ENTRY B0144 20011220 0000B014400000001 SUBENT B0144001 20011220 0000B014400100001 BIB 15 61 B014400100002 TITLE The C-12 + C-12 Sub-Coulomb Fusion Cross Section. B014400100003 AUTHOR (M.D.HIGH, B.CUJEC) B014400100004 INSTITUTE (1CANLUQ) B014400100005 REFERENCE (J,NP/A,282,181,1977) B014400100006 FACILITY (VDG,1CANLUQ) B014400100007 SAMPLE Solid Piece of Reactor Graphite, Surface-Purified B014400100008 Using an Electron Gun. B014400100009 DETECTOR (GELI) B014400100010 Two Detectors were Used Mounted at 90 Degrees and B014400100011 270 Degrees to the Beam Direction. B014400100012 METHOD (EXTB,SITA,BCINT) B014400100013 In-Beam Gamma-Ray Spectra were Measured. The Beam B014400100014 Energy was Increased in Steps of 125 KeV Between B014400100015 E=2.46 and 3.89 MeV and 250 KeV Between 4.14 MeV B014400100016 And 5.88 MeV. (ALL ENERGIES ARE GIVEN IN THE B014400100017 C.M.-SYSTEM). The Target Thickness was Essentially B014400100018 Greater Than the Range of the Incident C-12 Ions. B014400100019 From the Ratio of Counts in the Two Detectors Used It B014400100020 Was Concluded That the Position of the Beam Spot B014400100021 Remained Stable During the Experiment. B014400100022 Beam Currents Varied Between 3 and 5 Microamps. B014400100023 ANALYSIS For Cross Section Calculation It was Necessary Due to B014400100024 The Thick Target to Take the Difference of Yields B014400100025 Of Two Measurements at Different Bombarding Energies. B014400100026 This Yield Then Corresponds to a Definite Target B014400100027 Thickness and Beam Energy. B014400100028 Absolute Cross Sections were Obtained by Normalizing B014400100029 The Measured Yields Above 3.5 MeV to Data Obtained fromB014400100030 Measuring the Emitted Particles by Mazarakis and B014400100031 Stephens, Pr C7,1280(1970). B014400100032 CORRECTION A Branching Correction was Applied Taking Into Account B014400100033 That Some States Populated Via Particle Emission B014400100034 Do not Deexcitate Exclusively Via the Observed First B014400100035 Excited State. Included in this Correction are the B014400100036 Particle Decays Directly to the Ground State, Which B014400100037 Represent the Largest Correction. The Branching B014400100038 Correction has a Maximum Value of About 50%. B014400100039 The Energy Values were Corrected For the Nonlinear B014400100040 Effects of the Exponential Drop-Off of Cross Section B014400100041 In the Target. B014400100042 A Further Correction For Pulse Pile-Up of Cascading B014400100043 Gamma-Rays was Applied, Which was Found to Vary with B014400100044 Energy Negligibly. B014400100045 ERR-ANALYS The Errors Quoted in the Data Section Include the B014400100046 Uncertainty in Charge Collection Plus the Statistical B014400100047 Errors, Which Arise Mainly from the Subtraction of a B014400100048 Large Background. Further Information About Errors B014400100049 Is Missing. B014400100050 (DATA-ERR). See Above. B014400100051 MISC-COL (MISC) C.M.-Projectile Energies As Given by the AuthorsB014400100052 The Lab-Energies were Calculated by the Compiler. B014400100053 COMMENT The Neutron Decay-Channel has a Q-Value of -2.6 MeV B014400100054 And Accounts For Only 5% of the Fusion Cross Section atB014400100055 Higher Energies. B014400100056 ADD-RES The C-12 + C-12 Fusion Cross Section is Deduced. B014400100057 HISTORY (19800520C)Nekw B014400100058 (19940720A) Some Corrections have Been Included by B014400100059 CAJAD B014400100060 (19981123A) Reaction Lines are Corrected. Converted to B014400100061 Lower Case. B014400100062 (20011010U) Last checking has been done. B014400100063 ENDBIB 61 0 B014400100064 NOCOMMON 0 0 B014400100065 ENDSUBENT 64 0 B014400199999 SUBENT B0144002 20011220 0000B014400200001 BIB 3 3 B014400200002 REACTION (6-C-12(6-C-12,A)10-NE-20,PAR,SIG,,,EXP) B014400200003 PART-DET (G) 2+ to 0+ Transition in Ne-20. E(GAMMA)=1.63 MeV B014400200004 EN-SEC (E,G) B014400200005 ENDBIB 3 0 B014400200006 COMMON 1 3 B014400200007 E B014400200008 MEV B014400200009 1.63 B014400200010 ENDCOMMON 3 0 B014400200011 DATA 4 20 B014400200012 EN DATA DATA-ERR MISC B014400200013 MEV MB PER-CENT MEV B014400200014 4.92 0. 46. 2.46 B014400200015 5.14 0.00001 43. 2.57 B014400200016 5.38 0.00002 31. 2.69 B014400200017 5.64 0.00005 16. 2.82 B014400200018 5.88 0.00006 16. 2.94 B014400200019 6.14 0.00034 11. 3.07 B014400200020 6.38 0.00095 10. 3.19 B014400200021 6.64 0.00191 12. 3.32 B014400200022 6.88 0.00374 10. 3.44 B014400200023 7.14 0.00513 10. 3.57 B014400200024 7.38 0.00852 11. 3.69 B014400200025 7.78 0.0233 11. 3.89 B014400200026 8.28 0.143 11. 4.14 B014400200027 8.76 0.602 11. 4.38 B014400200028 9.26 0.762 11. 4.63 B014400200029 9.76 4.63 11. 4.88 B014400200030 10.26 5.92 11. 5.13 B014400200031 10.76 11.1 11. 5.38 B014400200032 11.26 32.2 11. 5.63 B014400200033 11.76 30.3 11. 5.88 B014400200034 ENDDATA 22 0 B014400200035 ENDSUBENT 34 0 B014400299999 SUBENT B0144003 20011220 0000B014400300001 BIB 3 8 B014400300002 REACTION (6-C-12(6-C-12,P)11-NA-23,PAR,SIG,,,EXP) B014400300003 The Given Cross Section May Contain a Small B014400300004 Contribution from the C-12(C-12,N)Mg-23 Reaction B014400300005 Channel Due to the Fact That the First Excited Levels B014400300006 In Na-23 (439 KEV) And Mg-23 (450 KEV) Could not B014400300007 Be Resolved. B014400300008 PART-DET (G) 5/2+ to 3/2+ Transition in Na-23. E(GAMMA)=439 KeV.B014400300009 EN-SEC (E,G) B014400300010 ENDBIB 8 0 B014400300011 COMMON 1 3 B014400300012 E B014400300013 MEV B014400300014 0.439 B014400300015 ENDCOMMON 3 0 B014400300016 DATA 4 20 B014400300017 EN DATA DATA-ERR MISC B014400300018 MEV MB PER-CENT MEV B014400300019 4.92 0. 58. 2.46 B014400300020 5.14 0.00001 52. 2.57 B014400300021 5.38 0.00002 26. 2.69 B014400300022 5.64 0.00004 21. 2.82 B014400300023 5.88 0.00006 22. 2.94 B014400300024 6.14 0.00022 13. 3.07 B014400300025 6.38 0.00054 12. 3.19 B014400300026 6.64 0.00176 10. 3.32 B014400300027 6.88 0.00386 12. 3.44 B014400300028 7.14 0.00578 11. 3.57 B014400300029 7.38 0.0101 11. 3.69 B014400300030 7.78 0.0152 11. 3.89 B014400300031 8.28 0.131 11. 4.14 B014400300032 8.76 0.372 11. 4.38 B014400300033 9.26 0.733 11. 4.63 B014400300034 9.76 4.02 11. 4.88 B014400300035 10.26 5.44 11. 5.13 B014400300036 10.76 8.19 11. 5.38 B014400300037 11.26 19.5 11. 5.63 B014400300038 11.76 25.4 11. 5.88 B014400300039 ENDDATA 22 0 B014400300040 ENDSUBENT 39 0 B014400399999 ENDENTRY 3 0 B014499999999