ENTRY 41510 20200720 41884151000000001
SUBENT 41510001 20200720 41884151000100001
BIB 16 63 4151000100002
TITLE REPS facility for investigation of structure of 4151000100003
neutron cross-sections and neutron fundamental 4151000100004
characteristics. 4151000100005
AUTHOR (A.I.Berlev, Yu.V.Grigor'ev) 4151000100006
INSTITUTE (4RUSFEI) Yu.V.Grigor'ev( = Yu.V.Grigoriev) 4151000100007
(4RUSJIA) A.I.Berlev 4151000100008
REFERENCE (R,JIA-1183,200707) Main reference. 4151000100009
FACILITY (LINAC,4RUSJIA) REPS (Resonance Experimental 4151000100010
Transmissions and Cross-sections) exp.setup of Meson 4151000100011
Facility at Institute for Nuclear Research of Russian 4151000100012
Academy of Science. 4151000100013
INC-SOURCE Pulse neutron source RADEX (Radiational experiments).4151000100014
System of collimators as carbon and lead disks. 4151000100015
DETECTOR (SCIN) Eight-sections liquid scintillator as aluminum 4151000100016
tank of 40 l volume, 40 cm length, 40 cm diameter, 4151000100017
with hole of 110 mm diameter; solution 4151000100018
of scintillation admixtures and 5.5 liter of trimethyl4151000100019
borate B(OCH3)3 and 34.5 l of toluene C6H5CH3 4151000100020
as scintillation liquid. For TOF spectra measurement 4151000100021
as (n,gamma)-detector. Registration efficiency 30%, 4151000100022
geometrical efficiency 96%, energy resolution about 4151000100023
30% for gamma-lines 662 keV of cesium source at 4151000100024
voltage of +1500 V. 4151000100025
(PROPC) He-3 cylindrical counter of high efficiency as4151000100026
neutron detector in form of cylinder of 12 cm 4151000100027
diameter and 3.5 cm thickness , made from stainless 4151000100028
steel of 1 mm thickness. Filled by gas mixture of 4151000100029
He-3 at 7 Athm. and Ar at 3 Athm. Thermal neutron 4151000100030
efficiency registration about 100%. Anode voltage 4151000100031
+2500 V. 4151000100032
Other He-3 proportional counter SNM-18 for neutron 4151000100033
source intensity monitoring. 4151000100034
Lead and boron carbid protection around 4151000100035
(n,gamma)- and neutron detectors. 4151000100036
METHOD (COINC) Coincidence multiplicities from pulses of eight4151000100037
spectrometric channels. 4151000100038
(TOF) Flight path 50 m. 4151000100039
(TRN) Transmission measurement for total cross-sections4151000100040
determination. 4151000100041
Resonance filters from manganese and cadmium for 4151000100042
background determination. 4151000100043
SAMPLE Thin metallic disks of 80 mm diameter. 4151000100044
ANALYSIS Radiative capture reaction group cross-sections were 4151000100045
defined from TOF spectra using normalization on 4151000100046
U-238 standard cross-sections. 4151000100047
Program GRUCON was used for group cross-section 4151000100048
calculations. 4151000100049
REL-REF (N,,V.V.Sinitsa,J,YK,5,(59),34,1984) Program GRUCON. 4151000100050
CORRECTION For background. 4151000100051
For resonance self-shielding. 4151000100052
For zero thickness of sample 4151000100053
STATUS (TABLE) Table 1 of rep. JIA-1183,2007 4151000100054
ERR-ANALYS (DATA-ERR) Errors are not specified. 4151000100055
COMMENT Of author and compiler . There is a misprint in data 4151000100056
Table 1 of reference : U-235 capture c-s was used as 4151000100057
monitor and given in Table, not total. 4151000100058
Of author. Measurement of this work (MESON,4RUSJIA) 4151000100059
repeats the measurement at (REAC,4ZZZDUB) IBR-30 4151000100060
as a confirmation test. 4151000100061
HISTORY (20080215C) Compiled at CJD. M.M. 4151000100062
(20081202U) One STATUS line was added. 4151000100063
(20200720U) MESON -> LINAC, 4151000100064
STATUS information was updated. 4151000100065
ENDBIB 63 0 4151000100066
NOCOMMON 0 0 4151000100067
ENDSUBENT 66 0 4151000199999
SUBENT 41510002 20200720 41884151000200001
BIB 3 4 4151000200002
REACTION (41-NB-93(N,TOT),,SIG,,AV) 4151000200003
MONITOR Absolute measurements. 4151000200004
STATUS (COREL,41505002) Measurement at IBR-30 reactor at Dubna4151000200005
, see COMMENT of author in 41505.001 4151000200006
ENDBIB 4 0 4151000200007
NOCOMMON 0 0 4151000200008
DATA 4 6 4151000200009
EN-MIN EN-MAX DATA DATA-ERR 4151000200010
KEV KEV B B 4151000200011
0.100 0.215 9.2 0.3 4151000200012
0.215 0.465 8.6 0.3 4151000200013
0.465 1.0 8.9 0.5 4151000200014
1.0 2.15 12. 0.3 4151000200015
2.15 4.65 11. 0.3 4151000200016
4.65 10.0 9.6 0.3 4151000200017
ENDDATA 8 0 4151000200018
ENDSUBENT 17 0 4151000299999
SUBENT 41510003 20200720 41884151000300001
BIB 3 6 4151000300002
REACTION (41-NB-93(N,G)41-NB-94,,SIG,,AV) 4151000300003
MONITOR ((MONIT)92-U-238(N,G)92-U-239,,SIG,,AV) Averaged over 4151000300004
energy group ENDF/B-6 cross-section used for 4151000300005
normalization. 4151000300006
STATUS (COREL,41505003) Measurement at IBR-30 reactor at Dubna4151000300007
, see COMMENT of author in 41505.001 4151000300008
ENDBIB 6 0 4151000300009
NOCOMMON 0 0 4151000300010
DATA 5 5 4151000300011
EN-MIN EN-MAX DATA DATA-ERR MONIT 4151000300012
KEV KEV B B B 4151000300013
0.100 0.215 3.0 0.1 20.3 4151000300014
0.215 0.465 1.7 0.1 4.55 4151000300015
0.465 1.0 1.2 0.1 3.32 4151000300016
1.0 2.15 2.0 0.3 1.70 4151000300017
2.15 4.65 0.8 0.1 1.24 4151000300018
ENDDATA 7 0 4151000300019
ENDSUBENT 18 0 4151000399999
SUBENT 41510004 20200720 41884151000400001
BIB 4 6 4151000400002
REACTION (42-MO-0(N,TOT),,SIG,,AV) 4151000400003
MONITOR Absolute measurement 4151000400004
STATUS (COREL,41505004) Measurement at IBR-30 reactor at Dubna4151000400005
, see COMMENT of author in 41505.001 4151000400006
HISTORY (20200720A) DATA-ERR at 2.15-4.65 group was corrected 4151000400007
0.4 -> 0.7 b. 4151000400008
ENDBIB 6 0 4151000400009
NOCOMMON 0 0 4151000400010
DATA 4 6 4151000400011
EN-MIN EN-MAX DATA DATA-ERR 4151000400012
KEV KEV B B 4151000400013
0.100 0.215 16.2 1.2 4151000400014
0.215 0.465 10.9 1.3 4151000400015
0.465 1.0 11.2 0.5 4151000400016
1.0 2.15 10.3 0.4 4151000400017
2.15 4.65 10.5 0.7 4151000400018
4.65 10.0 9.3 0.2 4151000400019
ENDDATA 8 0 4151000400020
ENDSUBENT 19 0 4151000499999
SUBENT 41510005 20200720 41884151000500001
BIB 3 6 4151000500002
REACTION (42-MO-0(N,G),,SIG,,AV) 4151000500003
MONITOR ((MONIT)92-U-238(N,G)92-U-239,,SIG,,AV) Averaged over 4151000500004
energy group ENDF/B-6 cross-section used for 4151000500005
normalization. 4151000500006
STATUS (COREL,41505005) Measurement at IBR-30 reactor at Dubna4151000500007
, see COMMENT of author in 41505.001 4151000500008
ENDBIB 6 0 4151000500009
NOCOMMON 0 0 4151000500010
DATA 5 5 4151000500011
EN-MIN EN-MAX DATA DATA-ERR MONIT 4151000500012
KEV KEV B B B 4151000500013
0.100 0.215 4.2 0.40 20.3 4151000500014
0.215 0.465 1.4 0.20 4.55 4151000500015
0.465 1.0 1.2 0.20 3.32 4151000500016
1.0 2.15 0.9 0.10 1.70 4151000500017
2.15 4.65 0.6 0.05 1.24 4151000500018
ENDDATA 7 0 4151000500019
ENDSUBENT 18 0 4151000599999
SUBENT 41510006 20200720 41884151000600001
BIB 3 4 4151000600002
REACTION (73-TA-0(N,TOT),,SIG,,AV) 4151000600003
MONITOR Absolute measurement 4151000600004
STATUS (COREL,41505006) Measurement at IBR-30 reactor at Dubna4151000600005
, see COMMENT of author in 41505.001 4151000600006
ENDBIB 4 0 4151000600007
NOCOMMON 0 0 4151000600008
DATA 4 6 4151000600009
EN-MIN EN-MAX DATA DATA-ERR 4151000600010
KEV KEV B B 4151000600011
0.100 0.215 69.5 5.0 4151000600012
0.215 0.465 48.4 4.0 4151000600013
0.465 1.0 40.2 4.0 4151000600014
1.0 2.15 34.4 3.0 4151000600015
2.15 4.65 26.8 1.0 4151000600016
4.65 10.0 17.4 1.5 4151000600017
ENDDATA 8 0 4151000600018
ENDSUBENT 17 0 4151000699999
SUBENT 41510007 20080215 41434151000700001
BIB 2 3 4151000700002
REACTION (74-W-0(N,TOT),,SIG,,AV) Average over energy group, 4151000700003
boundaries are given in data table. 4151000700004
MONITOR Absolute measurement 4151000700005
ENDBIB 3 0 4151000700006
NOCOMMON 0 0 4151000700007
DATA 4 4 4151000700008
EN-MIN EN-MAX DATA DATA-ERR 4151000700009
KEV KEV B B 4151000700010
0.465 1.0 40.6 1.5 4151000700011
1.0 2.15 33.5 1.4 4151000700012
2.15 4.65 24.1 1.0 4151000700013
4.65 10.0 19.3 0.8 4151000700014
ENDDATA 6 0 4151000700015
ENDSUBENT 14 0 4151000799999
ENDENTRY 7 0 4151099999999