ENTRY 13810 20110927 13751381000000001 SUBENT 13810001 20110927 13751381000100001 BIB 14 24 1381000100002 INSTITUTE (1USAANL) 1381000100003 REFERENCE (J,PR,87,1034,195209) 1381000100004 AUTHOR (D.L.Hill) 1381000100005 TITLE The Neutron Energy Spectrum from U235 Thermal Fission 1381000100006 FACILITY (REAC) Argonne heavy water reactor. 1381000100007 INC-SOURCE (THCOL) 1381000100008 INC-SPECT Thermal neutrons 1381000100009 SAMPLE Flat circular plate of natural or enriched uranium 1381000100010 metal or oxide. 1381000100011 METHOD (REC) Measured recoil protons from paraffin detector 1381000100012 chamber. 1381000100013 DETECTOR (COIN) Ranger detector containing two parallel coaxial 1381000100014 disks: 1) a layer of paraffin mounted on an aluminum 1381000100015 plate; 2) an interface between three coincidence and 1381000100016 one anticoincidence counter. 1381000100017 MONITOR Detector counts normalized to neutron source strength 1381000100018 using a fission counter in coincidence with Ranger 1381000100019 detector. 1381000100020 CORRECTION Corrected for background, floor scattered neutrons and 1381000100021 neutrons doubly scattered in chamber. 1381000100022 STATUS (TABLE) Data taken from Table II in reference. 1381000100023 HISTORY (20010622C) 1381000100024 (20110915A) OS. BIB corrections, REACTION code 1381000100025 corrected 1381000100026 ENDBIB 24 0 1381000100027 NOCOMMON 0 0 1381000100028 ENDSUBENT 27 0 1381000199999 SUBENT 13810002 20110927 13751381000200001 BIB 5 9 1381000200002 REACTION (92-U-235(N,F),,NU/DE,,MXW/REL) 1381000200003 ASSUMED (ASSUM,1-H-1(N,EL)1-H-1,,SIG) 1381000200004 ANALYSIS Data from six studies using two different samples and 1381000200005 four paraffin thicknesses were normalized to a common 1381000200006 source strength and paraffin/effective detector 1381000200007 thickness. 1381000200008 ERR-ANALYS (ERR-S) Statistical uncertainty given. 1381000200009 HISTORY (20110915A) OS. REACTION code corrected, units changed 1381000200010 to ARB-UNITS. 1381000200011 ENDBIB 9 0 1381000200012 COMMON 1 3 1381000200013 EN-DUMMY 1381000200014 EV 1381000200015 0.0253 1381000200016 ENDCOMMON 3 0 1381000200017 DATA 4 38 1381000200018 E DATA ERR-S ASSUM 1381000200019 MEV ARB-UNITS PER-CENT B 1381000200020 0.400 5.7 4. 7.20 1381000200021 0.525 6.6 6. 6.16 1381000200022 0.635 7.3 5. 5.65 1381000200023 0.725 5.4 7. 5.32 1381000200024 0.790 6.8 7. 5.11 1381000200025 0.865 7.0 7. 4.91 1381000200026 0.945 5.8 10. 4.67 1381000200027 1.000 6.2 2. 4.59 1381000200028 1.030 6.3 10. 4.47 1381000200029 1.095 6.2 11. 4.30 1381000200030 1.160 4.9 15. 4.15 1381000200031 1.215 6.9 12. 4.07 1381000200032 1.26 6.0 2. 4.00 1381000200033 1.49 5.6 2. 3.6 1381000200034 1.70 5.7 3. 3.4 1381000200035 1.88 5.53 2. 3.20 1381000200036 2.04 4.61 3. 3.05 1381000200037 2.20 4.03 3. 2.92 1381000200038 2.20 4.03 2. 2.92 1381000200039 2.36 4.07 3. 2.81 1381000200040 2.50 3.24 4. 2.71 1381000200041 2.64 3.15 4. 2.62 1381000200042 2.77 2.46 6. 2.53 1381000200043 2.80 2.85 3. 2.51 1381000200044 3.32 2.23 5. 2.26 1381000200045 3.76 1.52 8. 2.09 1381000200046 4.15 1.20 12. 1.95 1381000200047 4.55 0.83 13. 1.83 1381000200048 4.87 0.90 7. 1.75 1381000200049 4.91 0.94 19. 1.74 1381000200050 5.23 0.74 30. 1.65 1381000200051 5.57 0.58 25. 1.57 1381000200052 5.80 0.86 27. 1.53 1381000200053 5.9 0.63 10. 1.49 1381000200054 6.11 0.47 3. 1.47 1381000200055 6.11 0.21 15. 1.47 1381000200056 6.43 0.31 7. 1.41 1381000200057 6.44 0.16 21. 1.41 1381000200058 ENDDATA 40 0 1381000200059 ENDSUBENT 58 0 1381000299999 ENDENTRY 2 0 1381099999999