ENTRY M0310 20110316 M058M031000000001 SUBENT M0310001 20110316 M058M031000100001 BIB 18 60 M031000100002 TITLE Energy spectra of photoneutrons from Cr and Ta. M031000100003 AUTHOR (G.Cortini,C.Milone,A.Rubbino,F.Ferrero) M031000100004 INSTITUTE (2ITYCAT,2ITYTUR) M031000100005 REFERENCE (J,NC,9,(1),85,1958) M031000100006 FACILITY (BETAT,2ITYTUR) M031000100007 INC-SOURCE (BRST) M031000100008 SAMPLE Cr (weight=21.6 g) and Ta (weight=49 g) targets in the M031000100009 natural isotopic composition placed in cylinders of 2 M031000100010 cm diameter and 2 cm high coaxial with the beam. M031000100011 METHOD (REC) M031000100012 PART-DET (P) M031000100013 DETECTOR (PLATE) ILFORD C2 emulsion, 200 mu thick, 1*3 square M031000100014 inches. A foil of lead 6 mm thick screened the plates M031000100015 against the low energy photons coming from the target. M031000100016 CORRECTION Corrected for: M031000100017 a) the useful solid angle of the recoil tracks in the M031000100018 center of mass system, M031000100019 b) the probability of escape of the tracks from the M031000100020 emulsion, M031000100021 c) the cross section for n-p collisions in the M031000100022 emulsion, M031000100023 d) the number of hydrogen atoms per unit volume of M031000100024 nuclear emulsion, M031000100025 e) the gamma-ray absorption in the target, M031000100026 f) the neutron absorption in the target and in the M031000100027 lead screen. M031000100028 The background was negligible. M031000100029 ANALYSIS (4PI1A) M031000100030 ERR-ANALYS (ERR-S) Statistical errors are presented. M031000100031 ADD-RES (THEO,COMP) The authors try to fit the high energy M031000100032 tails of the spectra in the frame of the Wilkinson M031000100033 photoeffect model with some particularization of the M031000100034 shells from which high energy neutrons are supposed M031000100035 to came. The energy distributions of neutrons in the M031000100036 low energy range are compared with the evaporation M031000100037 theory. The calculated yields derived by spectra are M031000100038 compared with the experimental yields of high energy M031000100039 neutrons obtained by Ferrero and co-authors. M031000100040 COMMENT The high energy tail of the photoneutrons, coming M031000100041 from some direct process, shows, also in Cr and Ta, M031000100042 the small maxima at 5-6 MeV neutron energy. The tail M031000100043 accounts for 10% of all the photoneutrons observed. M031000100044 The increase in the yield of the high energy tails M031000100045 from 20 to 30 MeV in Cr and Ta is consistent with the M031000100046 second maximum in the cross section found by Ferrero M031000100047 and co-authors. M031000100048 REL-REF (N,,V.F.W.WEISSKOPF+,J,PR,57,472,1940) M031000100049 A description of the evaporation model. M031000100050 (N,,D.H.WILKINSON,J,PHY,22,1039,1956) M031000100051 A description of the direct photoeffect model. M031000100052 (N,,F.FERRERO+,J,NC,6,385,1957) M031000100053 Experimental yields of high energy photoneutrons M031000100054 obtained by Ferrero and co-authors. M031000100055 STATUS (CURVE) Data were compiled in SCJAD Of Saratov State M031000100056 University. M031000100057 HISTORY (19881227C) M031000100058 (19910202A) Corrected by V.Varlamov, V.Mclane M031000100059 (20110119A) Corrected by V.Varlamov: dates, REL-REF, M031000100060 lowercase. M031000100061 (20110316A) Corrected by V.Varlamov: typos. M031000100062 ENDBIB 60 0 M031000100063 COMMON 1 3 M031000100064 ANG M031000100065 ADEG M031000100066 90. M031000100067 ENDCOMMON 3 0 M031000100068 ENDSUBENT 67 0 M031000199999 SUBENT M0310002 20110119 M056M031000200001 BIB 2 2 M031000200002 REACTION (24-CR-0(G,X)0-NN-1,,DA/DE,,BRA/REL) M031000200003 COMMENT Dose of gamma-irradiation = 1458 roentgen. M031000200004 ENDBIB 2 0 M031000200005 COMMON 2 3 M031000200006 EN-MAX E-ERR M031000200007 MEV MEV M031000200008 20. 0.25 M031000200009 ENDCOMMON 3 0 M031000200010 DATA 3 13 M031000200011 E DATA ERR-S M031000200012 MEV ARB-UNITS ARB-UNITS M031000200013 1.25 104.9 9.2 M031000200014 1.75 92.7 9.2 M031000200015 2.25 65.3 7.7 M031000200016 2.75 30.5 6.7 M031000200017 3.25 28.7 6.1 M031000200018 3.75 18.3 4.9 M031000200019 4.25 9.8 3.7 M031000200020 4.75 7.9 3.6 M031000200021 5.25 14.0 4.9 M031000200022 5.75 0.0 M031000200023 6.25 6.1 3.1 M031000200024 6.75 6.1 3.1 M031000200025 7.25 4.3 2.4 M031000200026 ENDDATA 15 0 M031000200027 ENDSUBENT 26 0 M031000299999 SUBENT M0310003 20110119 M056M031000300001 BIB 2 2 M031000300002 REACTION (24-CR-0(G,X)0-NN-1,,DA/DE,,BRA/REL) M031000300003 COMMENT Dose of gamma-irradiation = 2607 roentgen. M031000300004 ENDBIB 2 0 M031000300005 COMMON 1 3 M031000300006 EN-MAX M031000300007 MEV M031000300008 30. M031000300009 ENDCOMMON 3 0 M031000300010 DATA 4 22 M031000300011 E E-ERR DATA ERR-S M031000300012 MEV MEV ARB-UNITS ARB-UNITS M031000300013 1.25 0.25 191.5 9.8 M031000300014 1.75 0.25 129.3 9.1 M031000300015 2.25 0.25 89.7 7.3 M031000300016 2.75 0.25 62.2 7.1 M031000300017 3.25 0.25 39.0 6.7 M031000300018 3.75 0.25 22.6 4.9 M031000300019 4.25 0.25 31.7 6.1 M031000300020 4.75 0.25 21.4 4.9 M031000300021 5.25 0.25 20.6 3.3 M031000300022 5.75 0.25 12.1 3.0 M031000300023 6.25 0.25 9.5 2.4 M031000300024 6.75 0.25 5.4 1.8 M031000300025 7.25 0.25 7.3 2.7 M031000300026 7.75 0.25 3.9 1.2 M031000300027 8.25 0.25 5.8 2.5 M031000300028 8.75 0.25 3.3 M031000300029 9.25 0.25 3.0 M031000300030 9.75 0.25 0.9 M031000300031 10.50 0.50 3.0 M031000300032 11.50 0.50 2.4 M031000300033 12.50 0.50 0.6 M031000300034 13.50 0.50 3.0 M031000300035 ENDDATA 24 0 M031000300036 ENDSUBENT 35 0 M031000399999 SUBENT M0310004 20110119 M056M031000400001 BIB 2 2 M031000400002 REACTION (73-TA-181(G,X)0-NN-1,,DA/DE,,BRA/REL) M031000400003 COMMENT Dose of gamma-irradiation = 1461 roentgen. M031000400004 ENDBIB 2 0 M031000400005 COMMON 2 3 M031000400006 EN-MAX E-ERR M031000400007 MEV MEV M031000400008 20. 0.25 M031000400009 ENDCOMMON 3 0 M031000400010 DATA 3 17 M031000400011 E DATA ERR-S M031000400012 MEV ARB-UNITS ARB-UNITS M031000400013 1.25 222.6 23.2 M031000400014 1.75 193.4 22.0 M031000400015 2.25 100.1 15.9 M031000400016 2.75 51.2 14.6 M031000400017 3.25 32.9 12.2 M031000400018 3.75 31.7 9.8 M031000400019 4.25 23.8 9.6 M031000400020 4.75 15.3 11.6 M031000400021 5.25 12.2 5.5 M031000400022 5.75 24.2 8.5 M031000400023 6.25 22.0 7.9 M031000400024 6.75 21.4 7.9 M031000400025 7.25 9.2 3.7 M031000400026 7.75 9.2 4.2 M031000400027 8.25 1.4 1.2 M031000400028 8.75 2.4 2.4 M031000400029 9.25 3.1 2.6 M031000400030 ENDDATA 19 0 M031000400031 ENDSUBENT 30 0 M031000499999 SUBENT M0310005 20110119 M056M031000500001 BIB 2 2 M031000500002 REACTION (73-TA-181(G,X)0-NN-1,,DA/DE,,BRA/REL) M031000500003 COMMENT Dose of gamma-irradiation = 2788 roentgen. M031000500004 ENDBIB 2 0 M031000500005 COMMON 1 3 M031000500006 EN-MAX M031000500007 MEV M031000500008 30. M031000500009 ENDCOMMON 3 0 M031000500010 DATA 4 27 M031000500011 E E-ERR DATA ERR-S M031000500012 MEV MEV ARB-UNITS ARB-UNITS M031000500013 1.25 0.25 211.1 14.7 M031000500014 1.75 0.25 183.0 14.6 M031000500015 2.25 0.25 131.8 13.4 M031000500016 2.75 0.25 64.7 6.1 M031000500017 3.25 0.25 46.4 9.2 M031000500018 3.75 0.25 29.3 7.3 M031000500019 4.25 0.25 22.0 6.1 M031000500020 4.75 0.25 16.5 4.3 M031000500021 5.25 0.25 21.8 2.7 M031000500022 5.75 0.25 15.8 2.1 M031000500023 6.25 0.25 14.2 1.5 M031000500024 6.75 0.25 14.5 1.8 M031000500025 7.25 0.25 11.8 1.3 M031000500026 7.75 0.25 9.1 1.2 M031000500027 8.25 0.25 6.4 1.0 M031000500028 8.75 0.25 5.2 M031000500029 9.25 0.25 4.5 M031000500030 9.75 0.25 3.3 M031000500031 10.50 0.50 3.0 M031000500032 11.50 0.50 2.0 M031000500033 12.50 0.50 1.5 M031000500034 13.50 0.50 2.8 M031000500035 14.50 0.50 0.0 M031000500036 15.50 0.50 2.4 M031000500037 16.50 0.50 1.6 M031000500038 17.50 0.50 0.0 M031000500039 18.50 0.50 0.9 M031000500040 ENDDATA 29 0 M031000500041 ENDSUBENT 40 0 M031000599999 ENDENTRY 5 0 M031099999999