G4FissLib.hh

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00001 //
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00024 // ********************************************************************
00025 //
00026 // $Id: G4FissLib.hh 69860 2013-05-16 14:39:02Z gcosmo $
00027 //
00028 // ********************************************************************
00029 // !                A neutron-induced fission package                 !
00030 // !                 J.M. Verbeke, Dec-2006 / LLNL                    !
00031 // !                                                                  !
00032 // ! G4NeutronFissionModule.cc                                        !
00033 // !                                                                  !
00034 // ! Classes to simulate neutron-induced fissions, emitting neutrons  !
00035 // ! and gamma-rays. Algorithm uses data whenever available, and      !
00036 // ! models such as the Terrell approximation, the Watt spectrum      !
00037 // ! otherwise.                                                       !
00038 // !                                                                  !
00039 // ! The complete list of references used is shown below:             !
00040 // !                                                                  !
00041 // ! J. Terrell, "Distributions of Fission Neutron Numbers", Phys.    !
00042 // !   Rev. 108, 783 (1957).                                          !
00043 // ! M.S. Zucker, N.E. Holden, "Energy Dependence of Neutron          !
00044 // !   Multiplicity P_nu in Fast-Neutron-Induced Fission for U-235,   !
00045 // !   U-238 and Pu-239," BNL-38491 (1986).                           !
00046 // ! T.E. Valentine, "MCNP-DSP Users Manual," ORNL/TM-13334, R2, Oak  !
00047 // !   Ridge National Laboratory (2000).                              !
00048 // ! T.E. Valentine, J.T. Mihalczo, "MCNP-DSP: A Neutron and Gamma    !
00049 // !   Ray Monte Carlo Calculation of Source-Driven Noise-Measured    !
00050 // !   Parameters ," Ann. of Nucl. Eng., 23, 16, p. 1271 (1996).      !
00051 // ! R. Gwin, R.R. Spencer, R.W. Ingle, "Measurements of the Energy   !
00052 // !   Dependence of Prompt Neutron Emission from U-233, U-235,       !
00053 // !   Pu-239, and Pu-241 for E_n=0.005 to 10 eV Relative to Emission !
00054 // !   from Spontaneous Fission of Cf-252," Nucl. Sci. Eng., 87, 381  !
00055 // !   (1984).                                                        !
00056 // ! J. Frehaut, "Neutron Multiplicity Distribution in Fast           !
00057 // !   Neutron-Induced Fission," Proc. of IAEA Consultant's Meeting   !
00058 // !   on Physics of Neutron Emission in Fission, Mito, Japan (1988). !
00059 // ! R.R. Spencer, R. Gwin, R.W. Ingle, "A measurement of the Average !
00060 // !   Number of Prompt Neutrons from Spontaneous Fission of          !
00061 // !   Californium-252," Nucl. Sci. Eng. 80, 603 (1982).              !
00062 // ! J.W. Boldeman, M.G. Hines, "Prompt Neutron Emission              !
00063 // !   Probabilities Following Spontaneous and Thermal Neutron        !
00064 // !   Fission," Nucl. Sci. Eng., 91, 114 (1985).                     !
00065 // ! N.E. Holden, M.S. Zucker, "A Reevaluation of the Average Prompt  !
00066 // !   Neutron Emission Multiplicity (nubar) Values from Fission of   !
00067 // !   Uranium and Transuranium Nuclides," BNL-NCS-35513, Brookhaven  !
00068 // !   National Laboratory).                                          !
00069 // ! R.J. Howerton, et al, "The LLL Evaluated Nuclear Data Library    !
00070 // !   (ENDL): Evaluation Techniques, Reaction Index, and Description !
00071 // !   of Individual Evaluations," UCRL-50400, V. 15, Part A,         !
00072 // !   Lawrence Livermore National Laboratory (1975).                 !
00073 // ! D.E. Cullen, "Sampling ENDL Watt Fission Spectra,"               !
00074 // !   UCRL-TR-203251, Lawrence Livermore National Laboratory (2004). !
00075 // ! C.J. Everett, E.D. Cashwell, "A Third Monte Carlo Sampler,"      !
00076 // !   LA-9721-MS, Los Alamos National Laboratory (1983).             !
00077 // ! D.E. Cullen, "TART 2002: A Couple Neutron-Photon 3-D,            !
00078 // !   Combinatorial Geometry, Time Dependent Monte-Carlo Transport   !
00079 // !   Code," UCRL-ID-126455, Rev. 4, Lawrence Livermore National     !
00080 // !   Laboratory (2003).                                             !
00081 // ! W. Mannhart, "Evaluation of the Cf-252 Fission Neutron Spectrum  !
00082 // !   Between 0 MeV and 20 MeV," Proc. Advisory Group Mtg. Neutron   !
00083 // !   Sources, Leningrad, USSR, 1986 (IAEA-TECDOC-410), Vienna       !
00084 // !   (1987).                                                        !
00085 // ! D.G. Madland, J.R. Nix, "Prompt Fission Neutron Spectra and      !
00086 // !   Average Prompt Neutron Multiplicities,"NEANDC Specialist's     !
00087 // !   Meeting on Yields and Decay Data of Fission Products,          !
00088 // !   Brookhaven National Laboratory, BNL 51778 (1984).              !
00089 // ! F.H. Froehner, "Evaluation of Cf-252 Prompt Fission Neutron Data !
00090 // !   from 0 to 20 MeV by Watt Spectrum Fit," Nucl. Sci. Eng. 106,   !
00091 // !   345 (1990).                                                    !
00092 // ! G.S. Brunson, Jr., "Multiplicity and Correlated Energy of Gamma  !
00093 // !   Rays Emitted in the Spontaneous Fission of Californium-252,"   !
00094 // !   Ph.D. Thesis, University of Utah (1982).                       !
00095 // ! T.E. Valentine, "Evaluation of Prompt Fission Gamma Rays for Use !
00096 // !   in Simulating Nuclear Safeguard Measurements," Ann. Nucl.      !
00097 // !   Eng., 28, 191 (2001).                                          !
00098 // ! C. Wagemans, "The Nuclear Fission Process," CRC Press, Inc., Boca!
00099 // !   Raton, Florida (1991).                                         !
00100 // ! F.C. Maienschein, R.W. Peelle, T.A. Love, Neutron Phys. Ann.     !
00101 // !   Prog. Rep. for Sept. 1, 1958, ORNL-2609, Oak Ridge National    !
00102 // !   Laboratory (1958).                                             !
00103 // ! "Fundamental Aspects of Reactor Shielding," Addison-Wesley       !
00104 // !   Publishing Company, Inc. Reading, Massachussetts (1959).       !
00105 // !                                                                  !
00106 // ********************************************************************
00107 //
00108  // Hadronic Process: High Precision low E neutron tracking
00109  // original by J.M. Verbeke, LLNL, 5-Jan-07
00110  // Builds and has the Cross-section data for one material.
00111   
00112 #ifndef G4FissLib_h
00113 #define G4FissLib_h 1
00114 
00115 // Class Description
00116 // Final state production model for a high precision (based on evaluated data
00117 // libraries) description of neutron induced fission below 10 MeV.
00118 // Note that this model (by intent of avoiding the possibility of heating studies) does
00119 // not provide the nuclear fragments.
00120 //
00121 // To be used in your physics list in case you need this physics.
00122 // In this case you want to register an object of this class with 
00123 // the corresponding process.
00124 // Class Description - End
00125 
00126 #include "globals.hh"
00127 #include "G4NeutronHPChannel.hh"
00128 #include "G4HadronicInteraction.hh"
00129 #include "G4NeutronHPThermalBoost.hh"
00130 #include "G4FissionLibrary.hh"
00131 // #include "G4FissLib.hh"
00132 
00133 class G4FissLib : public G4HadronicInteraction
00134 {
00135   public: 
00136     G4FissLib();
00137     ~G4FissLib();
00138   
00139     G4HadFinalState* ApplyYourself(const G4HadProjectile& aTrack,
00140                                    G4Nucleus& aTargetNucleus);
00141 
00142   private:
00143     G4FissionLibrary theLibrary;
00144   
00145   private:
00146     G4double* xSec;
00147     G4NeutronHPChannel* theFission;
00148     G4String dirName;
00149     G4int numEle;
00150 };
00151 
00152 #endif

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