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IN NO 43 // EVENT SHALL THE AUTHOR BE LIABLE FOR ANY DI 43 // EVENT SHALL THE AUTHOR BE LIABLE FOR ANY DIRECT, INDIRECT, INCIDENTAL, 44 // SPECIAL, EXEMPLARY, OR CONSEQUENTIAL DAMAGE 44 // SPECIAL, EXEMPLARY, OR CONSEQUENTIAL DAMAGES (INCLUDING, BUT NOT LIMITED TO, 45 // PROCUREMENT OF SUBSTITUTE GOODS OR SERVICES 45 // PROCUREMENT OF SUBSTITUTE GOODS OR SERVICES; LOSS OF USE, DATA, OR PROFITS; 46 // OR BUSINESS INTERRUPTION) HOWEVER CAUSED AN 46 // OR BUSINESS INTERRUPTION) HOWEVER CAUSED AND ON ANY THEORY OF LIABILITY, 47 // WHETHER IN CONTRACT, STRICT LIABILITY, OR T 47 // WHETHER IN CONTRACT, STRICT LIABILITY, OR TORT (INCLUDING NEGLIGENCE OR 48 // OTHERWISE) ARISING IN ANY WAY OUT OF THE US 48 // OTHERWISE) ARISING IN ANY WAY OUT OF THE USE OF THIS SOFTWARE, EVEN IF 49 // ADVISED OF THE POSSIBILITY OF SUCH DAMAGE. 49 // ADVISED OF THE POSSIBILITY OF SUCH DAMAGE. 50 // 50 // 51 // Copyright (c) 2006 The Regents of the Unive 51 // Copyright (c) 2006 The Regents of the University of California. 52 // All rights reserved. 52 // All rights reserved. 53 // UCRL-CODE-224807 53 // UCRL-CODE-224807 54 // 54 // 55 // 55 // 56 // 56 // 57 57 58 #include "G4fissionEvent.hh" 58 #include "G4fissionEvent.hh" 59 59 60 #define nSPfissIso 8 60 #define nSPfissIso 8 61 #define nSPfissn 11 61 #define nSPfissn 11 62 62 63 G4int G4fissionEvent::G4SmpSpNuDistData(G4int 63 G4int G4fissionEvent::G4SmpSpNuDistData(G4int isotope, G4int Cf252option) { 64 64 65 /* 65 /* 66 Description 66 Description 67 Sample Number of Neutrons from spontaneous 67 Sample Number of Neutrons from spontaneous fission 68 (a) from the neutron multiplicity data for 68 (a) from the neutron multiplicity data for 69 U-238, Pu-238, Pu-240, Pu-242, Cm-242, 69 U-238, Pu-238, Pu-240, Pu-242, Cm-242, Cm-244 70 using Holden and Zucker's tabulated 70 using Holden and Zucker's tabulated data 71 Cf-252 using either Spencer's tabulate 71 Cf-252 using either Spencer's tabulated data or 72 Boldeman's data 72 Boldeman's data 73 (b) from Terrell's approximation using nub 73 (b) from Terrell's approximation using nubar for 74 Th-232, 74 Th-232, 75 U-232, U-233, U-234, U-235, U-236, 75 U-232, U-233, U-234, U-235, U-236, 76 Np-237, 76 Np-237, 77 Pu-239, Pu-241, 77 Pu-239, Pu-241, 78 Am-241, 78 Am-241, 79 Bk-249 79 Bk-249 80 using Ensslin's data. 80 using Ensslin's data. 81 */ 81 */ 82 82 83 /* 83 /* 84 Input 84 Input 85 iso - isotope 85 iso - isotope 86 Cf252option - 0 to use Spencer's tabulate 86 Cf252option - 0 to use Spencer's tabulated data 87 1 to use Boldeman's data 87 1 to use Boldeman's data 88 Output 88 Output 89 G4SmpSpNuDistData - sampled multiplicity 89 G4SmpSpNuDistData - sampled multiplicity 90 -1 is the isotope has 90 -1 is the isotope has 91 no multiplicity data, 91 no multiplicity data, 92 nor any nubar data 92 nor any nubar data 93 */ 93 */ 94 94 95 G4int i, index; 95 G4int i, index; 96 G4double sum, nubar; 96 G4double sum, nubar; 97 G4double r; 97 G4double r; 98 98 99 static G4double sfnu [nSPfissIso][nSPfissn] 99 static G4double sfnu [nSPfissIso][nSPfissn] = { 100 {0.0481677,0.2485215,0.4253044,0.2284094,0 100 {0.0481677,0.2485215,0.4253044,0.2284094,0.0423438,0.0072533, 101 0.0000000,0.0000000,0.0000000,0.0000000,0 101 0.0000000,0.0000000,0.0000000,0.0000000,0.0000000}, 102 102 103 {0.0631852,0.2319644,0.3333230,0.2528207,0 103 {0.0631852,0.2319644,0.3333230,0.2528207,0.0986461,0.0180199, 104 0.0020407,0.0000000,0.0000000,0.0000000,0 104 0.0020407,0.0000000,0.0000000,0.0000000,0.0000000}, 105 105 106 {0.0679423,0.2293159,0.3341228,0.2475507,0 106 {0.0679423,0.2293159,0.3341228,0.2475507,0.0996922,0.0182398, 107 0.0031364,0.0000000,0.0000000,0.0000000,0 107 0.0031364,0.0000000,0.0000000,0.0000000,0.0000000}, 108 108 109 {0.0212550,0.1467407,0.3267531,0.3268277,0 109 {0.0212550,0.1467407,0.3267531,0.3268277,0.1375090,0.0373815, 110 0.0025912,0.0007551,0.0001867,0.0000000,0 110 0.0025912,0.0007551,0.0001867,0.0000000,0.0000000}, 111 111 112 {0.0150050,0.1161725,0.2998427,0.3331614,0 112 {0.0150050,0.1161725,0.2998427,0.3331614,0.1837748,0.0429780, 113 0.0087914,0.0002744,0.0000000,0.0000000,0 113 0.0087914,0.0002744,0.0000000,0.0000000,0.0000000}, 114 114 115 {0.0540647,0.2053880,0.3802279,0.2248483,0 115 {0.0540647,0.2053880,0.3802279,0.2248483,0.1078646,0.0276366, 116 0.0000000,0.0000000,0.0000000,0.0000000,0 116 0.0000000,0.0000000,0.0000000,0.0000000,0.0000000}, 117 117 118 {0.0021100,0.0246700,0.1229000,0.2714400,0 118 {0.0021100,0.0246700,0.1229000,0.2714400,0.3076300,0.1877000, 119 0.0677000,0.0140600,0.0016700,0.0001000,0 119 0.0677000,0.0140600,0.0016700,0.0001000,0.0000000}, 120 120 121 {0.0020900,0.0262100,0.1262000,0.2752000,0 121 {0.0020900,0.0262100,0.1262000,0.2752000,0.3018000,0.1846000, 122 0.0668000,0.0150000,0.0021000,0.0000000,0 122 0.0668000,0.0150000,0.0021000,0.0000000,0.0000000} }; 123 123 124 /* 124 /* 125 sample the spontaneous fission neutron numbe 125 sample the spontaneous fission neutron number distribution 126 */ 126 */ 127 index = -1; 127 index = -1; 128 128 129 if (isotope == 92238) index = 0; 129 if (isotope == 92238) index = 0; 130 else if (isotope == 94240) index = 1; 130 else if (isotope == 94240) index = 1; 131 else if (isotope == 94242) index = 2; 131 else if (isotope == 94242) index = 2; 132 else if (isotope == 96242) index = 3; 132 else if (isotope == 96242) index = 3; 133 else if (isotope == 96244) index = 4; 133 else if (isotope == 96244) index = 4; 134 else if (isotope == 94238) index = 5; 134 else if (isotope == 94238) index = 5; 135 else if (isotope == 98252 && Cf252option == 135 else if (isotope == 98252 && Cf252option == 0) index = 6; 136 else if (isotope == 98252 && Cf252option == 136 else if (isotope == 98252 && Cf252option == 1) index = 7; 137 137 138 if (index != -1) { 138 if (index != -1) { 139 r=fisslibrng(); 139 r=fisslibrng(); 140 140 141 sum = 0.; 141 sum = 0.; 142 for (i = 0; i < nSPfissn-1; i++) { 142 for (i = 0; i < nSPfissn-1; i++) { 143 sum = sum + sfnu[index][i]; 143 sum = sum + sfnu[index][i]; 144 if (r <= sum || sfnu[index][i+1] == 0.) 144 if (r <= sum || sfnu[index][i+1] == 0.) return i; 145 } 145 } 146 // 146 // 147 // Fall through 147 // Fall through 148 // 148 // 149 G4cout << " Random number out of range in 149 G4cout << " Random number out of range in SmpSpNuDistData " << G4endl; 150 return -1; 150 return -1; 151 151 152 } else { 152 } else { 153 // There is no full multiplicity distribution 153 // There is no full multiplicity distribution data available 154 // for that isotope, let's try to find a nubar 154 // for that isotope, let's try to find a nubar for it in 155 // N. Ensslin, et.al., "Application Guide to N 155 // N. Ensslin, et.al., "Application Guide to Neutron 156 // Multiplicity Counting," LA-13422-M (Novembe 156 // Multiplicity Counting," LA-13422-M (November 1998) 157 // and use Terrell's approximation 157 // and use Terrell's approximation 158 nubar = G4SmpSpNubarData(isotope); 158 nubar = G4SmpSpNubarData(isotope); 159 if (nubar != -1.) { 159 if (nubar != -1.) { 160 return (G4int) G4SmpTerrell(nubar); 160 return (G4int) G4SmpTerrell(nubar); 161 } else { 161 } else { 162 // There is no nubar information for that isot 162 // There is no nubar information for that isotope, return -1, 163 // meaning no data available for that isotope 163 // meaning no data available for that isotope 164 return -1; 164 return -1; 165 } 165 } 166 } 166 } 167 } 167 } 168 168