| Geant4 Cross Reference |
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25 //
26 // neutron_hp -- source file
27 // J.P. Wellisch, Nov-1996
28 // A prototype of the low energy neutron trans
29 //
30 // 070523 add neglecting doppler broadening on
31 // 070613 fix memory leaking by T. Koi
32 // 071002 enable cross section dump by T. Koi
33 // 080428 change checking point of "neglecting
34 // from GetCrossSection to BuildPhysics
35 // 081024 G4NucleiPropertiesTable:: to G4Nucle
36 //
37 // P. Arce, June-2014 Conversion neutron_hp to
38 // V. Ivanchenko July-2023 converted back
39 //
40 #include "G4NeutronHPCaptureData.hh"
41
42 #include "G4ElementTable.hh"
43 #include "G4HadronicParameters.hh"
44 #include "G4Neutron.hh"
45 #include "G4NucleiProperties.hh"
46 #include "G4ParticleHPData.hh"
47 #include "G4ParticleHPManager.hh"
48 #include "G4Element.hh"
49 #include "G4Material.hh"
50 #include "G4ParticleDefinition.hh"
51 #include "G4PhysicsTable.hh"
52 #include "G4PhysicalConstants.hh"
53 #include "G4Pow.hh"
54 #include "G4SystemOfUnits.hh"
55 #include "G4AutoLock.hh"
56
57 G4bool G4NeutronHPCaptureData::fLock = true;
58 G4PhysicsTable* G4NeutronHPCaptureData::theCro
59
60 namespace
61 {
62 G4Mutex theHPCaptureData = G4MUTEX_INITIALIZ
63 }
64
65 G4NeutronHPCaptureData::G4NeutronHPCaptureData
66 : G4VCrossSectionDataSet("NeutronHPCaptureXS
67 {
68 emax = 20.*CLHEP::MeV;
69 fManager = G4ParticleHPManager::GetInstance(
70 }
71
72 G4NeutronHPCaptureData::~G4NeutronHPCaptureDat
73 {
74 if (isFirst) {
75 if (nullptr != theCrossSections)
76 theCrossSections->clearAndDestroy();
77 delete theCrossSections;
78 theCrossSections = nullptr;
79 }
80 }
81
82 G4bool G4NeutronHPCaptureData::IsIsoApplicable
83
84
85
86 {
87 return true;
88 }
89
90 G4double G4NeutronHPCaptureData::GetIsoCrossSe
91
92
93
94
95 {
96 if (dp->GetKineticEnergy() == ke_cache && el
97 material == material_cache)
98 return xs_cache;
99
100 ke_cache = dp->GetKineticEnergy();
101 element_cache = element;
102 material_cache = material;
103 G4double xs = GetCrossSection(dp, element, m
104 xs_cache = xs;
105 return xs;
106 }
107
108 void G4NeutronHPCaptureData::BuildPhysicsTable
109 {
110 // the choice of the first instance
111 if (fLock) {
112 G4AutoLock l(&theHPCaptureData);
113 if (fLock) {
114 isFirst = true;
115 fLock = false;
116 }
117 l.unlock();
118 }
119 if (!isFirst) { return; }
120 if (p.GetParticleName() != "neutron") {
121 G4ExceptionDescription ed;
122 ed << p.GetParticleName() << " is a wrong
123 << " only neutron is allowed";
124 G4Exception("G4NeutronHPCaptureData::Build
125 FatalException, ed, "");
126 return;
127 }
128
129 // initialisation for the first instance, ot
130 G4AutoLock l(&theHPCaptureData);
131 if (theCrossSections != nullptr) {
132 theCrossSections->clearAndDestroy();
133 delete theCrossSections;
134 }
135 std::size_t numberOfElements = G4Element::Ge
136 theCrossSections = new G4PhysicsTable(number
137
138 // make a PhysicsVector for each element
139 auto theElementTable = G4Element::GetElement
140 for (std::size_t i = 0; i < numberOfElements
141 auto elm = (*theElementTable)[i];
142 #ifdef G4VERBOSE
143 if (fManager->GetDEBUG()) {
144 G4cout << "ElementIndex " << elm->GetInd
145 << elm->GetName() << G4endl;
146 }
147 #endif
148 G4PhysicsVector* physVec =
149 G4ParticleHPData::Instance(G4Neutron::Ne
150 theCrossSections->push_back(physVec);
151 }
152 fManager->RegisterCaptureCrossSections(theCr
153 l.unlock();
154 }
155
156 void G4NeutronHPCaptureData::DumpPhysicsTable(
157 {
158 #ifdef G4VERBOSE
159 if (fManager->GetVerboseLevel() == 0) return
160
161 //
162 // Dump element based cross section
163 // range 10e-5 eV to 20 MeV
164 // 10 point per decade
165 // in barn
166 //
167
168 G4cout << G4endl;
169 G4cout << G4endl;
170 G4cout << "Capture Cross Section of Neutron
171 G4cout << "(Pointwise cross-section at 0 Kel
172 G4cout << G4endl;
173 G4cout << "Name of Element" << G4endl;
174 G4cout << "Energy[eV] XS[barn]" << G4endl;
175 G4cout << G4endl;
176
177 std::size_t numberOfElements = G4Element::Ge
178 auto theElementTable = G4Element::GetElement
179
180 for (std::size_t i = 0; i < numberOfElements
181 G4cout << (*theElementTable)[i]->GetName()
182 G4cout << *((*theCrossSections)(i)) << G4e
183 }
184 #endif
185 }
186
187 G4double G4NeutronHPCaptureData::GetCrossSecti
188
189
190 {
191 G4double result = 0;
192 auto idx = (G4int)anE->GetIndex();
193
194 // prepare neutron
195 G4double eKinetic = aP->GetKineticEnergy();
196 if (eKinetic >= emax) { return 0.0; }
197
198 // NEGLECT_DOPPLER
199 if (fManager->GetNeglectDoppler()) {
200 return (*((*theCrossSections)(idx))).Value
201 }
202
203 G4ReactionProduct theNeutron(aP->GetDefiniti
204 theNeutron.SetMomentum(aP->GetMomentum());
205 theNeutron.SetKineticEnergy(eKinetic);
206
207 // prepare thermal nucleus
208 G4Nucleus aNuc;
209 G4int theA = anE->GetN();
210 G4int theZ = anE->GetZasInt();
211 G4double eleMass = G4NucleiProperties::GetNu
212 / CLHEP::neutron_mass_c2;
213
214 G4ReactionProduct boosted;
215 G4double aXsection;
216
217 // MC integration loop
218 G4int counter = 0;
219 G4double buffer = 0;
220 G4int size = G4int(std::max(10., aT / 60 * k
221 G4ThreeVector neutronVelocity =
222 1. / G4Neutron::Neutron()->GetPDGMass() *
223 G4double neutronVMag = neutronVelocity.mag()
224
225 while (counter == 0 ||
226 std::abs(buffer - result / std::max(1
227 // Loop checking, 11.05.2015, T. Koi
228 {
229 if (counter != 0) buffer = result / counte
230 while (counter < size) // Loop checking,
231 {
232 ++counter;
233 G4ReactionProduct aThermalNuc = aNuc.Get
234 boosted.Lorentz(theNeutron, aThermalNuc)
235 G4double theEkin = boosted.GetKineticEne
236 aXsection = (*((*theCrossSections)(idx))
237 // velocity correction, or luminosity fa
238 G4ThreeVector targetVelocity = 1. / aThe
239 aXsection *= (targetVelocity - neutronVe
240 result += aXsection;
241 }
242 size += size;
243 }
244 result /= counter;
245 /*
246 // Checking impact of G4NEUTRONHP_NEGLECT
247 G4cout << " result " << result << " "
248 << (*((*theCrossSections)(index))).
249 << (*((*theCrossSections)(index))).
250 */
251 return result;
252 }
253
254 void G4NeutronHPCaptureData::CrossSectionDescr
255 {
256 outF << "High Precision cross data based on
257 << " (ENDF) for radiative capture react
258 }
259