ENTRY 14745 20220208 14971474500000001 SUBENT 14745001 20220208 14971474500100001 BIB 8 28 1474500100002 TITLE Total cross sections of tritium, hydrogen, and helium 1474500100003 for fast neutrons 1474500100004 AUTHOR (J.H.Coon,R.O.Bondelid,D.D.Phillips) 1474500100005 REFERENCE (R,LA-1483,1952) 1474500100006 INSTITUTE (1USALAS) 1474500100007 DETECTOR (IOCH,SCIN) A variety of neutron detectors was 1474500100008 employed in the transmission geometry. In the neutron 1474500100009 energy region from 0.3 to 3.0 MeV a l/2-in. diameter 1474500100010 ionization chamber filled with hydrogen or deuterium 1474500100011 (200 to 700psi) was used. In the region from 3.4 to 7 1474500100012 MeV both the hydrogen filled recoil chamber and a 1474500100013 l/2-in. diameter by l-1/2-in. long stilbene crystal 1474500100014 were used at different times. In the region from 18 1474500100015 to 20 MeV a 3/4-in. diameter by l-1/2-in. long 1474500100016 anthracene crystal was was employed. At 14 MeV the 1474500100017 recoil chamber filled with 600 psi deuterium and 600 1474500100018 psi argon was employed. 1474500100019 METHOD (TRN) In the geometry employed for the transmission 1474500100020 neutron source and the neutron detector were spaced 1474500100021 30 cm from opposite ends of the 100-cm long cell. 1474500100022 ERR-ANALYS (DATA-ERR) Estimated probable errors. The quoted 1474500100023 errors are in general two to three tires the 1474500100024 statistical errors. Allowance for uncertainty of true 1474500100025 background, for uncertain influence of long steel 1474500100026 cell in spite of the fact that no scattering of 1474500100027 neutrons by the cell wall could be detected in the 1474500100028 geometry employed. 1474500100029 HISTORY (20220208C) BP 1474500100030 ENDBIB 28 0 1474500100031 NOCOMMON 0 0 1474500100032 ENDSUBENT 31 0 1474500199999 SUBENT 14745002 20220208 14971474500200001 BIB 5 17 1474500200002 REACTION (1-H-3(N,TOT),,SIG) 1474500200003 INC-SOURCE (P-T,D-D,D-T) The reactions T(p,n), D(D,n), and 1474500200004 T(D,n) with the electrostatic generator of Group P-9 1474500200005 gave neutrons in the respective energy intervals 0.3 1474500200006 to 3.0 MeV, 3.4 to 7.0 MeV, and 18 to 20 MeV. 1474500200007 Neutrons of energy 14.10 MeV were obtained from the 1474500200008 T(D,n) reaction with the 250 kV Cockcroft-Walton 1474500200009 accelerator of Group P-4. 1474500200010 FACILITY (ACCEL,1USALAS) The electrostatic generator. 1474500200011 (CCW,1USALAS) 1474500200012 SAMPLE All samples were contained in gaseous form in steel 1474500200013 cells 100 cm long and 1 in. outside dimeter. The cell 1474500200014 employed for hydrogen and tritium were designed by 1474500200015 CMR-9, which made accurate dimension and volume 1474500200016 measurements and filled the cell with accurately 1474500200017 measured quantities of gas. 1474500200018 STATUS (TABLE) Table III, page 12. 1474500200019 ENDBIB 17 0 1474500200020 NOCOMMON 0 0 1474500200021 DATA 4 23 1474500200022 EN EN-RSL DATA DATA-ERR 1474500200023 MEV MEV B B 1474500200024 0.29 0.06 1.39 0.07 1474500200025 0.54 0.05 1.57 0.05 1474500200026 0.71 0.16 1.58 0.05 1474500200027 0.99 0.15 1.69 0.05 1474500200028 1.11 0.04 1.72 0.05 1474500200029 1.50 0.12 1.89 0.04 1474500200030 2.03 0.10 2.09 0.04 1474500200031 2.49 0.09 2.28 0.05 1474500200032 2.99 0.08 2.40 0.05 1474500200033 3.4 1.26 2.43 0.05 1474500200034 3.73 0.21 2.49 0.05 1474500200035 4.1 0.82 2.40 0.05 1474500200036 4.77 0.15 2.28 0.05 1474500200037 4.80 0.47 2.28 0.05 1474500200038 5.34 0.34 2.16 0.04 1474500200039 5.52 0.19 2.17 0.04 1474500200040 6.07 0.15 2.05 0.04 1474500200041 6.58 0.15 1.90 0.04 1474500200042 6.97 0.20 1.81 0.04 1474500200043 14.10 0.06 0.978 0.007 1474500200044 18.0 0.34 0.76 0.04 1474500200045 19.1 0.21 0.76 0.04 1474500200046 20.0 0.13 0.66 0.04 1474500200047 ENDDATA 25 0 1474500200048 ENDSUBENT 47 0 1474500299999 SUBENT 14745003 20220208 14971474500300001 BIB 5 12 1474500300002 REACTION (1-H-1(N,TOT),,SIG) 1474500300003 INC-SOURCE (D-T) Neutrons of energy 14.10 MeV were obtained from 1474500300004 the T(D,n) reaction with the 250 kV Cockcroft-Walton 1474500300005 accelerator of Group P-4. 1474500300006 FACILITY (CCW,1USALAS) 1474500300007 SAMPLE All samples were contained in gaseous form in steel 1474500300008 cells 100 cm long and 1 in. outside dimeter. The cell 1474500300009 employed for hydrogen and tritium were designed by 1474500300010 CMR-9, which made accurate dimension and volume 1474500300011 measurements and filled the cell with accurately 1474500300012 measured quantities of gas. 1474500300013 STATUS (TABLE) Table III, page 12. 1474500300014 ENDBIB 12 0 1474500300015 NOCOMMON 0 0 1474500300016 DATA 4 1 1474500300017 EN EN-RSL DATA DATA-ERR 1474500300018 MEV MEV B B 1474500300019 14.10 0.06 0.687 0.007 1474500300020 ENDDATA 3 0 1474500300021 ENDSUBENT 20 0 1474500399999 SUBENT 14745004 20220208 14971474500400001 BIB 5 19 1474500400002 REACTION (2-HE-4(N,TOT),,SIG) 1474500400003 INC-SOURCE (P-T,D-D,D-T) The reactions T(p,n), D(D,n), and 1474500400004 T(D,n) with the electrostatic generator of Group P-9 1474500400005 gave neutrons in the respective energy intervals 0.3 1474500400006 to 3.0 MeV, 3.4 to 7.0 MeV, and 18 to 20 MeV. 1474500400007 Neutrons of energy 14.10 MeV were obtained from the 1474500400008 T(D,n) reaction with the 250 kV Cockcroft-Walton 1474500400009 accelerator of Group P-4. 1474500400010 FACILITY (ACCEL,1USALAS) The electrostatic generator. 1474500400011 (CCW,1USALAS) 1474500400012 SAMPLE All samples were contained in gaseous form in steel 1474500400013 cells 100 cm long and 1 in. outside dimeter. Normal 1474500400014 helium samples were contained in a having a 1474500400015 cylindrical wall of l/32-in. thickness as different 1474500400016 steel cell compared with 1/16-in. thickness for the 1474500400017 cell which held the tritium and hydrogen samples. The 1474500400018 number of atoms per cm2 of helium was determined from 1474500400019 data on gas weight, cell volume, and cell length. 1474500400020 STATUS (TABLE) Table III, page 12. 1474500400021 ENDBIB 19 0 1474500400022 NOCOMMON 0 0 1474500400023 DATA 5 9 1474500400024 EN EN-RSL DATA DATA-ERR DATA-MAX 1474500400025 MEV MEV B B B 1474500400026 0.94 0.15 6.31 0.13 1474500400027 1.50 0.12 5.62 0.11 1474500400028 1.98 0.10 3.98 0.08 1474500400029 2.49 0.09 3.16 0.06 1474500400030 2.99 0.08 2.79 0.006 1474500400031 4.10 0.82 2.43 1474500400032 5.04 0.34 2.11 1474500400033 6.46 0.24 2.06 1474500400034 14.10 0.06 1.03 0.02 1474500400035 ENDDATA 11 0 1474500400036 ENDSUBENT 35 0 1474500499999 ENDENTRY 4 0 1474599999999