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author | priyanka | 2015-06-24 15:03:17 +0530 |
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committer | priyanka | 2015-06-24 15:03:17 +0530 |
commit | b1f5c3f8d6671b4331cef1dcebdf63b7a43a3a2b (patch) | |
tree | ab291cffc65280e58ac82470ba63fbcca7805165 /3269/CH4 | |
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initial commit / add all books
Diffstat (limited to '3269/CH4')
-rwxr-xr-x | 3269/CH4/EX4.1/Ex4_1.sce | 24 | ||||
-rwxr-xr-x | 3269/CH4/EX4.2/Ex4_2.sce | 24 | ||||
-rwxr-xr-x | 3269/CH4/EX4.3/Ex4_3.sce | 30 | ||||
-rw-r--r-- | 3269/CH4/EX4.4/Ex4_4.sce | 28 | ||||
-rwxr-xr-x | 3269/CH4/EX4.5/Ex4_5.sce | 14 | ||||
-rw-r--r-- | 3269/CH4/EX4.6/Ex4_6.sce | 33 |
6 files changed, 153 insertions, 0 deletions
diff --git a/3269/CH4/EX4.1/Ex4_1.sce b/3269/CH4/EX4.1/Ex4_1.sce new file mode 100755 index 000000000..e31dd6da0 --- /dev/null +++ b/3269/CH4/EX4.1/Ex4_1.sce @@ -0,0 +1,24 @@ +// Example 4.1
+clear all;
+clc;
+
+// Given data
+// Number of neutrons absorbed by Uranium-238 in resonances for every neutron absorbed in Uranium-235
+n_resonance = 0.254;
+// Number of neutrons absorbed by Uranium-238 at thermal energy for every neutron absorbed in Uranium-235
+n_th = 0.64;
+m = 1; // Amount of Uranium-235 consumed in kg
+A_U = 235; // Atomic mass number of Uranium-235
+A_Pu = 239; // Atomic mass number of Plutonium-239
+
+// 1.
+// Calculation
+C = n_resonance+n_th;
+// Result
+printf('\n Conversion ratio of the reactor = %4.3f \n',C);
+
+// 2.
+// Calculation
+amt_Pu = m*C*A_Pu/A_U;
+// Result
+printf('\n Amount of Plutonium-239 produced in the reactor = %4.3f kg \n',amt_Pu);
diff --git a/3269/CH4/EX4.2/Ex4_2.sce b/3269/CH4/EX4.2/Ex4_2.sce new file mode 100755 index 000000000..632e7a8f2 --- /dev/null +++ b/3269/CH4/EX4.2/Ex4_2.sce @@ -0,0 +1,24 @@ +// Example 4.2
+clear all;
+clc;
+
+// Given data
+wP0 = 1; // Total fuel consumption rate in terms of kg/day
+M = 500; // Amount of Plutonium-239 in kg at startup of the reactor
+breeding_gain = 0.15; // Breeding gain of the reactor
+
+// 1.
+printf(" The Fast breeder reactor produces %.2f kg of plutonium-239 more for every kilogram consumed \n",breeding_gain);
+// Calculation
+// 1 year = 365 days
+production_rate = ceil(breeding_gain*365);
+// Result
+printf("\n Production rate of plutonium-239 = %3.2f kg/day = %d kg/year",breeding_gain,production_rate);
+
+// 2.
+// Calculation
+t_Dl = M/production_rate;
+t_De = log(2)*t_Dl;
+// Result
+printf(" \n Linear doubling time of plutonium fuel in the reactor = %2.1f years \n",t_Dl);
+printf(" \n Exponential doubling time of plutonium fuel in the reactor = %2.1f years \n",t_De);
diff --git a/3269/CH4/EX4.3/Ex4_3.sce b/3269/CH4/EX4.3/Ex4_3.sce new file mode 100755 index 000000000..782f847ab --- /dev/null +++ b/3269/CH4/EX4.3/Ex4_3.sce @@ -0,0 +1,30 @@ +// Example 4.3
+clear all;
+clc;
+
+// Given data
+power = 3300; // Reactor power in MW
+time = 750; // Reactor operation time in days
+amt_UO2 = 98; // Amount of Uranium dioxide (UO2) in metric tons
+atwt_U = 238; // As the enrichment of Uranium-235 is 3 w/o the majority portion is Uranium-238
+molwt_O = 16; // Molecular weight of Oxygen
+
+
+// 1.
+amt_U = amt_UO2*atwt_U/(atwt_U+2*molwt_O); // Amount of uranium in tonne
+total_burnup = power*time; // Total burnup in MWd
+// Calculation
+specific_burnup = total_burnup/amt_U;
+// Result
+printf(" \n Specific burnup = %3.2f MWd/tonne \n",specific_burnup);
+
+// 2.
+// Due to fission of 1.05 g of Uranium-235, 1 MWd of energy is released.
+m = 1.05;
+P = 10^6;
+maxth_burnup = P/m; // Theoritical maximum burnup
+// Calculation of Fractional burnup
+bet = specific_burnup/maxth_burnup;
+// Result
+printf(" \n Fractional burnup = %3.2f percent \n",bet*100);
+// Due to approximation of specific burnup value, there is a slight change in fractional burnup value as compared to the textbook value.
diff --git a/3269/CH4/EX4.4/Ex4_4.sce b/3269/CH4/EX4.4/Ex4_4.sce new file mode 100644 index 000000000..552239457 --- /dev/null +++ b/3269/CH4/EX4.4/Ex4_4.sce @@ -0,0 +1,28 @@ +// Example 4.4
+clear all;
+clc;
+
+// Given data
+ratpower = 1075; // Output rated electrical power in MWe of the reactor
+delpower_yr = 255000; // Net output power delivered in one year in terms of MWd
+time_refuel = 28; // Number of days the plant was shutdown for refuelling
+time_repairs = 45; // Number of days the plant was shutdown for repairs
+time_convrepairs = 18; // Number of days the plant was shutdown for conventional repairs
+
+// 1.
+// 1 year = 365 days
+ratpower_yr = ratpower*365; // Net output rated power in one year in terms of MWd
+// Calculation
+cap_factor = delpower_yr/ratpower_yr;
+// Result
+printf(" \n Plant capacity factor = %d percent\n",ceil(cap_factor*100));
+
+// 2.
+// Number of days the plant was shutdown in one year
+total_shutdown = time_refuel+time_repairs+time_convrepairs;
+// Number of days the plant was operable in one year
+total_operation = 365-total_shutdown;
+// Calculation
+ava_factor = total_operation/365;
+// Result
+printf(" \n Plant availability factor = %d percent\n",ava_factor*100);
diff --git a/3269/CH4/EX4.5/Ex4_5.sce b/3269/CH4/EX4.5/Ex4_5.sce new file mode 100755 index 000000000..8de1ba2af --- /dev/null +++ b/3269/CH4/EX4.5/Ex4_5.sce @@ -0,0 +1,14 @@ +// Example 4.5
+clear all;
+clc;
+
+// Given data
+t = 30; // Time of uranium sufficiency in years
+// Assuming once through Light Water Reactor (LWR)fuel cycle
+U_LWR = 0.0055; // Uranium Utilization factor for LWR
+// Assuming once through Liquid Metal cooled Fast Breeder Reactor (LMFBR) fuel cycle
+U_LMFBR = 0.67; // Uranium Utilization factor for LMFBR
+// Estimation
+est_time = 30*U_LMFBR/U_LWR;
+// Result
+printf("The time for which Uranium would fuel LMFBR = %d years \n",ceil(est_time));
diff --git a/3269/CH4/EX4.6/Ex4_6.sce b/3269/CH4/EX4.6/Ex4_6.sce new file mode 100644 index 000000000..e2f3078b2 --- /dev/null +++ b/3269/CH4/EX4.6/Ex4_6.sce @@ -0,0 +1,33 @@ +// Example 4.6
+clear all;
+clc;
+
+// Given data
+A_U = 238; // Atomic Mass number of Uranium
+A_O = 16; // Atomic Mass number of Oxygen
+amt_UO2 = 33000; // Amount of Uranium dioxide (UO2) present in kilogram(kg)
+x_P = 0.032; // Enrichment of 3.2 w/o uranium product
+x_T = 0.002; // Enrichemnt of 0.2 w/o residual tails
+// From Figure 4.45
+x_F = 0.00711; // Enrichemnt of 0.711 w/o feed
+
+// 1.
+// Estimation of enriched uranium in kg
+M_P = A_U*amt_UO2/(A_U+2*A_O);
+// Estimation of amount of Uranium feed in kg
+M_F = ((x_P-x_T)/(x_F-x_T))*M_P;
+// Result
+printf(" \n The amount of uranium feed required per reload = %d kg \n",ceil(M_F));
+
+// 2.
+V_x_P = (1-2*x_P)*log((1-x_P)/x_P); // Value function of uranium product with enrichemnt of 3.2 w/o
+V_x_F = (1-2*x_F)*log((1-x_F)/x_F); // Value function of feed with enrichemnt of 0.711 w/o
+V_x_T = (1-2*x_T)*log((1-x_T)/x_T); // Value function of tallings with enrichemnt of 0.2 w/o
+rate_SWU = 130.75; // Enrichment cost in dollars per SWU
+// Calculation
+SWU = M_P*(V_x_P-V_x_T)-M_F*(V_x_F-V_x_T); // Separative Work (SWU) in kg
+enrich_cost = ceil(SWU)*rate_SWU; // Enrichment cost in dollars
+// Result
+printf("\n The enrichment cost = $ %d \n",ceil(enrich_cost));
+// Due to approximation of Separative Work Unit(SWU), there is a difference in the value of enrichment cost on comparison with the textbook value.
+
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