ENTRY 41495 20150225 41684149500000001 SUBENT 41495001 20150225 41684149500100001 BIB 13 66 4149500100002 TITLE Method and setup for investigation of energy 4149500100003 dependence of delayed neutron parameters at nucleus 4149500100004 fission by neutrons from reactions T(p,n), D(d,n), 4149500100005 T(d,n). 4149500100006 AUTHOR (V.M.Piksaikin,N.N.Semenova,V.I.Mil'Shin,V.A.Roschenko,4149500100007 G.G.Korolev) 4149500100008 INSTITUTE (4RUSFEI) 4149500100009 REFERENCE (J,PTE,,(6),29,2006) Main reference 4149500100010 (J,IET,49,(6),765,200612) Eng.translation of PTE,6,29 4149500100011 #doi:10.1134/S0020441206060030 4149500100012 (R,INDC(NDS)-0646,2013) In English. 4149500100013 REL-REF (N,,V.M.Piksaikin+,R,INDC(CCP)-422,199908) Analysis 4149500100014 details 4149500100015 (R,,M.Drosg+,R,IAEA-273,8,1987)Handbook IAEA-TECDOC-2734149500100016 on nuclear activation data.For data of double differen.4149500100017 c-s of reactions T(d,n)He-4, T(p,n)He-3, D(d,n)He-3 . 4149500100018 FACILITY (VDG,4RUSFEI) Cascade Generator CG-2.5 4149500100019 INC-SOURCE (D-T) T(d,n)He-4 for monoenergetic neutrons from 14.23 4149500100020 to 17.98 MeV. 4149500100021 (P-T) T(p,n)He-3 for monoenergetic neutrons from 0.37 4149500100022 to 1.1 MeV. 4149500100023 (D-D) D(d,n)He-3 for monoenergetic neutrons from 3.25 4149500100024 to 4.72 MeV. 4149500100025 Polyethylene cube near target - for epithermal neutrons4149500100026 of 2.85 eV. 4149500100027 DETECTOR (FISCH) Two fission (with Np-237 or Pu-239 oxide layers4149500100028 of 100 microg/cm**2 thickness on aluminum backing of 4149500100029 0.2 mm thickness and 20 mm diameter, filled by mixture4149500100030 of CO2 - 10% and Ar - 90%) chambers near sample for 4149500100031 neutron beam monitoring. Average efficiency of fission4149500100032 fragments registration - 98%. 4149500100033 (LONGC) Long counter made on the base of boron counter 4149500100034 SNM-P was used for neutron beam stability control. 4149500100035 (SIBAR)Surface barrier detectors for alpha registration4149500100036 to define mass of fissionable layers of Np-237 and 4149500100037 Pu-239. 4149500100038 (D4PI) For delayed neutron registration, thirty SNM-11 4149500100039 boron counters in polyethylene 4149500100040 cylinder of 400 mm diameter and 300 mm height. 4149500100041 Counters were places as tree rings of 53, 80, 110 mm 4149500100042 diameters. 4149500100043 Boron Carbide powder, borated polyethylene, cadmium 4149500100044 sheets - for detector protection. 4149500100045 Dead time of neutron registration - 2.3+-0.2 microsec.4149500100046 Absolute efficiency of neutron detector was measured: 4149500100047 1) by source of monoenergetic neutrons from reaction 4149500100048 V-51(p,n)Cr-51, 4149500100049 2) by Cf-252 spontaneous fission neutrons energy 4149500100050 distribution. 4149500100051 SAMPLE Mass of fissionable sample near 1g. 4149500100052 Placed in stainless steel ampule, then in titanium 4149500100053 container. 4149500100054 METHOD (ACTIV) Cyclic radiation in neutron beam of fixed 4149500100055 energy, moving the sample in neutron detector by 4149500100056 pneumatic system, and measuring the time-dependence of 4149500100057 delayed neutron intensity. 4149500100058 ERR-ANALYS (ERR-1) Error of detector efficiency measured by 4149500100059 1st method, 4149500100060 (ERR-2) Error of detector efficiency measured by 4149500100061 2nd method. 4149500100062 (ERR-T) Total error - 5%. 4149500100063 COMMENT Work was made by support of RFBR grant #05-02-08044 4149500100064 and ISTC #2253. 4149500100065 HISTORY (20070428C) Compiled at CJD. M.M. 4149500100066 (20131129A) Ref. INDC(NDS)-0646 was added. 4149500100067 (20150225U) Minor correction in ref. J,PTE . 4149500100068 ENDBIB 66 0 4149500100069 COMMON 2 3 4149500100070 ERR-1 ERR-2 4149500100071 PER-CENT PER-CENT 4149500100072 3.64 2.14 4149500100073 ENDCOMMON 3 0 4149500100074 ENDSUBENT 73 0 4149500199999 SUBENT 41495002 20131130 41624149500200001 BIB 4 9 4149500200002 REACTION (92-U-233(N,F),DL,NU) Energy dependence of 4149500200003 absolute total yield of delayed neutrons 4149500200004 STATUS (APRVD) Data received from author V.Roschenko. 4149500200005 Fig.17 of main Reference. 4149500200006 (TABLE) Table on page 26 of R,INDC(NDS)-0646,2013. 4149500200007 COMMENT Of Author. On Fig.17 the data are presented for maximal4149500200008 energy of neutron spectrum. 4149500200009 HISTORY (20131130A) Data were corrected as given in newer 4149500200010 publication R,INDC(NDS)-0646,2013. EN-ERR was added. 4149500200011 ENDBIB 9 0 4149500200012 NOCOMMON 0 0 4149500200013 DATA 4 9 4149500200014 EN EN-ERR DATA ERR-T 4149500200015 MEV MEV PC/FIS PC/FIS 4149500200016 0.34 0.07 0.746 0.037 4149500200017 0.59 0.08 0.748 0.037 4149500200018 0.81 0.09 0.746 0.035 4149500200019 1.01 0.10 0.744 0.037 4149500200020 3.23 0.15 0.794 0.039 4149500200021 3.75 0.14 0.804 0.040 4149500200022 4.20 0.17 0.760 0.038 4149500200023 4.72 0.21 0.69 0.03 4149500200024 4.90 0.21 0.668 0.033 4149500200025 ENDDATA 11 0 4149500200026 ENDSUBENT 25 0 4149500299999 SUBENT 41495003 20131129 41624149500300001 BIB 4 14 4149500300002 REACTION (94-PU-239(N,F),DL,NU) Energy dependence of 4149500300003 absolute total yield of delayed neutrons 4149500300004 STATUS (APRVD) Data received from author V.Roschenko - 4149500300005 Fig.18 of J,PTE,6,29,2006 . 4149500300006 (TABLE) Table on page 28 of R,INDC(NDS)-0646,2013. 4149500300007 COMMENT Of Author. On Fig.18 the data are presented for maximal4149500300008 energy of neutron spectrum. 4149500300009 Of compiler 2013-12-03: 4149500300010 for 0.81 MeV data error of 0.001 pc/fis looks like too 4149500300011 low; in authors' data of 2007 year this error is 4149500300012 0.00779436 pc/fis. 4149500300013 HISTORY (20131129A) Data received from author in 2007 were 4149500300014 replaced by tabulated data of newer publication of 4149500300015 INDC(NDS)-0646. EN-ERR was added. 4149500300016 ENDBIB 14 0 4149500300017 NOCOMMON 0 0 4149500300018 DATA 4 9 4149500300019 EN EN-ERR DATA ERR-T 4149500300020 MEV MEV PC/FIS PC/FIS 4149500300021 0.34 0.07 0.651 0.020 4149500300022 0.59 0.08 0.645 0.009 4149500300023 0.81 0.09 0.643 0.010 4149500300024 1.01 0.10 0.656 0.014 4149500300025 3.23 0.15 0.712 0.033 4149500300026 3.75 0.14 0.704 0.017 4149500300027 4.20 0.17 0.689 0.017 4149500300028 4.72 0.21 0.668 0.019 4149500300029 4.90 0.12 0.608 0.094 4149500300030 ENDDATA 11 0 4149500300031 ENDSUBENT 30 0 4149500399999 ENDENTRY 3 0 4149599999999