ENTRY 30313 20090115 31343031300000001 SUBENT 30313001 20090115 31343031300100001 BIB 10 16 3031300100002 INSTITUTE (2GERDRE) 3031300100003 REFERENCE (J,JNE,27,747,1973) 3031300100004 (R,ZFK-277,197407) Original neutron emission data. 3031300100005 (R,ZFK-262,41,197309) Neutron emission spectrum. 3031300100006 (R,ZFK-271,184,197402) Evaluation of n-emission, 3031300100007 X-section 3031300100008 AUTHOR (D.Hermsdorf,S.Sassonoff,D.Seeliger,K.Seidel) 3031300100009 TITLE The Nb-93(n,2n)Nb-92 cross-section at 14 MeV extracted 3031300100010 from experimental neutron emission spectrum. 3031300100011 FACILITY (CCW) 150 KV-cascade accelerator with pulsed ion source3031300100012 INC-SOURCE (D-T) 3031300100013 METHOD (TOF) Time of flight. 3031300100014 DETECTOR (SCIN) Liquid scintillator. 3031300100015 PART-DET (N) Neutrons. 3031300100016 HISTORY (19751212C) KO. 3031300100017 (20090115A) BIB section updated 3031300100018 ENDBIB 16 0 3031300100019 NOCOMMON 0 0 3031300100020 ENDSUBENT 19 0 3031300199999 SUBENT 30313002 20090115 31343031300200001 BIB 5 17 3031300200002 REACTION (41-NB-93(N,X)0-NN-1,EM,SIG) 3031300200003 ANALYSIS Integration over differential neutron emission cross- 3031300200004 section (Exfor 30275.024), 3031300200005 and fitting with the sum of Weisskopf-Ewing formula 3031300200006 (equilibrium emission) and exciton model 3031300200007 formula(non-equilibrium emission), 3031300200008 K(1)*g(E,T) + K(2)*n(E) where K(1)=2.25*E-7/(MeV)**23031300200009 K(2)=8.0 *E-4/(MeV)**23031300200010 and E is for emitted neutron energy and T for nuclear 3031300200011 temperature. 3031300200012 Then extrapolation to E=0, and integration over the 3031300200013 range E=0 to E0, yields emission cross-section. 3031300200014 MONITOR Neutron source strength was absolutely determined by 3031300200015 the associated particle method. 3031300200016 STATUS (DEP,30275024) Dependent data on Exfor 30275.024 and 3031300200017 above-mentioned procedure. 3031300200018 ERR-ANALYS (ERR-S) Statistical error. 3031300200019 ENDBIB 17 0 3031300200020 NOCOMMON 0 0 3031300200021 DATA 3 1 3031300200022 EN DATA ERR-S 3031300200023 MEV MB MB 3031300200024 1.4600E+01 3.1500E+03 3.0000E+02 3031300200025 ENDDATA 3 0 3031300200026 ENDSUBENT 25 0 3031300299999 SUBENT 30313003 20090115 31343031300300001 BIB 7 26 3031300300002 REACTION (41-NB-93(N,2N)41-NB-92,,SIG) 3031300300003 ANALYSIS Total(n,2n) cross-section was deduced from 3031300300004 sig(n-emission)=sig(non-elast)+sig(n2n)-sig(na)-sig(np)3031300300005 data were taken from: 3031300300006 * 2000 mb by Blow,J.Nucl.Energy,26(1972)9 and 3031300300007 * neglecting the small contributions,10mb of sig(na) 3031300300008 * 20mb of sig(np), both the approximate values from 3031300300009 Cuzzocrea et al.,Nuov.Cim.4A(1971)251 and Qaim,Z.Naturf3031300300010 25A(1970)1977. 3031300300011 The value of the neutron emission cross-section is 3031300300012 taken from one in subent.2. 3031300300013 REL-REF (R,,Blow+,J,JNE,26,9,1972) 3031300300014 (R,,Cuzzocrea+,J,NC/A,4,251,1971) 3031300300015 (R,,Qaim+,J,ZN/A,25,1977,1970) 3031300300016 MONITOR (41-NB-93(N,NON),,SIG) 3031300300017 = 2000 mb by Blow,J.Nucl.Energy,26(1972)9 3031300300018 COMMENT Other independent evaluation confirms the magnitude of 3031300300019 the result. Subtracting the primary emitted neutron 3031300300020 with T=1.24+-0.05MeV. K(1)=3.0E-6/(MeV)**2 and 3031300300021 K(2)=6.24E-4/(MeV)**2, from the experimental emission 3031300300022 spectra, then the cross-section of secondary neutron 3031300300023 emission was obtained as about 1280 +- 140 mb. This is 3031300300024 in fair agreement with this result. 3031300300025 STATUS (DEP,30313002) Dependent data of subent.2 and 3031300300026 above-mentioned values. 3031300300027 ERR-ANALYS (DATA-ERR) No further information. 3031300300028 ENDBIB 26 0 3031300300029 NOCOMMON 0 0 3031300300030 DATA 3 1 3031300300031 EN DATA DATA-ERR 3031300300032 MEV MB MB 3031300300033 1.4600E+01 1.1500E+03 3.0000E+02 3031300300034 ENDDATA 3 0 3031300300035 ENDSUBENT 34 0 3031300399999 ENDENTRY 3 0 3031399999999