAICR) 2.25 X 2.25 inch sodium iodide crystal. 2120800300006 Counter efficiency calibrated using a known 2120800300007 quantity of U-237, standardized by counting 2120800300008 in a 4-pi proportional counter. 2120800300009 DECAY-DATA (92-U-237,6.75D,DG,59.,,DG,203.,,XR,100.) 2120800300010 MONITOR (29-CU-65(N,2N)29-CU-64,,SIG) Annihilation radiation 2120800300011 measured from monitor reaction. 2120800300012 CORRECTION Experimental corrections for gamma-ray attenuation in 2120800300013 the thick target. 2120800300014 ERR-ANALYS (ERR-T) Total uncertainty includes: 2120800300015 (ERR-1) Uncertainty in neutron flux.............. 5%. 2120800300016 (ERR-2) Uncertainty in thick source correction... 2%. 2120800300017 (ERR-3) Uncertainty in weight of uranium......... 1%. 2120800300018 (ERR-4) 4-Pi calibration of standard U-237 source 2%. 2120800300019 STATUS (TABLE) Text on p.73 of J.Nucl.En.,A/B,14(1961)69 2120800300020 HISTORY (19791210T) 2120800300021 (20201210U) SD: ERR-ANALYS updated. DATA-ERR -> ERR-T. 2120800300022 ENDBIB 20 0 2120800300023 NOCOMMON 0 0 2120800300024 DATA 8 1 2120800300025 EN EN-ERR DATA ERR-T ERR-1 ERR-2 2120800300026 ERR-3 ERR-4 2120800300027 MEV MEV B B PER-CENT PER-CENT 2120800300028 PER-CENT PER-CENT 2120800300029 14.5 0.4 0.69 0.04 5. 2.2120800300030 1. 2. 2120800300031 ENDDATA 6 0 2120800300032 ENDSUBENT 31 0 2120800399999 SUBENT 21208004 20201210 22962120800400001 BIB 10 20 2120800400002 REACTION (93-NP-237(N,2N)93-NP-236-M,,SIG) 2120800400003 SAMPLE 72 mg of purified neptunium dioxide, irradiated for 2120800400004 4 hours and left for a week for Np-237 to decay into 2120800400005 Pu-236 which was chemically separated. 2120800400006 DETECTOR (IOCH) Gridded ionization chamber. Efficiency 2120800400007 measured as 50% using Pu-239 from 2120800400008 a stock solution which had been standardized 2120800400009 with a 4-pi proportional counter. 2120800400010 DECAY-DATA (94-PU-236,2.7YR,A,5730.) 2120800400011 MONITOR (13-AL-27(N,A)11-NA-24-G,,SIG) 2120800400012 MISC-COL (MISC) B/EC branching ratio of Np-236 to Pu-236 and 2120800400013 U-236 taken as 0.96 +- 0.16 (see REL-REF). 2120800400014 REL-REF (R,,J.E.Gindler+,J,JIN,12,8,1959) 2120800400015 ERR-ANALYS (DATA-ERR) Total uncertainty including the errors in 2120800400016 the half-life and branching ratio 2120800400017 STATUS (TABLE) Text on p.75 of J.Nucl.En.,A/B,14(1961)69 2120800400018 HISTORY (19791210T) 2120800400019 (20060809U) Column order corrected 2120800400020 (20201210U) SD: DECAY-DATA corrected (the energy of 2120800400021 radiation was multiplied by 1000). ERR-ANALYS added. 2120800400022 ENDBIB 20 0 2120800400023 NOCOMMON 0 0 2120800400024 DATA 6 1 2120800400025 EN EN-ERR DATA DATA-ERR MISC MISC-ERR 2120800400026 MEV MEV B B NO-DIM NO-DIM 2120800400027 14.5 0.4 0.39 0.07 0.96 0.162120800400028 ENDDATA 3 0 2120800400029 ENDSUBENT 28 0 2120800499999 ENDENTRY 4 0 2120899999999