ENTRY 23224 20140210 22382322400000001 SUBENT 23224001 20140210 22382322400100001 BIB 15 30 2322400100002 TITLE The 127I(n,p)127mTe; 127I(n,p)127Te and 127I(n,2n)126I 2322400100003 mean fission neutron cross sections 2322400100004 AUTHOR (P.De Regge, R.Dams, J.Hoste) 2322400100005 INSTITUTE (2BLGGHT) Institute for Nuclear Sciences 2322400100006 REFERENCE (J,RCA,9,57,1968) 2322400100007 FACILITY (REAC,2BLGMOL) BR-1 reactor 2322400100008 INC-SPECT Reactor fast flux 2322400100009 SAMPLE 3 g suprapur KI (reaction sample) and 100 mg (NH4)SO4 2322400100010 (monitor sample). 2322400100011 Sealed in separate silica tubes and packed in a 2322400100012 standard Al container. 2322400100013 METHOD (CHSEP) Separation of Te and I from irradiated sample. 2322400100014 Tracer experiment confirmed that the chemical yield 2322400100015 was 95% to 100% for I and more than 97% for Te. 2322400100016 REL-REF (N,20253001,M.Deschuyter+,J,RCA,7,90,1967) 2322400100017 This article concludes that the fast neutron flux at 2322400100018 the irradiation position is practically unperturbed. 2322400100019 MONITOR (16-S-32(N,P)15-P-32,,SIG,,FIS) 2322400100020 DECAY-MON (15-P-32,,B-) 2322400100021 Beta activities of 32P and 35S (from 34S(n,g)35S) were 2322400100022 accurately discriminated. 2322400100023 COMMENT By authors: 2322400100024 The 159 keV gamma line from 123mTe (104 d) was not 2322400100025 detected. This shows the Te content of the KI sample 2322400100026 was below the detection limit, and consequently 2322400100027 no correction is required to 127I(n,p)127Te data due 2322400100028 to 126Te(n,g)127Te contribution. 2322400100029 ERR-ANALYS (DATA-ERR) No information on source of uncertainties 2322400100030 STATUS (TABLE) Abstract of Radiochim.Acta9(1968)57 2322400100031 HISTORY (20140210C) On 2322400100032 ENDBIB 30 0 2322400100033 COMMON 1 3 2322400100034 MONIT 2322400100035 MB 2322400100036 60. 2322400100037 ENDCOMMON 3 0 2322400100038 ENDSUBENT 37 0 2322400199999 SUBENT 23224002 20140210 22382322400200001 BIB 7 16 2322400200002 REACTION M(53-I-127(N,P)52-TE-127-M,,SIG,,FIS) 2322400200003 G(53-I-127(N,P)52-TE-127-G,,SIG,,FIS) 2322400200004 DECAY-DATAM(52-TE-127-M,115.D) 2322400200005 G(52-TE-127-G,9.3HR,B-,691.) 2322400200006 RAD-DET M(52-TE-127-G,B-) 2322400200007 METHOD (BSPEC) The measurement of the disintegration rate of 2322400200008 127mTe was performed at least 5 days after the end of 2322400200009 the irradiation to allow for the complete decay of 2322400200010 127gTe. 2322400200011 M(ACTIV) 4 or 10 daily irradiations for 2 hrs 2322400200012 G(ACTIV) Irradiated for 2 hrs 2322400200013 DETECTOR (GEMUC) 2322400200014 ANALYSIS M Mean of 5 measurements from 5 samples. 2322400200015 G Mean of 3 measurements from 3 samples. 2322400200016 REL-REF (D,,J.C.Roy+,R,CRC-1003,1960) 2322400200017 0.13 mb for g.s.+m.s. evaluated 2322400200018 ENDBIB 16 0 2322400200019 NOCOMMON 0 0 2322400200020 DATA 5 1 2322400200021 KT-DUMMY DATA MDATA-ERR MDATA GDATA-ERR G 2322400200022 MEV MICRO-B MICRO-B MICRO-B MICRO-B 2322400200023 1.32 11.1 0.2 7.62 0.11 2322400200024 ENDDATA 3 0 2322400200025 ENDSUBENT 24 0 2322400299999 SUBENT 23224003 20140210 22382322400300001 BIB 7 12 2322400300002 REACTION (53-I-127(N,2N)53-I-126,,SIG,,FIS) 2322400300003 DECAY-DATA (53-I-126,12.98D,DG,388.0,0.336, 2322400300004 DG,665.7,0.340) 2322400300005 METHOD (ACTIV) 9 or 10 daily irradiations of 2 hrs 2322400300006 (GSPEC) 2322400300007 DETECTOR (NAICR) 3 in x 3 in NaI(Tl) with resolution of 7.9% 2322400300008 (GELI) 19cm3 coaxial type with resolution of 4 keV 2322400300009 ANALYSIS Mean of 12 measurements from 5 samples. 2322400300010 One measurement was done with Ge(Li) detector. 2322400300011 ADD-RES (STRUC) Half-life and abundances of the 6 gamma lines 2322400300012 were determined in this experimental work. 2322400300013 REL-REF (D,,J.C.Roy+,R,CRC-1003,1960) 0.9 mb evaluated 2322400300014 ENDBIB 12 0 2322400300015 NOCOMMON 0 0 2322400300016 DATA 3 1 2322400300017 KT-DUMMY DATA DATA-ERR 2322400300018 MEV MB MB 2322400300019 1.32 0.647 0.010 2322400300020 ENDDATA 3 0 2322400300021 ENDSUBENT 20 0 2322400399999 ENDENTRY 3 0 2322499999999