ENTRY 21209 20071219 21902120900000001 SUBENT 21209001 20071219 21902120900100001 BIB 12 28 2120900100002 INSTITUTE (2UK ALD) 2120900100003 REFERENCE (J,JNE/AB,14,85,1961) 2120900100004 AUTHOR (B.Adams,R.Batchelor,T.S.Green) 2120900100005 TITLE -The energy dependence of the fission cross-sections 2120900100006 of U-238, U-235 and Pu-239 for neutrons in the energy 2120900100007 range 12.6 to 20 MeV- 2120900100008 FACILITY (VDG) 6 MeV Van de Graaff. 2120900100009 INC-SOURCE (D-T) Up to 3.7 MeV deuterons incident on tritium 2120900100010 gas cell through a 0.0002 inch thick nickel 2120900100011 window. Gas cell at 1 atmosphere pressure. 2120900100012 METHOD .Measurement of fission events. 2120900100013 DETECTOR (FISCH) Multiplate fission chamber consisting of 2120900100014 platinum backings coated with 1.5 mg/cm-sq 2120900100015 thick layers of fissile material. 2120900100016 (TELES) Proton recoil telescope to measure neutron 2120900100017 flux. 2120900100018 (LONGC) Long counter placed in forward direction to 2120900100019 monitor neutron production. 2120900100020 MONITOR (92-U-238(N,F),,SIG) 14 MeV cross-section from a.Moat, 2120900100021 private communication. 2120900100022 STATUS (NDD) From NEUDADA. 2120900100023 HISTORY (19791211T) 2120900100024 (19800110E) 2120900100025 (19810504A) Data pointers corrected. 2120900100026 (19810722E) 2120900100027 (20060809A) Date and reference code corrected 2120900100028 (20071219U) Last checking has been done. 2120900100029 CORRECTION .Background measured by removing the gas from the cell.2120900100030 ENDBIB 28 0 2120900100031 NOCOMMON 0 0 2120900100032 ENDSUBENT 31 0 2120900199999 SUBENT 21209002 20071219 21902120900200001 BIB 5 10 2120900200002 REACTION 1(92-U-238(N,F),,SIG,,REL) Cross-section normalized to 2120900200003 unity at 14 MeV. 2120900200004 2(92-U-238(N,F),,SIG) Normalized to U-238 cross-section 2120900200005 at 14 MeV. 2120900200006 SAMPLE .53 mg of natural uranium in the fission chamber. 2120900200007 ERR-ANALYS Declared by authors for pointer 1 2120900200008 Not specified for pointer 2 2120900200009 STATUS (TABLE) .Tables 2 and 3 of the publication. 2120900200010 HISTORY (20071219A) Errors specified 2120900200011 (20071219U) Last corrections have been done. 2120900200012 ENDBIB 10 0 2120900200013 COMMON 1 3 2120900200014 EN-NRM 2120900200015 MEV 2120900200016 1.4E+01 2120900200017 ENDCOMMON 3 0 2120900200018 DATA 5 14 2120900200019 EN DATA 1ERR-S 1DATA 2DATA-ERR 2 2120900200020 MEV ARB-UNITS ARB-UNITS B B 2120900200021 1.2700E+01 8.9000E-01 3.0000E-02 1.0100E+00 4.E-02 2120900200022 1.3000E+01 9.1000E-01 3.0000E-02 1.0300E+00 4.E-02 2120900200023 1.3500E+01 9.3000E-01 2.0000E-02 1.0500E+00 3.E-02 2120900200024 1.4000E+01 1.0000E+00 2.0000E-02 1.1300E+00 2.E-02 2120900200025 1.4500E+01 1.0400E+00 2.0000E-02 1.1800E+00 3.E-02 2120900200026 1.5000E+01 1.1100E+00 2.0000E-02 1.2500E+00 3.E-02 2120900200027 1.5400E+01 1.1100E+00 2.0000E-02 1.2500E+00 3.E-02 2120900200028 1.6000E+01 1.1300E+00 3.0000E-02 1.2800E+00 4.E-02 2120900200029 1.6400E+01 1.1900E+00 3.0000E-02 1.3400E+00 4.E-02 2120900200030 1.7000E+01 1.1500E+00 3.0000E-02 1.3000E+00 4.E-02 2120900200031 1.7500E+01 1.1800E+00 3.0000E-02 1.3300E+00 4.E-02 2120900200032 1.8400E+01 1.2000E+00 3.0000E-02 1.3600E+00 4.E-02 2120900200033 1.8900E+01 1.3000E+00 4.0000E-02 1.4700E+00 5.E-02 2120900200034 1.9400E+01 1.3100E+00 5.0000E-02 1.4800E+00 6.E-02 2120900200035 ENDDATA 16 0 2120900200036 ENDSUBENT 35 0 2120900299999 SUBENT 21209003 20071219 21902120900300001 BIB 5 10 2120900300002 REACTION 1((92-U-235(N,F),,SIG,,REL)/(92-U-238(N,F),,SIG,,REL)) 2120900300003 Normalized to unity at 14 MeV. 2120900300004 2(92-U-235(N,F),,SIG) 2120900300005 SAMPLE .80 mg enriched U-235 loaded in fission chamber. 2120900300006 Isotopic composition- U-235 (93.3 percent), 2120900300007 U-238 (5.5 percent), U-234 (1.2 percent). 2120900300008 ERR-ANALYS Declared by authors for pointer 1 2120900300009 Not specified for pointer 2 2120900300010 STATUS (TABLE) .Tables 2 and 3 of the publication. 2120900300011 HISTORY (20071219U) Last corrections have been done. 2120900300012 ENDBIB 10 0 2120900300013 COMMON 1 3 2120900300014 EN-NRM 2120900300015 MEV 2120900300016 1.4E+01 2120900300017 ENDCOMMON 3 0 2120900300018 DATA 5 13 2120900300019 EN DATA 1ERR-S 1DATA 2DATA-ERR 2 2120900300020 MEV ARB-UNITS ARB-UNITS B B 2120900300021 1.3200E+01 9.9000E-01 2.0000E-02 1.9000E+00 1.E-01 2120900300022 1.3500E+01 9.9000E-01 1.0000E-02 1.9800E+00 1.E-01 2120900300023 1.4000E+01 1.0000E+00 1.0000E-02 2.1300E+00 9.E-02 2120900300024 1.4400E+01 9.3000E-01 3.0000E-02 2.0600E+00 1.E-01 2120900300025 1.5300E+01 9.3000E-01 1.0000E-02 2.2100E+00 1.E-01 2120900300026 1.6000E+01 9.2000E-01 1.0000E-02 2.2200E+00 1.E-02 2120900300027 1.6500E+01 8.5000E-01 2.0000E-02 2.0700E+00 1.E-01 2120900300028 1.6900E+01 8.6000E-01 3.0000E-02 2.1100E+00 1.E-01 2120900300029 1.7400E+01 8.3000E-01 3.0000E-02 2.0500E+00 1.E-01 2120900300030 1.8000E+01 8.6000E-01 2.0000E-02 2.1700E+00 1.E-01 2120900300031 1.8400E+01 8.8000E-01 3.0000E-02 2.2700E+00 1.E-01 2120900300032 1.9000E+01 8.8000E-01 3.0000E-02 2.3200E+00 1.E-01 2120900300033 1.9400E+01 8.7000E-01 3.0000E-02 2.4300E+00 1.E-01 2120900300034 ENDDATA 15 0 2120900300035 ENDSUBENT 34 0 2120900399999 SUBENT 21209004 20071219 21902120900400001 BIB 5 10 2120900400002 REACTION 1((94-PU-239(N,F),,SIG,,REL)/(92-U-238(N,F),,SIG,,REL)) 2120900400003 Normalized to unity at 14 MeV. 2120900400004 2(94-PU-239(N,F),,SIG) 2120900400005 SAMPLE .20 mg Pu-239 loaded in fission counter. Isotopic 2120900400006 composition- Pu-239 (97.9 percent), Pu-240 (2.1 2120900400007 percent). 2120900400008 ERR-ANALYS Declared by authors for pointer 1 2120900400009 Not specified for pointer 2 2120900400010 STATUS .Data from tables 2 and 3 of the publication. 2120900400011 HISTORY (20071219U) Last checking has been done. 2120900400012 ENDBIB 10 0 2120900400013 COMMON 1 3 2120900400014 EN-NRM 2120900400015 MEV 2120900400016 1.4E+01 2120900400017 ENDCOMMON 3 0 2120900400018 DATA 5 13 2120900400019 EN DATA 1ERR-S 1DATA 2DATA-ERR 2 2120900400020 MEV ARB-UNITS ARB-UNITS B B 2120900400021 1.3400E+01 1.0100E+00 2.0000E-02 2.4800E+00 1.0E-01 2120900400022 1.4000E+01 1.0000E+00 1.0000E-02 2.6100E+00 8.0E-02 2120900400023 1.4400E+01 9.7000E-01 2.0000E-02 2.6400E+00 1.0E-01 2120900400024 1.4900E+01 9.1000E-01 2.0000E-02 2.5800E+00 1.1E-01 2120900400025 1.5300E+01 9.2000E-01 2.0000E-02 2.6600E+00 1.1E-01 2120900400026 1.6000E+01 8.6000E-01 2.0000E-02 2.5400E+00 1.1E-01 2120900400027 1.6500E+01 8.4000E-01 2.0000E-02 2.5200E+00 1.1E-01 2120900400028 1.6900E+01 8.3000E-01 2.0000E-02 2.5000E+00 1.1E-01 2120900400029 1.7500E+01 8.2000E-01 3.0000E-02 2.5100E+00 1.3E-01 2120900400030 1.8000E+01 7.9000E-01 3.0000E-02 2.4500E+00 1.3E-01 2120900400031 1.8400E+01 7.9000E-01 3.0000E-02 2.5000E+00 1.3E-01 2120900400032 1.9000E+01 7.6000E-01 3.0000E-02 2.4800E+00 1.3E-01 2120900400033 1.9400E+01 7.6000E-01 3.0000E-02 2.6100E+00 1.5E-01 2120900400034 ENDDATA 15 0 2120900400035 ENDSUBENT 34 0 2120900499999 ENDENTRY 4 0 2120999999999