ActivationAnalysis.h

Go to the documentation of this file.

#ifndef _ACTIVATION_ANALYSIS_H_
#define _ACTIVATION_ANALYSIS_H_
// root includes
#include "TH1.h"
#include "TFile.h"
// c++ includes
#include <utility>
#include <string>
 
 
#include <vector>
#include <map>
#include <string>
using std::map;
using std::vector;
using std::string;
class ActivationAnalysis
{
  public:
  // default constructor
  ActivationAnalysis();
 //Takes SPE files with calibration parameters from InterSpec. Key takes "Eu", "Foil", "Bkg"
 void readSPEFile(std::string a_fileName, std::string a_key);
 
  // add the start time for the beginning of irradiation
  void setIrradiationStartTime(double a_year,
                               double a_month,
                               double a_day,
                               double a_hour,
                               double a_minute,
                               double a_second);
  //Calculates the integrated beam current over irradiation time. Requires csv file containing beam on time.
  void addBeamCurrentFile(std::string a_fileName);
  //Takes distance from beam flange center to target in centimeters
  void setBeamFlightPath(double a_flightPath);
  //Add sTOF spectrum for flux-weighted cross section calculation
  void addFluxHistogram(std::string a_fileName, std::string a_histName="fluxHist");
  // path to directory where IRDFF-II.tab.txt file is located
  void setIRDFFTablePath(std::string a_fileName);
  //Reads the IRDFF table and gets cross section data for given reaction. Requries X-23(a,b)Y-27m) format
  std::map<int, std::vector<double> > readIRDFFTable(std::string a_reaction);
  // Calculate the flux weighted cross section. Requries X-23(a,b)Y-27m) format 
  void calcFluxWeightedXSec(std::string a_reaction);
  // Analyze Eu152 spectra and computes an efficiency curve for the given calibration histogram
  void analyzeEu152Data(double activity);
  //Takes parameters from SpectrumAnalysis getEffCurve and calculates the efficiency at a given energy
  std::pair<double,double> getEff(double energy);
  // Calculate activity at the end of irradiation. Requires ../SandiaDecay/CMakeLists.txt line 12 be SHARED.
  //if using InterSpec counts, autoFit=false and becomes the number of counts. a_time is uncertantity of the half-life
 void calcA0(std::string a_isotope,double a_peakMean,double a_time, bool autoFit);
//Calculates flux. Z is z number of foil, mass is mass of foil, allIso takes specific isotope in format "Na24" "C12" or "All" for every isotope
 //the abundancy error and mass error vectors must ordered by isotopoe so that the nth element is the mass and abundancy error of the nth isotope
 void calcNormalizedFlux(double mass,double a_Z,std::vector<double> a_abundancies_err, std::vector<double> a_mass_err,string allIso);
 
private:
  
  TH1F* m_effHist;
  TH1F* m_bkgHist;
  TH1F* m_foilHist;
  int m_mon=0;
  int m_day=0;
  int m_year=0;
  int m_hour=0;
  int m_tj=0;
  int m_eu=0;
  int m_ti=0;
  int m_bk=0;
  double m_a0=0.0;
  double m_xs=0.0;
  int m_tc=0;
  double m_counts=0;
  double m_lin=0.0;
  int m_minute=0;
  int m_second=0;
  double m_decay=0.0;
  double m_xs_err=0.0;
  double m_a0_err=0.0;
  double m_offset=0.0;
  int m_current=0;
  double m_decay_err=0.0;
  int m_flightPath=0;
  double m_efficiency=0.0;
  int m_curent_err=0;
  double m_decayConstant=0.0;
  std::vector<int> m_SPE;  
  std::string m_rootFile;
  std::string m_irdffPath;  
  std::string m_bkgrootFile;
  std::vector<int> m_bkgSPE;
  std::vector<double> m_effParams;
  std::vector<double> m_neutrons;
  std::vector<double> m_neutrons_err;
  std::vector<double> m_binsVect;
  std::vector<double> m_widthVect;
  time_t m_epochIrradiationStartTime;
};
#endif