/*===================================================================*/ /* NRDF D1756 Data No.21 */ /*===================================================================*/ /* Bibliography */ /*===================================================================*/ \\BIB,21; D#=D1756; TITLE=/ Neutron yields from thick C, Al, Cu, and Pb targets bombarded by 400 MeV/nucleon Ar, Fe, Xe and 800 MeV/nucleon Si ions /; PURPOSE=/ To perform a systematic study to measure the double differential neutron yields from thick targets of C, Al, Cu, and Pb bombarded by various heavy ions having energies of 100 to 800 MeV/nucleon using HIMAC. /; ATH=(T.KUROSAWA'1', T.NAKAO'2', T.NAKAMURA'1', H.IWASE'1', H.SATO'1', Y.UWAMINO'3', A.FUKUMURA'4'); INST-ATH=(2JPNTOH'1', 2JPNKEK'2', 2JPNIPC'3', 2JPNIRS'4'); /* '1' Cyclotron and Radioisotope Center */ REF=PR/C; VLP=62(2000)044615; RCTS=(C(40AR,N)X, 27AL(40AR,N)X, CU(40AR,N)X, PB(40AR,N)X, C(56FE,N)X, 27AL(56FE,N)X, CU(56FE,N)X, PB(56FE,N)X, C(132XE,N)X, 27AL(132XE,N)X, CU(132XE,N)X, PB(132XE,N)X, C(28SI,N)X, CU(28SI,N)X); PHQS=(ENGY-SPEC'5', ANGL-DSTRN'6', N-MLT'7'); /* '5' Neutron energy spectrum */ /* '6' Neutron yield */ /* '7' Thick target differential multiplicity of neutron with respect to angle integrated over partial angular range */ /*===================================================================*/ /* Experimental Conditions */ /*===================================================================*/ \\EXP,21; /* 2002-02-28 : Compiled+Checked, R.Suzuki + sK */ /* 2004-04-23 : Altered, N.Otuka. MLT in SF6 replaced by PY */ /* 2008-01-30 : Altered, N.Otuka. EDE addded under METHOD */ RTY=HEAVY-ION-RCT; ENR=NAT'8'; /* '8' (The enrichments of targets are not given in the reference. But compiler asked T.Kurosawa.) */ CHM=ELM; PHYS-FORM=SLD; BAC=X; POL-TGT=0%; ALGN-TGT=0%; ACC=SYN'9'; /* '9' Heavy Ion Medical Accelerator in Chiba (HIMAC) */ INST-ACC=2JPNIRS'10'; /* '10' The mass numbers of projectile nuclei are not given in the reference. But compiler asked NIRS staff. */ BEAM-INTNSTY=XMA'11'; /* '11' The beam intensities were maintained at 100,000-1,000,000 particles per pulse. */ POL-PRJ=0%; DET-PARTCL=N; COINC=NO; ANT-COINC=NO; DET-SYS=(SCT'12',SCT'13',TOF'14',EDE'15'); /* '12' Plastic scintillator (NE102A) was used as the delta-E counter and the beam pick-up counter. */ /* '13' Liquid scintillator (NE213) was used as the E counter. */ /* '14' To measure the energy of neutron */ /* '15' To eliminate charged particles */ ERS-DET=XKEV'16'; /* '16' The energy resolutions of measured neutron spectra are at maximum about 20% for about 2000 MeV neutrons of highest energy at 0 degree and 7.5 degree, about 20% for about 1000 MeV neutrons of highest energy at 15 degree and 30 degree, and about 40% for about 600 MeV neutrons of highest energy at 60 degree and 90 degree, which were produced by 800 MeV/nucleon Si ions. */ CALB-DET=/ Each E counter was calibrated with a 60Co Gamma-ray source. EFCN-DET=/ The neutron detection efficiencies were calculated with the Monte Carlo code of Cecil et al. for all energy ranges. Reference is R. A. Cecil, B. D. Anderson, and R. Madey, Nucl. Instrum. Methods 161, 439 (1979). /; /* 2006-09-13 : Altered, Mh. Re-digitized */ RCT=CU(56FE,N)X; PHQ=ANGL-DSTRN'66'; /* '66' Neutron yield */ THK-TGT=13395MG/CM**2; INC-ENGY-LAB-RANGE=400MEV/A; /* Analysis: - Integration of energy distribution (Integrated over neutron energy above 5 MeV) /*===================================================================*/ /* Descriptive Parameters */ /*===================================================================*/ \\DATA,21; STATIST-ERR=X%'17'; /* '17' The statistical uncertainties vary in a range of 2 to 5 % for the low- to medium-energy (5-400 MeV) region of the spectra and increase to about 30% at the highest energies. */ NORM=/ The total normalization uncertainty is 15%. /; INC-ENGY-LAB=400MEV/A; /*===================================================================*/ /* Data Table */ /*===================================================================*/ \DATA; THTL YLD (DEG) (UNIT) 0 3.154E+01 7.5 1.089E+01 15 3.339E+00 30 1.359E+00 60 3.723E-01 90 1.419E-01 \END; /*===================================================================*/ |