ENTRY 22902 20080130 21922290200000001 SUBENT 22902001 20080130 21922290200100001 BIB 16 59 2290200100002 TITLE .Measurement of Neutron Reaction Cross Sections 2290200100003 between 8 and 14 MeV 2290200100004 AUTHOR (W.MANNHART, D.SCHMIDT) 2290200100005 INSTITUTE (2GERPTB) 2290200100006 REFERENCE (C,2004SANTA,,609,200410) Main reference, graphs are 2290200100007 given 2290200100008 (J,NSE,106,308,1990) Data for correcting reaction 2290200100009 H-2(D,N+P) 2290200100010 REL-REF (N,,J.KANTELE+,J,NIM,112,501,1973) Method of 2290200100011 correction due to the 511-keV gamma annihilation 2290200100012 in flight 2290200100013 FACILITY (CYCLO) Compact cyclotron CV28 operating in a pulsed 2290200100014 mode with 1 ns pulse duration and aprx. 1 MHz 2290200100015 repetition rate 2290200100016 INC-SOURCE (D-D) Target is deuterium gas pressurized to 2290200100017 200 kPA, 3 cm long and 1 cm in diameter 2290200100018 MONITOR (92-U-238(N,F),,SIG) 2290200100019 MONIT-REF .Data of ENDF/B-VI, http://www-nds.iaea.org/endf/ 2290200100020 DETECTOR (HPGE) For annihilation 511-keV gamma ray detection 2290200100021 (FISCH) U-238 fission chamber for neutron fluence 2290200100022 monitoring 2290200100023 METHOD (TOF) For neutron energy determination, flight path 2290200100024 12 m 2290200100025 (ACTIV) 2290200100026 (SITA) Single target irradiation. Each irradiation was2290200100027 accompanied by a measurement with an empty gas 2290200100028 cell in order to compensate the low-energy neutrons 2290200100029 generated in the materials of the target 2290200100030 ANALYSIS (DECAY) For determiation of the individual reaction 2290200100031 channel that specifies cross section 2290200100032 CORRECTION .Correction in general - 2290200100033 .For dead-time effects; 2290200100034 for variation of the neutron fluence; 2290200100035 for fission fragment losses at the flux monitoring; 2290200100036 for the zero extrapolation of the fission events; 2290200100037 for neutron scattering in the gas target, fission 2290200100038 chamber and support structures 2290200100039 .Correction for the missing 511-keV radiation due to 2290200100040 the annihilation in flight is 1.1%; 2290200100041 ERR-ANALYS (ERR-T) Total error equal to the quadratic sum of its 2290200100042 constituents - 2290200100043 (MONIT-ERR) Error of the U-238 reference cross section2290200100044 (ERR-1) Error due to the fission deposit mass 2290200100045 (ERR-2) Max error due to the correction of the 2290200100046 break-up neutrons with U-238. Min error = 0 2290200100047 (ERR-3) Max error due to the U-238 fragment counting 2290200100048 statistics 2290200100049 (ERR-4) Error due to the peak efficiency of the HPGE 2290200100050 detector 2290200100051 (EN-ERR) Error of the maximum neutron energy spectrum 2290200100052 line 2290200100053 STATUS (TABLE) From the tables sent via INTERNET, 2290200100054 W.Mannhart, 2005-10-20 2290200100055 (COREL,22976001) 2290200100056 HISTORY (20051227C) + + SM 2290200100057 (20080130A) Four SUBENTs deleted due to new 2290200100058 compilation in ENTRY 22976: SAN 22976027 vs 22902002, 2290200100059 22976028 vs 22902003, 22976025 vs 22902004, 2290200100060 22976029 vs 22902005 - SM 2290200100061 ENDBIB 59 0 2290200100062 COMMON 6 3 2290200100063 EN-ERR MONIT-ERR ERR-1 ERR-2 ERR-3 ERR-4 2290200100064 KEV PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2290200100065 20. 1.5 0.6 3.1 1. 1.5 2290200100066 ENDCOMMON 3 0 2290200100067 ENDSUBENT 66 0 2290200199999 NOSUBENT 22902002 20080130 21922290200200001 NOSUBENT 22902003 20080130 21922290200300001 NOSUBENT 22902004 20080130 21922290200400001 NOSUBENT 22902005 20080130 21922290200500001 SUBENT 22902006 20080130 21922290200600001 BIB 4 7 2290200600002 REACTION (29-CU-63(N,G)29-CU-64,,SIG) 2290200600003 SAMPLE .Elemental high-purity metallic sample, 1 mm thick, 2290200600004 10 mm diameter. Cu-63 isotopic abundance is 0.6917. 2290200600005 DECAY-DATA (29-CU-64,12.700HR,B+,650.,0.1740, 2290200600006 DG,1345.8,0.00473) Endpoint 2290200600007 B+ energy is given 2290200600008 HISTORY (20080130A) Superseded by author's decision 2290200600009 ENDBIB 7 0 2290200600010 NOCOMMON 0 0 2290200600011 DATA 4 1 2290200600012 EN EN-RSL-FW DATA ERR-T 2290200600013 MEV MEV MB MB 2290200600014 9.53 0.115 7.0 0.3 2290200600015 ENDDATA 3 0 2290200600016 ENDSUBENT 15 0 2290200699999 ENDENTRY 6 0 2290299999999