ENTRY 22238 20171108 22672223800000001 SUBENT 22238001 20171108 22672223800100001 BIB 16 65 2223800100002 TITLE Average cross section measurement for several 2223800100003 dosimetry reactions in thick target Li(d,n) neutron 2223800100004 field 2223800100005 AUTHOR (J.R.Dumais,S.Tanaka,N.Odano,S.Iwasaki,K.Sugiyama) 2223800100006 REFERENCE ((S,JAERI-M-90-025,277,1990)= 2223800100007 (S,NEANDC(J)-149,277,1990)= 2223800100008 (S,INDC(JPN)-136,277,1990)) 2223800100009 (C,90STRASB,,421,1990) - uncertainty slightly different2223800100010 INSTITUTE (2JPNTOH) Tohoku University Sendai, Japan 2223800100011 FACILITY (DYNAM,2JPNTOH) The Tohuku University 4.5 MV dynamitron2223800100012 accelerator was used. 2223800100013 INC-SOURCE (D-LI) Intense neutron fields of energy from a few 2223800100014 hundred keV to 18 MeV were produced by bombarding a 2223800100015 1 mm thick Li target with a 10 micro-A deuteron beam. 2223800100016 The targets were made from Li metal melted and 2223800100017 flattened under vacuum on copper disks. 2223800100018 Five kinds of samples, AI, Ti, Fe, Ni and Co, were 2223800100019 placed at 50 mm from neutron source. Irradiation of two2223800100020 runs, 10 and 24 hours were performed according to the 2223800100021 half lives of residual nuclei of the reactions. 2223800100022 (D-T) For normalization of the Li+d neutron fluence, 2223800100023 and was done with the same experimental arrangement to 2223800100024 the above. The samples of Al, Zr and Nb were 2223800100025 irradiated for 15 hours. 2223800100026 INC-SPECT .The neutron spectrum was determined by TOF technique 2223800100027 METHOD (ACTIV) The neutron activation technique was used 2223800100028 to measure the cross-sections. 2223800100029 (TOF) The neutron spectra were measured by TOF. 2223800100030 The neutron flux was normalized at 14 MeV by 2223800100031 measurement of the standard Al-27(n,alpha)Na-24 2223800100032 reaction rate in the t-d neutron field under the same 2223800100033 experimental arrangement.The Monte Carlo code, O5S. 2223800100034 technique. 2223800100035 SAMPLE .Samples of Al,Ti,Fe,Ni and Co, 19 mm in diameter and 2223800100036 0.1 mm in thickness, were placed at 50 mm from the 2223800100037 Li+d neutron source. 2223800100038 DETECTOR (HPGE) The gamma activity of the irradiated samples 2223800100039 was measured using a 80 cc hyper-pure Ge detector. 2223800100040 (SCIN) A 2 x 2 inch NE213 liquid scintillation detector2223800100041 was used as a main counter in the TOF measurement of 2223800100042 the neutron spectra. A second NE213 detector, of size 2223800100043 1 x 1 inch, was used as a monitor. Their relative 2223800100044 neutron detection efficiencies were determined using 2223800100045 the spontaneous fission neutrons from a Cf-252 2223800100046 source and a Monte Carlo code. 2223800100047 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) - neutron flux norm. 2223800100048 MONIT-REF (,H.Vonach+,R,INDC-36,(A-22),1981) 2223800100049 PART-DET (DG) 2223800100050 (N) 2223800100051 ERR-ANALYS (DATA-ERR) Error on the experimental values was derived2223800100052 taking into account the error on the following: 2223800100053 * neutron fluence; 2223800100054 * statistical error; 2223800100055 * neutron energy of time TOF measurement; 2223800100056 * efficiency of neutron detector; 2223800100057 * error on normalizing by Al-27(n,alpha)Na-24; 2223800100058 * reaction rate. 2223800100059 STATUS (TABLE) .Data taken from JAERI-M-90-025,277 2223800100060 HISTORY (19930630C) N.O. 2223800100061 (20131207A) SD: Updated to new date formats,lower case.2223800100062 Corrections according last EXFOR rules and Dict. 2223800100063 SF8=SPA was added to REACTION code in Subents 3-7. 2223800100064 Minor corrections in all Subents. 2223800100065 (20171108A) SD: Ref. 90STRASB was added. Data errors 2223800100066 were corrected according this publication. 2223800100067 ENDBIB 65 0 2223800100068 COMMON 3 3 2223800100069 EN-MIN EN-MAX EN-NRM 2223800100070 KEV MEV MEV 2223800100071 100. 18. 14. 2223800100072 ENDCOMMON 3 0 2223800100073 ENDSUBENT 72 0 2223800199999 SUBENT 22238002 20131207 22382223800200001 BIB 2 2 2223800200002 REACTION (13-AL-27(N,A)11-NA-24,,SIG,,SPA) 2223800200003 DECAY-DATA (11-NA-24,15.02HR,DG,1368.,1.00) 2223800200004 ENDBIB 2 0 2223800200005 NOCOMMON 0 0 2223800200006 DATA 2 1 2223800200007 DATA DATA-ERR 2223800200008 B PER-CENT 2223800200009 2.11E-02 7.2 2223800200010 ENDDATA 3 0 2223800200011 ENDSUBENT 10 0 2223800299999 SUBENT 22238003 20171108 22672223800300001 BIB 3 5 2223800300002 REACTION (22-TI-48(N,P)21-SC-48,,SIG,,SPA) 2223800300003 DECAY-DATA (21-SC-48,43.7HR,DG,983.5,1.00) 2223800300004 HISTORY (20131207A) SD:SF8=SPA was added to REACTION code. 2223800300005 (20171108A) SD: DATA-ERR value was update according to 2223800300006 presentation in 90STRASB (6.5 -> 7.1). 2223800300007 ENDBIB 5 0 2223800300008 NOCOMMON 0 0 2223800300009 DATA 2 1 2223800300010 DATA DATA-ERR 2223800300011 B PER-CENT 2223800300012 1.04E-2 7.1 2223800300013 ENDDATA 3 0 2223800300014 ENDSUBENT 13 0 2223800399999 SUBENT 22238004 20171108 22672223800400001 BIB 2 4 2223800400002 REACTION (26-FE-56(N,P)25-MN-56,,SIG,,SPA) 2223800400003 HISTORY (20131207A) SD:SF8=SPA was added to REACTION code 2223800400004 (20171108A) SD: DATA-ERR value was update according to 2223800400005 presentation in 90STRASB (7.4 -> 7.3). 2223800400006 ENDBIB 4 0 2223800400007 NOCOMMON 0 0 2223800400008 DATA 2 1 2223800400009 DATA DATA-ERR 2223800400010 B PER-CENT 2223800400011 2.14E-02 7.3 2223800400012 ENDDATA 3 0 2223800400013 ENDSUBENT 12 0 2223800499999 SUBENT 22238005 20131207 22382223800500001 BIB 2 2 2223800500002 REACTION (28-NI-58(N,P)27-CO-58,,SIG,,SPA) 2223800500003 HISTORY (20131207A) SD:SF8=SPA was added to REACTION code 2223800500004 ENDBIB 2 0 2223800500005 NOCOMMON 0 0 2223800500006 DATA 2 1 2223800500007 DATA DATA-ERR 2223800500008 B PER-CENT 2223800500009 1.62E-01 7.1 2223800500010 ENDDATA 3 0 2223800500011 ENDSUBENT 10 0 2223800599999 SUBENT 22238006 20131207 22382223800600001 BIB 2 2 2223800600002 REACTION (28-NI-58(N,2N)28-NI-57,,SIG,,SPA) 2223800600003 HISTORY (20131207A) SD:SF8=SPA was added to REACTION code 2223800600004 ENDBIB 2 0 2223800600005 NOCOMMON 0 0 2223800600006 DATA 2 1 2223800600007 DATA DATA-ERR 2223800600008 B PER-CENT 2223800600009 3.37E-03 7.9 2223800600010 ENDDATA 3 0 2223800600011 ENDSUBENT 10 0 2223800699999 SUBENT 22238007 20131207 22382223800700001 BIB 2 2 2223800700002 REACTION (27-CO-59(N,2N)27-CO-58,,SIG,,SPA) 2223800700003 HISTORY (20131207A) SD:SF8=SPA was added to REACTION code 2223800700004 ENDBIB 2 0 2223800700005 NOCOMMON 0 0 2223800700006 DATA 2 1 2223800700007 DATA DATA-ERR 2223800700008 B PER-CENT 2223800700009 9.30E-02 7.8 2223800700010 ENDDATA 3 0 2223800700011 ENDSUBENT 10 0 2223800799999 ENDENTRY 7 0 2223899999999