ENTRY 14064 20140416 14011406400000001 SUBENT 14064001 20140416 14011406400100001 BIB 11 22 1406400100002 INSTITUTE (1USABRK) 1406400100003 REFERENCE (J,PR,97,564,1955) 1406400100004 AUTHOR (D.A.Hicks,J.Ise,R.V.Pyle) 1406400100005 TITLE Multiplicity of neutrons from the spontaneous fission 1406400100006 of californium-252 1406400100007 SAMPLE Cf-252 sample with about 300 spontaneous fission per 1406400100008 minute 1406400100009 METHOD (PHD) 1406400100010 DETECTOR (STANK) Cylindrical tank of cadmium-loaded liquid 1406400100011 scintillator. The 8494 fissions reported here gave an 1406400100012 average of 1.43 neutrons, from which we conclude that 1406400100013 our detection efficiency was 46.0+-2.8% (probable 1406400100014 error) for this measurement. 1406400100015 (IOCH) Fission chamber 1406400100016 MONITOR (98-CF-252(0,F),PR,NU) - for detection efficiency 1406400100017 MONIT-REF (13717002,W.W.T.Crane+,J,PR,101,1804,1956) 1406400100018 PART-DET (N) 1406400100019 HISTORY (20051215C) DR 1406400100020 (20060331C) DR Format corrected (line 14064002 4) 1406400100021 (20120812U) SD: INC-SOURCE was deleted. 1406400100022 (20140416A) SD: REACTION code in Subent 2 corrected. 1406400100023 Subent 3 added. 1406400100024 ENDBIB 22 0 1406400100025 COMMON 2 3 1406400100026 MONIT MONIT-ERR 1406400100027 PRT/FIS PRT/FIS 1406400100028 3.10 0.18 1406400100029 ENDCOMMON 3 0 1406400100030 ENDSUBENT 29 0 1406400199999 SUBENT 14064002 20140416 14011406400200001 BIB 4 6 1406400200002 REACTION (98-CF-252(0,F),NUM,NU) 1406400200003 Neutron distribution probability 1406400200004 ERR-ANALYS (DATA-ERR) No information 1406400200005 STATUS (CURVE) Data taken from Fig. 1 of PR,97,564,1955 1406400200006 HISTORY (20140416A) SD: SF4=NPART deleted in REACTION code. 1406400200007 MONIT-REF, MONIT added. 1406400200008 ENDBIB 6 0 1406400200009 NOCOMMON 0 0 1406400200010 DATA 3 7 1406400200011 PART-OUT DATA DATA-ERR 1406400200012 NO-DIM NO-DIM NO-DIM 1406400200013 0.00E+00 1.87E-01 2.57E-03 1406400200014 1.00E+00 3.77E-01 3.61E-03 1406400200015 2.00E+00 2.88E-01 3.61E-03 1406400200016 3.00E+00 1.18E-01 3.60E-03 1406400200017 4.00E+00 2.56E-02 2.57E-03 1406400200018 5.00E+00 3.37E-03 1406400200019 6.00E+00 1.16E-03 1406400200020 ENDDATA 9 0 1406400200021 ENDSUBENT 20 0 1406400299999 SUBENT 14064003 20140416 14011406400300001 BIB 5 6 1406400300002 REACTION (98-CF-252(0,F),NUM,NU,,REL) 1406400300003 Neutron multiplicities 1406400300004 CORRECTION A correction has been made for a background of 0.75% 1406400300005 ERR-ANALYS No information 1406400300006 STATUS (TABLE) Data taken from Tbl. 1 of PR,97,564,1955 1406400300007 HISTORY (20140416C) SD 1406400300008 ENDBIB 6 0 1406400300009 NOCOMMON 0 0 1406400300010 DATA 2 7 1406400300011 PART-OUT DATA 1406400300012 NO-DIM ARB-UNITS 1406400300013 0.00E+00 1596. 1406400300014 1.00E+00 3200. 1406400300015 2.00E+00 2445. 1406400300016 3.00E+00 1001. 1406400300017 4.00E+00 214. 1406400300018 5.00E+00 33. 1406400300019 6.00E+00 5. 1406400300020 ENDDATA 9 0 1406400300021 ENDSUBENT 20 0 1406400399999 ENDENTRY 3 0 1406499999999