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 76-Os-  0 FEI        EVAL-JAN90 NIKOLAEV M.N.                    
                      DIST-JAN09                     20090105     
----JEFF-311          MATERIAL 7600                               
-----INCIDENT NEUTRON DATA                                        
------ENDF-6 FORMAT                                               
***************************  JEFF-3.1.1  *************************
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**         Original data taken from:  JEFF-3.1                  **
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*****************************  JEFF-3.1  *************************
**                                                              **
**   Original data taken from:        JEFF-3.0 + Corrections    **
**                                                              **
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*****************************   JEFF-3.0   ***********************
                                                                  
   DATA TAKEN FROM   :-   BROND-2.2 (DIST-OCT91)                  
                                                                  
19/02/2002: Decay scheme in MF12 modified by A. Hogenbirk         
            (NRG Petten)                                          
                                                                  
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 76-OS-  0                                                        
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          CONTENT OF THE FILE:                                    
                                                                  
MF = 1    GENERAL INFORMATION:                                    
                                                                  
          MT = 451    COMMENTS  ON  EVALUATIONS,  REFERENCES AND  
                    DICTIONARY.                                   
                                                                  
                    RESULTS OF EVALUATION FULFILLED  BY NIKOLAEV  
                    M.N.   (MF = 1-5,    9) AND ZABRODSKAYA S.V.  
                    (MF = 12, 14, 15) ARE GIVEN. DATA   COMPILED  
                    AND CHECKED BY SAVOSKINA G.V.                 
                                                                  
                    DESCRIPTION IS WRITTEN DOWN BY NIKOLAEV M.N.  
                                                                  
                    0.0253 EV CROSS SECTIONS:                     
                                                                  
                    RADIATIVE CAPTURE   OS-184   3002.+-150.BARN  
                    RADIATIVE CAPTURE   OS-186   79.+-13.   BARN  
                    RADIATIVE CAPTURE   OS-187   319.+-10.  BARN  
                    RADIATIVE CAPTURE   OS-188   4.8+-0.5   BARN  
                    RADIATIVE CAPTURE   OS-189   25.4+-4.   BARN  
                    RADIATIVE CAPTURE   OS-190   13.1+-0.3  BARN  
                    RADIATIVE CAPTURE   OS-192   1.93+-0.1  BARN  
                    RADIATIVE CAPTURE   OS-NAT   15.9+-0.4  BARN  
                    ELASTIC SCATTERING  OS-184   108.       BARN  
                    ELASTIC SCATTERING  OS-186   14.2+-5.   BARN  
                    ELASTIC SCATTERING  OS-187   10.9+-6.   BARN  
                    ELASTIC SCATTERING  OS-188   7.6+-0.6   BARN  
                    ELASTIC SCATTERING  OS-189   15.3+-1.0  BARN  
                    ELASTIC SCATTERING  OS-190   15.9+-0.9  BARN  
                    ELASTIC SCATTERING  OS-192   17.9+-0.6  BARN  
                    ELASTIC SCATTERING  OS-NAT   15.4+-0.4  BARN  
                                                                  
MF = 2    RESONANCE REGION:                                       
                                                                  
          MT = 151    ONLY RESOLVED RESONANCE REGION IS DESCRIBED 
                    FOR EVERY  OSMIUM  ISOTOPE.  PARAMETERS  ONLY 
                    S-RESONANCE  ARE  GIVEN.  AVERAGE   RESONANCE 
                    PARAMETERS NOT GIVEN. LOW ENERGY BOUNDARY  OF 
                    RRR IS 10-5 EV FOR EVERY ISOTOPE.  PARAMETERS 
                    OF  BOUND  LEVEL  ARE  SPECIFIED  FOR   EVERY 
                    ISOTOPE  TO  OBTAIN  THE  EXPERIMENTAL  CROSS 
                    SECTIONS VALUE AT 0.0253 EV.  PARAMETERS OF   
                    SEVERAL  FICTITIOUS  RESONANCES ARE GIVEN FOR 
                    ENERGIES  GREATER  THAN  UPPER BOUNDARY  OF   
                    RRR  FOR  TAKING  INTO  ACCOUNT UNRESOLVED    
                    RESONANCE CONTRIBUTION IN RRR.                
                                                                  
                    --------------------------------------------- 
                           !   TOTAL    !   UPPER   ! NUMBER OF   
                    ISOTOPE! NUMBER OF  ! BOUNDARY, ! ARTIFICIAL  
                           ! RESONANCES !    EV     ! RESONANCES  
                    --------------------------------------------- 
                    OS-184        1          160          -       
                    OS-186      133         3360          5       
                    OS-187      182          990          5       
                    OS-188      107         5000          5       
                    OS-189       27           77          5       
                    OS-190        7          150          4       
                    OS-192        4          150          1       
                    --------------------------------------------- 
                                                                  
MF = 3    NEUTRON CROSS-SECTIONS:                                 
                                                                  
          IN THE REGION FROM 10-5 EV TO 77 EV ALL CROSS SECTIONS  
          ARE FULLY DETERMINED BY RESONANCE PARAMETERS LISTED IN  
          MF=2. IN THE FILE  MF=3  ALL  CROSS  SECTIONS  IN  THIS 
          REGION PUT EQUAL TO ZERO. ABOVE THE 77 EV  CONTRIBUTION 
          OF OS-189 IS TAKEN INTO ACCOUNT IN THE FILE MF=3. ABOVE 
          150 EV CONTRIBUTIONS OF OS-190  AND  OS-192  ARE  TAKEN 
          INTO  ACCOUNT  ALSO.  ABOVE  990  EV  AND  TO  5000  EV 
          CONTRIBUTION OF OS-187  IS  TAKEN  INTO  ACCOUNT  ALSO. 
          THESE CONTRIBUTIONS WERE CALCULATED WITH  THE  HELP  OF 
          EVPAR CODE  [1]  ON  THE  BASIS  OF  AVERAGE  RESONANCE 
          PARAMETERS. ABOUT DETERMINATION OF CROSS SECTIONS ABOVE 
          5000 EV SEE BELOW.                                      
                                                                  
          MT = 1    TOTAL CROSS SECTION FROM 5 KEV TO 100 KEV WAS 
                    CALCULATED   ON   THE   BASIS   OF    AVERAGE 
                    PARAMETERS. ABOVE 100  KEV  -  FROM  THE  EYE 
                    GUIDE CURVE FROM [2].                         
                                                                  
          MT = 2    ELASTIC SCATTERING CROSS SECTION ABOVE  5 KEV 
                    IS EQUAL TO DIFFERENCE  BETWEEN  TOTAL  CROSS 
                    SECTION  AND  SUMMARIZED   NONELASTIC   CROSS 
                    SECTION.                                      
                                                                  
          MT = 4    INELASTIC SCATTERING CROSS SECTION IS THE SUM 
                    OF MT = 51-67 AND MT = 91.                    
                                                                  
          MT = 16    CROSS  SECTION  OF   (N,2N)   REACTION   WAS 
                    CALCULATED BY TNG CODE [3] FOR EVERY ABUNDANT 
                    ISOTOPE.  FOR  OS-184,  OS-186   AND   OS-192 
                    PARAMETERS OF CALCULATION  WERE  FITTED   FOR 
                    AGREEMENT WITH EXPERIMENTAL DATA. FOR  OS-187 
                    PARAMETERS OF OS-189 WERE  USED.  FOR  OS-190 
                    PARAMETERS OF OS-192  WERE  USED.  ABOVE  THE 
                    THRESHOLD OF (N,3N) REACTION COMPETITION  OF  
                    THIS REACTION WAS TAKEN INTO ACCOUNT.         
                                                                  
          MT = 17    CROSS SECTION OF (N,3N) REACTION  CALCULATED 
                    BY  MULTIPLYING  OF  SUMMARIZED  (N,2N)   AND 
                    (N,3N) CROSS SECTION CALCULATED BY  TNG  CODE 
                    ON  THE  PROBABILITY  OF  EMISSION  OF  THIRD 
                    NEUTRON CALCULATED BY NEVA CODE [4]           
                                                                  
          MT = 51-67    LEVEL  EXCITATION   CROSS   SECTION WERE  
                    CALCULATED BY TNG CODE WITH  THE  NEXT  LEVEL 
                    PARAMETERS                                    
                                                                  
                    MT   ISOTOPE   EN,KEV   SPIN,PARITY           
                                                                  
                    51     189       31       9/2-                
                    52     189       36       1/2-                
                    53     189       69       5/2-                
                    54     189       95       3/2-                
                    55     188      155       2+                  
                    56     190      187       2+                  
                    57     192      206       2+                  
                    58     189      217       7/2-                
                    59     189      219       7/2-                
                    60     189      234       3/2-                
                    61     189      276       5/2-                
                    62     189      439       5/2-                
                    63     188      478       4+                  
                    64     192      489       2+                  
                    65     190      548       4+                  
                    66     192      580       4+                  
                    67     192      690       3+                  
                                                                  
                    INELASTIC SCATTERING ON  THE  LIGHT  ISOTOPES 
                    WITH LOW ABUNDANCE WAS TAKEN INTO ACCOUNT  BY 
                    CORRESPONDING  INCREASING  OS-188   ABUNDANCE 
                    WHEN CROSS SECTIONS FOR  NATURAL  OSMIUM  WAS 
                    CALCULATED.                                   
                                                                  
          MT = 91    CONTINUUM INELASTIC CROSS SECTION CALCULATED 
                    ON THE BASIS OF STATISTICAL MODEL. BELOW  THE 
                    THRESHOLD  OF  (N,3N)  REACTION   THIS  CROSS 
                    SECTION CALCULATED BY TNG  CODE.  ABOVE  THIS 
                    THRESHOLD CONTINUUM INELASTIC  CROSS  SECTION 
                    IS  THE  DIFFERENCE  BETWEEN  SUM  OF   CROSS 
                    SECTIONS MT = 4 + 16 + 17 + 102 + 103 + 107   
                    CALCULATED BY TNG CODE AND SUM ADOPTED  CROSS 
                    SECTIONS OF (N,2N), (N,3N), (N,GAMMA),  (N,P) 
                    AND (N,ALFA).                                 
                                                                  
          MT = 102    ISOTOPE CAPTURE CROSS SECTIONS FROM  5  KEV 
                    TO 1 MEV ADOPTED AS IN THE EYE  GUIDE  CURVES 
                    IN   REF.[2]   (FOR   OS-190    AND    OS-192 
                    IRREGULARITIES   ON   THESE    CURVES    WERE 
                    SMOOTHED). CROSS SECTION FOR  NATURAL  OSMIUM 
                    WAS THEN CALCULATED. ABOVE 1 MEV FOR  NATURAL 
                    OSMIUM  THE PLATINUM  RADIATIVE CAPTURE CROSS 
                    SECTION WAS ADOPTED AFTER RENORMALIZATION  ON 
                    EVALUATED OSMIUM CROSS SECTION AT 1 MEV.  (IN 
                    REF.[2]  CROSS  SECTION  CURVES  FOR  OS-186, 
                    OS-187, OS-188 ARE SHARPLY INCREASED  ON  THE 
                    BASIS  OF  DATA  OF  REF.[5].  SO   ANOMALOUS 
                    BEHAVIOR OF CROSS SECTIONS FOR  ALL  MEASURED 
                    ISOTOPES LEAD TO DOUBT IN THIS DATA).         
                                                                  
          MT = 103, 107    (N,P) AND (N,ALFA) CROSS SECTIONS WERE 
                    CALCULATED  BY  TNG  CODE  WITH  FITTING   OF 
                    PARAMETERS OF CALCULATION FOR AGREEMENT  WITH 
                    EXPERIMENTAL DATA.                            
                                                                  
          MT = 251, 252, 253    ARE  CALCULATED  ON  THE          
                    BASIS OF MF = 4, MT = 2 DATA.                 
                                                                  
MF = 4    ANGULAR DISTRIBUTIONS:                                  
                                                                  
          MT = 2    ELASTIC   SCATTERING   ANGULAR   DISTRIBUTION 
                    ACCEPTED  AS  THOSE  FOR  PLATINUM  (ENDF/B-4 
                    DATA).                                        
                                                                  
          MT = 16, 17, 51-67, 91    (N,2N), (N,3N) AND  INELASTIC 
                    SCATTERING  NEUTRON   ANGULAR   DISTRIBUTIONS 
                    ACCEPTED AS ISOTROPIC IN THE LAB SYSTEM.      
                                                                  
MF = 5    ENERGY DISTRIBUTIONS:                                   
                                                                  
          MT = 16, 17, 91    CONTINUOUS   ENERGY    DISTRIBUTIONS 
                    (N,2N),  (N,3N)  AND   INELASTIC   SCATTERING 
                    NEUTRONS ARE CALCULATED BY THE NEVA CODE  [8] 
                    IN   THE   FRAME   OF   EVAPORATION    MODEL. 
                    EVAPORATION   TEMPERATURES   WERE   ESTIMATED 
                    ACCORDING TO  GILBERT-CAMERON   PRESCRIPTION. 
                    COMPETITION FROM THE  RADIATIVE  CHANNEL  WAS 
                    NOT TAKEN INTO ACCOUNT. PRECOMPOUND  EMISSION 
                    WAS TAKEN INTO ACCOUNT APPROXIMATELY.         
                                                                  
MF = 12   MULTIPLICITIES OF RADIATIVE TRANSITIONS.                
                                                                  
          MT = 16, 17    MULTIPLICITIES  OF   CONTINUOUS   ENERGY 
                    SPECTRA PHOTONS EMITTED IN (N,2N) AND  (N,3N) 
                    REACTIONS IS ADOPTED AS FOR  IRIDIUM  BECAUSE 
                    RESULTS OF CALCULATIONS OF THESE  SPECTRA  BY 
                    TNG CODE FOR OSMIUM AND IRIDIUM  WERE  FINDED 
                    VERY CLOSE ONE TO ANOTHER.                    
                                                                  
          MT = 51-67    FOR EACH OF THIS  REACTIONS  LINE  PHOTON 
                    SPECTRUM  ARE  GIVEN.   PHOTON   LINES   WERE 
                    DETERMINED   OR   BY   TRANSITIONS   ON   THE 
                    UNDERLYING LEVELS OR IN THE CASE OF  INTERNAL 
                    CONVERSION BY CORRESPONDING ROENTGEN.  OPTION 
                    L0=1 IS USED.                                 
                                                                  
          MT = 91    PHOTON SPECTRA FOR INELASTIC SCATTERING WITH 
                    CONTINUOUS NEUTRON SPECTRA WERE ALSO  ADOPTED 
                    CONTINUOUS. THIS PHOTON SPECTRA WERE WEIGHTED 
                    FOR AVERAGE ISOTOPE SPECTRA.  THE  LAST  WAS  
                    CALCULATED FOR THE MAIN  OSMIUM  ISOTOPES  BY 
                    TNG CODE.                                     
                                                                  
          MT = 102    CONTINUOUS RADIATIVE CAPTURE PHOTON SPECTRA 
                    WERE    ADOPTED.    THESE     SPECTRA     AND 
                    MULTIPLICITIES  WAS  TAKEN  BY  AVERAGING  OF 
                    CONTRIBUTIONS OF ODD AND EVEN OSMIUM ISOTOPES 
                    CALCULATED BY TNG CODE.                       
                                                                  
                                                                  
          MT = 103, 107    SPECTRA AND MULTIPLICITIES OF  PHOTONS 
                    EMITTED IN (N,P) AND (N,ALFA) REACTIONS  WERE 
                    CALCULATED BY TNG CODE.                       
                                                                  
MF = 14   PHOTON ANGULAR DISTRIBUTIONS:                           
                                                                  
          MT = 16, 17, 51-67, 91, 102, 103, 107    ALL PHOTON     
                    ANGULAR DISTRIBUTIONS WERE TAKEN ISOTROPIC IN 
                    LAB. SYSTEM.                                  
                                                                  
MF = 15   CONTINUOUS PHOTON SPECTRA.                              
                                                                  
          MT = 16, 17, 51-67, 91, 102, 103, 107    SEE COMMENTS   
                    TO MF = 12.                                   
                                                                  
                           REFERENCES                             
                                                                  
1.        MANTUROV G.N. ET AL. VANT  "YADERNYE  CONSTANTY"  ISSUE 
          1(50),P.50.  MOSCOW, 1983.                              
2.        NEUTRON CROSS  SECTIONS.  V2.  NEUTRON  CROSS  SECTIONS 
          CURVES.  V.MCLANE,  C.L.DUNFORD,  P.F.ROSE.  NNDC  BNL, 
          ACADEMIC PRESS 1988.                                    
3.        SHIBATA K., FU C.Y. ORNL/TM-10093, 1986.                
4.        NIKOLAEV  M.N.  AND  GILFANOVA  O.  NEVA  -  CODE   FOR 
          CALCULATION  OF    SPECTRA   CONSEQUENTLY   EVAPORATED  
          NEUTRONS. FEI, 1988. UNPUBLISHED.                       
5.        WINTERS ET.AL. PHYS.REV.C.21, P.563 (1980).             
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