def setup_neutron(self):
"""
Creates Neutron Plotter GUI
"""
self.globals.logger.debug("Creating neutron plotter frame GUI...")
# MENU
ID = self.NEUTRON_ID
self.menu_buttons[ID] = tk.Button(self.menu_frame, text="Neutron", relief=tk.FLAT,
command=lambda page=ID: self.page(page))
# PAGE
self.pages[ID] = Neutron(self.main_frame, self.globals)
self.globals.logger.debug("Neutron plotter frame GUI created.")
credentials = { 'user' : os.environ['OS_USERNAME'],
'password' : os.environ['OS_PASSWORD'],
'project' : os.environ['OS_TENANT_NAME'] }
auth_url = os.environ['OS_AUTH_URL']
else:
print "Can't find OpenStack auth credentials in environment or spec file, giving up..."
sys.exit(1)
if args.auth:
print "credentials string:\nexport OS_USERNAME=%s OS_PASSWORD=%s OS_TENANT_NAME=%s OS_AUTH_URL=%s" % (credentials['user'],credentials['password'],credentials['project'],auth_url)
sys.exit(0)
config = {}
config['external_network_name'] = spec['external network name']
config['dns'] = spec['dns']
neutron = Neutron(auth_url, credentials, config)
nova = novaclient.client.Client("2",
username = credentials['user'],
api_key = credentials['password'],
project_id = credentials['project'],
auth_url = auth_url)
servers = nova.servers.list()
server_list = {}
for server in servers:
server_list[server.name] = (server.id,server.status)
def server_suspend(name):
for s in servers:
if s.name == name:
(id,status) = server_list[name]
super(IPPool, self).__init__()
self.log = logger.setup_logging(self.__class__.__name__)
self.schema_class = 'ip_pool_schema.IpPoolSchema'
if neutron is not None:
self.set_connection(neutron.get_connection())
self.set_create_endpoint('/pools/ip-pools')
self.id = None
if __name__ == '__main__':
import base_client
from neutron import Neutron
from ip_pool_schema import IpPoolSchema
nu = Neutron('10.110.30.9', 'admin', 'default')
ip_pool_client = IPPool(nu)
py_dict = {
'subnets': [{
'static_routes': [{
'next_hop': '192.168.10.5',
'destination_cidr': '192.168.10.0/24'
}],
'allocation_ranges': [{
'start': '192.168.1.2',
'end': '192.168.1.6'
}, {
'start': '192.168.1.10',
'end': '192.168.1.100'
}],
'dns_nameservers': ['10.10.10.11', '10.10.10.12'],
def main(neutron_cycle, cycle):
# Fission and neutron source bank
neutron_bank = np.zeros((cycle * neutron_cycle, 8))
# [No., site_x, site_y, travel_length, velocity_angle, reaction_type, number_neutron]
rand_num = np.zeros((2, neutron_cycle), float)
for n in range(neutron_cycle):
rand_num[0][n] = random.uniform(-b, b)
rand_num[1][n] = random.uniform(-b, b)
fission_num = neutron_cycle
for i in range(cycle):
m = 0
print rand_num
for j in range(neutron_cycle):
row_num = neutron_cycle * i + j
neutron = Neutron(row_num, 1)
neutron_bank[row_num, 1] = neutron.no
if j < fission_num:
x_rand = rand_num[0][j]
y_rand = rand_num[1][j]
else:
site_num = random.randint(0, fission_num - 1)
x_rand = rand_num[0][site_num]
y_rand = rand_num[1][site_num]
energy = 1e6
# unit: eV
angle = -1
neutron_status = {
'x_rand': x_rand,
'y_rand': y_rand,
'x_next': 0,
'y_next': 0,
'energy': 1e6,
'angle': -1,
'iso_col': ''
}
neutron.status(neutron_status)
neutron_bank[row_num, 2] = neutron.x_rand
neutron_bank[row_num, 3] = neutron.y_rand
# print neutron_bank[row_num,2];
# generate the first collision position
circle_flag = geo_circle(neutron.x_rand, neutron.y_rand)
if circle_flag == 1:
neutron.domain(1)
else:
neutron.domain(2)
neutron = new_position(neutron)
geo_intersc(neutron)
#neutron_bank[j,4] = neutron['x_next'];
#neutron_bank[j,5] = neutron['y_next'];
# loop core
react_judge(neutron)
# print neutron_bank[row_num,2];
neutron_bank[row_num, 4] = neutron.x_next
neutron_bank[row_num, 5] = neutron.y_next
neutron_bank[row_num, 6] = neutron.col
neutron_bank[row_num, 7] = neutron.type
if neutron.iso_col:
x = neutron.iso_col.name
else:
x = 'NaN'
print neutron.no, neutron.col, neutron_bank[
row_num, 2], neutron_bank[row_num, 3], neutron_bank[
row_num,
4], neutron_bank[row_num,
5], neutron.energy, x, neutron.type
# filter out fission sites
if neutron.type == 1:
rand_num[0][m] = neutron.x_next
rand_num[1][m] = neutron.y_next
m = m + 1
print m
del neutron
print m
fission_num = m
fission_yield = 2.5
print 'Keff = %f' % (fission_num * fission_yield / neutron_cycle)
end = time.time()
print(end - start)
plt.subplot(2, 2, 1)
circle1 = plt.Circle((0, 0), r, alpha=0.1)
point1 = plt.scatter(neutron_bank[0:neutron_cycle, 2],
neutron_bank[0:neutron_cycle, 3])
fig = plt.gcf()
fig.gca().add_artist(circle1)
fig.gca().add_artist(point1)
plt.title('Neutron source - 1st cycle')
plt.xlim([-b, b])
plt.ylim([-b, b])
plt.subplot(2, 2, 2)
circle1 = plt.Circle((0, 0), r, alpha=0.1)
point1 = plt.scatter(neutron_bank[0:neutron_cycle, 4],
neutron_bank[0:neutron_cycle, 5])
fig = plt.gcf()
fig.gca().add_artist(circle1)
fig.gca().add_artist(point1)
plt.title('Fission site - 1st cycle')
plt.xlim([-b, b])
plt.ylim([-b, b])
plt.subplot(2, 2, 3)
circle1 = plt.Circle((0, 0), r, alpha=0.1)
point1 = plt.scatter(neutron_bank[neutron_cycle:neutron_cycle * 2, 2],
neutron_bank[neutron_cycle:neutron_cycle * 2, 3])
fig = plt.gcf()
fig.gca().add_artist(circle1)
fig.gca().add_artist(point1)
plt.title('Neutron source - 2nd cycle')
plt.xlim([-b, b])
plt.ylim([-b, b])
plt.subplot(2, 2, 4)
circle1 = plt.Circle((0, 0), r, alpha=0.1)
point1 = plt.scatter(neutron_bank[neutron_cycle:neutron_cycle * 2, 4],
neutron_bank[neutron_cycle:neutron_cycle * 2, 5])
fig = plt.gcf()
fig.gca().add_artist(circle1)
fig.gca().add_artist(point1)
plt.title('Fission site - 2nd cycle')
plt.xlim([-b, b])
plt.ylim([-b, b])
plt.show()
def main(neutron_cycle,cycle):
# Fission and neutron source bank
neutron_bank = np.zeros((cycle*neutron_cycle,8));
# [No., site_x, site_y, travel_length, velocity_angle, reaction_type, number_neutron]
rand_num = np.zeros((2,neutron_cycle),float);
for n in range(neutron_cycle):
rand_num[0][n] = random.uniform(-width,width);
rand_num[1][n] = random.uniform(-width,width);
rand_num_new = np.zeros((2,neutron_cycle),float);
fission_num = neutron_cycle;
for i in range(cycle):
m = 0;
#print rand_num;
for j in range(neutron_cycle):
row_num = neutron_cycle * i + j;
neutron = Neutron(row_num,1);
neutron_bank[row_num,1] = neutron.no;
if j < fission_num:
x_rand = rand_num[0][j];
y_rand = rand_num[1][j];
else:
site_num = random.randint(0,fission_num-1);
x_rand = rand_num[0][site_num];
y_rand = rand_num[1][site_num];
energy = 2*1e6; # unit: eV
angle = -1;
neutron_status = {'x_rand':x_rand,'y_rand':y_rand,'x_next':0,'y_next':0,'energy':1e6,'angle':-1,'iso_col':'','type':0};
neutron.status(neutron_status);
neutron_bank[row_num,2] = neutron.x_rand;
neutron_bank[row_num,3] = neutron.y_rand;
# print neutron_bank[row_num,2];
# generate the first collision position
circle_flag = geo_circle(neutron.x_rand, neutron.y_rand);
if circle_flag == 1:
neutron.domain(1);
else:
neutron.domain(2);
neutron = new_position(neutron);
geo_intersc(neutron);
#neutron_bank[j,4] = neutron['x_next'];
#neutron_bank[j,5] = neutron['y_next'];
# loop core
react_judge(neutron);
# print neutron_bank[row_num,2];
neutron_bank[row_num,4] = neutron.x_next;
neutron_bank[row_num,5] = neutron.y_next;
neutron_bank[row_num,6] = neutron.col;
neutron_bank[row_num,7] = neutron.type;
if neutron.iso_col:
x= neutron.iso_col.name;
else:
x= 'NaN';
#print neutron.no, neutron.col, neutron_bank[row_num,2], neutron_bank[row_num,3], neutron_bank[row_num,4], neutron_bank[row_num,5], neutron.energy, x, neutron.type;
# filter out fission sites
if neutron.type == 2:
rand_num_new[0][m] = deepcopy(neutron.x_next);
rand_num_new[1][m] = deepcopy(neutron.y_next);
#print rand_num_new[0][:]
#try:
# print rand_num[0][:]
# except:
# print 'xxx'
m = m + 1;
#print m;
del neutron;
#print rand_num;
#print m;
fission_num = m;
fission_yield = 2.5;
keff[i] = fission_num * fission_yield / neutron_cycle;
print ('Keff = %f' % (fission_num * fission_yield / neutron_cycle));
#del rand_num
rand_num = deepcopy(rand_num_new);
#del rand_num_new;
end = time.time();
print(end - start);