ENTRY 20775 20060429 21762077500000001 SUBENT 20775001 20060429 21762077500100001 BIB 15 64 2077500100002 INSTITUTE (2GERKFK) Wisshak, Kaeppeler, and Experimental site. 2077500100003 (2ZZZISP) Hage 2077500100004 REFERENCE (J,NSE,78,(3),248,198107) Main reference 2077500100005 (R,BNL-50991,197811) Preliminary data. 2077500100006 (P,NEANDC(E)-212,(5),14,198006) Abstract. 2077500100007 (P,NEANDC(E)-202,(5),17,197906) Graphs. 2077500100008 (P,NEANDC(E)-192,(5),26,197804) Preliminary work. 2077500100009 Curves and some informations are given. 2077500100010 (W,WISSHAK,19781020) Superseded. 2077500100011 AUTHOR (W.HAGE, K.WISSHAK, F.KAEPPELER) 2077500100012 TITLE "Neutron fission cross-section measurement of 2077500100013 americium-241 in the energy range from 10 to 1030 KeV"2077500100014 FACILITY (VDG,2GERKFK) The Karlsruhe pulsed 3 MV Van de Graaff 2077500100015 accelerator. 2077500100016 SAMPLE .Am-dioxide + Al pressed pellet, canned in 0.1 mm 2077500100017 stainless steel. Isotopic composition 98.65 percent 2077500100018 Am-241, 1.35 percent Np-237. Sample thickness 2077500100019 1.8 mm, diameter of 30 mm and a weight of 3.296 gr. 2077500100020 .U-235 metal sample with isotopic composition 92.9 2077500100021 percent U-235 and 7.09 percent U-238. Sample 2077500100022 thickness 0.58 mm, 30 mm diameter and with a weight 2077500100023 of 7.649 gr. 2077500100024 .A natural uo2 + Al pressed pellet canned in 0.1 mm 2077500100025 stainless steel and with the same dimensions as the 2077500100026 Am-sample was used for background corrections. 2077500100027 MONITOR ((MONIT1)(95-AM-241(N,F),PR,NU)/(92-U-235(N,F),PR,NU)) 2077500100028 ((MONIT2)(93-NP-237(N,F),PR,NU)/(95-AM-241(N,F),PR,NU))2077500100029 ((93-NP-237(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2077500100030 ((92-U-238(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2077500100031 ((MONIT5)(92-U-238(N,F),PR,NU)/(92-U-235(N,F),PR,NU)) 2077500100032 (92-U-235(N,F),,SIG) Values taken from endf/B-iv. 2077500100033 MONIT-REF ((MONIT1),W.G.DAVEY,J,NSE,44,345,1971) 2077500100034 (,F.MANERO+,J,REA,10,637,1972) 2077500100035 (10125004,A.H.JAFFEY+,J,NP/A,145,1,1970) 2077500100036 (,V.I.LEBEDEV+,J,SJA,5,1019,1958) 2077500100037 ((MONIT2),V.I.LEBEDEV+,J,SJA,10,357,1961) 2077500100038 (,W.G.DAVEY,J,NSE,32,35,1968) 2077500100039 (,D.B.GAYTHER+,C,72VIENNA,,201,1972) Proc.Conf. 2077500100040 Neutron standard reference data, vienna, 1972. 2077500100041 ((MONIT5),W.G.DAVEY,J,NSE,44,345,1971) 2077500100042 (,F.MANERO+,J,REA,10,637,1972) 2077500100043 METHOD (TOF) Time of flight techniques. 2077500100044 (PSD) Pulse shape discrimination. 2077500100045 DETECTOR (SCIN) Fission events were detected observing the 2077500100046 prompt fission neutrons, using a Ne213 liquid 2077500100047 scintillator with pulse shape discrimination. 2077500100048 This detector was located at an angle of 120 degrees 2077500100049 with respect to the neutron beam. 2077500100050 (GLASD) A Li-6 glass detector at 0 deg. As neutron 2077500100051 spectrum monitor. 2077500100052 PART-DET (PN ) Prompt fission neutrons above 2.3 MeV. 2077500100053 COMMENT .Comparison with other authors data. 2077500100054 STATUS .Data taken from preprint of nucl.Sci.Eng. Article. 2077500100055 HISTORY (19781023C) 2077500100056 (19781213E) 2077500100057 (19801107A) Updated with final publication. 2077500100058 (19801124E) 2077500100059 (20060429A) Date is corrected. Main reference added. 2077500100060 MONITOR and MONIT-REF keywords moved to SAN 001, one 2077500100061 SUBENT added after N.Otsuka and O.Schwerer comments 2077500100062 ERR-ANALYS (ERR-S) Statistical error. 2077500100063 (ERR-SYS) Total systematic uncertainties. For detailed 2077500100064 information see each subwork. 2077500100065 (ERR-T) Total error. 2077500100066 ENDBIB 64 0 2077500100067 COMMON 4 3 2077500100068 EN-NRM MONIT1 MONIT2 MONIT5 2077500100069 EV NO-DIM NO-DIM NO-DIM 2077500100070 2.53E-02 1.29 9.5E-01 9.26E-01 2077500100071 ENDCOMMON 3 0 2077500100072 ENDSUBENT 71 0 2077500199999 SUBENT 20775002 20060429 21762077500200001 BIB 6 44 2077500200002 REACTION ((95-AM-241(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2077500200003 INC-SOURCE (P-LI7) Thick Li targets were used, generating a 2077500200004 continuous neutron spectrum that was kinemati- 2077500200005 cally collimated in forward direction as the 2077500200006 proton energy was just above the reaction thresh- 2077500200007 hold. 2077500200008 STATUS .Data taken from table III in preprint of Nucl.Sci.Eng.2077500200009 Article. 2077500200010 (SPSDD,20775004) 2077500200011 CORRECTION .For- 2077500200012 - differences in flight path for the samples, 2077500200013 - background of the sample holder, 2077500200014 - sample canning and aluminum admixture (Am-sample), 2077500200015 - incomplete pulse shape discrimination, 2077500200016 - background from (alpha,N) reactions in the Am 2077500200017 sample and from neutrons scattered in the 2077500200018 experimental area, 2077500200019 - time distribution of the fission neutrons, 2077500200020 - detected fraction of prompt fission neutrons 2077500200021 above the discrimination level of 2.3 MeV, 2077500200022 - self shielding and muliple scattering in the 2077500200023 sample, 2077500200024 - neutron flux depression inside the Am-241 sample 2077500200025 caused by the strong scattering resonance in 2077500200026 Fe-56 at 27.7 KeV. 2077500200027 ERR-ANALYS .The systematic uncertainty consists of the 2077500200028 following contributions, 2077500200029 (ERR-1) - Sample mass error 1.6% 2077500200030 (ERR-2) - Flight path sample and 2077500200031 reference sample max.Error 0.7-3.9 % 2077500200032 (ERR-3) - Unfolding procedure 5.5% 2077500200033 (ERR-4) - Max. Correction for incomplete 2077500200034 gamma discrimination error 0.9-1.6% 2077500200035 (ERR-5) - Max.Isotopic impurities error 0.03-0.08%2077500200036 (ERR-6) - Fraction of fission neutron 2077500200037 spectrum above threshold error 2.3% 2077500200038 (ERR-7) - Delta-e of Am-241 error 4.4 % 2077500200039 (ERR-8) - Max. Scattering in canning error 2.0-3.0% 2077500200040 (ERR-9) - Multiple scattering and 2077500200041 self shielding error 0.8 % 2077500200042 (ERR-10) - Neutron flux error 0.4 % 2077500200043 (ERR-11) - Nu(e) of Am-241 error 1.5 % 2077500200044 (ERR-12) - Nu(e) of U-235 error 0.95% 2077500200045 HISTORY (20060429A) Data values corrected - divided by 1000 2077500200046 ENDBIB 44 0 2077500200047 COMMON 12 6 2077500200048 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2077500200049 ERR-7 ERR-8 ERR-9 ERR-10 ERR-11 ERR-12 2077500200050 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2077500200051 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2077500200052 1.6 3.9 5.5 1.6 0.8 2.32077500200053 4.4 3. 0.8 0.4 1.5 0.952077500200054 ENDCOMMON 6 0 2077500200055 DATA 6 7 2077500200056 EN EN-RSL DATA ERR-S ERR-SYS ERR-T 2077500200057 KEV KEV NO-DIM PER-CENT PER-CENT PER-CENT 2077500200058 2.22E+01 5.9 8.36E-03 4.7 8.3 9.52077500200059 3.23E+01 5.8 9.91E-03 3.1 7.7 8.32077500200060 4.47E+01 1.02E+01 1.03E-02 2.1 7.7 8.02077500200061 5.83E+01 8.2 8.81E-03 2.7 7.9 8.32077500200062 7.20E+01 1.13E+01 9.96E-03 2.2 8.2 8.42077500200063 9.14E+01 1.61E+01 1.02E-02 1.6 8.5 8.62077500200064 1.203E+02 2.48E+01 1.21E-02 9.E-01 7.6 7.62077500200065 ENDDATA 9 0 2077500200066 ENDSUBENT 65 0 2077500299999 SUBENT 20775003 20060429 21762077500300001 BIB 6 33 2077500300002 REACTION ((95-AM-241(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2077500300003 INC-SOURCE (P-LI7) Thin Li-targets were used, producing quasi 2077500300004 monoenergetic neutrons with a resolution of about 2077500300005 20 to 30 KeV. 2077500300006 STATUS .Data taken from table III in preprint. 2077500300007 (SPSDD,20775004) 2077500300008 CORRECTION .For- 2077500300009 - differences in flight path for the samples, 2077500300010 - background from the sample holder, 2077500300011 - detected fraction of prompt fission neutrons 2077500300012 above the discrimination level at 2.3 MeV, 2077500300013 - self shielding and multiple scattering in the 2077500300014 sample, 2077500300015 - the second neutron group from the Li-7(P,N) 2077500300016 reaction. 2077500300017 ERR-ANALYS .The systematic uncertainty consists of the 2077500300018 following contributions, 2077500300019 (ERR-1) - Sample mass error 1.6 % 2077500300020 (ERR-2) - Flight path sample and 2077500300021 reference sample error 1.8 % 2077500300022 (ERR-3) - Max.Isotopic impurities error 0.08- 0.3 % 2077500300023 (ERR-4) - Fraction of fission neutron 2077500300024 spectrum above threshold error 2.3 % 2077500300025 (ERR-5) - Delta-e of Am-241 error 4.4 % 2077500300026 (ERR-6) - Multiple scattering and 2077500300027 self shielding error 0.8 % 2077500300028 (ERR-7) - Neutron flux error 0.4 % 2077500300029 (ERR-8) - Nu(e) of Am-241 error 1.5 % 2077500300030 (ERR-9) - Nu(e) of U-235 error 0.95 % 2077500300031 (ERR-10) - Max.Correction for second neutron 2077500300032 group avove proton energies 2077500300033 of 2.373 MeV error 0.12-0.35 % 2077500300034 HISTORY (20060429A) Data values corrected - divided by 1000 2077500300035 ENDBIB 33 0 2077500300036 COMMON 11 6 2077500300037 ERR-SYS ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2077500300038 ERR-6 ERR-7 ERR-8 ERR-9 ERR-10 2077500300039 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2077500300040 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2077500300041 5.4 1.6 1.8 0.3 2.3 4.42077500300042 0.8 0.4 1.5 0.95 0.35 2077500300043 ENDCOMMON 6 0 2077500300044 DATA 5 20 2077500300045 EN EN-RSL DATA ERR-S ERR-T 2077500300046 KEV KEV NO-DIM PER-CENT PER-CENT 2077500300047 1.2 E+02 1.5E+01 1.19E-02 6.2 8.2 2077500300048 1.25E+02 2.5E+01 1.24E-02 10.3 11.6 2077500300049 1.55E+02 1.4E+01 1.41E-02 4.8 7.2 2077500300050 1.6 E+02 1.8E+01 1.55E-02 5.7 7.8 2077500300051 1.93E+02 1.6E+01 1.76E-02 3.6 6.5 2077500300052 2.06E+02 1.9E+01 1.90E-02 2.8 6.0 2077500300053 2.73E+02 3.7E+01 2.51E-02 10.0 11.3 2077500300054 3.18E+02 2.9E+01 3.09E-02 6.0 8.1 2077500300055 3.67E+02 3.0E+01 3.62E-02 2.8 6.1 2077500300056 4.02E+02 3.4E+01 5.07E-02 1.1 5.5 2077500300057 4.69E+02 2.8E+01 7.40E-02 3.3 6.3 2077500300058 5.12E+02 2.6E+01 9.60E-02 7.0E-01 5.4 2077500300059 5.59E+02 3.0E+01 1.34E-01 7.5E-01 5.4 2077500300060 6.17E+02 2.9E+01 1.79E-01 5.7E-01 5.4 2077500300061 6.77E+02 2.0E+01 2.56E-01 6.5E-01 5.4 2077500300062 7.1 E+02 2.6E+01 3.91E-01 8.0E-01 5.4 2077500300063 7.71E+02 2.5E+01 5.58E-01 6.0E-01 5.4 2077500300064 8.32E+02 1.9E+01 7.52E-01 8.1E-01 5.4 2077500300065 9.29E+02 2.2E+01 8.79E-01 6.7E-01 5.4 2077500300066 1.03E+03 2.8E+01 1.171E-00 6.0E-01 5.4 2077500300067 ENDDATA 22 0 2077500300068 ENDSUBENT 67 0 2077500399999 SUBENT 20775004 20060429 21762077500400001 BIB 5 13 2077500400002 REACTION 1((95-AM-241(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2077500400003 2((95-AM-241(N,F),,SIG)/(92-U-235(N,F),,SIG)) 2077500400004 INC-SOURCE (P-LI7) Thick and thin Li targets were used,generating 2077500400005 a continuous and quasi-monoenergetic neutron spectrum 2077500400006 that was kinematically collimated in forward direction2077500400007 as the proton energy was just above the reaction 2077500400008 threshhold. 2077500400009 INC-SPECT 1.Continuous neutron spectrum 2077500400010 2.Quasi-monoenergetic neutron spectrum 2077500400011 STATUS .From table III of main reference 2077500400012 (COREL,20775002) 2077500400013 (COREL,20775003) 2077500400014 HISTORY (20060429C) SM 2077500400015 ENDBIB 13 0 2077500400016 NOCOMMON 0 0 2077500400017 DATA 10 25 2077500400018 EN EN-RSL DATA 1ERR-S 1ERR-SYS 1ERR-T 12077500400019 DATA 2ERR-S 2ERR-SYS 2ERR-T 2 2077500400020 KEV KEV NO-DIM PER-CENT PER-CENT PER-CENT 2077500400021 NO-DIM PER-CENT PER-CENT PER-CENT 2077500400022 22.2 5.9 8.36E-03 4.7 8.3 9.5 2077500400023 2077500400024 32.3 5.8 9.91E-03 3.1 7.7 8.3 2077500400025 2077500400026 44.7 10.2 10.3 E-03 2.1 7.7 8.0 2077500400027 2077500400028 66.7 16.6 9.43E-03 1.7 8.0 8.2 2077500400029 2077500400030 110.2 14.9 11.5 E-03 0.8 8.0 8.1 2077500400031 2077500400032 120. 15. 2077500400033 11.9E-03 6.2 5.4 8.2 2077500400034 125. 25. 2077500400035 12.4E-03 10.3 5.4 11.6 2077500400036 155. 14. 2077500400037 14.4E-03 4.8 5.4 7.2 2077500400038 160. 18. 2077500400039 15.5E-03 5.7 5.4 7.8 2077500400040 193. 16. 2077500400041 17.6E-03 3.6 5.4 6.5 2077500400042 206. 19. 2077500400043 19.0E-03 2.8 5.4 6.0 2077500400044 273. 37. 2077500400045 25.1E-03 10.0 5.4 11.3 2077500400046 318. 29. 2077500400047 30.9E-03 6.0 5.4 8.1 2077500400048 367. 30. 2077500400049 36.2E-03 2.8 5.4 6.1 2077500400050 402. 34. 2077500400051 50.7E-03 1.1 5.4 5.5 2077500400052 469. 28. 2077500400053 74.0E-03 3.3 5.4 6.3 2077500400054 512. 26. 2077500400055 96.0E-03 0.70 5.4 5.4 2077500400056 559. 30. 2077500400057 134. E-03 0.75 5.4 5.4 2077500400058 611. 29. 2077500400059 179. E-03 0.57 5.4 5.4 2077500400060 677. 20. 2077500400061 256. E-03 0.65 5.4 5.4 2077500400062 710. 26. 2077500400063 391. E-03 0.80 5.4 5.4 2077500400064 771. 25. 2077500400065 558. E-03 0.60 5.4 5.4 2077500400066 832. 19. 2077500400067 752. E-03 0.81 5.4 5.4 2077500400068 929. 22. 2077500400069 879. E-03 0.67 5.4 5.4 2077500400070 1030. 28. 2077500400071 1171. E-03 0.60 5.4 5.4 2077500400072 ENDDATA 54 0 2077500400073 ENDSUBENT 72 0 2077500499999 ENDENTRY 4 0 2077599999999