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made for review
some fixes and increaseing a number of batches
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dryuri92
GitHub
parent
b8763f1934
commit
ce4439ef14
1 changed files with 45 additions and 39 deletions
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@ -5,7 +5,7 @@ names = ['H', 'O', 'Zr', 'U235', 'U238']
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def build_openmc_xs_lib(name, groups, temperatures, xsdict, micro=True):
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"""Build an Openm XSdata based on dictonary values"""
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"""Build an Openm XSdata based on dictionary values"""
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xsdata = openmc.XSdata(name, groups, temperatures=temperatures)
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xsdata.order = 0
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for tt in temperatures:
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@ -34,15 +34,15 @@ def create_micro_xs_dict():
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xs_micro[300]['absorption']['U238'] = np.array([0.0056, 0.0094])
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# nu-scatter matrix
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xs_micro[300]['scatter']['H'] = np.array([[[0.0910, 0.01469],
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[2.1545E-8, 0.3316]]])
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[0.0, 0.3316]]])
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xs_micro[300]['scatter']['O'] = np.array([[[0.0814, 3.3235E-4],
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[1.4152E-8, 0.0960]]])
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[0.0, 0.0960]]])
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xs_micro[300]['scatter']['Zr'] = np.array([[[0.0311, 2.6373E-5],
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[6.1273E-8, 0.0315]]])
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[0.0, 0.0315]]])
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xs_micro[300]['scatter']['U235'] = np.array([[[0.0311, 2.6373E-5],
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[6.1273E-8, 0.0315]]])
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[0.0, 0.0315]]])
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xs_micro[300]['scatter']['U238'] = np.array([[[0.0551, 2.2341E-5],
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[8.7247E-8, 0.0526]]])
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[0.0, 0.0526]]])
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# nu-fission
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xs_micro[300]['nu-fission']['U235'] = np.array([0.0059, 0.2160])
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xs_micro[300]['nu-fission']['U238'] = np.array([0.0019, 1.4627E-7])
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@ -71,15 +71,15 @@ def create_micro_xs_dict():
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xs_micro[600]['absorption']['U238'] = np.array([0.0058, 0.0079])
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# nu-scatter matrix
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xs_micro[600]['scatter']['H'] = np.array([[[0.0910, 0.0138],
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[8.9e-08, 0.3316]]])
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[0.0, 0.3316]]])
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xs_micro[600]['scatter']['O'] = np.array([[[0.0814, 3.5367E-4],
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[3.4404E-8, 0.0959]]])
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[0.0, 0.0959]]])
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xs_micro[600]['scatter']['Zr'] = np.array([[[0.0311, 3.2293E-5],
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[8.3859E-8, 0.0314]]])
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[0.0, 0.0314]]])
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xs_micro[600]['scatter']['U235'] = np.array([[[0.0022, 1.9763E-6],
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[9.1634E-8, 0.0039]]])
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xs_micro[600]['scatter']['U238'] = np.array([[[0.0556, 2.8803E-5],
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[1.1967E-8, 0.0536]]])
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[0.0, 0.0536]]])
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# nu-fission
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xs_micro[600]['nu-fission']['U235'] = np.array([0.0059, 0.1767])
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xs_micro[600]['nu-fission']['U238'] = np.array([0.0019, 1.2405E-7])
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@ -114,15 +114,15 @@ def create_micro_xs_dict():
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xs_micro[900]['total']['U238'] = np.array([0.0707, 0.0613])
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# nu-scatter matrix
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xs_micro[900]['scatter']['H'] = np.array([[[0.0913, 0.0147],
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[8.9e-08, 0.4020]]])
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[0.0, 0.4020]]])
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xs_micro[900]['scatter']['O'] = np.array([[[0.0812, 4.0413E-4],
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[6.8186E-8, 0.0965]]])
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[0.0, 0.0965]]])
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xs_micro[900]['scatter']['Zr'] = np.array([[[0.0311, 3.6735E-5],
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[1.3439E-8, 0.0314]]])
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[0.0, 0.0314]]])
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xs_micro[900]['scatter']['U235'] = np.array([[[0.0022, 2.9034E-6],
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[1.3117E-8, 0.0039]]])
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xs_micro[900]['scatter']['U238'] = np.array([[[0.0560, 3.7619E-5],
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[1.4553E-8, 0.0538]]])
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[0.0, 0.0538]]])
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# nu-fission
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xs_micro[900]['nu-fission']['U235'] = np.array([0.0059, 0.1545])
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xs_micro[900]['nu-fission']['U238'] = np.array([0.0019, 1.1017E-7])
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@ -159,6 +159,9 @@ def create_macro_dict(xs_micro):
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xs_macro[t][r] = {}
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for n, v in d2.items():
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temp.append(d2[n])
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# The name 'macro' is needed to store data at the same level
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# of a xs_macro dictionary as for xs_micro and use it in
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# function build_openmc_xs_lib
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xs_macro[t][r]['macro'] = sum(temp)
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return xs_macro
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@ -194,20 +197,21 @@ def create_openmc_2mg_libs(names):
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def analytical_solution_2g_therm(xsmin, xsmax=None, wgt=1.0):
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""" Calculate eigenvalue based on analytical solution for eq Lf = (1/k)Qf
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in two group for infinity dilution media in assumption of group
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boundary in thernmal spectra < 1.e+3 Ev
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Parametres:
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----------
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xsmin : dict
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- macro cross-sections dictonary with minimum range temperature
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xsmax : dict
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- macro cross-sections dictonary with maximum range temperature
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by default: None not used for standalone temperature
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wgt : double
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- weight for interpolation by default 1.0
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Returns:
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---------
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keff : np.double - analytical eigenvalue of critical eq matrix
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in two group for infinity dilution media in assumption of group
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boundary in thermal spectra < 1.e+3 Ev
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Parameters:
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----------
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xsmin : dict
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macro cross-sections dictionary with minimum range temperature
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xsmax : dict
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macro cross-sections dictionary with maximum range temperature
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by default: None not used for standalone temperature
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wgt : float
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weight for interpolation by default 1.0
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Returns:
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-------
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keff : np.float64
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analytical eigenvalue of critical eq matrix
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"""
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if xsmax is None:
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sa = xsmin['absorption']['macro']
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@ -223,20 +227,21 @@ def analytical_solution_2g_therm(xsmin, xsmax=None, wgt=1.0):
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L = np.array([sa[0] + ss12, 0.0, -ss12, sa[1]]).reshape(2, 2)
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Q = np.array([nsf[0], nsf[1], 0.0, 0.0]).reshape(2, 2)
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arr = np.linalg.inv(L).dot(Q)
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return np.linalg.eigvals(arr)[1]
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return np.amax(np.linalg.eigvals(arr))
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def build_inf_model(xsnames, xslibname, temperature, tempmethod='nearest'):
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""" Building an infinite medium for openmc multi-group testing
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Parametres:
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----------
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xsnames : list of str()
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- list with xs names
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xslibname:
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- name of hdf5 file with cross-section library
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temperature : float
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- value of a current temperature in K
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tempmethod : str {'nearest', 'interpolstion'} by default 'nearest'
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Parameters:
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----------
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xsnames : list of str()
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list with xs names
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xslibname:
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name of hdf5 file with cross-section library
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temperature : float
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value of a current temperature in K
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tempmethod : {'nearest', 'interpolation'}
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by default 'nearest'
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"""
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inf_medium = openmc.Material(name='test material', material_id=1)
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inf_medium.set_density("sum")
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@ -273,9 +278,10 @@ def build_inf_model(xsnames, xslibname, temperature, tempmethod='nearest'):
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openmc_geometry.export_to_xml()
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# OpenMC simulation parameters
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batches = 15
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batches = 200
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inactive = 5
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particles = 5000
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# Instantiate a Settings object
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settings_file = openmc.Settings()
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settings_file.batches = batches
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