ENTRY 21075 20101114 22252107500000001 SUBENT 21075001 20101114 22252107500100001 BIB 11 27 2107500100002 INSTITUTE (2UK HAR) 2107500100003 REFERENCE (J,PPS/A,70,573,1957) 2107500100004 (J,PPS/A,70,639,1957) neutron flux measurement. 2107500100005 (J,PHY,22,1187(125),195611) Abstract. 2107500100006 AUTHOR (W.D.Allen,A.T.G.Ferguson) 2107500100007 TITLE -The fission cross sections of U-233, U-235, U-238 2107500100008 and Pu-239 for neutrons in the energy range 0.030 2107500100009 MeV to 3.0 MeV-. 2107500100010 FACILITY (CCW,2UK HAR) Electrostatic generator. 2107500100011 INC-SOURCE (P-LI7) Proton bombardment of lithium. 2107500100012 (P-T ) Proton bombardment of tritium at up to 4.5MeV. 2107500100013 Both gas targets and zirconium tritide. 2107500100014 DETECTOR (IOCH ) Back to back ionisation chamber. 2107500100015 MONITOR (1-H-1(N,EL)1-H-1,,SIG) Proton recoil counter for 2107500100016 neutron flux measurement, PPS/A,70,639. 2107500100017 STATUS (NDD ) 2107500100018 ERR-ANALYS (ERR-1) Normalisation error from neutron flux 2107500100019 about 3% at one standard deviation. 2107500100020 (ERR-S) Statistical error. 2107500100021 HISTORY (19790824T) 2107500100022 (19790918E) 2107500100023 (19810505A) ERR-ANALYS changed. 2107500100024 (19810722E) 2107500100025 (20101114A) SD:Updated to new date formats,lower case. 2107500100026 corrected according to last EXFOR rules and Dict. 2107500100027 Ref.correctd: PHY,22,1187,.. => PHY,22,1187(125),.2107500100028 Description of targets was added. 2107500100029 ENDBIB 27 0 2107500100030 COMMON 1 3 2107500100031 ERR-1 2107500100032 PER-CENT 2107500100033 3.0000E+00 2107500100034 ENDCOMMON 3 0 2107500100035 ENDSUBENT 34 0 2107500199999 SUBENT 21075002 20101114 22252107500200001 BIB 3 4 2107500200002 REACTION (92-U-233(N,F),,SIG) 2107500200003 SAMPLE .The stock material was better than 99% of 233U pure 2107500200004 chemically and isotopically. Four foils were used. 2107500200005 STATUS (NDD ) 2107500200006 ENDBIB 4 0 2107500200007 COMMON 1 3 2107500200008 EN-NRM 2107500200009 KEV 2107500200010 5.5000E+02 2107500200011 ENDCOMMON 3 0 2107500200012 DATA 3 25 2107500200013 EN DATA ERR-S 2107500200014 MEV B B 2107500200015 3.0000E-02 4.0000E+00 1.2000E-01 2107500200016 6.0000E-02 3.1800E+00 1.0000E-01 2107500200017 8.0000E-02 2.9100E+00 9.0000E-02 2107500200018 1.2000E-01 2.2800E+00 5.0000E-02 2107500200019 1.5000E-01 2.3500E+00 7.0000E-02 2107500200020 1.7500E-01 2.1900E+00 2.0000E-02 2107500200021 2.0000E-01 2.3000E+00 7.0000E-02 2107500200022 2.2000E-01 2.2600E+00 3.0000E-02 2107500200023 2.4000E-01 2.1700E+00 4.0000E-02 2107500200024 2.7500E-01 2.2600E+00 2.0000E-02 2107500200025 3.0000E-01 2.3000E+00 7.0000E-02 2107500200026 3.3000E-01 2.2700E+00 6.0000E-02 2107500200027 3.5000E-01 2.3200E+00 2.0000E-02 2107500200028 4.0000E-01 2.2200E+00 4.0000E-02 2107500200029 4.4500E-01 2.1500E+00 2.0000E-02 2107500200030 4.8000E-01 2.0300E+00 3.0000E-02 2107500200031 5.0000E-01 2.0600E+00 3.0000E-02 2107500200032 5.5000E-01 2.0000E+00 2.0000E-02 2107500200033 6.5000E-01 1.9500E+00 2.0000E-02 2107500200034 1.0000E+00 1.9000E+00 2.0000E-02 2107500200035 1.5000E+00 1.9100E+00 2.0000E-02 2107500200036 1.8000E+00 1.9100E+00 4.0000E-02 2107500200037 2.0000E+00 1.9000E+00 4.0000E-02 2107500200038 2.5000E+00 1.8200E+00 5.0000E-02 2107500200039 3.0000E+00 1.6500E+00 5.0000E-02 2107500200040 ENDDATA 27 0 2107500200041 ENDSUBENT 40 0 2107500299999 SUBENT 21075003 20101114 22252107500300001 BIB 3 4 2107500300002 REACTION (92-U-235(N,F),,SIG) 2107500300003 SAMPLE .The 235U stock material contained 80% 235U, 1% 234U, 2107500300004 and 19.% 238U. 2107500300005 STATUS (NDD ) 2107500300006 ENDBIB 4 0 2107500300007 COMMON 1 3 2107500300008 EN-NRM 2107500300009 KEV 2107500300010 5.5000E+02 2107500300011 ENDCOMMON 3 0 2107500300012 DATA 3 25 2107500300013 EN DATA ERR-S 2107500300014 MEV B B 2107500300015 3.0000E-02 2.7200E+00 8.0000E-02 2107500300016 6.0000E-02 2.3200E+00 5.0000E-02 2107500300017 1.2000E-01 1.6500E+00 3.0000E-02 2107500300018 1.5000E-01 1.6800E+00 5.0000E-02 2107500300019 1.7500E-01 1.5100E+00 2.0000E-02 2107500300020 2.0000E-01 1.4700E+00 5.0000E-02 2107500300021 2.2000E-01 1.4800E+00 3.0000E-02 2107500300022 2.4000E-01 1.4200E+00 3.0000E-02 2107500300023 2.7500E-01 1.8300E+00 2.0000E-02 2107500300024 3.0000E-01 1.3800E+00 4.0000E-02 2107500300025 3.3000E-01 1.3700E+00 3.0000E-02 2107500300026 3.5000E-01 1.4400E+00 3.0000E-02 2107500300027 4.0000E-01 1.3400E+00 3.0000E-02 2107500300028 4.1500E-01 1.2900E+00 2.0000E-02 2107500300029 4.4500E-01 1.3200E+00 2.0000E-02 2107500300030 4.8000E-01 1.2500E+00 2.0000E-02 2107500300031 5.0000E-01 1.2600E+00 2.0000E-02 2107500300032 5.5000E-01 1.2700E+00 2.0000E-02 2107500300033 6.5000E-01 1.1900E+00 2.0000E-02 2107500300034 1.0000E+00 1.2200E+00 2.0000E-02 2107500300035 1.5000E+00 1.3300E+00 2.0000E-02 2107500300036 1.8000E+00 1.3800E+00 2.0000E-02 2107500300037 2.0000E+00 1.3700E+00 3.0000E-02 2107500300038 2.5000E+00 1.3900E+00 3.0000E-02 2107500300039 3.0000E+00 1.1800E+00 4.0000E-02 2107500300040 ENDDATA 27 0 2107500300041 ENDSUBENT 40 0 2107500399999 SUBENT 21075004 20101114 22252107500400001 BIB 3 5 2107500400002 REACTION (92-U-238(N,F),,SIG) 2107500400003 SAMPLE .For relative measurements, 238U whose 235 U content 2107500400004 had been depleted by a factor of 40, was used. 2107500400005 .For absolute measurements, natural uranium was used. 2107500400006 STATUS (NDD ) 2107500400007 ENDBIB 5 0 2107500400008 NOCOMMON 0 0 2107500400009 DATA 3 6 2107500400010 EN DATA ERR-S 2107500400011 MEV B B 2107500400012 1.0000E+00 1.8000E-02 1.0000E-03 2107500400013 1.3300E+00 6.6000E-02 4.0000E-03 2107500400014 1.5000E+00 3.2000E-01 2.0000E-02 2107500400015 2.0000E+00 5.0000E-01 3.0000E-02 2107500400016 2.5000E+00 4.8000E-01 2.0000E-02 2107500400017 3.0000E+00 4.3000E-01 2.0000E-02 2107500400018 ENDDATA 8 0 2107500400019 ENDSUBENT 18 0 2107500499999 SUBENT 21075005 20101114 22252107500500001 BIB 3 4 2107500500002 REACTION (94-PU-239(N,F),,SIG) 2107500500003 SAMPLE .Two foils of plutonium were used in which the mass 2107500500004 of 239Pu determined by alpha-counting. 2107500500005 STATUS (NDD ) 2107500500006 ENDBIB 4 0 2107500500007 COMMON 1 3 2107500500008 EN-NRM 2107500500009 KEV 2107500500010 5.5000E+02 2107500500011 ENDCOMMON 3 0 2107500500012 DATA 3 22 2107500500013 EN DATA ERR-S 2107500500014 MEV B B 2107500500015 3.0000E-02 2.2500E+00 6.0000E-02 2107500500016 6.0000E-02 1.9800E+00 4.0000E-02 2107500500017 8.0000E-02 1.8400E+00 6.0000E-02 2107500500018 1.2000E-01 1.5900E+00 3.0000E-02 2107500500019 1.5000E-01 1.7300E+00 6.0000E-02 2107500500020 1.7500E-01 1.5500E+00 2.0000E-02 2107500500021 2.0000E-01 1.5600E+00 3.0000E-02 2107500500022 2.2000E-01 1.6400E+00 3.0000E-02 2107500500023 2.4000E-01 1.5400E+00 3.0000E-02 2107500500024 2.7500E-01 1.6500E+00 2.0000E-02 2107500500025 3.0000E-01 1.6700E+00 3.0000E-02 2107500500026 3.3000E-01 1.6500E+00 3.0000E-02 2107500500027 3.5000E-01 1.8000E+00 3.0000E-02 2107500500028 4.4500E-01 1.6800E+00 2.0000E-02 2107500500029 5.0000E-01 1.6800E+00 3.0000E-02 2107500500030 5.5000E-01 1.6800E+00 2.0000E-02 2107500500031 6.5000E-01 1.6800E+00 2.0000E-02 2107500500032 1.0000E+00 1.8000E+00 2.0000E-02 2107500500033 1.5000E+00 1.9300E+00 2.0000E-02 2107500500034 2.0000E+00 1.8300E+00 4.0000E-02 2107500500035 2.5000E+00 1.8300E+00 5.0000E-02 2107500500036 3.0000E+00 1.6700E+00 6.0000E-02 2107500500037 ENDDATA 24 0 2107500500038 ENDSUBENT 37 0 2107500599999 ENDENTRY 5 0 2107599999999