ENTRY            M0437   20160906                             M084M043700000001 
SUBENT        M0437001   20160906                             M084M043700100001 
BIB                 15         48                                 M043700100002 
TITLE      Alpha particles from photodisintegration of  Be-9  in  M043700100003 
            the photon energy region 18 - 26 MeV.                 M043700100004 
AUTHOR     (A.Buchnea,R.G.Johnson,K.G.Mcneill)                    M043700100005 
REFERENCE  (J,CJP,56,47,1978)                                     M043700100006 
INSTITUTE  (1CANTOR)                                              M043700100007 
FACILITY   (LINAC,1USALAS)                                        M043700100008 
INC-SOURCE (BRST)                                                 M043700100009 
METHOD     (EXTB)                                                 M043700100010 
SAMPLE     The 0.0127 mm thick beryllium foil.                    M043700100011 
PART-DET   (A)                                                    M043700100012 
DETECTOR   (SOLST) Liquid nitrogen cooled Si(Li) detectors.       M043700100013 
ANALYSIS   (INTAD,UNFLD,DIFFR) Measurements  of  alpha  particle  M043700100014 
            energy spectra were fulfilled at the angles of 45  -  M043700100015 
            160 degrees to the direction of bremsstrahlung beam.  M043700100016 
            The  alpha  particle  yields   at   each   of   used  M043700100017 
            bremsstrahlung end-point energy were normalized.  By  M043700100018 
            substracting the alpha particle yields at successive  M043700100019 
            end-point  energies  from each other and dividing by  M043700100020 
            corresponding photon  spectrum  difference,  average  M043700100021 
            cross  sections  over  2  MeV  energy intervals were  M043700100022 
            obtained by the  photon  difference  technique.  The  M043700100023 
            energies  of the median points of the alpha particle  M043700100024 
            distributions of a pure reaction Be-9(g,n)Be-8(E-exc  M043700100025 
            =  16.6  MeV)  at  each  angle of detection for each  M043700100026 
            bremsstrahlung end-point energy were  determined  by  M043700100027 
            kinematic calculations.                               M043700100028 
CORRECTION The detected  alpha  particles  were  corrected   for  M043700100029 
            energy  losses  in  the  beryllium target and in the  M043700100030 
            inert silicon 'windows' of the Si(Li) detectors. The  M043700100031 
            alpha  particle  energy spectra were then normalized  M043700100032 
            for geometric efficiency of the detection system and  M043700100033 
            for photon flux.                                      M043700100034 
COMMENT    Alpha particles from  the  Be-9(g,n)Be-8  ->  2a  and  M043700100035 
            Be-9(g,a-0)He-5  were  studied  in the photon energy  M043700100036 
            region 18 - 26 MeV;  the results yielded a  combined  M043700100037 
            integrated cross section of 13.1 (2.0) MeV*mb and an  M043700100038 
            upper limit on the integrated (g,a-0) cross  section  M043700100039 
            of  4.0  MeV*mb.  these  reactions together with the  M043700100040 
            Be-9(g,n-1)Be-8 reaction (which  has  an  integrated  M043700100041 
            cross  section  of  2.4  (0.4) MeV*mb) are the major  M043700100042 
            reaction  channels   contributing   to   the   total  M043700100043 
            photoneutron  cross  section  in this energy region.  M043700100044 
            the  (g,n-1)  reaction  are  consistent   with   the  M043700100045 
            population of 3/2+ and 5/2+ states of Be-9.           M043700100046 
STATUS     (TABLE) Data from Tab. 2.                              M043700100047 
HISTORY    (19910218C)                                            M043700100048 
           (20160906A) Corrected by V.Varlamov: ANALYSIS,         M043700100049 
            ERR-ANALYS, REACTION, dates, lowercase.               M043700100050 
ENDBIB              48          0                                 M043700100051 
NOCOMMON             0          0                                 M043700100052 
ENDSUBENT           51          0                                 M043700199999 
SUBENT        M0437002   20160906                             M084M043700200001 
BIB                  5          7                                 M043700200002 
REACTION   (4-BE-9(G,X)2-HE-4,PAR,SIG,,BRA)                       M043700200003 
EN-SEC     (E-LVL,2-HE-5)                                         M043700200004 
ANALYSIS   Average cross    sections    for   energy   intervals  M043700200005 
            mentioned.                                            M043700200006 
ERR-ANALYS No information.                                        M043700200007 
HISTORY    (20160906A) Corrected by V.Varlamov: ANALYSIS,         M043700200008 
            REACTIOB, ERR-ANALYS.                                 M043700200009 
ENDBIB               7          0                                 M043700200010 
COMMON               1          3                                 M043700200011 
E-LVL                                                             M043700200012 
MEV                                                               M043700200013 
  0.0                                                             M043700200014 
ENDCOMMON            3          0                                 M043700200015 
DATA                 3          4                                 M043700200016 
EN-MIN     EN-MAX     DATA                                        M043700200017 
MEV        MEV        MB                                          M043700200018 
  18.        20.00        .15                                     M043700200019 
  20.        22.0        1.9                                      M043700200020 
  22.        24.0        2.8                                      M043700200021 
  24.        26.0        1.7                                      M043700200022 
ENDDATA              6          0                                 M043700200023 
ENDSUBENT           22          0                                 M043700299999 
SUBENT        M0437003   20160906                             M084M043700300001 
BIB                  4          7                                 M043700300002 
REACTION   (4-BE-9(G,X)2-HE-4,PAR,INT)                            M043700300003 
           Cumulative integrated   cross   sections   for   both  M043700300004 
            reactions  (Be-8(E-exc  =  16.6  MeV) -> 2a) and for  M043700300005 
            energy intervals mentioned.                           M043700300006 
EN-SEC     (E-LVL,2-HE-4)                                         M043700300007 
ERR-ANALYS (DATA-ERR) Mean-root-squared uncertainties.            M043700300008 
HISTORY    (20160906A) Corrected by V.Varlamov: ERR-ANALYS.       M043700300009 
ENDBIB               7          0                                 M043700300010 
COMMON               1          3                                 M043700300011 
E-LVL                                                             M043700300012 
MEV                                                               M043700300013 
  0.0                                                             M043700300014 
ENDCOMMON            3          0                                 M043700300015 
DATA                 4          4                                 M043700300016 
EN-MIN     EN-MAX     DATA       DATA-ERR                         M043700300017 
MEV        MEV        MB*MEV     MB*MEV                           M043700300018 
  18.        20.          .3                                      M043700300019 
  18.        22.         4.1                                      M043700300020 
  18.        24.         9.7                                      M043700300021 
  18.        26.        13.1       2.                             M043700300022 
ENDDATA              6          0                                 M043700300023 
ENDSUBENT           22          0                                 M043700399999 
ENDENTRY             3          0                                 M043799999999