ENTRY 23277 20150805 22432327700000001 SUBENT 23277001 20150805 22432327700100001 BIB 17 59 2327700100002 TITLE Nuclear data measurements for FR-wall and structural 2327700100003 materials 2327700100004 AUTHOR (S.M.Qaim,N.I.Molla) 2327700100005 REFERENCE (C,76GARMIS,,589,197606) EUR-5602. 2327700100006 Only cr.sections for nuclear reactions induced by fast2327700100007 neutrons produced in the break-up 30 MeV deuterons 2327700100008 on beryllium are presented here. 2327700100009 Final data for reactions at En=14.7 MeV published 2327700100010 in NP/A,283,269,1977 (see REL-REF, Entry 20721). 2327700100011 FACILITY (CYCLO,2GERKFK) The Karlsruhe Cyclotron was used for 2327700100012 the deuteron breakup neutrons. 2327700100013 INSTITUTE (2GERJUL) Institut fuer Chemie of the Kernforschungs- 2327700100014 Anlage,Juelich. 2327700100015 INC-SOURCE (D-BE) Fast neutrons were produced by bombarding a 2327700100016 1cm thick Be-target with 30MeV deuterons at 2 microA 2327700100017 current, measured by a Faraday cup. 2327700100018 METHOD (ACTIV) No fast pneumatic system used (comment 2327700100019 from Prof. S.M.Qaim) 2327700100020 (GSPEC) Gamma-and X-ray-spectroscopy were employed. 2327700100021 (COINC) Gamma-gamma coincidence. 2327700100022 (BCINT) 2327700100023 SAMPLE High purity enriched samples were used. 2327700100024 DETECTOR (GELI) Co-axial 28 cm**3 GeLi detector in case of 2327700100025 very low energy gamma-rays, or Ge detector of active 2327700100026 area 2 cm**2 with thin beryllium window. 2327700100027 INC-SPECT Deuteron break-up spectrum has an approximate 2327700100028 Maxwellian shape with a maximum intensity at 11.5 MeV. 2327700100029 The shape of spectrum calculated by the method of 2327700100030 Schmidt and Muenzel is in Fig.1 of 76GARMIS. 2327700100031 EN-MIN about 2.0 MeV. 2327700100032 EN-MAX about 28. MeV . 2327700100033 Neutron flux densities obtained via the two methods 2327700100034 (exp. and calc.) were found to be almost identical. 2327700100035 REL-REF (M,,G.W.Schweimer,J,NP/A,100,537,1967) 2327700100036 (M,,K.Schmidt+,R,KFK-1288,1970) - calc. of neutr.flux; 2327700100037 Method of Schmidt and Muenzel was used for the shape 2327700100038 spectrum calculation. 2327700100039 (M,,J.P.Meulders+,J,PMB,20,235,1975) 2327700100040 References for neutron spectra exp.measurements for 2327700100041 various incident deuterons energies. 2327700100042 (O,20721001,N.I.Molla+,J,NP/A,283,269,197706) Final 2327700100043 data for reactions at 14.7 MeV 2327700100044 MONITOR (26-FE-54(N,P)25-MN-54,,SIG)For neutron flux monitoring2327700100045 MONIT-REF (,A.Paulsen+,C,71CANT,129,1971) Excitation function 2327700100046 has been evaluated ( in MONIT-REF ) over the major 2327700100047 portion of neutron spectrum encountered in this work. 2327700100048 CORRECTION Usual corrections for: 2327700100049 - Decay, 2327700100050 - Gamma-transition intensities, 2327700100051 - Internal conversion coefficients, 2327700100052 - Counting efficiency, 2327700100053 - Geometry, 2327700100054 - Absorption. 2327700100055 ERR-ANALYS (DATA-ERR) Between 6 and 15 % were the errors. 2327700100056 STATUS (TABLE) Table 2 of Conference Proceeding 76GARMIS. 2327700100057 HISTORY (20150805T) SD: Part of the data from Entry 20721. 2327700100058 Cr.sections for nuclear reactions induced by fast 2327700100059 neutrons produced in the break-up 30 MeV deuterons 2327700100060 on beryllium are presented here. 2327700100061 ENDBIB 59 0 2327700100062 NOCOMMON 0 0 2327700100063 ENDSUBENT 62 0 2327700199999 SUBENT 23277002 20150805 22432327700200001 BIB 3 6 2327700200002 REACTION (26-FE-54(N,P)25-MN-54,,SIG,,SPA) 2327700200003 Measured effective cross-section for wide neutron 2327700200004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327700200005 PART-DET (DG) 25-Mn-54 2327700200006 ANALYSIS Q-value +0.09 MeV, threshold energy 2.0 MeV are given 2327700200007 in Table 2. 2327700200008 ENDBIB 6 0 2327700200009 NOCOMMON 0 0 2327700200010 DATA 4 1 2327700200011 EN-MIN EN-MEAN DATA DATA-ERR 2327700200012 MEV MEV MB MB 2327700200013 2. 11.5 342. 36. 2327700200014 ENDDATA 3 0 2327700200015 ENDSUBENT 14 0 2327700299999 SUBENT 23277003 20150805 22432327700300001 BIB 2 5 2327700300002 REACTION (26-FE-54(N,A)24-CR-51,,SIG,,SPA) 2327700300003 Measured effective cross-section for wide neutron 2327700300004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327700300005 ANALYSIS Q-value +0.85 MeV, threshold energy 2.0 MeV are given 2327700300006 in Table 2. 2327700300007 ENDBIB 5 0 2327700300008 NOCOMMON 0 0 2327700300009 DATA 4 1 2327700300010 EN-MIN EN-MEAN DATA DATA-ERR 2327700300011 MEV MEV MB MB 2327700300012 2. 11.5 88. 10. 2327700300013 ENDDATA 3 0 2327700300014 ENDSUBENT 13 0 2327700399999 SUBENT 23277004 20150805 22432327700400001 BIB 2 5 2327700400002 REACTION (26-FE-56(N,P)25-MN-56,,SIG,,SPA) 2327700400003 Measured effective cross-section for wide neutron 2327700400004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327700400005 ANALYSIS Q-value -2.92 MeV, threshold energy 3.5 MeV are given 2327700400006 in Table 2. 2327700400007 ENDBIB 5 0 2327700400008 COMMON 1 3 2327700400009 EN-MEAN 2327700400010 MEV 2327700400011 11.5 2327700400012 ENDCOMMON 3 0 2327700400013 DATA 3 2 2327700400014 EN-MIN DATA DATA-ERR 2327700400015 MEV MB MB 2327700400016 2. 82. 12. 2327700400017 3.5 88. 12. 2327700400018 ENDDATA 4 0 2327700400019 ENDSUBENT 18 0 2327700499999 SUBENT 23277005 20150805 22432327700500001 BIB 2 5 2327700500002 REACTION (27-CO-59(N,2N)27-CO-58,,SIG,,SPA) 2327700500003 Measured effective cross-section for wide neutron 2327700500004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327700500005 ANALYSIS Q-value -10.46MeV, threshold energy 10.5 MeV are given2327700500006 in Table 2. 2327700500007 ENDBIB 5 0 2327700500008 COMMON 1 3 2327700500009 EN-MEAN 2327700500010 MEV 2327700500011 11.5 2327700500012 ENDCOMMON 3 0 2327700500013 DATA 3 2 2327700500014 EN-MIN DATA DATA-ERR 2327700500015 MEV MB MB 2327700500016 2. 388. 60. 2327700500017 10.5 590. 60. 2327700500018 ENDDATA 4 0 2327700500019 ENDSUBENT 18 0 2327700599999 SUBENT 23277006 20150805 22432327700600001 BIB 2 5 2327700600002 REACTION (27-CO-59(N,A)25-MN-56,,SIG,,SPA) 2327700600003 Measured effective cross-section for wide neutron 2327700600004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327700600005 ANALYSIS Q-value +0.32 MeV, threshold energy 6.5 MeV are given 2327700600006 in Table 2. 2327700600007 ENDBIB 5 0 2327700600008 COMMON 1 3 2327700600009 EN-MEAN 2327700600010 MEV 2327700600011 11.5 2327700600012 ENDCOMMON 3 0 2327700600013 DATA 3 2 2327700600014 EN-MIN DATA DATA-ERR 2327700600015 MEV MB MB 2327700600016 2. 17. 2. 2327700600017 6.5 22. 2. 2327700600018 ENDDATA 4 0 2327700600019 ENDSUBENT 18 0 2327700699999 SUBENT 23277007 20150805 22432327700700001 BIB 2 5 2327700700002 REACTION (28-NI-58(N,2N)28-NI-57,,SIG,,SPA) 2327700700003 Measured effective cross-section for wide neutron 2327700700004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327700700005 ANALYSIS Q-value -12.20MeV, threshold energy 12.2 MeV are given2327700700006 in Table 2. 2327700700007 ENDBIB 5 0 2327700700008 COMMON 1 3 2327700700009 EN-MEAN 2327700700010 MEV 2327700700011 11.5 2327700700012 ENDCOMMON 3 0 2327700700013 DATA 3 2 2327700700014 EN-MIN DATA DATA-ERR 2327700700015 MEV MB MB 2327700700016 2. 23. 5. 2327700700017 12.2 44. 5. 2327700700018 ENDDATA 4 0 2327700700019 ENDSUBENT 18 0 2327700799999 SUBENT 23277008 20150805 22432327700800001 BIB 2 5 2327700800002 REACTION (28-NI-58(N,P)27-CO-58,,SIG,,SPA) 2327700800003 Measured effective cross-section for wide neutron 2327700800004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327700800005 ANALYSIS Q-value +0.39 MeV, threshold energy 1.5 MeV are given 2327700800006 in Table 2. 2327700800007 ENDBIB 5 0 2327700800008 COMMON 1 3 2327700800009 EN-MEAN 2327700800010 MEV 2327700800011 11.5 2327700800012 ENDCOMMON 3 0 2327700800013 DATA 3 2 2327700800014 EN-MIN DATA DATA-ERR 2327700800015 MEV MB MB 2327700800016 2. 395. 46. 2327700800017 1.5 388. 46. 2327700800018 ENDDATA 4 0 2327700800019 ENDSUBENT 18 0 2327700899999 SUBENT 23277009 20150805 22432327700900001 BIB 2 5 2327700900002 REACTION (28-NI-60(N,P)27-CO-60,,SIG,,SPA) 2327700900003 Measured effective cross-section for wide neutron 2327700900004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327700900005 ANALYSIS Q-value -2.04 MeV, threshold energy 5.5 MeV are given 2327700900006 in Table 2. 2327700900007 ENDBIB 5 0 2327700900008 COMMON 1 3 2327700900009 EN-MEAN 2327700900010 MEV 2327700900011 11.5 2327700900012 ENDCOMMON 3 0 2327700900013 DATA 3 2 2327700900014 EN-MIN DATA DATA-ERR 2327700900015 MEV MB MB 2327700900016 2. 87. 12. 2327700900017 5.5 104. 12. 2327700900018 ENDDATA 4 0 2327700900019 ENDSUBENT 18 0 2327700999999 SUBENT 23277010 20150805 22432327701000001 BIB 2 5 2327701000002 REACTION (40-ZR-90(N,2N)40-ZR-89,,SIG,,SPA) 2327701000003 Measured effective cross-section for wide neutron 2327701000004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327701000005 ANALYSIS Q-value -11.99MeV, threshold energy 12.0 MeV are given2327701000006 in Table 2. 2327701000007 ENDBIB 5 0 2327701000008 COMMON 1 3 2327701000009 EN-MEAN 2327701000010 MEV 2327701000011 11.5 2327701000012 ENDCOMMON 3 0 2327701000013 DATA 3 2 2327701000014 EN-MIN DATA DATA-ERR 2327701000015 MEV MB MB 2327701000016 2. 438. 70. 2327701000017 12.0 832. 70. 2327701000018 ENDDATA 4 0 2327701000019 ENDSUBENT 18 0 2327701099999 SUBENT 23277011 20150805 22432327701100001 BIB 2 5 2327701100002 REACTION (40-ZR-90(N,P)39-Y-90,,SIG,,SPA) 2327701100003 Measured effective cross-section for wide neutron 2327701100004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327701100005 ANALYSIS Q-value -1.49 MeV, threshold energy 8.0 MeV are given 2327701100006 in Table 2. 2327701100007 ENDBIB 5 0 2327701100008 COMMON 1 3 2327701100009 EN-MEAN 2327701100010 MEV 2327701100011 11.5 2327701100012 ENDCOMMON 3 0 2327701100013 DATA 3 2 2327701100014 EN-MIN DATA DATA-ERR 2327701100015 MEV MB MB 2327701100016 2. 39. 5. 2327701100017 8.0 55. 5. 2327701100018 ENDDATA 4 0 2327701100019 ENDSUBENT 18 0 2327701199999 SUBENT 23277012 20150805 22432327701200001 BIB 2 5 2327701200002 REACTION (40-ZR-90(N,A)38-SR-87-M,,SIG,,SPA) 2327701200003 Measured effective cross-section for wide neutron 2327701200004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327701200005 ANALYSIS Q-value +1.35 MeV, threshold energy 9.0 MeV are given 2327701200006 in Table 2. 2327701200007 ENDBIB 5 0 2327701200008 COMMON 1 3 2327701200009 EN-MEAN 2327701200010 MEV 2327701200011 11.5 2327701200012 ENDCOMMON 3 0 2327701200013 DATA 3 2 2327701200014 EN-MIN DATA DATA-ERR 2327701200015 MEV MB MB 2327701200016 2. 2.0 0.2 2327701200017 9.0 3.0 0.2 2327701200018 ENDDATA 4 0 2327701200019 ENDSUBENT 18 0 2327701299999 SUBENT 23277013 20150805 22432327701300001 BIB 2 5 2327701300002 REACTION (41-NB-93(N,2N)41-NB-92-M,,SIG,,SPA) 2327701300003 Measured effective cross-section for wide neutron 2327701300004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327701300005 ANALYSIS Q-value -8.96 MeV, threshold energy 9.0 MeV are given 2327701300006 in Table 2. 2327701300007 ENDBIB 5 0 2327701300008 COMMON 1 3 2327701300009 EN-MEAN 2327701300010 MEV 2327701300011 11.5 2327701300012 ENDCOMMON 3 0 2327701300013 DATA 3 2 2327701300014 EN-MIN DATA DATA-ERR 2327701300015 MEV MB MB 2327701300016 2. 240. 40. 2327701300017 9.0 363. 40. 2327701300018 ENDDATA 4 0 2327701300019 ENDSUBENT 18 0 2327701399999 SUBENT 23277014 20150805 22432327701400001 BIB 2 5 2327701400002 REACTION (41-NB-93(N,A)39-Y-90-M,,SIG,,SPA) 2327701400003 Measured effective cross-section for wide neutron 2327701400004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327701400005 ANALYSIS Q-value +4.25 MeV, threshold energy 7.0 MeV are given 2327701400006 in Table 2. 2327701400007 ENDBIB 5 0 2327701400008 COMMON 1 3 2327701400009 EN-MEAN 2327701400010 MEV 2327701400011 11.5 2327701400012 ENDCOMMON 3 0 2327701400013 DATA 3 2 2327701400014 EN-MIN DATA DATA-ERR 2327701400015 MEV MB MB 2327701400016 2. 3.5 0.5 2327701400017 7.0 4.5 0.5 2327701400018 ENDDATA 4 0 2327701400019 ENDSUBENT 18 0 2327701499999 SUBENT 23277015 20150805 22432327701500001 BIB 2 5 2327701500002 REACTION (42-MO-92(N,P)41-NB-92-M,,SIG,,SPA) 2327701500003 Measured effective cross-section for wide neutron 2327701500004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327701500005 ANALYSIS Q-value +0.30 MeV, threshold energy 8.0 MeV are given 2327701500006 in Table 2. 2327701500007 ENDBIB 5 0 2327701500008 COMMON 1 3 2327701500009 EN-MEAN 2327701500010 MEV 2327701500011 11.5 2327701500012 ENDCOMMON 3 0 2327701500013 DATA 3 2 2327701500014 EN-MIN DATA DATA-ERR 2327701500015 MEV MB MB 2327701500016 2. 53. 8. 2327701500017 8.0 74. 8. 2327701500018 ENDDATA 4 0 2327701500019 ENDSUBENT 18 0 2327701599999 SUBENT 23277016 20150805 22432327701600001 BIB 2 5 2327701600002 REACTION (42-MO-92(N,A)40-ZR-89,,SIG,,SPA) 2327701600003 Measured effective cross-section for wide neutron 2327701600004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327701600005 ANALYSIS Q-value +3.69 MeV, threshold energy 8.0 MeV are given 2327701600006 in Table 2. 2327701600007 ENDBIB 5 0 2327701600008 COMMON 1 3 2327701600009 EN-MEAN 2327701600010 MEV 2327701600011 11.5 2327701600012 ENDCOMMON 3 0 2327701600013 DATA 3 2 2327701600014 EN-MIN DATA DATA-ERR 2327701600015 MEV MB MB 2327701600016 2. 14. 2. 2327701600017 8.0 1.9 2. 2327701600018 ENDDATA 4 0 2327701600019 ENDSUBENT 18 0 2327701699999 SUBENT 23277017 20150805 22432327701700001 BIB 2 5 2327701700002 REACTION (42-MO-95(N,P)41-NB-95,,SIG,,SPA) 2327701700003 Measured effective cross-section for wide neutron 2327701700004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327701700005 ANALYSIS Q-value -0.14 MeV, threshold energy 8.5 MeV are given 2327701700006 in Table 2. 2327701700007 ENDBIB 5 0 2327701700008 COMMON 1 3 2327701700009 EN-MEAN 2327701700010 MEV 2327701700011 11.5 2327701700012 ENDCOMMON 3 0 2327701700013 DATA 3 2 2327701700014 EN-MIN DATA DATA-ERR 2327701700015 MEV MB MB 2327701700016 2. 23. 3. 2327701700017 8.5 32. 3. 2327701700018 ENDDATA 4 0 2327701700019 ENDSUBENT 18 0 2327701799999 SUBENT 23277018 20150805 22432327701800001 BIB 2 5 2327701800002 REACTION (42-MO-100(N,2N)42-MO-99,,SIG,,SPA) 2327701800003 Measured effective cross-section for wide neutron 2327701800004 spectrum. Averaging in neutron energy rage > EN-MIN. 2327701800005 ANALYSIS Q-value -8.30 MeV, threshold energy 8.4 MeV are given 2327701800006 in Table 2. 2327701800007 ENDBIB 5 0 2327701800008 COMMON 1 3 2327701800009 EN-MEAN 2327701800010 MEV 2327701800011 11.5 2327701800012 ENDCOMMON 3 0 2327701800013 DATA 3 2 2327701800014 EN-MIN DATA DATA-ERR 2327701800015 MEV MB MB 2327701800016 2. 547. 85. 2327701800017 8.0 704. 85. 2327701800018 ENDDATA 4 0 2327701800019 ENDSUBENT 18 0 2327701899999 ENDENTRY 18 0 2327799999999