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25 //
26 // neutron_hp -- source file
27 // J.P. Wellisch, Nov-1996
28 // A prototype of the low energy neutron transport model.
29 //
30 // 070618 fix memory leaking by T. Koi
31 // 071002 enable cross section dump by T. Koi
32 // 081024 G4NucleiPropertiesTable:: to G4NucleiProperties::
33 // 081124 Protect invalid read which caused run time errors by T. Koi
34 // 100729 Add safty for 0 lenght cross sections by T. Ko
35 // P. Arce, June-2014 Conversion neutron_hp to particle_hp
36 //
37 #include "G4ParticleHPFissionData.hh"
38
39 #include "G4ElementTable.hh"
40 #include "G4HadronicParameters.hh"
41 #include "G4Neutron.hh"
42 #include "G4NucleiProperties.hh"
43 #include "G4ParticleHPData.hh"
44 #include "G4ParticleHPManager.hh"
45 #include "G4PhysicalConstants.hh"
46 #include "G4Pow.hh"
47 #include "G4SystemOfUnits.hh"
48
49 G4ParticleHPFissionData::G4ParticleHPFissionData() : G4VCrossSectionDataSet("NeutronHPFissionXS")
50 {
51 SetMinKinEnergy(0 * MeV);
52 SetMaxKinEnergy(20 * MeV);
53
54 theCrossSections = nullptr;
55 instanceOfWorker = false;
56 if (G4Threading::IsWorkerThread()) {
57 instanceOfWorker = true;
58 }
59 element_cache = nullptr;
60 material_cache = nullptr;
61 ke_cache = 0.0;
62 xs_cache = 0.0;
63 }
64
65 G4ParticleHPFissionData::~G4ParticleHPFissionData()
66 {
67 if (theCrossSections != nullptr && !instanceOfWorker) {
68 theCrossSections->clearAndDestroy();
69 delete theCrossSections;
70 theCrossSections = nullptr;
71 }
72 }
73
74 G4bool G4ParticleHPFissionData::IsIsoApplicable(const G4DynamicParticle* dp, G4int /*Z*/,
75 G4int /*A*/, const G4Element* /*elm*/,
76 const G4Material* /*mat*/)
77 {
78 G4double eKin = dp->GetKineticEnergy();
79 return eKin <= GetMaxKinEnergy() && eKin >= GetMinKinEnergy()
80 && dp->GetDefinition() == G4Neutron::Neutron();
81 }
82
83 G4double G4ParticleHPFissionData::GetIsoCrossSection(const G4DynamicParticle* dp, G4int /*Z*/,
84 G4int /*A*/, const G4Isotope* /*iso*/,
85 const G4Element* element,
86 const G4Material* material)
87 {
88 if (dp->GetKineticEnergy() == ke_cache && element == element_cache && material == material_cache)
89 return xs_cache;
90
91 ke_cache = dp->GetKineticEnergy();
92 element_cache = element;
93 material_cache = material;
94 G4double xs = GetCrossSection(dp, element, material->GetTemperature());
95 xs_cache = xs;
96 return xs;
97 }
98
99 void G4ParticleHPFissionData::BuildPhysicsTable(const G4ParticleDefinition&)
100 {
101 if (G4Threading::IsWorkerThread()) {
102 theCrossSections = G4ParticleHPManager::GetInstance()->GetFissionCrossSections();
103 return;
104 }
105
106 std::size_t numberOfElements = G4Element::GetNumberOfElements();
107 if (theCrossSections == nullptr)
108 theCrossSections = new G4PhysicsTable(numberOfElements);
109 else
110 theCrossSections->clearAndDestroy();
111
112 // make a PhysicsVector for each element
113
114 auto theElementTable = G4Element::GetElementTable();
115 for (std::size_t i = 0; i < numberOfElements; ++i) {
116 G4PhysicsVector* physVec = G4ParticleHPData::Instance(G4Neutron::Neutron())
117 ->MakePhysicsVector((*theElementTable)[i], this);
118 theCrossSections->push_back(physVec);
119 }
120
121 G4ParticleHPManager::GetInstance()->RegisterFissionCrossSections(theCrossSections);
122 }
123
124 void G4ParticleHPFissionData::DumpPhysicsTable(const G4ParticleDefinition&)
125 {
126 #ifdef G4VERBOSE
127 if (G4HadronicParameters::Instance()->GetVerboseLevel() == 0) return;
128
129 //
130 // Dump element based cross section
131 // range 10e-5 eV to 20 MeV
132 // 10 point per decade
133 // in barn
134 //
135 G4cout << G4endl;
136 G4cout << G4endl;
137 G4cout << "Fission Cross Section of Neutron HP" << G4endl;
138 G4cout << "(Pointwise cross-section at 0 Kelvin.)" << G4endl;
139 G4cout << G4endl;
140 G4cout << "Name of Element" << G4endl;
141 G4cout << "Energy[eV] XS[barn]" << G4endl;
142 G4cout << G4endl;
143
144 std::size_t numberOfElements = G4Element::GetNumberOfElements();
145 auto theElementTable = G4Element::GetElementTable();
146
147 for (std::size_t i = 0; i < numberOfElements; ++i) {
148 G4cout << (*theElementTable)[i]->GetName() << G4endl;
149
150 if ((*((*theCrossSections)(i))).GetVectorLength() == 0) {
151 G4cout << "The cross-section data of the fission of this element is not available." << G4endl;
152 G4cout << G4endl;
153 continue;
154 }
155
156 for (G4int ie = 0; ie < 130; ++ie) {
157 G4double eKinetic = 1.0e-5 * G4Pow::GetInstance()->powA(10.0, ie / 10.0) * eV;
158 G4bool outOfRange = false;
159
160 if (eKinetic < 20 * MeV) {
161 G4cout << eKinetic / eV << " "
162 << (*((*theCrossSections)(i))).GetValue(eKinetic, outOfRange) / barn << G4endl;
163 }
164 }
165
166 G4cout << G4endl;
167 }
168 #endif
169 }
170
171 G4double G4ParticleHPFissionData::GetCrossSection(const G4DynamicParticle* aP, const G4Element* anE,
172 G4double aT)
173 {
174 G4double result = 0;
175 if (anE->GetZ() < 88) return result;
176 G4bool outOfRange;
177 auto index = (G4int)anE->GetIndex();
178
179 if (((*theCrossSections)(index))->GetVectorLength() == 0) return result;
180
181 // prepare neutron
182 G4double eKinetic = aP->GetKineticEnergy();
183 G4ReactionProduct theNeutronRP(aP->GetDefinition());
184 theNeutronRP.SetMomentum(aP->GetMomentum());
185 theNeutronRP.SetKineticEnergy(eKinetic);
186
187 if (G4ParticleHPManager::GetInstance()->GetNeglectDoppler()) {
188 // NEGLECT_DOPPLER
189 G4double factor = 1.0;
190 if (eKinetic < aT * k_Boltzmann) {
191 // below 0.1 eV neutrons
192 // Have to do some, but now just igonre.
193 // Will take care after performance check.
194 // factor = factor * targetV;
195 }
196 return ((*((*theCrossSections)(index))).GetValue(eKinetic, outOfRange)) * factor;
197 }
198
199 // prepare thermal nucleus
200 G4Nucleus aNuc;
201 G4double eps = 0.0001;
202 G4double theA = anE->GetN();
203 G4double theZ = anE->GetZ();
204 G4double eleMass;
205 eleMass = (G4NucleiProperties::GetNuclearMass(static_cast<G4int>(theA + eps),
206 static_cast<G4int>(theZ + eps)))
207 / G4Neutron::Neutron()->GetPDGMass();
208
209 G4ReactionProduct boosted;
210 G4double aXsection;
211
212 // MC integration loop
213 G4int counter = 0;
214 G4double buffer = 0;
215 G4int size = G4int(std::max(10., aT / 60 * kelvin));
216 G4ThreeVector neutronVelocity =
217 1. / G4Neutron::Neutron()->GetPDGMass() * theNeutronRP.GetMomentum();
218 G4double neutronVMag = neutronVelocity.mag();
219
220 while (counter == 0
221 || std::abs(buffer - result / std::max(1, counter))
222 > 0.01 * buffer) // Loop checking, 11.05.2015, T. Koi
223 {
224 if (counter != 0) buffer = result / counter;
225 while (counter < size) // Loop checking, 11.05.2015, T. Koi
226 {
227 counter++;
228 G4ReactionProduct aThermalNuc = aNuc.GetThermalNucleus(eleMass, aT);
229 boosted.Lorentz(theNeutronRP, aThermalNuc);
230 G4double theEkin = boosted.GetKineticEnergy();
231 aXsection = (*((*theCrossSections)(index))).GetValue(theEkin, outOfRange);
232 // velocity correction.
233 G4ThreeVector targetVelocity = 1. / aThermalNuc.GetMass() * aThermalNuc.GetMomentum();
234 aXsection *= (targetVelocity - neutronVelocity).mag() / neutronVMag;
235 result += aXsection;
236 }
237 size += size;
238 }
239 result /= counter;
240 return result;
241 }
242
243 G4int G4ParticleHPFissionData::GetVerboseLevel() const
244 {
245 return G4ParticleHPManager::GetInstance()->GetVerboseLevel();
246 }
247
248 void G4ParticleHPFissionData::SetVerboseLevel(G4int newValue)
249 {
250 G4ParticleHPManager::GetInstance()->SetVerboseLevel(newValue);
251 }
252
253 void G4ParticleHPFissionData::CrossSectionDescription(std::ostream& outFile) const
254 {
255 outFile << "High Precision cross data based on Evaluated Nuclear Data Files (ENDF)\n"
256 << "for induced fission reaction of neutrons below 20MeV\n";
257 }
258