Cinda reaction Codes

EVL         Evaluation
               Complete and consistent set of cross sections in      
                some energy range.                                   
TOT         Total
               Total neutron cross section                           
SEL         Elastic
               Total elastic scattering cross section, integrated    
                over all angles.                                     
DEL         Diff elastic
               Angular distribution or differential scattering       
                cross section for elastically scattered neutrons.    
POL         Polarization
               Polarization of neutrons in the exit channel.         
POT         Potntal scat
               That part of the scattering cross section which       
                corresponds to scattering by a hard sphere.          
SIN         Tot Inelastc
               Total inelastic scattering cross section, integrated  
                over all angles and excited levels.                  
DIN         Diff inelast
               Angular distributions or energy spectra of            
                inelastically scattered neutrons, or partial cross   
                sections for inelastic scattering.                   
TSL         Thermal Scat
               Elastic or inelastic scattering of slow neutrons      
                depending on the structure of target material, e.g., 
                chemical binding, crystal vibrations, etc.           
SCT         Scattering
               Total scattering cross section                        
SNE         nonelastic
               Sum  of all non-elastic cross sections                
ABS         Absorption
               Absorption cross section, i.e., sum of all            
                non-scattering cross sections.                       
RIA         Res Int Abs
               Resonance integral for absorption.                    
NG          (n,gamma)
               Radiative capture cross section.                      
RIG         Res Int Capt
               Capture resonance integral, for fissioning nuclides   
                only.                                                
SNG         Spec n,gamma
               Spectrum of gamma rays or conversion electrons        
                following neutron capture.                           
DNG         Inelastic gam
               Production cross section, angular distributions or    
                energy spectra for gamma rays following inelastic    
                scattering of neutrons.                              
NEG         Nonelast gam
               Production cross section, angular distributions or    
                energy spectra for gamma rays following unseparated  
                neutron induced nonelastic processes.                
N2N         (n,2n)
               (n,2n) or (n,2n+CP) reaction (CP=charged particles).  
                Integral and differential data.                      
NXN         (n,xn x=3,4..)
               Reactions producing at least 3 neutrons. Integral and 
                differential data.                                   
NEM         n emission
               Sum cross section for all nonelastic processes        
                resulting in neutron emission, weighted for the      
                number of neutrons produced.                         
NX          Nucl Product
               Sum of all (unspecified) processes in a given target  
                producing a given nuclide.                           
NP          (n,p)
               (n,proton) reaction. Integral and differential data.  
NNP         (n,np)
               (n,n'p) reaction. Integral and differential data.     
PEM         p emission
               Proton emission cross section                         
ND          (n,d)
               (n,deuteron) reaction. Integral and differential data.
NND         (n,nd)
               (n,n'd) reaction. Integral and differential data.     
DEM         d emission
               Deuteron emission cross section                       
NT          (n,t)
               (N,triton) reaction. Integral and differential data.  
NNT         (n,nt)
               (n,n't) reaction. Integral and differential data.     
TEM         t emission
               Triton emission cross section                         
NHE         (n,He3)
               (n,3He) reaction. Integral and differential data.     
NA          (n,alfa)
               (n,alpha) reaction. Integral and differential data    
NNA         (n,n+alfa)
               (n,n'alpha) reaction. Integral and differential data. 
AEM         Alpha Emiss
               Alpha emission cross section                          
NF          (n,fission)
               Cross section for neutron induced fission, or for     
                inelastic scattering to a spontaneously fissioning   
                isomer.                                              
RIF         Res int fiss
               Resonance integral for fission                        
ALF         Alpha
               Capture to fission cross section ratio.               
ETA         Eta
               For fissionable nuclides: number of neutrons          
                emitted per absorption                               
NU          Nu
               Number of prompt neutrons emitted per fission, also   
                average number of prompt or total neutrons per       
                fission.                                             
NUD         Delayd neuts
               Delayed neutrons from fission. Total or group yields, 
                energies.                                            
NUF         Frag neuts
               Number or energy of neutrons emitted by given fission 
                fragments.                                           
SFN         Spect Fiss n
               Energy spectrum or mean energy of prompt fission      
                neutrons.                                            
SFG         Spec fis gam
               Spectrum of prompt gamma rays emitted in fission.     
FPG         Fis Prod gams
               Spectrum, yields, etc., of delayed gamma rays from    
                unseparated fission products.                        
FPB         FisProd beta
               Spectra, mean energies, etc., of beta-rays from THE   
                unseparated fission products.                        
NFY         Fiss yield
               Yields of fission fragments or products.              
FRS         Frag spectra
               Energy or angular distribution of fission products.   
CHG         Frag Charge
               Charge distribution of fission fragments: charge      
                dispersion, most probable charge of mass chain,      
                fractional yields.                                   
RES         Reson Params
               Individual and averaged neutron resonance parameters. 
STF         Strnth fnctn
               Neutron strength function.                            
LDL         Lvl Density
               Density of levels in the continuum, as determined     
                from particles emitted in neutron reactions.         
GN          Gamma-n
               (gamma,n) reaction. Integral and differential data.   
GF          Photo-fissn
               Photon induced fission: cross sections, yields and    
                spectra of neutrons, fragments, etc.