ENTRY 40968 20110720 41534096800000001 SUBENT 40968001 20110720 41534096800100001 BIB 13 43 4096800100002 TITLE Cross section for radiative capture of neutrons by 4096800100003 Au-197. An analysis of sources of systematic errors in 4096800100004 measurement of activation. 4096800100005 AUTHOR (A.N.Davletshin,V.N.Korytchenko,A.O.Tipunkov, 4096800100006 S.V.Tikhonov,V.A.Tolstikov) 4096800100007 INSTITUTE (4RUSFEI) 4096800100008 REFERENCE (J,AE,65,(5),343,198810) Data table is given 4096800100009 (J,AE,58,(3),183,1985) Error structure is given 4096800100010 Au-197 prelim.data. 4096800100011 Also U-236,Np-237 prelim data - see ENTRY 40969. 4096800100012 (J,SJA,65,(5),913,1988) Engl.translation of J,AE,65 . 4096800100013 #doi:10.1007/BF01121251 4096800100014 (J,SJA,58,(3),216,1985) Engl.translation of J,AE,58 . 4096800100015 #doi:10.1007/BF01125358 4096800100016 FACILITY (VDG,4RUSFEI) Cascade Generator 4096800100017 INC-SOURCE (P-T,P-LI7) 4096800100018 DECAY-DATA (79-AU-198-G,2.7D,DG,142.) 4096800100019 DETECTOR (GELI) Ge(Li) gamma-spectrometer to measure the 4096800100020 Au sample induced activity. 4096800100021 STATUS (APRVD) Approved by the authors (Tikhonov) and 4096800100022 Tolstikov). Data in the table are corrected 4096800100023 1988-12-12 4096800100024 (COREL,40969001) Data for Np-237,U-236. 4096800100025 HISTORY (19890203C) Compiled at the CJD 4096800100026 (20030729A) DATE is corrected 4096800100027 (20110720A) Upper -> lower case correction. 4096800100028 References of Engl.translations were added. 4096800100029 BIB information was added. 4096800100030 ERR-ANALYS was corrected. 4096800100031 CORRECTION Thorough investigation of systematic errors was made 4096800100032 and corresponding corrections in earlier results 4096800100033 introduced 4096800100034 METHOD (ACTIV) Activation 4096800100035 ERR-ANALYS (ERR-T) Total error is square root of the quadratic 4096800100036 sum of all errors 4096800100037 (ERR-1) Error due to the active nuclei number 4096800100038 uncertainty 4096800100039 (ERR-2) Error due to the Ge-Li detector efficiency 4096800100040 uncertainty 4096800100041 (ERR-7) Error due to the number of atoms in a sample 4096800100042 of gold 4096800100043 (ERR-9) Error due to the sample geometrical factor 4096800100044 correction 4096800100045 ENDBIB 43 0 4096800100046 COMMON 4 3 4096800100047 ERR-1 ERR-2 ERR-7 ERR-9 4096800100048 PER-CENT PER-CENT PER-CENT PER-CENT 4096800100049 0.7 1.5 0.1 0.6 4096800100050 ENDCOMMON 3 0 4096800100051 ENDSUBENT 50 0 4096800199999 SUBENT 40968002 20110720 41534096800200001 BIB 7 14 4096800200002 REACTION (79-AU-197(N,G)79-AU-198-G,(M),SIG) 4096800200003 MONITOR (92-U-235(N,F),,SIG) 4096800200004 INC-SPECT EN given in the DATA table is the average energy 4096800200005 of the neutron beam and EN-RSL is square root of the 4096800200006 spectrum dispersion 4096800200007 DETECTOR (FISCH) U-235 fission chamber. 4096800200008 FLAG (1.) Data given in this line are obtained with the 4096800200009 gas-cooled neutron target 4096800200010 ERR-ANALYS (MONIT-ERR) Error of the (N,F) standard cross-section 4096800200011 (ERR-3) Uncertainty due to correction for scattered 4096800200012 neutrons. 4096800200013 (ERR-4) Uncertainty of FF registration efficiency by 4096800200014 fission chamber. 4096800200015 STATUS (TABLE) Table of J,AE,65,(5),343,1988. 4096800200016 ENDBIB 14 0 4096800200017 COMMON 3 3 4096800200018 MONIT-ERR ERR-3 ERR-4 4096800200019 PER-CENT PER-CENT PER-CENT 4096800200020 3.5 1.5 2.0 4096800200021 ENDCOMMON 3 0 4096800200022 DATA 6 11 4096800200023 EN EN-RSL DATA ERR-T MONIT FLAG 4096800200024 KEV KEV B PER-CENT B NO-DIM 4096800200025 619. 35. .111 5. 1. 4096800200026 627. 34. .107 5. 1. 4096800200027 630. 37. .106 5. 1.142 1. 4096800200028 636. 34. .105 6. 1.142 1. 4096800200029 637. 20. .103 5. 4096800200030 637.01 20. .110 5. 4096800200031 645. 23. .105 5. 1.141 4096800200032 764. 34. .091 5. 1. 4096800200033 779. 31. .087 5. 1. 4096800200034 779.1 31. .090 5. 1. 4096800200035 780. 31. .094 5. 1.137 1. 4096800200036 ENDDATA 13 0 4096800200037 ENDSUBENT 36 0 4096800299999 SUBENT 40968003 20110720 41534096800300001 BIB 7 19 4096800300002 REACTION (79-AU-197(N,G)79-AU-198,,SIG) 4096800300003 MONITOR (1-H-1(N,EL)1-H-1,,SIG) 4096800300004 INC-SPECT Energy 'EN' given in the DATA table is the average 4096800300005 one of the neutron beam spectrum and EN-RSL is 4096800300006 square root of the neutron spectrum dispersion 4096800300007 DETECTOR (PROPC) Cylindrical proportional counters filled by 4096800300008 helium or methane . 4096800300009 FLAG (1.) Data given in this line are obtained with the 4096800300010 help of gas-cooled neutron target 4096800300011 ERR-ANALYS (MONIT-ERR) Error of the (N,P) standard cross-section 4096800300012 (ERR-3,1.8,2.7) Error due to the scattered neutron 4096800300013 correction uncertainty 4096800300014 (ERR-5) Error due to the uncertainty of the number 4096800300015 of interactions in the hydrogen counter 4096800300016 (ERR-6) Error due to the uncertainty of the number 4096800300017 of hydrogen atoms in the prop-counter 4096800300018 (ERR-8) Error due to the counter geometrical factor 4096800300019 correction 4096800300020 STATUS (TABLE) Table of J,AE,65,(5),343,1988. 4096800300021 ENDBIB 19 0 4096800300022 COMMON 4 3 4096800300023 MONIT-ERR ERR-5 ERR-6 ERR-8 4096800300024 PER-CENT PER-CENT PER-CENT PER-CENT 4096800300025 1.0 2.0 1.1 0.3 4096800300026 ENDCOMMON 3 0 4096800300027 DATA 6 40 4096800300028 EN EN-RSL DATA ERR-T MONIT FLAG 4096800300029 KEV KEV B PER-CENT B NO-DIM 4096800300030 164. 23. .275 5. 4096800300031 166. 22. .312 5. 4096800300032 166.1 22. .275 5. 4096800300033 336. 17. .193 4. 4096800300034 340. 17. .198 4. 4096800300035 340.1 17. .185 4. 4096800300036 342. 10. .198 4. 4096800300037 344. 24. .180 4. 4096800300038 344.1 24. .185 4. 7.421 4096800300039 467. 21. .142 4. 4096800300040 471. 22. .144 4. 4096800300041 475. 21. .140 4. 6.289 4096800300042 544. 27. .120 4. 4096800300043 544.1 28. .118 4. 4096800300044 619. 35. .107 4. 1. 4096800300045 627. 34. .100 4. 1. 4096800300046 630. 37. .106 4. 1. 4096800300047 636. 34. .100 4. 5.403 1. 4096800300048 636.1 21. .101 4. 4096800300049 637. 20. .100 4. 4096800300050 637.1 20. .106 4. 4096800300051 645. 23. .102 4. 4096800300052 693. 22. .118 4. 4096800300053 708. 22. .097 4. 5.127 4096800300054 710. 23. .090 4. 4096800300055 764. 34. .092 4. 1. 4096800300056 779. 31. .086 4. 1. 4096800300057 779.1 31. .086 4. 4.872 1. 4096800300058 780. 31. .091 4. 1. 4096800300059 881. 21. .091 4. 4096800300060 883. 17. .091 4. 4096800300061 885. 21. .090 4. 4096800300062 1037. 18. .081 4. 4096800300063 1042. 22. .080 4. 4096800300064 1133. 20. .083 4. 4096800300065 1135. 21. .081 4. 4096800300066 1142. 17. .080 4. 4096800300067 1181. 20. .074 4. 4096800300068 1192. 15. .072 4. 4096800300069 1389. 17. .068 4. 4096800300070 ENDDATA 42 0 4096800300071 ENDSUBENT 70 0 4096800399999 ENDENTRY 3 0 4096899999999