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