Geant4 11.1.1
Toolkit for the simulation of the passage of particles through matter
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G4FissLib.hh
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1//
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24// ********************************************************************
25//
26//
27// ********************************************************************
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"
129#include "G4FissionLibrary.hh"
130// #include "G4FissLib.hh"
131
133{
134 public:
135 G4FissLib();
136 ~G4FissLib();
137
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 G4int numEle;
150};
151
152#endif
double G4double
Definition: G4Types.hh:83
int G4int
Definition: G4Types.hh:85
G4HadFinalState * ApplyYourself(const G4HadProjectile &aTrack, G4Nucleus &aTargetNucleus)
Definition: G4FissLib.cc:96
~G4FissLib()
Definition: G4FissLib.cc:90
const std::pair< G4double, G4double > GetFatalEnergyCheckLevels() const
Definition: G4FissLib.cc:148