00001 // 00002 // ******************************************************************** 00003 // * License and Disclaimer * 00004 // * * 00005 // * The Geant4 software is copyright of the Copyright Holders of * 00006 // * the Geant4 Collaboration. It is provided under the terms and * 00007 // * conditions of the Geant4 Software License, included in the file * 00008 // * LICENSE and available at http://cern.ch/geant4/license . These * 00009 // * include a list of copyright holders. * 00010 // * * 00011 // * Neither the authors of this software system, nor their employing * 00012 // * institutes,nor the agencies providing financial support for this * 00013 // * work make any representation or warranty, express or implied, * 00014 // * regarding this software system or assume any liability for its * 00015 // * use. Please see the license in the file LICENSE and URL above * 00016 // * for the full disclaimer and the limitation of liability. * 00017 // * * 00018 // * This code implementation is the result of the scientific and * 00019 // * technical work of the GEANT4 collaboration. * 00020 // * By using, copying, modifying or distributing the software (or * 00021 // * any work based on the software) you agree to acknowledge its * 00022 // * use in resulting scientific publications, and indicate your * 00023 // * acceptance of all terms of the Geant4 Software license. * 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