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/* NRDF D1788 Data No.4 */
/*===================================================================*/
/* Bibliography */
/*===================================================================*/
\\BIB,4;
D#=D1788;
TITLE=/ Measurements of neutron spectra produced from a thick lead
target bombarded with 0.5- and 1.5-GeV protons /;
PURPOSE=/ To provide experimental data for benchmarking the
medium-energy particle transport calculations /;
ATH=(S.MEIGO'1', H.TAKADA'1', S.CHIBA'1', T.NAKAMOTO'2',
K.ISHIBASHI'2', N.MATSUFUJI'2', K.MAEHATA'2', N.SHIGYO'2',
Y.WATANABE'3', M.NUMAJIRI'4');
INST-ATH=(2JPNJAE'1', 2JPNKYU'2', 2JPNKYU'3', 2JPNKEK'4');
/* '2' Department of Nuclear Engineering */
/* '3' Energy Conversion Engineering */
REF=NIM/A;
VLP=431(1999)521;
/* Secondary reference
- JAERI-C, 97-004(1997)247 (Preliminary report)
RCTS=PB(P,N)X;
PHQS=ENGY-SPEC'5';
/* '5' Neutron spectra produced from a thick target */
/*===================================================================*/
/* Experimental Conditions */
/*===================================================================*/
\\EXP,4;
/* 2003-05-01 : Compiled */
PHQ=ENGY-SPEC'6';
/* '6' Neutron spectra produced from a thick target */
ENR=NAT;
CHM=ELM'7';
/* '7' Chemical purity is 99.95% */
PHYS-FORM=SLD;
THK-TGT=XMG/CM**2'8';
/* '8' Target was a rectangular parallelepiped 15x15x20cm**3 */
POL-TGT=0%;
ALGN-TGT=0%;
ACC=SYN'9';
/* '9' pi2 beam line of the 12 GeV Proton Synchrotron */
INST-ACC=2JPNKEK;
POL-PRJ=0%;
ION-SOURCE=/ Incident protons were generated as secondary beam. TOF
method with a pair of Pilot U scintillators was adopted
for the separation of the protons from the pions. /;
DET-PARTCL=N;
COINC=NO;
ANT-COINC=NO;
DET-SYS=(SCT'10',SCT'11',TOF'12');
/* '10' NE213, used as neutron detectors. These were of
cylindrical shapes of 12.7 cm in diameter and 12.7 cm in
thicknes. The pulse height of the neutron detectors was
calibrated using gamma-rays from 137Cs, 60Co and 241Am-Be. The
neutron detection efficiency was obtained from calculation
results of SCINFUL-R [S. Meigo, Nucl. Instr. Meth.
A401(1997)365] and CECIL [R.A. Cecil et al., Nucl. Instr.
Meth. 161(1979)439] codes. */
/* '11' NE102A, used as veto counters to reject the detection of
the charged particles, placed at a distance of 2 cm from the
surface of the NE213 */
/* '12' Time difference between prompt gamma emission (assumed to
be emitted when neutron were scattered by target) and neutron
detection are used to deduce outgoing neutron above 2.5 MeV
Below 2.5 MeV unfolding analysis was used because scattered
neutron has some delay in the flight time due to multiple
scattering in thic target). */
ERS-DET=X%'13';
/* '13' Outgoing neutron energy dependence of neutron detection
efficiency is shown in Table 2. */
EFCN-DET=/ Outgoing neutron energy dependence of neutron detection
efficiency is shown in Fig.5. /;
ANL=MONTE-MTHD'14';
/* '14' NMTC/JAERI [Y. Nakahara et al., A Code System for High
Energy Nuclear Reactions and Nucleon-Meson Transport Code,
JAERI-M 82-198, 1982 (in Japanese)] and MCNP-4A [J.F.
Briesmeister (Ed.), MCNP A General Monte Carlo N-Particle
Transport Code Version 4A, LA-12625, 1993] */
/* Experimental Method:
- Time-of-flight (Time difference between prompt gamma emission
(assumed to be emitted when neutron were scattered by target) and
neutron detection are used to deduce outgoing neutron above 2.5
MeV Below 2.5 MeV unfolding analysis was used because scattered
neutron has some delay in the flight time due to multiple
scattering in thic target).)
/* Analysis:
- Calculated from thick target using unfolding proced. (Neutron
spectra by the unfolding analysis are adopted for the neutron
below 2.5 MeV.)
RCT=PB(P,N)X;
INC-ENGY-LAB=0.5GEV;
/*===================================================================*/
/* Descriptive Parameters */
/*===================================================================*/
\\DATA,4;
SYS-ERR=X%'15';
/* '15' Outgoing neutron energy dependences of uncertainties due
to detection efficiency, number of projectile, and neutron
flux are shown in Table 2. */
STATIST-ERR=X%'16';
/* '16' Outgoing neutron energy dependences of statistical
uncertainty is given in Table 2. */
INC-ENGY-LAB=0.5GEV;
EMT=N;
THTL=90DEG;
/*===================================================================*/
/* Data Table */
/*===================================================================*/
\DATA;
ENGY-EMT-LAB DELTA-ENGY-EMT-LAB DATA1 DELTA-DATA1
(MEV) (MEV) (1/SR/MEV/PARTCL) (1/SR/MEV/PARTCL)
1.400E+00 +-1.400E-01 1.472E-01 +-8.162E-03
1.600E+00 +-1.600E-01 1.473E-01 +-7.471E-03
1.800E+00 +-1.800E-01 1.308E-01 +-7.478E-03
2.000E+00 +-2.000E-01 1.103E-01 +-7.073E-03
2.200E+00 +-2.200E-01 9.329E-02 +-6.690E-03
2.400E+00 +-2.400E-01 7.976E-02 +-7.178E-03
2.600E+00 +-2.600E-01 6.730E-02 +-7.942E-03
2.800E+00 +-2.800E-01 5.533E-02 +-8.347E-03
3.000E+00 +-3.308E-01 4.808417E-02 +-1.356673E-03
3.500E+00 +-3.877E-01 4.285266E-02 +-1.273299E-03
4.000E+00 +-4.451E-01 3.266216E-02 +-1.068205E-03
4.500E+00 +-5.030E-01 2.603649E-02 +-9.341685E-04
5.000E+00 +-5.615E-01 1.908349E-02 +-6.567305E-04
6.000E+00 +-6.798E-01 1.401235E-02 +-5.022462E-04
7.000E+00 +-8.002E-01 1.002175E-02 +-4.115217E-04
8.200E+00 +-9.472E-01 6.757993E-03 +-3.685658E-04
9.000E+00 +-1.047E+00 5.465545E-03 +-3.557180E-04
1.000E+01 +-1.173E+00 4.299345E-03 +-2.335687E-04
1.250E+01 +-1.497E+00 2.951018E-03 +-1.908511E-04
1.400E+01 +-1.697E+00 2.622316E-03 +-2.243863E-04
1.500E+01 +-1.832E+00 1.772903E-03 +-1.212920E-04
2.000E+01 +-2.538E+00 1.310805E-03 +-7.682996E-05
2.600E+01 +-3.444E+00 1.113235E-03 +-8.019991E-05
3.000E+01 +-4.083E+00 9.967138E-04 +-8.132856E-05
3.600E+01 +-5.093E+00 7.897535E-04 +-7.576980E-05
4.000E+01 +-5.799E+00 6.871941E-04 +-7.644835E-05
4.500E+01 +-6.719E+00 6.365210E-04 +-7.256518E-05
5.000E+01 +-7.679E+00 5.210802E-04 +-6.751611E-05
5.500E+01 +-8.678E+00 4.364969E-04 +-5.349138E-05
6.500E+01 +-1.079E+01 3.645531E-04 +-5.151690E-05
7.000E+01 +-1.191E+01 3.263907E-04 +-5.027476E-05
8.000E+01 +-1.425E+01 2.275610E-04 +-3.806265E-05
9.000E+01 +-1.674E+01 1.273244E-04 +-2.952539E-05
1.000E+02 +-1.938E+01 9.146221E-05 +-1.617169E-05
1.500E+02 +-3.471E+01 5.493987E-05 +-1.000367E-05
2.000E+02 +-5.354E+01 7.080705E-06 +-6.939004E-06
\END;
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