ENTRY 14738 20220126 14961473800000001 SUBENT 14738001 20220126 14961473800100001 BIB 11 24 1473800100002 TITLE Neutron spectrum for fast fission of 25 1473800100003 AUTHOR (H.T.Richards,L.Speck) 1473800100004 REFERENCE (R,LA-200,1945) 1473800100005 REL-REF (O,14729001,H.T.Richards+,R,LA-84,1944) Thermal 1473800100006 neutrons data. 1473800100007 (M,,H.T.Richards,J,PR,59,796,1941) Neutron spectrum 1473800100008 measuring criteria. 1473800100009 INSTITUTE (1USALAS) 1473800100010 FACILITY (ACCEL,1USALAS) The short electrostatic generator. 1473800100011 INC-SOURCE (P-LI7) 300- to 650 keV neutrons from the Li7(p,n)Be7 1473800100012 reaction. 1473800100013 DETECTOR (PLATE) The Ilford Special Halftone emulsions (200 1473800100014 microm thick). 1473800100015 METHOD (REC) A disk of enriched 235U was irradiated by 1473800100016 neutrons. Photographic emulsions placed at 170 1473800100017 degrees to the target were used to detect the fission 1473800100018 neutrons. Approximately 1500 recoil proton tracks 1473800100019 have been measured on the exposed plates. 1473800100020 CORRECTION Corrected for a variation of n-p scattering cross 1473800100021 section with energy, and corrected for the 1473800100022 discrimination against slightly inclined long tracks 1473800100023 which results from the finite thickness of the 1473800100024 emulsion. 1473800100025 HISTORY (20220126C) BP 1473800100026 ENDBIB 24 0 1473800100027 COMMON 2 3 1473800100028 EN-MIN EN-MAX 1473800100029 KEV KEV 1473800100030 300.0 650.0 1473800100031 ENDCOMMON 3 0 1473800100032 ENDSUBENT 31 0 1473800199999 SUBENT 14738002 20220126 14961473800200001 BIB 3 3 1473800200002 REACTION (92-U-235(N,F),PR,NU/DE,,REL) 1473800200003 ERR-ANALYS (DATA-ERR) No details on sources of uncertainties. 1473800200004 STATUS (CURVE) Fig. 2, page 9. 1473800200005 ENDBIB 3 0 1473800200006 NOCOMMON 0 0 1473800200007 DATA 3 21 1473800200008 E DATA DATA-ERR 1473800200009 MEV ARB-UNITS ARB-UNITS 1473800200010 1.036 383.166 26.370 1473800200011 1.436 571.927 35.204 1473800200012 1.832 649.601 31.881 1473800200013 2.217 578.796 38.491 1473800200014 2.628 450.767 29.681 1473800200015 3.037 383.237 36.316 1473800200016 3.428 273.928 31.893 1473800200017 3.811 183.327 29.669 1473800200018 4.204 160.911 28.582 1473800200019 4.594 125.298 22.031 1473800200020 5.020 102.845 33.005 1473800200021 5.403 93.638 29.717 1473800200022 5.799 92.118 27.518 1473800200023 6.186 32.310 17.596 1473800200024 6.581 27.490 19.832 1473800200025 6.987 22.658 23.131 1473800200026 7.395 26.624 12.085 1473800200027 8.173 16.996 10.974 1473800200028 8.592 16.550 18.672 1473800200029 8.999 22.716 17.584 1473800200030 11.398 33.363 33.017 1473800200031 ENDDATA 23 0 1473800200032 ENDSUBENT 31 0 1473800299999 SUBENT 14738003 20220126 14961473800300001 BIB 3 4 1473800300002 REACTION (92-U-235(N,F)0-NN-1,PR,KE) 1473800300003 ERR-ANALYS (DATA-ERR) Probable error. 1473800300004 STATUS (DEP,14738002) 1473800300005 (TABLE) page 5. 1473800300006 ENDBIB 4 0 1473800300007 NOCOMMON 0 0 1473800300008 DATA 2 1 1473800300009 DATA DATA-ERR 1473800300010 MEV MEV 1473800300011 2.63 0.1 1473800300012 ENDDATA 3 0 1473800300013 ENDSUBENT 12 0 1473800399999 ENDENTRY 3 0 1473899999999