ENTRY 11695 19831011 00001169500000001 SUBENT 11695001 19831011 00001169500100001 BIB 7 9 1169500100002 INSTITUTE (1USAWES) 1169500100003 REFERENCE (J,BAP,1,339(P8),5612) 1169500100004 AUTHOR (J.B.WEDDELL) 1169500100005 TITLE SCATTERING OF 4.4-MEV NEUTRONS AT 90DEG. BY FE, CO, 1169500100006 NI, AND PB. 1169500100007 DETECTOR (TRD) NUCLEAR EMULSIONS 1169500100008 STATUS (SCSRS) 1169500100009 HISTORY (760730T) TRANSLATED FROM SCISRS 1169500100010 (831011A) CONVERTED TO REACTION FORMALISM 1169500100011 ENDBIB 9 0 1169500100012 COMMON 3 3 1169500100013 ANG ANG-RSL EN-RSL 1169500100014 ADEG ADEG MEV 1169500100015 90. 5. 5. 1169500100016 ENDCOMMON 3 0 1169500100017 ENDSUBENT 16 0 1169500199999 SUBENT 11695002 19831011 00001169500200001 BIB 1 1 1169500200002 REACTION (26-FE-0(N,EL),,DA) 1169500200003 ENDBIB 1 0 1169500200004 NOCOMMON 0 0 1169500200005 DATA 3 1 1169500200006 EN DATA DATA-ERR 1169500200007 MEV MB/SR MB/SR 1169500200008 4.40 32. 5. 1169500200009 ENDDATA 3 0 1169500200010 ENDSUBENT 9 0 1169500299999 SUBENT 11695003 19831011 00001169500300001 BIB 2 2 1169500300002 REACTION (26-FE-0(N,INL),,DA) 1169500300003 EN-SEC FOR SCATTERED NEUTRON ENERGY ABOVE 0.8 MEV. 1169500300004 ENDBIB 2 0 1169500300005 NOCOMMON 0 0 1169500300006 DATA 3 1 1169500300007 EN DATA DATA-ERR 1169500300008 MEV MB/SR MB/SR 1169500300009 4.4 32. 10. 1169500300010 ENDDATA 3 0 1169500300011 ENDSUBENT 10 0 1169500399999 SUBENT 11695004 19831011 00001169500400001 BIB 1 1 1169500400002 REACTION (27-CO-59(N,EL)27-CO-59,,DA) 1169500400003 ENDBIB 1 0 1169500400004 NOCOMMON 0 0 1169500400005 DATA 3 1 1169500400006 EN DATA DATA-ERR 1169500400007 MEV MB/SR MB/SR 1169500400008 4.4 50. 10. 1169500400009 ENDDATA 3 0 1169500400010 ENDSUBENT 9 0 1169500499999 SUBENT 11695005 19831011 00001169500500001 BIB 2 2 1169500500002 REACTION (27-CO-59(N,INL)27-CO-59,,DA) 1169500500003 EN-SEC FOR SCATTERED NEUTRON ENERGY ABOVE 0.8 MEV. 1169500500004 ENDBIB 2 0 1169500500005 NOCOMMON 0 0 1169500500006 DATA 3 1 1169500500007 EN DATA DATA-ERR 1169500500008 MEV MB/SR MB/SR 1169500500009 4.4 44. 12. 1169500500010 ENDDATA 3 0 1169500500011 ENDSUBENT 10 0 1169500599999 SUBENT 11695006 19831011 00001169500600001 BIB 1 1 1169500600002 REACTION (28-NI-0(N,EL),,DA) 1169500600003 ENDBIB 1 0 1169500600004 NOCOMMON 0 0 1169500600005 DATA 3 1 1169500600006 EN DATA DATA-ERR 1169500600007 MEV MB/SR MB/SR 1169500600008 4.4 32. 5. 1169500600009 ENDDATA 3 0 1169500600010 ENDSUBENT 9 0 1169500699999 SUBENT 11695007 19831011 00001169500700001 BIB 2 2 1169500700002 REACTION (28-NI-0(N,INL),,DA) 1169500700003 EN-SEC FOR SCATTERED NEUTRON ENERGY ABOVE 0.8 MEV. 1169500700004 ENDBIB 2 0 1169500700005 NOCOMMON 0 0 1169500700006 DATA 3 1 1169500700007 EN DATA DATA-ERR 1169500700008 MEV MB/SR MB/SR 1169500700009 4.4 20. 7. 1169500700010 ENDDATA 3 0 1169500700011 ENDSUBENT 10 0 1169500799999 SUBENT 11695008 19831011 00001169500800001 BIB 1 1 1169500800002 REACTION (82-PB-0(N,EL),,DA) 1169500800003 ENDBIB 1 0 1169500800004 NOCOMMON 0 0 1169500800005 DATA 3 1 1169500800006 EN DATA DATA-ERR 1169500800007 MEV MB/SR MB/SR 1169500800008 4.4 125. 25. 1169500800009 ENDDATA 3 0 1169500800010 ENDSUBENT 9 0 1169500899999 SUBENT 11695009 19831011 00001169500900001 BIB 1 1 1169500900002 REACTION (82-PB-0(N,INL),,DA) 1169500900003 ENDBIB 1 0 1169500900004 NOCOMMON 0 0 1169500900005 DATA 3 1 1169500900006 EN DATA DATA-ERR 1169500900007 MEV MB/SR MB/SR 1169500900008 4.4 68. 23. 1169500900009 ENDDATA 3 0 1169500900010 ENDSUBENT 9 0 1169500999999 ENDENTRY 9 0 1169599999999