ENTRY 22312 20151215 22462231200000001 SUBENT 22312001 20151215 22462231200100001 BIB 14 45 2231200100002 TITLE Absolute measurements of activation cross sections of 2231200100003 27-Al(n,p)27-Mg, 27-Al(n,alpha)24-Na, 56-Fe(n,p)56-Mn,2231200100004 90-Zr(n,2n)89-Zr-m+g and 93-Nb(n,2n)92-Nb-m at 2231200100005 energy range of 13.3 - 14.9 MeV 2231200100006 AUTHOR (Y.Ikeda,C.Konno,Y.Oyama,K.Kosako,K.Oishi,H.Maekawa) 2231200100007 INSTITUTE (2JPNJAE) Ikeda, Konno, Oyama, Kosako, Maekawa 2231200100008 (2JPNJPN) Oishi, Inst.of Technol., Shimizu Corporation,2231200100009 Tokyo 2231200100010 REFERENCE (J,NST,30,870,199309) Main reference. Data are given 2231200100011 REL-REF (M,,Y.Oyama+,R,JAERI-M-83-195,1983) Experim. details 2231200100012 MONITOR Absolute measurements 2231200100013 METHOD (ACTIV) Activation method for cross sect.measurements 2231200100014 (ASSOP) Associated particle method for neutron 2231200100015 flux monitoring 2231200100016 FACILITY (CCW,2JPNJAE) Fusion Neutron Source Facility - FNS. 2231200100017 INC-SOURCE (D-T) Tritiated titanium target irradiated by 2231200100018 deuteron beam 2 milliamperes, 350 keV 2231200100019 DETECTOR (HPGE) 2231200100020 (SCIN) NE213 scintillation detector for neutron 2231200100021 flux determination 2231200100022 CORRECTION Corrections were made of the sum peak for cascade 2231200100023 gamma-rays, the severest was for 24Na and equal 5% 2231200100024 STATUS (TABLE) Tbl. 3 from NST,30,870,1993 2231200100025 ERR-ANALYS (ERR-T) Total error equal to sum of all errors given 2231200100026 below 2231200100027 (a) Uncertainty in neutron flux determination: 2231200100028 (ERR-1) Error of neutron yield 2231200100029 (ERR-2,2.,4.) Error of anisotropy 2231200100030 (ERR-3) Error of foil distance from target 2231200100031 (b) Uncertainty in activation reaction rate 2231200100032 determination: 2231200100033 (ERR-S,0.1,1.0) Gamma-ray counting statistics error 2231200100034 (ERR-4) Gamma-ray detector efficiency error 2231200100035 (ERR-5,,0.2) Error of correction or saturation factor 2231200100036 (ERR-6,,0.1) Error of gamma-ray self-absorption 2231200100037 (ERR-7,0.2,1.2) Error due to half-life 2231200100038 (ERR-8,,0.1) Error due to foils weight 2231200100039 (ERR-9,,0.1) Error due to natural isotope abundance 2231200100040 (ERR-10,,0.01) Error due to foils impurity 2231200100041 HISTORY (19970124C) + + Compiled by S.M. + + 2231200100042 (20010330A) NDS Correction - eV changed to MeV 2231200100043 (20020519U) . . Corrected, J.O.S. 2231200100044 (20070725U) M.M. Misprint in TITLE was corrected. 2231200100045 (20151215A) SD: DECAY-DATA corrected in Subent 005. 2231200100046 ERR-ANALYS update. Cosmetic corrections. 2231200100047 ENDBIB 45 0 2231200100048 COMMON 3 3 2231200100049 ERR-1 ERR-3 ERR-4 2231200100050 PER-CENT PER-CENT PER-CENT 2231200100051 1.5 0.7 2. 2231200100052 ENDCOMMON 3 0 2231200100053 ENDSUBENT 52 0 2231200199999 SUBENT 22312002 20020519 00002231200200001 BIB 4 7 2231200200002 REACTION (13-AL-27(N,A)11-NA-24,,SIG) 2231200200003 SAMPLE Metallic foil 10 mm diameter, 0.1 mm thickness, 99.99%2231200200004 chemical purity, placed in a holder of acrylic resin 2231200200005 put on a thin copper ring. Normal distance of sample 2231200200006 from the centre of neutron source is 124 mm. 2231200200007 DECAY-DATA (11-NA-24,15.02HR,DG,1368.60,1.0) 2231200200008 ERR-ANALYS (ERR-14) Systematic error due to sum peak correction 2231200200009 ENDBIB 7 0 2231200200010 COMMON 1 3 2231200200011 ERR-14 2231200200012 PER-CENT 2231200200013 0.3 2231200200014 ENDCOMMON 3 0 2231200200015 DATA 3 8 2231200200016 EN DATA ERR-T 2231200200017 MEV MB MB 2231200200018 14.91 112. 3.9 2231200200019 14.65 112.5 4. 2231200200020 14.42 114.5 4. 2231200200021 14.22 119. 5.7 2231200200022 13.98 122.7 4.4 2231200200023 13.75 122. 4.5 2231200200024 13.57 128. 4.7 2231200200025 13.33 126.2 4.4 2231200200026 ENDDATA 10 0 2231200200027 ENDSUBENT 26 0 2231200299999 SUBENT 22312003 20020519 00002231200300001 BIB 3 6 2231200300002 REACTION (13-AL-27(N,P)12-MG-27,,SIG) 2231200300003 SAMPLE Metallic foil 10 mm diameter, 0.1 mm thickness, 99.99%2231200300004 chemical purity, placed in a holder of acrylic resin 2231200300005 put on a thin copper ring. Normal distance of sample 2231200300006 from the centre of neutron source is 124 mm. 2231200300007 DECAY-DATA (12-MG-27,9.462MIN,DG,843.76,0.730) 2231200300008 ENDBIB 6 0 2231200300009 NOCOMMON 0 0 2231200300010 DATA 3 8 2231200300011 EN DATA ERR-T 2231200300012 MEV MB MB 2231200300013 14.91 64.1 2.2 2231200300014 14.65 68.8 3.1 2231200300015 14.42 67.5 6.3 2231200300016 14.22 72.1 3.8 2231200300017 13.98 76. 3. 2231200300018 13.75 77.6 3. 2231200300019 13.57 80.9 3. 2231200300020 13.33 85.2 3.1 2231200300021 ENDDATA 10 0 2231200300022 ENDSUBENT 21 0 2231200399999 SUBENT 22312004 20020519 00002231200400001 BIB 4 8 2231200400002 REACTION (26-FE-56(N,P)25-MN-56,,SIG) 2231200400003 SAMPLE Metallic foil 10 mm diameter, 0.1 mm thickness, 99.99%2231200400004 chemical purity, placed in a holder of acrylic resin 2231200400005 put on a thin copper ring. Normal distance of sample 2231200400006 from the centre of neutron source is 124 mm. 2231200400007 56Fe abundance is 91.72+-0.30%. 2231200400008 DECAY-DATA (25-MN-56,2.5785HR,DG,846.812,0.989) 2231200400009 ERR-ANALYS (ERR-14) Systematic Error Due to Sum Peak Correction 2231200400010 ENDBIB 8 0 2231200400011 COMMON 1 3 2231200400012 ERR-14 2231200400013 PER-CENT 2231200400014 0.1 2231200400015 ENDCOMMON 3 0 2231200400016 DATA 3 7 2231200400017 EN DATA ERR-T 2231200400018 MEV MB MB 2231200400019 14.91 106.1 3.7 2231200400020 14.65 109.8 3.8 2231200400021 14.42 111.1 3.8 2231200400022 14.22 112.2 5. 2231200400023 13.98 115.2 4. 2231200400024 13.75 115.6 4. 2231200400025 13.57 118.2 4. 2231200400026 ENDDATA 9 0 2231200400027 ENDSUBENT 26 0 2231200499999 SUBENT 22312005 20151215 22462231200500001 BIB 4 9 2231200500002 REACTION (40-ZR-90(N,2N)40-ZR-89,,SIG) 2231200500003 SAMPLE Metallic foil 10 mm diameter, 0.1 mm thickness, 99.99%2231200500004 chemical purity, placed in a holder of acrylic resin 2231200500005 put on a thin copper ring. Normal distance of sample 2231200500006 from the centre of neutron source is 124 mm. 2231200500007 90Zr abundance is 51.45+-0.02% 2231200500008 DECAY-DATA (40-ZR-89-G,3.268D,DG,909.15,0.9901) 2231200500009 HISTORY (20020519U) 'M+G'in SF4 deleted 2231200500010 (20151215A) SD: Zr-89m -> Zr-89g in DECAY-DATA. 2231200500011 ENDBIB 9 0 2231200500012 NOCOMMON 0 0 2231200500013 DATA 3 3 2231200500014 EN DATA ERR-T 2231200500015 MEV MB MB 2231200500016 14.95 834. 33. 2231200500017 14.65 693. 39. 2231200500018 14.37 382. 16. 2231200500019 ENDDATA 5 0 2231200500020 ENDSUBENT 19 0 2231200599999 SUBENT 22312006 20000519 00002231200600001 BIB 3 6 2231200600002 REACTION (41-NB-93(N,2N)41-NB-92-M,,SIG) 2231200600003 SAMPLE Metallic foil 10 mm diameter, 0.1 mm thickness, 99.99%2231200600004 chemical purity, placed in a holder of acrylic resin 2231200600005 put on a thin copper ring. Normal distance of sample 2231200600006 from the centre of neutron source is 124 mm. 2231200600007 DECAY-DATA (41-NB-92-M,10.15D,DG,934.53,0.990) 2231200600008 ENDBIB 6 0 2231200600009 NOCOMMON 0 0 2231200600010 DATA 3 8 2231200600011 EN DATA ERR-T 2231200600012 MEV MB MB 2231200600013 14.95 469. 15. 2231200600014 14.65 456. 15. 2231200600015 14.37 457. 15. 2231200600016 14.22 457. 22. 2231200600017 13.98 460. 16. 2231200600018 13.75 451. 15. 2231200600019 13.57 455. 15. 2231200600020 13.33 456. 15. 2231200600021 ENDDATA 10 0 2231200600022 ENDSUBENT 21 0 2231200699999 ENDENTRY 6 0 2231299999999