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28 // ! A neutron-induced fission package !
29 // ! J.M. Verbeke, Dec-2006 / LLNL !
30 // ! !
31 // ! G4NeutronFissionModule.cc !
32 // ! !
33 // ! Classes to simulate neutron-induced fissions, emitting neutrons !
34 // ! and gamma-rays. Algorithm uses data whenever available, and !
35 // ! models such as the Terrell approximation, the Watt spectrum !
36 // ! otherwise. !
37 // ! !
38 // ! The complete list of references used is shown below: !
39 // ! !
40 // ! J. Terrell, "Distributions of Fission Neutron Numbers", Phys. !
41 // ! Rev. 108, 783 (1957). !
42 // ! M.S. Zucker, N.E. Holden, "Energy Dependence of Neutron !
43 // ! Multiplicity P_nu in Fast-Neutron-Induced Fission for U-235, !
44 // ! U-238 and Pu-239," BNL-38491 (1986). !
45 // ! T.E. Valentine, "MCNP-DSP Users Manual," ORNL/TM-13334, R2, Oak !
46 // ! Ridge National Laboratory (2000). !
47 // ! T.E. Valentine, J.T. Mihalczo, "MCNP-DSP: A Neutron and Gamma !
48 // ! Ray Monte Carlo Calculation of Source-Driven Noise-Measured !
49 // ! Parameters ," Ann. of Nucl. Eng., 23, 16, p. 1271 (1996). !
50 // ! R. Gwin, R.R. Spencer, R.W. Ingle, "Measurements of the Energy !
51 // ! Dependence of Prompt Neutron Emission from U-233, U-235, !
52 // ! Pu-239, and Pu-241 for E_n=0.005 to 10 eV Relative to Emission !
53 // ! from Spontaneous Fission of Cf-252," Nucl. Sci. Eng., 87, 381 !
54 // ! (1984). !
55 // ! J. Frehaut, "Neutron Multiplicity Distribution in Fast !
56 // ! Neutron-Induced Fission," Proc. of IAEA Consultant's Meeting !
57 // ! on Physics of Neutron Emission in Fission, Mito, Japan (1988). !
58 // ! R.R. Spencer, R. Gwin, R.W. Ingle, "A measurement of the Average !
59 // ! Number of Prompt Neutrons from Spontaneous Fission of !
60 // ! Californium-252," Nucl. Sci. Eng. 80, 603 (1982). !
61 // ! J.W. Boldeman, M.G. Hines, "Prompt Neutron Emission !
62 // ! Probabilities Following Spontaneous and Thermal Neutron !
63 // ! Fission," Nucl. Sci. Eng., 91, 114 (1985). !
64 // ! N.E. Holden, M.S. Zucker, "A Reevaluation of the Average Prompt !
65 // ! Neutron Emission Multiplicity (nubar) Values from Fission of !
66 // ! Uranium and Transuranium Nuclides," BNL-NCS-35513, Brookhaven !
67 // ! National Laboratory). !
68 // ! R.J. Howerton, et al, "The LLL Evaluated Nuclear Data Library !
69 // ! (ENDL): Evaluation Techniques, Reaction Index, and Description !
70 // ! of Individual Evaluations," UCRL-50400, V. 15, Part A, !
71 // ! Lawrence Livermore National Laboratory (1975). !
72 // ! D.E. Cullen, "Sampling ENDL Watt Fission Spectra," !
73 // ! UCRL-TR-203251, Lawrence Livermore National Laboratory (2004). !
74 // ! C.J. Everett, E.D. Cashwell, "A Third Monte Carlo Sampler," !
75 // ! LA-9721-MS, Los Alamos National Laboratory (1983). !
76 // ! D.E. Cullen, "TART 2002: A Couple Neutron-Photon 3-D, !
77 // ! Combinatorial Geometry, Time Dependent Monte-Carlo Transport !
78 // ! Code," UCRL-ID-126455, Rev. 4, Lawrence Livermore National !
79 // ! Laboratory (2003). !
80 // ! W. Mannhart, "Evaluation of the Cf-252 Fission Neutron Spectrum !
81 // ! Between 0 MeV and 20 MeV," Proc. Advisory Group Mtg. Neutron !
82 // ! Sources, Leningrad, USSR, 1986 (IAEA-TECDOC-410), Vienna !
83 // ! (1987). !
84 // ! D.G. Madland, J.R. Nix, "Prompt Fission Neutron Spectra and !
85 // ! Average Prompt Neutron Multiplicities,"NEANDC Specialist's !
86 // ! Meeting on Yields and Decay Data of Fission Products, !
87 // ! Brookhaven National Laboratory, BNL 51778 (1984). !
88 // ! F.H. Froehner, "Evaluation of Cf-252 Prompt Fission Neutron Data !
89 // ! from 0 to 20 MeV by Watt Spectrum Fit," Nucl. Sci. Eng. 106, !
90 // ! 345 (1990). !
91 // ! G.S. Brunson, Jr., "Multiplicity and Correlated Energy of Gamma !
92 // ! Rays Emitted in the Spontaneous Fission of Californium-252," !
93 // ! Ph.D. Thesis, University of Utah (1982). !
94 // ! T.E. Valentine, "Evaluation of Prompt Fission Gamma Rays for Use !
95 // ! in Simulating Nuclear Safeguard Measurements," Ann. Nucl. !
96 // ! Eng., 28, 191 (2001). !
97 // ! C. Wagemans, "The Nuclear Fission Process," CRC Press, Inc., Boca!
98 // ! Raton, Florida (1991). !
99 // ! F.C. Maienschein, R.W. Peelle, T.A. Love, Neutron Phys. Ann. !
100 // ! Prog. Rep. for Sept. 1, 1958, ORNL-2609, Oak Ridge National !
101 // ! Laboratory (1958). !
102 // ! "Fundamental Aspects of Reactor Shielding," Addison-Wesley !
103 // ! Publishing Company, Inc. Reading, Massachussetts (1959). !
104 // ! !
105 // ********************************************************************
106 //
107 // Hadronic Process: High Precision low E neutron tracking
108 // original by J.M. Verbeke, LLNL, 5-Jan-07
109 // Builds and has the Cross-section data for one material.
110
111 #ifndef G4FissLib_h
112 #define G4FissLib_h 1
113
114 // Class Description
115 // Final state production model for a high precision (based on evaluated data
116 // libraries) description of neutron induced fission below 10 MeV.
117 // Note that this model (by intent of avoiding the possibility of heating studies) does
118 // not provide the nuclear fragments.
119 //
120 // To be used in your physics list in case you need this physics.
121 // In this case you want to register an object of this class with
122 // the corresponding process.
123 // Class Description - End
124
125 #include "globals.hh"
126 #include "G4ParticleHPChannel.hh"
127 #include "G4HadronicInteraction.hh"
128 #include "G4ParticleHPThermalBoost.hh"
129 #include "G4FissionLibrary.hh"
130 // #include "G4FissLib.hh"
131
132 class G4FissLib : public G4HadronicInteraction
133 {
134 public:
135 G4FissLib();
136 ~G4FissLib();
137
138 G4HadFinalState* ApplyYourself(const G4HadProjectile& aTrack,
139 G4Nucleus& aTargetNucleus);
140 const std::pair<G4double, G4double> GetFatalEnergyCheckLevels() const;
141
142 private:
143 G4FissionLibrary theLibrary;
144
145 private:
146 G4double* xSec;
147 G4ParticleHPChannel* theFission;
148 G4String dirName;
149 std::size_t numEle;
150 };
151
152 #endif
153