SurfaceFluxTally#

class montepy.SurfaceFluxTally(input: Input | str = None, number: montepy.types.PositiveInt = None, *, jit_parse: bool = True)#

Bases: SurfaceTally

F2: average surface flux tally.

Added in version 1.6.0b2.

Methods:

`add_group`(surfaces)	Add surfaces as a single union (averaged) bin.
`add_path_group`(*surfaces)	Add a universe-path group rooted at the given surfaces.
`add_surface`(surface)	Add a single surface as a separate scoring bin.
`clone`([starting_number, step])	Clone this tally with a new number.
`clone_as`(new_type[, starting_number, step])	Clone this tally as a different tally type, keeping the same scoring geometry.
`format_for_mcnp_input`(mcnp_version)	Creates a list of strings representing this MCNP_Object that can be written to file.
`from_input`(input, *[, jit_parse])	Factory: create the appropriate `Tally` subclass from an input.
`full_parse`()	Fully parses this object, and disable just-in-time parsing for it.
`link_to_problem`(problem, *[, deepcopy])	Links the input to the parent problem for this input.
`mcnp_str`([mcnp_version])	Returns a string of this input as it would appear in an MCNP input file.
`remove_group`(group)	Remove a scoring group previously added via `add_surface`/`add_group`/`add_path_group`.
`remove_surface`(surface)	Remove the single-surface scoring bin added via `add_surface()`.
`search`(search)	Searches this input for the given string, or compiled regular expression.
`validate`()	Validates that the object is in a usable state.
`wrap_string_for_mcnp`(string, mcnp_version, ...)	Wraps the list of the words to be a well formed MCNP input.

Attributes:

`classifier`	The syntax tree object holding the data classifier.
`comments`	The comments associated with this object if any.
`data`	The syntax tree actually holding the data.
`filters`	A shallow analog of OpenMC's tally filters.
`fully_parsed`	Whether this has been fully parsed, or is just JIT parsed.
`groups`	The list of `TallyGroup` objects defining what is scored.
`include_total`	`True` if a total bin (T) is appended.
`leading_comments`	Any comments that come before the beginning of the input proper.
`multiplier`	The `FM` tally-multiplier card linked to this tally, if any.
`number`	The current number of the object that will be written out to a new input.
`old_number`	The tally number as read from the input file.
`parameters`	A dictionary of the additional parameters for the object.
`particle_classifiers`	The particle class part of the input identifier as a parsed list.
`prefix`	The text part of the input identifier parsed from the input.
`prefix_modifier`	The modifier to a name prefix that was parsed from the input.
`scores`	The physical quantities this tally scores, e.g. `[Score.FLUX]` for `F4`.
`surfaces`	The surfaces this tally scores over.
`tally_type`	The MCNP tally type (e.g. `TallyType.CELL_FLUX` for `F4`).
`trailing_comment`	The trailing comments and padding of an input.

Parameters:

input (InitInput)
number (ty.PositiveInt)
jit_parse (bool)

classmethod from_input(input, *, jit_parse: bool = True) → Tally#

Factory: create the appropriate Tally subclass from an input.

Parameters:

input (Input | str) – The raw MCNP input object.
jit_parse (bool) – Whether to defer full parsing.

Returns:

An instance of the correct subclass for the tally type digit.

Return type:

Tally

static wrap_string_for_mcnp(string: str, mcnp_version: montepy.types.VersionType, is_first_line: bool, suppress_blank_end: bool = True) → list[str]#

Wraps the list of the words to be a well formed MCNP input.

multi-line inputs will be handled by using the indentation format, and not the “&” method.

Parameters:

string (str) – A long string with new lines in it, that needs to be chunked appropriately for MCNP inputs
mcnp_version (tuple[Integral, Integral, Integral]) – the tuple for the MCNP that must be formatted for.
is_first_line (bool) – If true this will be the beginning of an MCNP input. The first line will not be indented.
suppress_blank_end (bool) – Whether or not to suppress any blank lines that would be added to the end. Good for anywhere but cell modifiers in the cell block.

Returns:

A list of strings that can be written to an input file, one item to a line.

Return type:

list[str]

add_group(surfaces: list[Surface] | tuple[Surface, ...]) → None#

Add surfaces as a single union (averaged) bin.

Parameters:: surfaces (list[Surface] | tuple[Surface, ...]) – The surfaces to group, in order.
Return type:: None

add_path_group(*surfaces: Surface) → PathGroup#

Add a universe-path group rooted at the given surfaces.

Returns the PathGroup for chaining via inside().

Parameters:: surfaces (Surface) – The innermost-level surfaces.
Returns:: The new path group (already appended).
Return type:: PathGroup

add_surface(surface: Surface) → None#

Add a single surface as a separate scoring bin.

Parameters:: surface (Surface) – The surface to add.
Return type:: None

clone(starting_number: montepy.types.PositiveInt = None, step: montepy.types.PositiveInt = None) → Tally#

Clone this tally with a new number.

If this tally has a linked FM multiplier (see multiplier), it’s cloned too and linked to the new tally’s number – unlike clone_as(), clone is like-for-like (same tally type), so the multiplier’s scoring relationship still applies.

See clone().

Return type:

Tally

Parameters:

starting_number (montepy.types.PositiveInt)
step (montepy.types.PositiveInt)

clone_as(new_type: TallyType | type[Tally], starting_number: montepy.types.PositiveInt = None, step: montepy.types.PositiveInt = None) → Tally#

Clone this tally as a different tally type, keeping the same scoring geometry.

For example, this can turn an F4 cell-flux tally into an F6 energy-deposition tally scoring the same cells:

heating = flux_tally.clone_as(montepy.EnergyDepositionTally)
# or, equivalently:
heating = flux_tally.clone_as(montepy.TallyType.ENERGY_DEPOSITION)

Only conversions within the same tally category are allowed: F1/F2 (surface-based) convert freely among each other, as do F4/F6/F7/F8 (cell-based); F5 (point/ring detector) has no cell/surface geometry to carry over and can’t be converted to or from.

Note

The clone does not carry over a linked FM multiplier (see multiplier) – a multiplier is a companion card tied to this exact tally number, not something that meaningfully transfers to a retyped/renumbered copy.

Parameters:

new_type (TallyType | type[Tally]) – The target tally type, either as a TallyType member or as a Tally subclass (e.g. montepy.EnergyDepositionTally).
starting_number (Integral) – The starting number to request for the new object’s number.
step (Integral) – The step size to use to find a new valid number.

Returns:

A new tally of the requested type, with the same scoring groups.

Return type:

Tally

format_for_mcnp_input(mcnp_version: montepy.types.VersionType) → list[str]#

Creates a list of strings representing this MCNP_Object that can be written to file.

Parameters:: mcnp_version (tuple[Integral, Integral, Integral]) – The tuple for the MCNP version that must be exported to.
Returns:: a list of strings for the lines that this input will occupy.
Return type:: list[str]

full_parse()#

Fully parses this object, and disable just-in-time parsing for it.

Returns:: The object will be mutated and fully parsed.
Return type:: None

link_to_problem(problem, *, deepcopy=False)#

Links the input to the parent problem for this input.

This is done so that inputs can find links to other objects.

Parameters:

problem (MCNP_Problem) – The problem to link this input to.
deepcopy (bool) – If this is occuring during a problem level deepcopy

mcnp_str(mcnp_version: montepy.types.VersionType = None) → str#

Returns a string of this input as it would appear in an MCNP input file.

..versionadded:: 1.0.0

Parameters:: mcnp_version (tuple[Integral, Integral, Integral]) – The tuple for the MCNP version that must be exported to.
Returns:: The string that would have been printed in a file
Return type:: str

remove_group(group: TallyGroup) → None#

Remove a scoring group previously added via add_surface/add_group/add_path_group.

A surface is only dropped from surfaces if no other remaining group still references it.

Parameters:: group (TallyGroup) – The group to remove.
Return type:: None

remove_surface(surface: Surface) → None#

Remove the single-surface scoring bin added via add_surface().

Parameters:: surface (Surface) – The surface to remove.
Return type:: None

search(search: str | Pattern) → bool#

Searches this input for the given string, or compiled regular expression.

Parameters:: search (str | Pattern) – The pattern to search for.
Returns:: Whether this
Return type:: bool

validate()#: Validates that the object is in a usable state.

property classifier#

The syntax tree object holding the data classifier.

For example this would container information like M4, or F104:n.

Returns:: the classifier for this data_input.
Return type:: montepy.input_parser.syntax_node.ClassifierNode

property comments: CommentCollection#

The comments associated with this object if any.

This includes all C comments before this card that aren’t part of another card, and any comments that are inside this card.

Changed in version 1.5.0: Returns a CommentCollection instead of a list.

Returns:: the comments associated with this object; supports searching the comments’ text, e.g. "foo" in obj.comments.
Return type:: CommentCollection

property data: ListNode#

The syntax tree actually holding the data.

Returns:: The syntax tree with the information.
Return type:: montepy.input_parser.syntax_node.ListNode

property filters: list[Filter]#

A shallow analog of OpenMC’s tally filters.

Defaults to a ParticleFilter (from particle_classifiers) and a SpatialFilter (from groups), whichever are present.

property fully_parsed#

Whether this has been fully parsed, or is just JIT parsed.

Returns:: True iff this is fully parsed, False means this is still just-in-time parsed.
Return type:: bool

property groups: list[TallyGroup]#: The list of TallyGroup objects defining what is scored.

property include_total: bool#: True if a total bin (T) is appended.

property leading_comments: CommentCollection#

Any comments that come before the beginning of the input proper.

Changed in version 1.5.0: Returns a CommentCollection instead of a list.

Returns:: the leading comments; supports searching the comments’ text, e.g. "foo" in obj.leading_comments.
Return type:: CommentCollection

property multiplier: TallyMultiplier#

The FM tally-multiplier card linked to this tally, if any.

Return type:: TallyMultiplier

property number#

The current number of the object that will be written out to a new input.

Return type:: int

property old_number#: The tally number as read from the input file.

property parameters: dict[str, str]#

A dictionary of the additional parameters for the object.

e.g.: 1 0 -1 u=1 imp:n=0.5 has the parameters {"U": "1", "IMP:N": "0.5"}

Returns:: a dictionary of the key-value pairs of the parameters.
Return type:: dict[str, str]
Return type:: dict

property particle_classifiers: list[Particle]#

The particle class part of the input identifier as a parsed list.

This is parsed from the input that was read.

For example: the classifier for F7:n is :n, and imp:n,p is :n,p This will be parsed as a list: [<Particle.NEUTRON: 'N'>, <Particle.PHOTON: 'P'>].

Returns:: the particles listed in the input if any. Otherwise None
Return type:: list[montepy.Particle]

property prefix: str#

The text part of the input identifier parsed from the input.

For example: for a material like: m20 the prefix is m. this will always be lower case. Can also be called the mnemonic.

Returns:: The prefix read from the input
Return type:: str

property prefix_modifier: str#

The modifier to a name prefix that was parsed from the input.

For example: for a transform: *tr5 the modifier is *

Returns:: the prefix modifier that was parsed if any. None if otherwise.
Return type:: str

property scores: list[Score] | list[MultiplierScore]#

The physical quantities this tally scores, e.g. [Score.FLUX] for F4.

This is just the quantity implied by the tally type digit, unless an FM tally-multiplier card is linked (see multiplier), in which case this returns one MultiplierScore per output bin the multiplier defines instead.

property surfaces: Surfaces#: The surfaces this tally scores over.

property tally_type: TallyType | None#: The MCNP tally type (e.g. TallyType.CELL_FLUX for F4).

property trailing_comment: list[PaddingNode]#

The trailing comments and padding of an input.

Generally this will be blank as these will be moved to be a leading comment for the next input.

Returns:: the trailing c style comments and intermixed padding (e.g., new lines)
Return type:: list