From 691d8f30aa22efcdb90391f8d51bfe5f7d574c1f Mon Sep 17 00:00:00 2001 From: lukelabrie Date: Thu, 20 Feb 2025 14:36:15 +0100 Subject: [PATCH] clean up pump transient writeup --- .../parameters_U233.py | 154 ------------- .../parameters_U235.py | 202 ------------------ .../pump_transients.ipynb | 3 +- .../steady_state.ipynb | 22 -- 4 files changed, 2 insertions(+), 379 deletions(-) delete mode 100644 dynamic_model/pump_transient_benchmark/parameters_U233.py delete mode 100644 dynamic_model/pump_transient_benchmark/parameters_U235.py delete mode 100644 dynamic_model/pump_transient_benchmark/steady_state.ipynb diff --git a/dynamic_model/pump_transient_benchmark/parameters_U233.py b/dynamic_model/pump_transient_benchmark/parameters_U233.py deleted file mode 100644 index aab95ea..0000000 --- a/dynamic_model/pump_transient_benchmark/parameters_U233.py +++ /dev/null @@ -1,154 +0,0 @@ -import numpy as np - - - -# domain -t0 = 0.0 -tf = 1000.00 -T = np.arange(t0,tf,0.01) - -# REACTIVITY INSERTION -inserted = 1.39e-4 # 1MW -# inserted = 1.96e-4 # 5MW -# inserted = 2.48e-4 # 8MW - -# NEUTRONICS DATA -tau_l = 16.73 -tau_c = 8.46 -# P = 0.1 -P = 1 -# P = 5 -# P = 8 -n_frac0 = 1 # initial fractional neutron density n/n0 -Lam = 4.0E-04 -lam = np.array([1.260E-02, 3.370E-02, 1.390E-01, 3.250E-01, 1.130E+00, 2.500E+00]) -beta = np.array([0.00023, 0.00079, 0.00067, 0.00073, 0.00013, 0.00009]) -beta_t = np.sum(beta) # total delayed neutron fraction MSRE -rho_0 = beta_t-sum(np.divide(beta,1+np.divide(1-np.exp(-lam*tau_l),lam*tau_c))) # reactivity change in going from stationary to circulating fuel -C0 = beta / Lam * (1.0 / (lam - (np.exp(-lam * tau_l) - 1.0) / tau_c)) - -# Feedback coefficients -a_f = -11.034E-5 -a_g = -05.814E-5 - -# CORE HEAT TRANSFER PARAMETERS -vdot_f = 7.5708E-02 -rho_f = 2.14647E+03 -W_f = 1.623879934566580e+02 -m_f = W_f * tau_c -nn_f = 2 -mn_f = m_f / nn_f -scp_f = 1.9665E-3 - -# Core Upflow -v_g = 1.95386 -rho_g = 1.860E3 -m_g = v_g * rho_g -scp_g = 1.773E-3 -mcp_g1 = m_g * scp_g -mcp_f1 = mn_f * scp_f -mcp_f2 = mn_f * scp_f -hA_fg = 0.02 * 9 / 5 -k_g = 0.07 -k_1 = 0.5 -k_2 = 0.5 -k_f = 0.93 -k_f1 = k_f / nn_f -k_f2 = k_f / nn_f - -# Heat Exchanger -d_he = 16 -h_he = 72 -od_tube = 0.5 -id_tube = od_tube - 2 * 0.042 -n_tube = 159 -a_tube = 254 * 144 -l_tube = a_tube / n_tube / (np.pi * od_tube) -v_tube = n_tube * np.pi * (od_tube / 2) ** 2 * l_tube -v_cool = n_tube * np.pi * (id_tube / 2) ** 2 * l_tube -v_he = (d_he / 2) ** 2 * np.pi * h_he -v_he_fuel = v_he - v_tube -in_m = 1.63871e-5 -W_p = W_f -m_p = v_he_fuel * in_m * rho_f -nn_p = 4 -mn_p = m_p / nn_p -cp_p = scp_f -vdot_s = 5.36265E-02 -rho_s = 1.922e3 -W_s = 1.005793369810108e+02 -m_s = v_cool * in_m * rho_s -nn_s = 4 -mn_s = m_s / nn_s -scp_s = 2.39E-3 -A_phe = 2.359E+01 -ha_p = 6.480E-01 -ha_s = 3.060E-01 -mcp_pn = mn_p * cp_p -hA_pn = ha_p / nn_s -nn_t = 2 -rho_tube = 8.7745E+03 -m_tn = (v_tube - v_cool) * in_m * rho_tube / nn_t -scp_t = 5.778E-04 -mcp_tn = m_tn * scp_t -mcp_sn = mn_s * scp_s -hA_sn = ha_s / nn_s - -# Initial conditions -Tf_in = 6.3222E+02 -T0_f2 = 6.5727E+02 -T0_f1 = Tf_in + (T0_f2 - Tf_in) / 2 -T0_g1 = T0_f1 + (k_g * P / hA_fg) -Tp_in = T0_f2 -T0_p4 = Tf_in -T0_p1 = Tp_in - (Tp_in - T0_p4) / 4 -T0_p2 = Tp_in - 2 * (Tp_in - T0_p4) / 4 -T0_p3 = Tp_in - 3 * (Tp_in - T0_p4) / 4 -Ts_in = 5.4611E+02 -T0_s4 = 5.7939E+02 -T0_s1 = Ts_in + (T0_s4 - Ts_in) / nn_s -T0_s2 = Ts_in + 2 * (T0_s4 - Ts_in) / nn_s -T0_s3 = Ts_in + 3 * (T0_s4 - Ts_in) / nn_s -T0_t1 = (T0_p1 * hA_pn + T0_s3 * hA_sn) / (hA_pn + hA_sn) -T0_t2 = (T0_p3 * hA_pn + T0_s1 * hA_sn) / (hA_pn + hA_sn) - -# Radiator Parameters -Trp_in = T0_s4 -T0_rp = Ts_in -Trs_in = 37.78 -T0_rs = 148.9 -od_rad = 0.01905 -tube_wall_thick = 0.0018288 -id_rad = od_rad - 2 * tube_wall_thick -n_rtubes = 120 -l_rtube = 9.144 -v_rp = np.pi * (id_rad / 2) ** 2 * l_rtube * n_rtubes -n_tpr = 12 -n_row = 10 -tube_space = 0.0381 -v_rs = (n_row * od_rad + (n_row - 1) * tube_space) * (n_tpr * od_rad + (n_tpr - 1) * tube_space) * l_rtube -W_rp = W_s -m_rp = v_rp * rho_s -nn_rp = 1 -mn_rp = m_rp / nn_rp -cp_rp = scp_s -vdot_rs = 94.389 -rho_rs = 1.1237 -W_rs = vdot_rs * rho_rs -m_rs = v_rs * rho_rs -nn_rs = 1 -mn_rs = m_rs / nn_rs -scp_rs = 1.0085E-3 -A_rad = 6.503E1 -h_roverall = P / A_rad / ((T0_rp + Trp_in) / 2 - (T0_rs + Trs_in) / 2) -mcp_rpn = mn_rp * cp_rp -hA_rpn = h_roverall * A_rad / nn_rs -mcp_rsn = mn_rs * scp_rs -hA_rsn = h_roverall * A_rad / nn_rs - -# Pure time delays between components -tau_hx_c = 8.67 #+2.145 -tau_c_hx = 3.77 #+2.145 -tau_hx_r = 4.71 -tau_r_hx = 8.24 - diff --git a/dynamic_model/pump_transient_benchmark/parameters_U235.py b/dynamic_model/pump_transient_benchmark/parameters_U235.py deleted file mode 100644 index 95e6c15..0000000 --- a/dynamic_model/pump_transient_benchmark/parameters_U235.py +++ /dev/null @@ -1,202 +0,0 @@ -import numpy as np -import math -pi = math.pi - -# domain -t0 = 0.0 -tf = 50000.00 -T = np.arange(t0,tf,1.0) - -# NEUTRONICS DATA -tau_l = 16.73 # ORNL-TM-0728 %16.44; % (s) -tau_c = 8.46 # ORNL-TM-0728 %8.460; % (s) -# P = 8.0 # Thermal Power in MW ORNL-TM-1070, p.2 -P = 1.0e-5 -n_frac0 = 1.0 # initial fractional neutron density n/n0 (n/cm^3/s) -Lam = 2.400E-04 # mean generation time ORNL-TM-1070 p.15 U235 -# Lam = 4.0E-04; # mean generation time ORNL-TM-1070 p.15 U233 -lam = np.array([1.240E-02, 3.05E-02, 1.11E-01, 3.01E-01, 1.140E+00, 3.014E+00]) -beta = np.array([0.000223, 0.001457, 0.001307, 0.002628, 0.000766, 0.00023]) # U235 -# beta = np.array([0.00023, 0.00079, 0.00067, 0.00073, 0.00013, 0.00009]) # U233 -beta_t = np.sum(beta) # total delayed neutron fraction MSRE -rho_0 = beta_t-sum(np.divide(beta,1+np.divide(1-np.exp(-lam*tau_l),lam*tau_c))) # reactivity change in going from stationary to circulating fuel -C0 = beta / Lam * (1.0 / (lam - (np.exp(-lam * tau_l) - 1.0) / tau_c)) - -# Feedback co-efficients -a_f = -8.71E-05 # U235 (drho/°C) fuel salt temperature-reactivity feedback coefficient ORNL-TM-1647 p.3 % -5.904E-05; % ORNL-TM-0728 p. 101 % -a_g = -6.66E-05 # U235 (drho/°C) graphite temperature-reactivity feedback coefficient ORNL-TM-1647 p.3 % -6.624E-05; % ORNL-TM-0728 p.101 - -# CORE HEAT TRANSFER PARAMETERS -# FUEL PARAMETERS - DONE -vdot_f = 7.5708E-02 # ORNL-TM-0728 % 7.571e-2; % vol. flow rate (m^3/s) ORNL-TM-1647 p.3, ORNL-TM-0728 p.12 -rho_f = 2.14647E+03 # (partially enriched U-235)ORNL-TM-0728 p.8 2.243E+03; % (Th-U) density of fuel salt (kg/m^3) ORNL-TM-0728 p.8 -W_f = 1.623879934566580e+02 # 1.83085e+02;%vdot_f*rho_f; % 182.78; % calcd from m_dot*cp*delT=P; vdot_f*rho_f; % fuel flow rate (kg/s) -# tau_f_c = tau_c; % ORNL-TM-0728 % 8.45; % transit time of fuel in core (s) ORNL-TM-1070 p.15, TDAMSRE p.5 -m_f = W_f * tau_c # fuel mass in core (kg) -nn_f = 2 # number of fuel nodes in core model -mn_f = m_f / nn_f # fuel mass per node (kg) -# cp_f = 4.2*9/5; % (MJ/deg-C) total fuel heat capacity TDAMSRE p.5 -scp_f = 1.9665E-3 # specific heat capacity of fuel salt (MJ/kg-C) ORNL-TM-0728 p.8 - -# Core Upflow - DONE -v_g = 1.95386 # graphite volume(m^3) ORNL-TM-0728 p. 101 -rho_g = 1.860E3 # graphite density (kg/m^3) ORNL-3812 p.77, ORNL-TM-0728 p.87 -m_g = v_g * rho_g # graphite mass (kg) -cp_g = 3.6 * 9 / 5 # TDAMSRE p.5 graphite total heat capacity (MW-s/C) ORNL-TM-1647 p.3 -scp_g = 1.773E-3 # cp_g/m_g; % graphite specific heat capacity (MW-s/kg-C) ORNL-TM-1647 p.3 -mcp_g1 = m_g * scp_g # (mass of material x heat capacity of material) of graphite per lump (MW-s/°C) -mcp_f1 = mn_f * scp_f # (mass of material x heat capacity of material) of fuel salt per lump (MW-s/°C) -mcp_f2 = mn_f * scp_f # (mass of material x heat capacity of material) of fuel salt per lump (MW-s/°C) -hA_fg = 0.02 * 9 / 5 # (fuel to graphite heat transfer coeff x heat transfer area) (MW/°C) ORNL-TM-1647 p.3, TDAMSRE p.5 -k_g = 0.07 # fraction of total power generated in the graphite ORNL-TM-0728 p.9 -k_1 = 0.5 # fraction of heat transferred from graphite which goes to the first fuel lump -k_2 = 0.5 # fraction of heat transferred from graphite which goes to the second fuel lump -k_f = 0.93 # fraction of heat generated in fuel - that generated in the external loop ORNL-TM-0728 p.9 -k_f1 = k_f / nn_f # fraction of total power generated in lump f1 -k_f2 = k_f / nn_f # fraction of total power generated in lump f2 - -# New node for power deposited in fuel outside the core -k_out = 1 - (k_g + k_f) # fraction of power generated in fuel in external loop ORNL-TM-0728 p.9 -m_out = W_f # (kg) Mass of node such that resident time is 1 sec (W_f needs to be defined) - -# Initial conditions - DONE -Tf_in = 6.3222E+02 # in °C ORNL-TM-1647 p.2 -T0_f2 = 6.5727E+02 # 6.5444E+02; % in °C 6.461904761904777e+02; ORNL-TM-1647 p.2 -T0_f1 = Tf_in + (T0_f2 - Tf_in) / 2 # 6.405952380952389e+02; in °C -T0_g1 = T0_f1 + (k_g * P / hA_fg) # 6.589285714285924e+02; in °C -# T0_out = k_out * P / m_out / scp_f + T0_f2 # in °C (scp_f needs to be defined) - - -# Heat Exchanger - DONE -# Geometry -d_he = 16 # (in) he diameter ORNL-TM-0728 p. 164 -h_he = 72 # (in) active height % 96; %(in) he height ORNL-TM-0728 p. 164 -od_tube = 0.5 # (in) coolant tube OD ORNL-TM-0728 p. 164 -id_tube = od_tube - 2 * 0.042 # (in) coolant tube ID ORNL-TM-0728 p. 164 -n_tube = 159 # number of coolant tubes ORNL-TM-0728 p. 164 -a_tube = 254 * 144 # (in^2) total area of tubes ORNL-TM-0728 p. 164 -l_tube = a_tube / n_tube / (np.pi * od_tube) # (in) tube length -v_tube = n_tube * np.pi * (od_tube / 2) ** 2 * l_tube # (in^3) hx shell volume occupied by tubes -v_cool = n_tube * np.pi * (id_tube / 2) ** 2 * l_tube # (in^3) hx volume occupied by coolant -v_he = (d_he / 2) ** 2 * np.pi * h_he # (in^3) volume of heat exchanger shell -v_he_fuel = v_he - v_tube # (in^3) volume available to fuel in shell - -# Unit conversions -in_m = 1.63871e-5 # 1 cubic inch = 1.63871e-5 cubic meters - -# PRIMARY FLOW PARAMETERS - DONE -W_p = W_f # fuel flow rate (kg/s) - -m_p = v_he_fuel * in_m * rho_f # fuel mass in PHE (kg) -nn_p = 4 # number of fuel nodes in PHE -mn_p = m_p / nn_p # fuel mass per node (kg) -cp_p = scp_f # fuel heat capacity (MJ/(kg-C)) - -# SECONDARY FLOW PARAMETERS - DONE -vdot_s = 5.36265E-02 # ORNL-TM-0728 p. 164 % 5.236E-02; % coolant volume flow rate (m^3/s) ORNL-TM-1647 p.3 -rho_s = 1.922e3 # coolant salt density (kg/m^3) ORNL-TM-0728 p.8 -W_s = 1.005793369810108e+02 # vdot_s*rho_s; % calcd from mdot*cp*delT; vdot_s*rho_s; % coolant flow rate (kg/s) ORNL-TM-1647 p.3 - -m_s = v_cool * in_m * rho_s # coolant mass in PHE (kg) -nn_s = 4 # number of coolant nodes in PHE -mn_s = m_s / nn_s # coolant mass per node (kg) -scp_s = 2.39E-3 # cp_s/m_s; % specific heat capacity of coolant (MJ/(kg-C) ORNL-TM-0728 p.8 - -A_phe = 2.359E+01 # effective area for heat transfer (primary and secondary, m^2) ORNL-TM-0728 p.164 - -ha_p = 6.480E-01 # heat transfer*area coefficient from primary to tubes (MW/C) ORNL-TM-1647 p.3 -ha_s = 3.060E-01 # heat transfer*area coefficient from tubes to secondary (MW/C) ORNL-TM-1647 p.3 - -# Primary Side -mcp_pn = mn_p * cp_p # (mass of material x heat capacity of material) of fuel salt per lump in MW-s/°C -hA_pn = ha_p / nn_s # 3.030; % (primary to tube heat transfer coeff x heat transfer area) in MW/°C - -# Tubes - DONE -nn_t = 2 # number of nodes of tubes in the model -rho_tube = 8.7745E+03 # (kg/m^3) density of INOR-8 ORNL-TM-0728 p.20 -m_tn = (v_tube - v_cool) * in_m * rho_tube / nn_t # mass of tubes (kg) -scp_t = 5.778E-04 # specific heat capacity of tubes (MJ/(kg-C)) ORNL-TM-0728 p.20 -mcp_tn = m_tn * scp_t # mass*(heat capacity) of tubes per lump in MW-s/°C - -# Secondary Side - DONE -mcp_sn = mn_s * scp_s # (mass of material x heat capacity of material) of coolant salt per lump in MW-s/°C -hA_sn = ha_s / nn_s # (tube to secondary heat transfer coeff x heat transfer area) in MW/°C - -# Initial conditions - DONE -# Primary nodes -Tp_in = T0_f2 # in °C ORNL-TM-1647 p.2 -T0_p4 = Tf_in # 6.5444E+02; % in °C 6.461904761904777e+02; ORNL-TM-1647 p.2 -T0_p1 = Tp_in + (T0_p4 - Tp_in) / 4 # in °C -T0_p2 = Tp_in + 2 * (T0_p4 - Tp_in) / 4 # in °C -T0_p3 = Tp_in + 3 * (T0_p4 - Tp_in) / 4 # in °C - -# Secondary nodes -Ts_in = 5.4611E+02 # in °C ORNL-TM-1647 p.2 -T0_s4 = 5.7939E+02 # in °C ORNL-TM-1647 p.2 -T0_s1 = Ts_in + (T0_s4 - Ts_in) / nn_s # in °C -T0_s2 = Ts_in + 2 * (T0_s4 - Ts_in) / nn_s # in °C -T0_s3 = Ts_in + 3 * (T0_s4 - Ts_in) / nn_s # in °C -# Tube nodes -T0_t1 = (T0_p1 * hA_pn + T0_s3 * hA_sn) / (hA_pn + hA_sn) # in °C -T0_t2 = (T0_p3 * hA_pn + T0_s1 * hA_sn) / (hA_pn + hA_sn) # in °C - -# Radiator Parameters - DONE - -# Initial conditions - DONE -# Primary nodes -Trp_in = T0_s4 # 5.933E+02; % in °C ORNL-TM-1647 p.2 -T0_rp = Ts_in # in °C ORNL-TM-1647 p.2 - -# Secondary nodes - DONE -Trs_in = 37.78 # (C) air inlet temperature ORNL-TM-1647 p.2 -T0_rs = 148.9 # (C) air exit temperature ORNL-TM-1647 p.2 - -# Radiator Geometry -od_rad = 0.01905 # (m) outer diameter of tubes in the radiator ORNL-TM-0728 p.296 -tube_wall_thick = 0.0018288 # (m) thickness of tubes in the radiator ORNL-TM-0728 p.296 -id_rad = od_rad - 2 * tube_wall_thick -n_rtubes = 120 # number of tubes in the radiator (rows times tubes per row) ORNL-TM-0728 p.296 -l_rtube = 9.144 # (m) length of tubes in the radiator ORNL-TM-0728 p.296 -v_rp = pi * (id_rad / 2) ** 2 * l_rtube * n_rtubes # volume available to salt in the radiator -# v_rtube = pi * (od_rad / 2) ** 2 * l_rtube * n_rtubes - v_rp # volume of metal in radiator tubes *TUBES NOT MODELED - -n_tpr = 12 # number of tubes per row in the radiator matrix -n_row = 10 # number rows in the radiator matrix -tube_space = 0.0381 # (m) spacing between tubes and rows of matrix -v_rs = (n_row * od_rad + (n_row - 1) * tube_space) * (n_tpr * od_rad + (n_tpr - 1) * tube_space) * l_rtube # volume of air inside radiator - -# PRIMARY FLOW PARAMETERS - DONE -W_rp = W_s # coolant salt flow rate (kg/s) -m_rp = v_rp * rho_s # coolant salt mass in rad (kg) -nn_rp = 1 # number of coolant salt nodes in the radiator -mn_rp = m_rp / nn_rp # coolant mass per node (kg) -cp_rp = scp_s # coolant specific heat capacity (MJ/(kg-C)) - -# SECONDARY FLOW PARAMETERS - DONE -vdot_rs = 94.389 # ORNL-TM-0728 p. 296; 78.82; % air volume flow rate (m^3/s) ORNL-TM-1647 p.2 -rho_rs = 1.1237 # air density (kg/m^3) REFPROP (310K and 0.1MPa) -W_rs = vdot_rs * rho_rs # air flow rate (kg/s) - -m_rs = v_rs * rho_rs # coolant air mass in rad (kg) -nn_rs = 1 # number of coolant nodes in rad -mn_rs = m_rs / nn_rs # coolant mass per node (kg) -scp_rs = 1.0085E-3 # (MJ/kg-C) specific heat capacity of air at (air_out+air_in)/2 REFPROP - -A_rad = 6.503E1 # (m^2) surface area of the radiator ORNL-TM-0728 p.14 -h_roverall = P / A_rad / ((T0_rp + Trp_in) / 2 - (T0_rs + Trs_in) / 2) # cald as: P/A_rad/((T0_rp+Trp_in)/2-(T0_rs+Trs_in)/2) 3.168E-4; % (MW/m^2-C) polimi thesis - -# Primary Side -mcp_rpn = mn_rp * cp_rp # (mass of material x heat capacity of material) of fuel salt per lump in MW-s/°C -hA_rpn = h_roverall * A_rad / nn_rs # 3.030; % (primary to secondary heat transfer coeff x heat transfer area) in MW/°C - -# Secondary Side - DONE -mcp_rsn = mn_rs * scp_rs # (mass of material x heat capacity of material) of coolant salt per lump in MW-s/°C -hA_rsn = h_roverall * A_rad / nn_rs # (tube to secondary heat transfer coeff x heat transfer area) in MW/°C - -# Pure time delays between components - DONE -tau_hx_c = 8.67 # (sec) delay from hx to core TDAMSRE p.6 -tau_c_hx = 3.77 # (sec) subtracted 1 sec for external loop power generation node resident time; delay from core to fuel hx TDAMSRE p.6 -tau_hx_r = 4.71 # (sec) fertile hx to core TDAMSRE p.6 -tau_r_hx = 8.24 # (sec) core to fertile hx TDAMSRE p.6 - -first_val = (rho_0 - beta_t) * n_frac0 / Lam + lam[0] * C0[0] + lam[1] * C0[1] + lam[2] * C0[2] + lam[3] * C0[3] + lam[4] * C0[4] + lam[5] * C0[5] \ No newline at end of file diff --git a/dynamic_model/pump_transient_benchmark/pump_transients.ipynb b/dynamic_model/pump_transient_benchmark/pump_transients.ipynb index 2eacef8..5b49482 100644 --- a/dynamic_model/pump_transient_benchmark/pump_transients.ipynb +++ b/dynamic_model/pump_transient_benchmark/pump_transients.ipynb @@ -26,7 +26,7 @@ "cell_type": "markdown", "metadata": {}, "source": [ - "This notebook simulates pump transients for the MSRE at zero power (10W). The system is run at steady-state until $t = 2500$, where the fuel and coolant pumps are spun down at the rate defined by the ORNL data. The model includes a reactivity response, $\\texttt{rho_control}$, which models the response of the MSRE control rod to maintain constant power. It is modeled as a pure integrator of $\\frac{dn}{dt}$ from the point-kinetics equations with a coefficient of -1.0, i.e. it tries to exactly cancel reactivity changes introduced by flow changes. " + "This notebook simulates pump transients for the MSRE at zero power (10W). The system is run at steady-state until $t = 2500$, where the fuel and coolant pumps are spun down at the rate defined by the ORNL data. After allowing the system to settle to a new equilibrium, at $t = 7500$, the pumps are spun up again. The model includes a reactivity response, `rho_control`, which models the response of the MSRE control rod to maintain constant power. It is modeled as a pure integrator of $\\frac{dn}{dt}$ from the point-kinetics equations with a coefficient of -1.0, i.e. it tries to exactly cancel reactivity changes introduced by flow changes, with the caveat that changes are limited to $\\pm$29 pcm/s, which was the maximum rate achievable by the MSRE control rods. " ] }, { @@ -174,6 +174,7 @@ "C5.set_dcdt(n.y(), beta = beta[4],Lambda = Lam, lam = lam[4], t_c = tau_c/flow_pct, t_l = tau_l/flow_pct, flow = True)\n", "C6.set_dcdt(n.y(), beta = beta[5],Lambda = Lam, lam = lam[5], t_c = tau_c/flow_pct, t_l = tau_l/flow_pct, flow = True)\n", "\n", + "# control rod response\n", "rho_control.dydt = -sp.Min(29.0e-5, sp.Max(-29.0e-5, n.dydt))\n", "\n", "\n", diff --git a/dynamic_model/pump_transient_benchmark/steady_state.ipynb b/dynamic_model/pump_transient_benchmark/steady_state.ipynb deleted file mode 100644 index 7ad2046..0000000 --- a/dynamic_model/pump_transient_benchmark/steady_state.ipynb +++ /dev/null @@ -1,22 +0,0 @@ -{ - "cells": [ - { - "cell_type": "code", - "execution_count": null, - "metadata": { - "vscode": { - "languageId": "plaintext" - } - }, - "outputs": [], - "source": [] - } - ], - "metadata": { - "language_info": { - "name": "python" - } - }, - "nbformat": 4, - "nbformat_minor": 2 -}