ENTRY 21560 20201222 22962156000000001 SUBENT 21560001 20201222 22962156000100001 BIB 11 31 2156000100002 TITLE The mass distribution of neutron induced fission 2156000100003 for 239Pu at the 0.297 eV resonance 2156000100004 AUTHOR (P.H.M.Van Assche,G.Vandenput,L.Jacobs, 2156000100005 J.M.Van Den Cruyce,R.Silvernans) 2156000100006 INSTITUTE (2BLGMOL,2BLGLVN) 2156000100007 REFERENCE (R,RCN-203,95,1973) Report and table. 2156000100008 (C,73ROCH,2,492,1973) Short description 2156000100009 (P,INDC(SEC)-43,30,1974) Short description 2156000100010 ((P,NEANDC(E)-161,191,1974)=(P,INDC(EUR)-7,191,1974)) 2156000100011 - Short description, data on figure 2156000100012 (P,INDC(SEC)-36,31,1973) Short abstract 2156000100013 FACILITY (REAC,2BLGMOL) BR2 reactor, Mol. 2156000100014 INC-SOURCE (REAC) Reactor neutrons. 2156000100015 SAMPLE Samples of 10 mg Pu/Al alloys with 20% Pu meta 2156000100016 enriched to 93% in Pu-239. A fission density 2156000100017 of 7. x 10**8 was reached. 2156000100018 METHOD (ACTIV) Gamma spectra of unseparated fission products 2156000100019 taken from 10 minutes to a few weeks after the 2156000100020 irradiation were compared in intensity with those 2156000100021 for thermal fission. 2156000100022 DETECTOR (GELI) 20 cm*3 active volume coaxial Ge(Li) detector. 2156000100023 An energy resolution of 1.6 keV at 100 keV and 2.7 keV 2156000100024 at 1 MeV was obtained. 2156000100025 ERR-ANALYS (DATA-ERR) One standard deviation, no details. 2156000100026 HISTORY (19800606C) 2156000100027 (19800729A) Decay-data in subwork 002 corrected. 2156000100028 (20070926A) Date is corrected. Bib information in 2156000100029 SAN 002 corrected/added 2156000100030 (20071001U) Last checking has been done. 2156000100031 (20201221U) SD: Ref. INDC(SEC)-36 added. Cosmetic 2156000100032 corrections. 2156000100033 ENDBIB 31 0 2156000100034 NOCOMMON 0 0 2156000100035 ENDSUBENT 34 0 2156000199999 SUBENT 21560002 20071001 21872156000200001 BIB 6 29 2156000200002 REACTION ((94-PU-239(N,F)MASS,CHN,FY,,SPA)// 2156000200003 (94-PU-239(N,F)MASS,CHN,FY,,MXW)) Ratio of yields at 2156000200004 resonance 0.297 eV averaged over resonance to 2156000200005 thermal yield 2156000200006 INC-SPECT .A samarium filter, O,29 g/cm*2 thick, was used to 2156000200007 remove thermal neutrons below 0.25 eV, giving a 2156000200008 spectrum in which more than 90 percent of fissions 2156000200009 are produced by neutrons in the 0.297 eV resonance. 2156000200010 .Ratios are measured to fission yields in a 2156000200011 maxwellian thermal neutron spectrum. 2156000200012 ANALYSIS .All ratios are normalised to unity for mass 97. 2156000200013 DECAY-DATA ((1.)36-KR-87,81.MIN,DG,402.7) 2156000200014 ((2.)36-KR-88,3.HR,DG,196.2) 2156000200015 ((3.)40-ZR-97,17.HR,DG,743.3) 2156000200016 ((3.)41-NB-97,74.MIN,DG,658.2) 2156000200017 ((4.)44-RU-105,4.5HR,DG,724.4) 2156000200018 ((4.)45-RH-105,36.5HR,DG,306.2) 2156000200019 ((5.)45-RH-107,21.MIN,DG,302.6) 2156000200020 ((6.)47-AG-111,6.7D,DG,341.0) 2156000200021 ((7.)49-IN-115-M,4.5HR,DG,336.0) 2156000200022 ((8.)51-SB-127,3.9D,DG,685.7) 2156000200023 ((9.)51-SB-128-M,10.MIN,DG,754.2) 2156000200024 ((10.)51-SB-129,4.4HR,DG,812.6) 2156000200025 ((11.)57-LA-140,40.HR,DG,487.2,,DG,1595.3) 2156000200026 ((12.)61-PM-149,2.2D,DG,284.8) 2156000200027 STATUS (TABLE) Table 1, RCN-203, page 96. 2156000200028 HISTORY (20071001U) RATIO to DATA, ARB-UNITS to NO-DIM 2156000200029 changed. 2156000200030 (20071001U) Last corrections have been done. 2156000200031 ENDBIB 29 0 2156000200032 COMMON 2 3 2156000200033 EN-MEAN-NM EN-MEAN-DN 2156000200034 EV EV 2156000200035 2.97E-01 2.5E-02 2156000200036 ENDCOMMON 3 0 2156000200037 DATA 4 12 2156000200038 MASS DATA DATA-ERR DECAY-FLAG 2156000200039 NO-DIM NO-DIM NO-DIM NO-DIM 2156000200040 8.7000E+01 8.9900E-01 3.0E-02 1. 2156000200041 8.8000E+01 9.7300E-01 3.8E-02 2. 2156000200042 9.7000E+01 1.0000E+00 1.2E-02 3. 2156000200043 1.0500E+02 9.9200E-01 1.4E-02 4. 2156000200044 1.0700E+02 9.3500E-01 3.7E-02 5. 2156000200045 1.1100E+02 7.7100E-01 2.5E-02 6. 2156000200046 1.1500E+02 6.5900E-01 4.5E-02 7. 2156000200047 1.2700E+02 8.1900E-01 5.6E-02 8. 2156000200048 1.2800E+02 9.4000E-01 3.3E-02 9. 2156000200049 1.2900E+02 9.9800E-01 2.5E-02 10. 2156000200050 1.4000E+02 1.0100E+00 2.5E-02 11. 2156000200051 1.4900E+02 9.8000E-01 3.6E-02 12. 2156000200052 ENDDATA 14 0 2156000200053 ENDSUBENT 52 0 2156000299999 ENDENTRY 2 0 2156099999999