ENTRY 40201 20151126 41734020100000001 SUBENT 40201001 20151126 41734020100100001 BIB 12 34 4020100100002 TITLE Cross section and angular anisotropy of Cf-249 fission 4020100100003 in the neutron-energy range 0.5- 7.0 MeV 4020100100004 AUTHOR (B.I.Fursov,V.I.Ivanov,G.N.Smirenkin) 4020100100005 INSTITUTE (4RUSFEI) 4020100100006 REFERENCE (J,SNP,19,25,1974) Eng.transl.of YF,19,(1),50,1974 4020100100007 (J,YF,19,(1),50,1974) Data were taken from the article 4020100100008 FACILITY (VDG,4RUSFEI) Van de Graaff 4020100100009 DETECTOR (GLASD) Glass detectors for fission fragments 4020100100010 (SOLST) Semiconductor detector for alpha-activity of 4020100100011 samples. 4020100100012 INC-SOURCE (P-T) Proton-tritium 4020100100013 (D-D) Deuteron-deuterium 4020100100014 SAMPLE Cf-249 sample with 4 mm diameter, ~3 microg weight 4020100100015 californium on the platinum backing with the Cf-252 4020100100016 content up to 2*10**(-6) % . 4020100100017 Distance neutron-source - Cf249-sample 50mm, 4020100100018 Cf249-sample - detector 40mm. 4020100100019 Spontaneous fission < 10%. 4020100100020 Pu-239 sample, Pu-239 content 99.8% , attached to 4020100100021 Cf249 sample. 4020100100022 Ratio of nuclei numbers in Cf and Pu layers was 4020100100023 measured by alpha-activity by means of semiconductor 4020100100024 detector and usage of following half-lives: 4020100100025 DECAY-DATA (94-PU-239,2.438E+4YR) (2.438+-0.005)*10**4 yr 4020100100026 (98-CF-249,352.YR) 352+-6 yr. 4020100100027 PART-DET (FF) Fission fragments 4020100100028 STATUS (TABLE) Table from YF,19,(1),50,1974 4020100100029 HISTORY (19740220C) Compiled at the centre 4020100100030 (19860707U) Some minor corrections made 4020100100031 (20150109A) SD: Updated to new date formats,lower case.4020100100032 Ref. on Engl.transl. of YF added. Minor corrections. 4020100100033 (20151126A) M.M. Article was checked. BIB information 4020100100034 was updated in TITLE,DETECTOR,SAMPLE,ERR-ANALYS, 4020100100035 ANALYSIS. DECAY-DATA were added. 4020100100036 ENDBIB 34 0 4020100100037 NOCOMMON 0 0 4020100100038 ENDSUBENT 37 0 4020100199999 SUBENT 40201002 20151126 41734020100200001 BIB 3 12 4020100200002 REACTION ((98-CF-249(N,F),,SIG)/(94-PU-239(N,F),,SIG)) 4020100200003 CORRECTION Corrections were introduced on the fragments angular 4020100200004 anisotropy and samples-neutron source distances 4020100200005 ERR-ANALYS (ERR-T) Total error consist of 4020100200006 (ERR-1) Cf-249 and Pu-239 nuclei numbers ratio error, 4020100200007 including alpha-decay constants error, 4020100200008 (ERR-S,1.0,2.5) statistical error, 4020100200009 (ERR-2) error in scanning the glass detectors, 4020100200010 (ERR-3) neutron background estimation error, 4020100200011 (ERR-4) Cf-249 spontaneous fission estimate error, 4020100200012 (ERR-5) another isotopes fission contribution error,4020100200013 (ERR-6) correction error 4020100200014 ENDBIB 12 0 4020100200015 COMMON 6 3 4020100200016 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 4020100200017 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4020100200018 2.5 .5 1. 0.2 .1 .3 4020100200019 ENDCOMMON 3 0 4020100200020 DATA 4 13 4020100200021 EN EN-ERR DATA ERR-T 4020100200022 MEV MEV NO-DIM NO-DIM 4020100200023 0.50 0.090 1.011 0.060 4020100200024 0.75 0.080 0.870 0.054 4020100200025 0.85 0.075 0.790 0.050 4020100200026 1.10 0.075 0.875 0.055 4020100200027 1.45 0.070 0.875 0.057 4020100200028 2.00 0.070 1.022 0.063 4020100200029 2.70 0.070 1.053 0.070 4020100200030 3.30 0.070 1.063 0.072 4020100200031 4.00 0.100 1.042 0.070 4020100200032 4.50 0.100 1.044 0.071 4020100200033 5.02 0.100 1.093 0.066 4020100200034 6.00 0.100 1.123 0.067 4020100200035 7.00 0.100 0.959 0.050 4020100200036 ENDDATA 15 0 4020100200037 ENDSUBENT 36 0 4020100299999 SUBENT 40201003 20151126 41734020100300001 BIB 5 11 4020100300002 REACTION (98-CF-249(N,F),,SIG) Cf-249 fission cross-section 4020100300003 MONITOR (94-PU-239(N,F),,SIG) Pu-239 fission 4020100300004 cross-section taken from 4020100300005 Third Conf. Neutron Cross-Section and Technology, 4020100300006 University of Tennessee, Knoxville, USA, 1971, T.Byer,4020100300007 V.Konshin . 4020100300008 STATUS (DEP,40201002) Measured ratio in Subent 002. 4020100300009 ANALYSIS Data were obtained by multiplication of measured ratio 4020100300010 ( Subent 40201002) by standard cross-section 4020100300011 ERR-ANALYS (DATA-ERR) Data-error does not include the standard 4020100300012 error 4020100300013 ENDBIB 11 0 4020100300014 NOCOMMON 0 0 4020100300015 DATA 5 13 4020100300016 EN EN-ERR DATA DATA-ERR MONIT 4020100300017 MEV MEV B B B 4020100300018 0.50 0.090 1.602 0.095 1.585 4020100300019 0.75 0.080 1.422 0.088 1.635 4020100300020 0.85 0.075 1.319 0.084 1.670 4020100300021 1.10 0.075 1.575 0.100 1.800 4020100300022 1.45 0.070 1.684 0.110 1.925 4020100300023 2.00 0.070 2.024 0.125 1.980 4020100300024 2.70 0.070 2.038 0.135 1.935 4020100300025 3.30 0.070 1.993 0.135 1.875 4020100300026 4.00 0.100 1.865 0.125 1.790 4020100300027 4.50 0.100 1.822 0.124 1.745 4020100300028 5.02 0.100 1.880 0.114 1.720 4020100300029 6.00 0.100 2.044 0.122 1.820 4020100300030 7.00 0.100 1.961 0.102 2.045 4020100300031 ENDDATA 15 0 4020100300032 ENDSUBENT 31 0 4020100399999 SUBENT 40201004 20151126 41734020100400001 BIB 4 10 4020100400002 REACTION (98-CF-249(N,F),,DA,FF,RSD) Angular distribution 4020100400003 of fission fragments at 0 deg relative to 90 deg 4020100400004 W(0deg)/W(90deg) . 4020100400005 ANALYSIS Angular distribution was described as 4020100400006 sigma=1+a2*cos(theta)**2 and fitting was done by least 4020100400007 squares method . 4020100400008 ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained. 4020100400009 HISTORY (20151125A) M.M. COS/RSD -> RSD , ANALYSIS and free 4020100400010 text were corrected. NUMBER was deleted, 4020100400011 ANG=0 deg was added. 4020100400012 ENDBIB 10 0 4020100400013 COMMON 1 3 4020100400014 ANG 4020100400015 ADEG 4020100400016 0. 4020100400017 ENDCOMMON 3 0 4020100400018 DATA 4 13 4020100400019 EN EN-ERR DATA DATA-ERR 4020100400020 MEV MEV NO-DIM NO-DIM 4020100400021 0.50 0.090 1.132 0.062 4020100400022 0.75 0.080 1.022 0.039 4020100400023 0.85 0.075 1.167 0.052 4020100400024 1.10 0.075 1.091 0.060 4020100400025 1.45 0.070 1.058 0.056 4020100400026 2.00 0.070 1.076 0.066 4020100400027 2.70 0.070 1.059 0.116 4020100400028 3.30 0.070 1.214 0.132 4020100400029 4.00 0.100 1.150 0.049 4020100400030 4.50 0.100 1.186 0.028 4020100400031 5.02 0.100 1.134 0.062 4020100400032 6.00 0.100 1.125 0.065 4020100400033 7.00 0.100 1.139 0.015 4020100400034 ENDDATA 15 0 4020100400035 ENDSUBENT 34 0 4020100499999 ENDENTRY 4 0 4020199999999