ENTRY 21742 20090315 22082174200000001 SUBENT 21742001 20090315 22082174200100001 BIB 10 34 2174200100002 INSTITUTE (2UK HAR) 2174200100003 REFERENCE (R,AERE-R-9929,198009) 2174200100004 (W,SWINHOE,19810326) Letter with detailed error 2174200100005 analysis. 2174200100006 (R,AERE-PR/NP-27,40,198004) 2174200100007 (P,AERE-PR/NP-26,39,197903) 2174200100008 (P,AERE-PR/NP-25,44,197806) 2174200100009 AUTHOR (M.T.Swinhoe,C.A.Uttley) 2174200100010 TITLE -An absolute measurement of the Li-7(N,N'at) 2174200100011 reaction cross section between 5 and 14 MeV 2174200100012 by tritium assaying.- 2174200100013 SAMPLE .Lithium samples 99.8 percent Li-7, in a lithium 2174200100014 hydroxide compressed pellet, enclosed in a 1 mm thick 2174200100015 cadmium case. 2174200100016 METHOD (ACTIV) Activation. 2174200100017 COMMENT .The tritium produced is counted using a liquid 2174200100018 scintillation technique. The counting efficiency 2174200100019 of each vial was determined using the external 2174200100020 standards channels ratio technique, with a quench 2174200100021 curve obtained by using standard tritiated water 2174200100022 added to solutions made with unirradiated pellets. 2174200100023 The background was also found using unirradiated 2174200100024 pellets. 2174200100025 STATUS .Data taken from main reference and private 2174200100026 communication. 2174200100027 HISTORY (19810605C) G.C., Formerly present in EXFOR20986. 2174200100028 (19810722E) 2174200100029 subents 003 and 004. 2174200100030 Err-analysis corrected: err-t, err-S, 2174200100031 err-1 adn err-4 moved to subents 2174200100032 (20090315U) Last checking has been done. 2174200100033 ERR-ANALYS (ERR-2) Labile fraction. 2174200100034 (ERR-3) Number of lithium atoms. 2174200100035 .Other errors. (See subworks). 2174200100036 ENDBIB 34 0 2174200100037 COMMON 2 3 2174200100038 ERR-2 ERR-3 2174200100039 PER-CENT PER-CENT 2174200100040 1.E-01 5.4E-01 2174200100041 ENDCOMMON 3 0 2174200100042 ENDSUBENT 41 0 2174200199999 SUBENT 21742002 19811030 00002174200200001 BIB 8 19 2174200200002 REACTION (3-LI-7(N,N+T)2-HE-4,,SIG) 2174200200003 FACILITY (VDGT ) TANDEM VAN DE GRAAF ACCELERATOR AT HARWELL. 2174200200004 INC-SOURCE (D-D ) D(D,N)HE-3 REACTION, USING A 10 CM LONG GAS 2174200200005 CELL FILLED TO 2 ATM. 2174200200006 DETECTOR (SCIN ) NE 213 LIQUID SCINTILLATOR, ABSOLUTE EFFICIENCY2174200200007 CALIBRATED, WAS USED AS NEUTRON MONITOR. 2174200200008 (SCIN ) LIQUID SCINTILLATOR AS BETA COUNTER. 2174200200009 DECAY-DATA (1-H-3,,B) NO INFORMATION GIVEN. 2174200200010 STATUS .DATA TAKEN FROM AERE-R-9929 2174200200011 HISTORY (810605C) FORMERLY PRESENT IN EXFOR20986.002 2174200200012 (810722E) 2174200200013 ERR-ANALYS (EN-RSL) TOTAL ENERGY SPREAD OF THE INCOMING NEUTRONS. 2174200200014 THE CONTRIBUTIONS OF THIS TOTAL SPREAD FROM THE 2174200200015 GEOMETRY OF THE EXPERIMENT AND FROM THE ENERGY LOSS 2174200200016 OF THE DEUTERONS IN THE DEUTERIUM TARGET ARE LISTED 2174200200017 IN TABLE 1 OF AERE-R-9929. 2174200200018 .THE FOLLOWING SYSTEMATIC ERROR CONTRIBUTES TO THE 2174200200019 TOTAL ERROR 2174200200020 (ERR-5) NEUTRON DETECTOR EFFIECIENCY. 2174200200021 ENDBIB 19 0 2174200200022 NOCOMMON 0 0 2174200200023 DATA 8 5 2174200200024 EN EN-RSL DATA ERR-T ERR-S ERR-1 2174200200025 ERR-4 ERR-5 2174200200026 MEV MEV MB MB PER-CENT PER-CENT 2174200200027 PER-CENT PER-CENT 2174200200028 5.4700E+00 7.2000E-01 2.8200E+02 2.7000E+01 3.1000E+00 4.1000E-012174200200029 9.0000E+00 2.9000E+00 2174200200030 7.3500E+00 4.1000E-01 3.2200E+02 2.6000E+01 2.4000E+00 6.7000E-012174200200031 7.5400E+00 2.5000E+00 2174200200032 9.7200E+00 3.9000E-01 3.1000E+02 2.1000E+01 2.2000E+00 7.4000E-012174200200033 5.4100E+00 2.5000E+00 2174200200034 9.7700E+00 2.6000E-01 3.1400E+02 1.9000E+01 4.5000E+00 7.4000E-012174200200035 2.6500E+00 2.5000E+00 2174200200036 1.1760E+01 2.2000E-01 2.8900E+02 1.5000E+01 2.4000E+00 8.1000E-012174200200037 3.8600E+00 2.5000E+00 2174200200038 ENDDATA 14 0 2174200200039 ENDSUBENT 38 0 2174200299999 SUBENT 21742003 20090315 22082174200300001 BIB 11 33 2174200300002 REACTION (3-LI-7(N,N+T)2-HE-4,,SIG) 2174200300003 FACILITY (CCW ) Cockroft-Walton accelerator at Harwell. 2174200300004 INC-SOURCE (D-T ) The T(d,n)He-4 reaction using a titanium 2174200300005 tritide target. 2174200300006 METHOD (ASSOP) Associated alpha particles from d-t reaction 2174200300007 are measured to monitor the neutron flux. 2174200300008 DETECTOR (SOLST) Silicon surface barrier detector for the 2174200300009 detection of the associated alphas. (Neutron flux). 2174200300010 (SCIN ) Liquid scintillator as beta counter. 2174200300011 (GELI ) For the measurement of the activation of the 2174200300012 monitor foils. 2174200300013 DECAY-DATA (1-H-3,,B) No information given. 2174200300014 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 2174200300015 DECAY-MON (11-NA-24,,DG,1369.) No further information given. 2174200300016 STATUS .Data taken from table 5, aere-r-9929. 2174200300017 HISTORY (19810605C) G.C., Formerly present in EXFOR20986.002 2174200300018 (19810722E) 2174200300019 and err-analys corrected 2174200300020 (20090315U) Last checking has been done. 2174200300021 ERR-ANALYS (MONIT-ERR) Error of the monitor reaction. 2174200300022 (ERR-T) Total error given. It includes the following 2174200300023 contributions 2174200300024 (ERR-S) Non correlated error. It consists of 2174200300025 - deuteron break up correction. 2174200300026 - Sample geometry. 2174200300027 - Tritium counting statistics. 2174200300028 - Sodium counting statistics. 2174200300029 (ERR-1) Multiple scattering correction. 2174200300030 (ERR-4) Combined error from tritium efficiency 2174200300031 calibration, tritium halflife and tritium back- 2174200300032 ground. 2174200300033 (ERR-5) Na-24 detection efficiency, 2174200300034 and alpha particle flux monitor. 2174200300035 ENDBIB 33 0 2174200300036 COMMON 7 6 2174200300037 EN MONIT MONIT-ERR ERR-T ERR-S ERR-1 2174200300038 ERR-5 2174200300039 MEV MB MB MB PER-CENT PER-CENT 2174200300040 PER-CENT 2174200300041 1.41E+01 1.236E+02 2.3 9. 2.5 9.E-012174200300042 1.4 2174200300043 ENDCOMMON 6 0 2174200300044 DATA 2 2 2174200300045 DATA ERR-4 2174200300046 MB PER-CENT 2174200300047 2.28E+02 3.28 2174200300048 2.35E+02 3.17 2174200300049 ENDDATA 4 0 2174200300050 ENDSUBENT 49 0 2174200399999 SUBENT 21742004 20090315 22082174200400001 BIB 11 34 2174200400002 REACTION (3-LI-7(N,N+T)2-HE-4,,SIG) 2174200400003 FACILITY (VDGT ) Tandem van de graaf accelerator at harwell. 2174200400004 INC-SOURCE (D-D ) D(d,N)He-3 reaction, using a 10 cm long gas 2174200400005 cell filled to 2 atm. 2174200400006 DETECTOR (SCIN ) Ne 213 liquid scintillator, absolute efficiency2174200400007 calibrated, was used as neutron monitor. 2174200400008 (SCIN ) Liquid scintillator for beta counting. 2174200400009 (GELI ) Calibrated Ge(Li) detector to measure the 2174200400010 the monitor foil activation. 2174200400011 DECAY-DATA (1-H-3,,B) No information given. 2174200400012 MONITOR (28-NI-58(N,P)27-CO-58,,SIG) 2174200400013 DECAY-MON (27-CO-58-G,,DG,810.) No further information given. 2174200400014 STATUS .Data taken from table 5, aere-r-9929. 2174200400015 HISTORY (19810605C) G.C., Formerly present in EXFOR 20986.002 2174200400016 (19810722E) 2174200400017 and err-analys corrected 2174200400018 (20090315U) Last checking has been done. 2174200400019 INC-SPECT En-rsl: total energy spread of the incoming neutrons 2174200400020 the contributions to this total spread from the 2174200400021 geometry of the experiment and from the energy loss 2174200400022 of the deuterons in the deuterium target are listed 2174200400023 in table 1 of aere-r-9929. 2174200400024 ERR-ANALYS (ERR-T) Total error given. It includes the following 2174200400025 contributions 2174200400026 (ERR-S) Non correlated error. It consists of 2174200400027 - deuteron break up correction. 2174200400028 - Sample geometry. 2174200400029 - Tritium counting statistics. 2174200400030 - Sodium counting statistics. 2174200400031 (ERR-1) Multiple scattering correction. 2174200400032 (ERR-4) Combined error from tritium efficiency 2174200400033 calibration, tritium halflife and tritium back- 2174200400034 ground. 2174200400035 (ERR-5) Neutron detection efficiency. 2174200400036 ENDBIB 34 0 2174200400037 COMMON 2 3 2174200400038 MONIT MONIT-ERR 2174200400039 MB MB 2174200400040 4.14E+02 2.E+01 2174200400041 ENDCOMMON 3 0 2174200400042 DATA 8 1 2174200400043 EN EN-RSL DATA ERR-T ERR-S ERR-1 2174200400044 ERR-4 ERR-5 2174200400045 MEV MEV MB MB PER-CENT PER-CENT 2174200400046 PER-CENT PER-CENT 2174200400047 4.57 1.15 6.9E+01 1.5E+01 5.5 1.4E-012174200400048 1.74E+01 3.4 2174200400049 ENDDATA 6 0 2174200400050 ENDSUBENT 49 0 2174200499999 ENDENTRY 4 0 2174299999999