ENTRY 22367 20000615 00002236700000001 SUBENT 22367001 20000615 00002236700100001 BIB 15 79 2236700100002 TITLE Cross-Section For the 103-Rh(N,N')103-Rh-M Reaction 2236700100003 In the Energy Range 5.7 - 12 MeV 2236700100004 AUTHOR (M.M.H.MIAH,STROHMAIER,H.VONACH,W.MANNHART,D.SCHMIDT) 2236700100005 INSTITUTE (2AUSIRK) Miah, Strohmaier, Vonach 2236700100006 (2GERPTB) Mannhart, Schmidt 2236700100007 REFERENCE (J,PR/C,54,(1),222,199607) Main Reference 2236700100008 Data are Given 2236700100009 (J,NSE,106,308,1990) Experimental Details 2236700100010 (C,94GATLIN,,278,199405) Preliminary Results 2236700100011 FACILITY (CYCLO,2GERPTB) PTB Compact Cyclotron CV-28 Interacted 2236700100012 With a Gas Target 3 Cm Long at Pressure 0.2 Mpa 2236700100013 INC-SOURCE (D-D) 2236700100014 METHOD (ACTIV) Activation Technique For Reaction Rate 2236700100015 Determination 2236700100016 (TOF) Time-Of-Flight For Neutron Energy Determination 2236700100017 DETECTOR (SCIN) NE-123 Liquid Scintillation Detector 2236700100018 For Neurton Detection 2236700100019 (FISCH) U-238 Fission Chamber For Neutron Flux 2236700100020 Monitoring 2236700100021 (SILI) Silicium-Lithium Detector For K-Shell X-Rays 2236700100022 MONITOR (92-U-238(N,F),,SIG) For Neutron Fluence Measurements 2236700100023 PART-DET (N) 2236700100024 (FF) 2236700100025 (XR) K-Shell X-Rays of 103Rh-M 2236700100026 DECAY-DATA (45-RH-103-M,56.114MIN,XR) 2236700100027 CORRECTION .Corrections were Made on the Efficiency of Extended 2236700100028 Source, on Self-Absorption in Samples, Mass Attenu- 2236700100029 Ation Coefficient, Elastic and Inelastic Scattering 2236700100030 Of Neutrons in Sample or an Adjusted Part of Fission 2236700100031 Chamber, For Neutrons Produced in the Windows and 2236700100032 Backing of Gas Target. The Most Important Correction 2236700100033 Made is That For Breakup Neutrons Which Comprise 2236700100034 65 Pc of Observed Rh-103-M Activity and 33 Pc of 2236700100035 Fission Rate at 12 MeV 2236700100036 SAMPLE .Metallic Rhodium Samples 0.125 mm Thick, 10 mm in 2236700100037 Diameter Attached to the Front of a Low-Mass Fission 2236700100038 Chamber 2236700100039 ERR-ANALYS (ERR-T) Total Error at One-Sigma Confidence Interval 2236700100040 Equal to Quadratic Sum of All Errors Listed Below 2236700100041 (ERR-S) Max Statistical Count Rate Error. 2236700100042 Min Error=0.63 Pc 2236700100043 (ERR-1) Max Error of Subtraction of Activities from 2236700100044 Gas-Out Run 2236700100045 (ERR-2) Min Error of Subtraction of Activities from 2236700100046 Gas-Out Run 2236700100047 (ERR-3) Error of Transfer Factor from Measurement 2236700100048 Position to Calibrated Position 2236700100049 (ERR-4) Error of Effficiency of Si(LI) Detector 2236700100050 (ERR-5) Max Error of Self-Absorption of X-Rays 2236700100051 In the Samples. Min Error=1.08 Pc 2236700100052 (ERR-6) Max Error of Activity Due to Elastically and 2236700100053 Inelastically Scattered Neutrons. 2236700100054 Min Error=0.12 Pc 2236700100055 (ERR-7) Max Error of Activity Correction Due to 2236700100056 Breakup Neutrons. Min Error = 0.05 Pc 2236700100057 (ERR-8) Error of Half-Life Og Rh-103-M 2236700100058 (ERR-9) Error of Emission Probability of K X-Rays 2236700100059 (ERR-10) Max Fission-Fragments Counting Statistics 2236700100060 Error (GAS-IN RUN). Min Error=1.02 Pc 2236700100061 (ERR-11) Max Fission-Fragments Subtraction Error 2236700100062 (GAS-OUT RUN). Min Error=0.30 Pc 2236700100063 (ERR-12) Max Error of Extrapolation Correction For 2236700100064 Fission Fragments. Min Error=0.35 Pc 2236700100065 (ERR-13) Max Error of Self-Absorption of U-238 Deposit 2236700100066 Min Error=0.14 Pc 2236700100067 (ERR-14) Max Error of U-238 Reference Cross-Section 2236700100068 Min Error=0.93 Pc 2236700100069 (ERR-15) Error of Mass Calibration of U-238 2236700100070 (DATA-ERR1) Error of Fluence Transformation from 2236700100071 Monitor to Sample Level 2236700100072 (DATA-ERR2) Max Error Due to Fission Fragments from 2236700100073 Breakup Neutrons. Min Error=0.01 Pc 2236700100074 . 2236700100075 Error Due to Neutron Attenuation Between Sample and 2236700100076 Monitor = 0.06 Pc 2236700100077 HISTORY (19971231C) + + Compiled by S.M. + + 2236700100078 (19990604U) Dates are Corrected 2236700100079 (20000614U) . Corrected by Sm 2236700100080 (20000615U) Last checking has been done. 2236700100081 ENDBIB 79 0 2236700100082 COMMON 18 9 2236700100083 ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2236700100084 ERR-6 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 2236700100085 ERR-12 ERR-13 ERR-14 ERR-15 DATA-ERR1 DATA-ERR2 2236700100086 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2236700100087 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2236700100088 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2236700100089 0.89 1.3 0.3 0.49 1.8 1.132236700100090 0.22 6.78 0.036 1.83 1.51 1.842236700100091 1.81 0.25 1.47 0.59 0.07 1.732236700100092 ENDCOMMON 9 0 2236700100093 ENDSUBENT 92 0 2236700199999 SUBENT 22367002 20000615 00002236700200001 BIB 2 3 2236700200002 REACTION (45-RH-103(N,INL)45-RH-103-M,,SIG) 2236700200003 STATUS (TABLE) Data from Table 1 of Main Reference 2236700200004 (COREL,22328002) 2236700200005 ENDBIB 3 0 2236700200006 COMMON 1 3 2236700200007 EN-ERR 2236700200008 KEV 2236700200009 20. 2236700200010 ENDCOMMON 3 0 2236700200011 DATA 4 14 2236700200012 EN EN-RSL-FW DATA ERR-T 2236700200013 MEV MEV MB MB 2236700200014 5.689 0.21 1314. 58. 2236700200015 6.039 0.19 1296. 46. 2236700200016 6.525 0.172 1312. 49. 2236700200017 6.932 0.16 1321. 46. 2236700200018 7.575 0.144 1203. 43. 2236700200019 7.979 0.136 1247. 44. 2236700200020 8.55 0.124 1221. 44. 2236700200021 8.965 0.13 1293. 48. 2236700200022 9.55 0.12 1228. 48. 2236700200023 9.915 0.116 1195. 50. 2236700200024 10.579 0.112 938. 48. 2236700200025 11.039 0.11 771. 47. 2236700200026 11.424 0.108 721. 49. 2236700200027 12.003 0.108 565. 45. 2236700200028 ENDDATA 16 0 2236700200029 ENDSUBENT 28 0 2236700299999 ENDENTRY 2 0 2236799999999