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// $Id: G4FissLib.hh,v 1.2 2007-06-01 13:46:53 gcosmo Exp $
// GEANT4 tag $Name: not supported by cvs2svn $
//
// ********************************************************************
// ! A neutron-induced fission package !
// ! J.M. Verbeke, Dec-2006 / LLNL !
// ! !
// ! G4NeutronFissionModule.cc !
// ! !
// ! Classes to simulate neutron-induced fissions, emitting neutrons !
// ! and gamma-rays. Algorithm uses data whenever available, and !
// ! models such as the Terrell approximation, the Watt spectrum !
// ! otherwise. !
// ! !
// ! The complete list of references used is shown below: !
// ! !
// ! J. Terrell, "Distributions of Fission Neutron Numbers", Phys. !
// ! Rev. 108, 783 (1957). !
// ! M.S. Zucker, N.E. Holden, "Energy Dependence of Neutron !
// ! Multiplicity P_nu in Fast-Neutron-Induced Fission for U-235, !
// ! U-238 and Pu-239," BNL-38491 (1986). !
// ! T.E. Valentine, "MCNP-DSP Users Manual," ORNL/TM-13334, R2, Oak !
// ! Ridge National Laboratory (2000). !
// ! T.E. Valentine, J.T. Mihalczo, "MCNP-DSP: A Neutron and Gamma !
// ! Ray Monte Carlo Calculation of Source-Driven Noise-Measured !
// ! Parameters ," Ann. of Nucl. Eng., 23, 16, p. 1271 (1996). !
// ! R. Gwin, R.R. Spencer, R.W. Ingle, "Measurements of the Energy !
// ! Dependence of Prompt Neutron Emission from U-233, U-235, !
// ! Pu-239, and Pu-241 for E_n=0.005 to 10 eV Relative to Emission !
// ! from Spontaneous Fission of Cf-252," Nucl. Sci. Eng., 87, 381 !
// ! (1984). !
// ! J. Frehaut, "Neutron Multiplicity Distribution in Fast !
// ! Neutron-Induced Fission," Proc. of IAEA Consultant's Meeting !
// ! on Physics of Neutron Emission in Fission, Mito, Japan (1988). !
// ! R.R. Spencer, R. Gwin, R.W. Ingle, "A measurement of the Average !
// ! Number of Prompt Neutrons from Spontaneous Fission of !
// ! Californium-252," Nucl. Sci. Eng. 80, 603 (1982). !
// ! J.W. Boldeman, M.G. Hines, "Prompt Neutron Emission !
// ! Probabilities Following Spontaneous and Thermal Neutron !
// ! Fission," Nucl. Sci. Eng., 91, 114 (1985). !
// ! N.E. Holden, M.S. Zucker, "A Reevaluation of the Average Prompt !
// ! Neutron Emission Multiplicity (nubar) Values from Fission of !
// ! Uranium and Transuranium Nuclides," BNL-NCS-35513, Brookhaven !
// ! National Laboratory). !
// ! R.J. Howerton, et al, "The LLL Evaluated Nuclear Data Library !
// ! (ENDL): Evaluation Techniques, Reaction Index, and Description !
// ! of Individual Evaluations," UCRL-50400, V. 15, Part A, !
// ! Lawrence Livermore National Laboratory (1975). !
// ! D.E. Cullen, "Sampling ENDL Watt Fission Spectra," !
// ! UCRL-TR-203251, Lawrence Livermore National Laboratory (2004). !
// ! C.J. Everett, E.D. Cashwell, "A Third Monte Carlo Sampler," !
// ! LA-9721-MS, Los Alamos National Laboratory (1983). !
// ! D.E. Cullen, "TART 2002: A Couple Neutron-Photon 3-D, !
// ! Combinatorial Geometry, Time Dependent Monte-Carlo Transport !
// ! Code," UCRL-ID-126455, Rev. 4, Lawrence Livermore National !
// ! Laboratory (2003). !
// ! W. Mannhart, "Evaluation of the Cf-252 Fission Neutron Spectrum !
// ! Between 0 MeV and 20 MeV," Proc. Advisory Group Mtg. Neutron !
// ! Sources, Leningrad, USSR, 1986 (IAEA-TECDOC-410), Vienna !
// ! (1987). !
// ! D.G. Madland, J.R. Nix, "Prompt Fission Neutron Spectra and !
// ! Average Prompt Neutron Multiplicities,"NEANDC Specialist's !
// ! Meeting on Yields and Decay Data of Fission Products, !
// ! Brookhaven National Laboratory, BNL 51778 (1984). !
// ! F.H. Froehner, "Evaluation of Cf-252 Prompt Fission Neutron Data !
// ! from 0 to 20 MeV by Watt Spectrum Fit," Nucl. Sci. Eng. 106, !
// ! 345 (1990). !
// ! G.S. Brunson, Jr., "Multiplicity and Correlated Energy of Gamma !
// ! Rays Emitted in the Spontaneous Fission of Californium-252," !
// ! Ph.D. Thesis, University of Utah (1982). !
// ! T.E. Valentine, "Evaluation of Prompt Fission Gamma Rays for Use !
// ! in Simulating Nuclear Safeguard Measurements," Ann. Nucl. !
// ! Eng., 28, 191 (2001). !
// ! C. Wagemans, "The Nuclear Fission Process," CRC Press, Inc., Boca!
// ! Raton, Florida (1991). !
// ! F.C. Maienschein, R.W. Peelle, T.A. Love, Neutron Phys. Ann. !
// ! Prog. Rep. for Sept. 1, 1958, ORNL-2609, Oak Ridge National !
// ! Laboratory (1958). !
// ! "Fundamental Aspects of Reactor Shielding," Addison-Wesley !
// ! Publishing Company, Inc. Reading, Massachussetts (1959). !
// ! !
// ********************************************************************
//
// Hadronic Process: High Precision low E neutron tracking
// original by J.M. Verbeke, LLNL, 5-Jan-07
// Builds and has the Cross-section data for one material.
#ifndef G4FissLib_h
#define G4FissLib_h 1
// Class Description
// Final state production model for a high precision (based on evaluated data
// libraries) description of neutron induced fission below 10 MeV.
// Note that this model (by intent of avoiding the possibility of heating studies) does
// not provide the nuclear fragments.
//
// To be used in your physics list in case you need this physics.
// In this case you want to register an object of this class with
// the corresponding process.
// Class Description - End
#include "globals.hh"
#include "G4NeutronHPChannel.hh"
#include "G4HadronicInteraction.hh"
#include "G4NeutronHPThermalBoost.hh"
#include "G4FissionLibrary.hh"
#include "G4FissLib.hh"
class G4FissLib : public G4HadronicInteraction
{
public:
G4FissLib();
~G4FissLib();
G4HadFinalState * ApplyYourself(const G4HadProjectile& aTrack, G4Nucleus& aTargetNucleus);
private:
G4FissionLibrary theLibrary;
private:
G4double * xSec;
G4NeutronHPChannel * theFission;
G4String dirName;
G4int numEle;
// static G4String theNames[3];
};
#endif