OpenMC/ChangeLog

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2011-02-27 Paul Romano <romano7@mit.edu>
* ace.f90: Fixed minor bugs associated with reading angular
distributions.
* data_structures.f90: Added dict_keys routines.
* fileio.f90: Considerably changed read_count and read_cell to be
able to handle universes.
* geometry.f90: Added universe logic to find_cell and allowed it
to be recursively called.
* global.f90: Added universe array and dictionary, cell types,
pointer to lowest universe, angular distribution types,
interpolation types, as well as ERROR_CODE and adjusted str_to_int
to return ERROR_CODE on error.
* output.f90: Added print_cell, print_universe, and print_summary
subroutines. Need a few more useful routines like this!
* physics.f90: Added ability to sample cosine of scattering angle
from a 32-equiprobable bin distribution or a tabular
distribution. This is done by the sample_energy routine. The
rotate_angle subroutine takes a particles direction and applies
that scattering angle to it. Also added some logic for universes.
* types.f90: Changed some attributes in the Neutron structure,
added type to angular distribution within AceReaction.
2011-02-22 Paul Romano <romano7@mit.edu>
* ace.f90: Added read_angular_dist and read_energy_dist
subroutines that read the energy and angle distributions for
secondary neutrons for reactions with MT < 100. Note that these
routines don't actually parse the distributions since their form
will depend on the secondary law is for that particle reaction.
* global.f90: Incremented minor version
* types.f90: Put angular and energy distribution information
within AceReaction since it is unique to each reaction
2011-02-13 Paul Romano <romano7@mit.edu>
* ace.f90: Fixed xs_continuous allocation again -- cross sections
were not being assigned correctly to materials. Added elastic
scattering in list of reactions. Changed name of rxn %
energy_index to IE.
* endf.f90: New module. Includes subroutine reaction_name which
returns the name of a reaction for a given ENDF MT value.
* geometry.f90: Fixed bug in dist_to_boundary (the 'w' in uvw was
actually being set to 'z', not 'w'). Changed 0's and 1's to ZEROs
and ONEs.
* global.f90: Added ZERO and ONE.
* physics.f90: Can now sample reactions once nuclide is
selected. Added subroutines elastic_scatter, level_inelastic, and
n_gamma (level_inelastic is just a stub), and significantly
changed elastic scattering (currently based on stationary target).
* types.f90: Added n_reaction attribute on AceContinuous, changed
AceReaction % energy_index to IE.
2011-02-09 Paul Romano <romano7@mit.edu>
* ace.f90: Fixed bug in the way xs_continuous was allocated. If,
e.g., 92235.03c was listed twice in a file, two spots would be
allocated in the array instead of one.
* cross_section.f90: Added calculation of total material
cross-section.
* data_structures.f90: Added list routines for each different
type (integer, real, key/value pairs) and an interface for
them. Dictionaries can now take character keys or integer
keys. New hash function for integers is simple mod function.
* energy_grid.f90: Removed grid_count since we now have a generic
list_size routine in data_structures. Added original_indices
routine in order to do SERPENT-style double-indexing.
* fileio.f90: Fixed normalize_ao routine to include calculations
based on atom or gram density (this should probably be moved to
different module). Added get_next_line routine that reads a full
line of input including any continuation lines marked by an
ampersand.
* global.f90: Added separate dictionary types (CI and II), added
pointers for current cell, surface, and material. Added e_grid and
n_grid
* physics.f90: Neutron energy sampled at beginning of
transport. Added watt_spectrum and maxwell_spectrum
routines. Changed collision routine so that actual nuclide is
sampled.
* search.f90: Fixed binary_search routine
* string.f90: Changed concatenate subroutine into a function
* types.f90: Moved List and Dictionary types from data_structures
to here (including new types). LinkedListGrid is now ListReal.
2011-02-03 Paul Romano <romano7@mit.edu>
* ace.f90: Added initial routines for reading continuous-energy
ACE cross section tables. No secondary energy/angle distributions
or nu data is read.
* cross_section.f90: Added read_xsdata routine which reads
information from an xsdata file from SERPENT.
* data_structures.f90: Moved derived types to the types module and
change dict_create so that one doesn't need to add a (key,value)
pair on initialization.
* energy_grid.f90: First routines for energy grid unionization
based on insertion sorts.
* fileio.f90: Added routines for reading integer and real data,
particularly from cross-section libraries. Made an interface so
that a single routine can be called regardless of type. Ability to
read material cards and added subroutine for normalization of
atom/weight percents.
* Makefile: Added 'unittest' target
* output.f90: Fixed bug in get_today subroutine whereby the day
was displayed wrong.
* search.f90: Added binary search which will eventually be used
for energy grid searches
* unittest.f90: Added this program for unit testing.
2011-01-26 Paul Romano <romano7@mit.edu>
* physics.f90: Added collision routine, still segfaults though.
* geometry.f90: Added messages for high verbosities
* global.f90: Added verbosity parameter, key length for
dictionaries
* output.f90: Implemented verbosity for messages.
* data_structures.f90: Added implementations of linked list and
dictionaries based on the flib open source package
2011-01-23 Paul Romano <romano7@mit.edu>
* types.f90: Added cell, surface, and alive attributes to Neutron
* fileio.f90: External source no longer array
* geometry.f90: Changed cell_contains slightly so that it can
evaluate simple cell logical expressions. Added find_cell and
cross_boundary subroutines. Changed dist_to_boundary to also give
back closest surface
* global.f90: Added set_defaults subroutine
* source.f90: Isotropic angle is now sampled in init_source, fixed
sampling in box, checks for external source type. Added
get_source_particle function.
2011-01-22 Paul Romano <romano7@mit.edu>
* input_sample: Added a sample input file
* main.f90: Added run_problem subroutine
* mcnp_random.f90: Added random number generator based on MCNP's
linear congruential generator
* fileio.f90: Completely changed how cells, surfaces, and
materials are allocated. Now there is a first pass through the
input file made by read_count which allows the arrays to be
pre-allocated, then read_input actually parses the input data.
* geometry.f90: Only formatting changes
* output.f90: Added the echo_input subroutine, made formatting
changes
* string.f90: Moved int_to_str to the global module, changed
string splitting to recognize tab characters
* types.f90: Deleted List types, added Isotope, Material, and
Source
* source.f90: Added init_source routine which initializes source
particles