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0001 // 0002 // ******************************************************************** 0003 // * License and Disclaimer * 0004 // * * 0005 // * The Geant4 software is copyright of the Copyright Holders of * 0006 // * the Geant4 Collaboration. It is provided under the terms and * 0007 // * conditions of the Geant4 Software License, included in the file * 0008 // * LICENSE and available at http://cern.ch/geant4/license . These * 0009 // * include a list of copyright holders. * 0010 // * * 0011 // * Neither the authors of this software system, nor their employing * 0012 // * institutes,nor the agencies providing financial support for this * 0013 // * work make any representation or warranty, express or implied, * 0014 // * regarding this software system or assume any liability for its * 0015 // * use. Please see the license in the file LICENSE and URL above * 0016 // * for the full disclaimer and the limitation of liability. * 0017 // * * 0018 // * This code implementation is the result of the scientific and * 0019 // * technical work of the GEANT4 collaboration. * 0020 // * By using, copying, modifying or distributing the software (or * 0021 // * any work based on the software) you agree to acknowledge its * 0022 // * use in resulting scientific publications, and indicate your * 0023 // * acceptance of all terms of the Geant4 Software license. * 0024 // ******************************************************************** 0025 // 0026 // 0027 // ******************************************************************** 0028 // ! A neutron-induced fission package ! 0029 // ! J.M. Verbeke, Dec-2006 / LLNL ! 0030 // ! ! 0031 // ! G4NeutronFissionModule.cc ! 0032 // ! ! 0033 // ! Classes to simulate neutron-induced fissions, emitting neutrons ! 0034 // ! and gamma-rays. Algorithm uses data whenever available, and ! 0035 // ! models such as the Terrell approximation, the Watt spectrum ! 0036 // ! otherwise. ! 0037 // ! ! 0038 // ! The complete list of references used is shown below: ! 0039 // ! ! 0040 // ! J. Terrell, "Distributions of Fission Neutron Numbers", Phys. ! 0041 // ! Rev. 108, 783 (1957). ! 0042 // ! M.S. Zucker, N.E. Holden, "Energy Dependence of Neutron ! 0043 // ! Multiplicity P_nu in Fast-Neutron-Induced Fission for U-235, ! 0044 // ! U-238 and Pu-239," BNL-38491 (1986). ! 0045 // ! T.E. Valentine, "MCNP-DSP Users Manual," ORNL/TM-13334, R2, Oak ! 0046 // ! Ridge National Laboratory (2000). ! 0047 // ! T.E. Valentine, J.T. Mihalczo, "MCNP-DSP: A Neutron and Gamma ! 0048 // ! Ray Monte Carlo Calculation of Source-Driven Noise-Measured ! 0049 // ! Parameters ," Ann. of Nucl. Eng., 23, 16, p. 1271 (1996). ! 0050 // ! R. Gwin, R.R. Spencer, R.W. Ingle, "Measurements of the Energy ! 0051 // ! Dependence of Prompt Neutron Emission from U-233, U-235, ! 0052 // ! Pu-239, and Pu-241 for E_n=0.005 to 10 eV Relative to Emission ! 0053 // ! from Spontaneous Fission of Cf-252," Nucl. Sci. Eng., 87, 381 ! 0054 // ! (1984). ! 0055 // ! J. Frehaut, "Neutron Multiplicity Distribution in Fast ! 0056 // ! Neutron-Induced Fission," Proc. of IAEA Consultant's Meeting ! 0057 // ! on Physics of Neutron Emission in Fission, Mito, Japan (1988). ! 0058 // ! R.R. Spencer, R. Gwin, R.W. Ingle, "A measurement of the Average ! 0059 // ! Number of Prompt Neutrons from Spontaneous Fission of ! 0060 // ! Californium-252," Nucl. Sci. Eng. 80, 603 (1982). ! 0061 // ! J.W. Boldeman, M.G. Hines, "Prompt Neutron Emission ! 0062 // ! Probabilities Following Spontaneous and Thermal Neutron ! 0063 // ! Fission," Nucl. Sci. Eng., 91, 114 (1985). ! 0064 // ! N.E. Holden, M.S. Zucker, "A Reevaluation of the Average Prompt ! 0065 // ! Neutron Emission Multiplicity (nubar) Values from Fission of ! 0066 // ! Uranium and Transuranium Nuclides," BNL-NCS-35513, Brookhaven ! 0067 // ! National Laboratory). ! 0068 // ! R.J. Howerton, et al, "The LLL Evaluated Nuclear Data Library ! 0069 // ! (ENDL): Evaluation Techniques, Reaction Index, and Description ! 0070 // ! of Individual Evaluations," UCRL-50400, V. 15, Part A, ! 0071 // ! Lawrence Livermore National Laboratory (1975). ! 0072 // ! D.E. Cullen, "Sampling ENDL Watt Fission Spectra," ! 0073 // ! UCRL-TR-203251, Lawrence Livermore National Laboratory (2004). ! 0074 // ! C.J. Everett, E.D. Cashwell, "A Third Monte Carlo Sampler," ! 0075 // ! LA-9721-MS, Los Alamos National Laboratory (1983). ! 0076 // ! D.E. Cullen, "TART 2002: A Couple Neutron-Photon 3-D, ! 0077 // ! Combinatorial Geometry, Time Dependent Monte-Carlo Transport ! 0078 // ! Code," UCRL-ID-126455, Rev. 4, Lawrence Livermore National ! 0079 // ! Laboratory (2003). ! 0080 // ! W. Mannhart, "Evaluation of the Cf-252 Fission Neutron Spectrum ! 0081 // ! Between 0 MeV and 20 MeV," Proc. Advisory Group Mtg. Neutron ! 0082 // ! Sources, Leningrad, USSR, 1986 (IAEA-TECDOC-410), Vienna ! 0083 // ! (1987). ! 0084 // ! D.G. Madland, J.R. Nix, "Prompt Fission Neutron Spectra and ! 0085 // ! Average Prompt Neutron Multiplicities,"NEANDC Specialist's ! 0086 // ! Meeting on Yields and Decay Data of Fission Products, ! 0087 // ! Brookhaven National Laboratory, BNL 51778 (1984). ! 0088 // ! F.H. Froehner, "Evaluation of Cf-252 Prompt Fission Neutron Data ! 0089 // ! from 0 to 20 MeV by Watt Spectrum Fit," Nucl. Sci. Eng. 106, ! 0090 // ! 345 (1990). ! 0091 // ! G.S. Brunson, Jr., "Multiplicity and Correlated Energy of Gamma ! 0092 // ! Rays Emitted in the Spontaneous Fission of Californium-252," ! 0093 // ! Ph.D. Thesis, University of Utah (1982). ! 0094 // ! T.E. Valentine, "Evaluation of Prompt Fission Gamma Rays for Use ! 0095 // ! in Simulating Nuclear Safeguard Measurements," Ann. Nucl. ! 0096 // ! Eng., 28, 191 (2001). ! 0097 // ! C. Wagemans, "The Nuclear Fission Process," CRC Press, Inc., Boca! 0098 // ! Raton, Florida (1991). ! 0099 // ! F.C. Maienschein, R.W. Peelle, T.A. Love, Neutron Phys. Ann. ! 0100 // ! Prog. Rep. for Sept. 1, 1958, ORNL-2609, Oak Ridge National ! 0101 // ! Laboratory (1958). ! 0102 // ! "Fundamental Aspects of Reactor Shielding," Addison-Wesley ! 0103 // ! Publishing Company, Inc. Reading, Massachussetts (1959). ! 0104 // ! ! 0105 // ******************************************************************** 0106 // 0107 // Hadronic Process: High Precision low E neutron tracking 0108 // original by J.M. Verbeke, LLNL, 5-Jan-07 0109 // Builds and has the Cross-section data for one material. 0110 0111 #ifndef G4FissLib_h 0112 #define G4FissLib_h 1 0113 0114 // Class Description 0115 // Final state production model for a high precision (based on evaluated data 0116 // libraries) description of neutron induced fission below 10 MeV. 0117 // Note that this model (by intent of avoiding the possibility of heating studies) does 0118 // not provide the nuclear fragments. 0119 // 0120 // To be used in your physics list in case you need this physics. 0121 // In this case you want to register an object of this class with 0122 // the corresponding process. 0123 // Class Description - End 0124 0125 #include "globals.hh" 0126 #include "G4ParticleHPChannel.hh" 0127 #include "G4HadronicInteraction.hh" 0128 #include "G4ParticleHPThermalBoost.hh" 0129 #include "G4FissionLibrary.hh" 0130 // #include "G4FissLib.hh" 0131 0132 class G4FissLib : public G4HadronicInteraction 0133 { 0134 public: 0135 G4FissLib(); 0136 ~G4FissLib(); 0137 0138 G4HadFinalState* ApplyYourself(const G4HadProjectile& aTrack, 0139 G4Nucleus& aTargetNucleus); 0140 const std::pair<G4double, G4double> GetFatalEnergyCheckLevels() const; 0141 0142 private: 0143 G4FissionLibrary theLibrary; 0144 0145 private: 0146 G4double* xSec; 0147 G4ParticleHPChannel* theFission; 0148 G4String dirName; 0149 G4int numEle; 0150 }; 0151 0152 #endif
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