INFN homepage
FLUKA: MATERIAL Previous Index Next


    Defines a single-element material or (coupled to a COMPOUND card) a compound


= atomic number (meaningful only when NOT coupled to a COMPOUND card; otherwise set = 0.) No default.
= NOT to be filled. It allows to overwrite the default value of atomic weight (in g/mole).
: computed according to the natural composition of an element with atomic number
or to the identity of its isotope specified by
. Meaningless if coupled to a COMPOUND card.
= density in g/cm**3. Note that if the density is lower than 0.01, the material is considered to be a gas at atmospheric pressure unless set otherwise by MAT-PROP No default.
= number (index) of the material NOT to be filled in case of name-based input.
= NMAT + 1, where NMAT is the current higher number of defined materials. The number sequence of the defined materials must be uninterrupted. Its value is = 25 before any MATERIAL card is given, and doesn't change if
overrides a number which has already been assigned.
> 2.0: alternate material number (or name, in name-based input) for ionisation processes (this material will be used instead of
for dE/dx etc.) 0 =<
=< 2: ignored < 0.0: reset to default
: no alternate material
= mass number of the material Only integer values (still in real format) make sense.
= 0 i.e. natural isotopic composition of the
element (but see Note 8). For isotopic composition other than natural or single isotope, see COMPOUND
= name of the material No default.
(option MATERIAL not given): standard pre-defined material numbers are used (see list in 5}).
1) MATERIAL cards can be used in couple with COMPOUND cards in order to define compounds, mixtures or isotopic compositions. See COMPOUND for input instructions. 2) Material number 1 is always Black Hole (called also External Vacuum) and it can not be redefined. (All particles vanish when they reach the Black Hole, which has an infinite absorption cross section) 3) Material number 2 is always Vacuum (of zero absorption cross section) and it can not be redefined. 4) In name-based inputs it is recommended to omit the number of the material (and use its name in COMPOUND and ASSIGNMAt commands). On the contrary, if the input is number-based, it is not recommended to omit it. 5) In an explicitely number-based input (declared as such by
= 4.0 in command GLOBAL) it is allowed to redefine a material overriding a number already assigned (either by default, see list 5}, or by a previous MATERIAL card), or by using a new number. If the number has not been assigned before, it must be the next number available (26, 27... for successive MATERIAL cards). In a number-based input, it is dangerous to leave empty gaps in the number sequence, although the program takes care of redefining the number: in fact, the incorrect number is likely to be still used in other commands such as ASSIGNMAt and COMPOUND, leading to crashes or to undetected errors. If the input is name-based and the number is not given explicitely, the program automatically assigns it and the number sequence is automatically respected. The assigned number can be read from standard output, but the user only needs to refer to that material by its name in other input cards. 6) Materials having a different density at the macroscopic and at the microscopic level (e.g. spongy matter or approximations for not entirely empty vacuum) need a special treatment regarding stopping power (density effect). In such cases, see MAT-PROP. 7) If low-energy neutron transport is desired, the material name must coincide with that of one of the low-energy neutron cross section materials in the Fluka library (see 10}), or a correspondence must be set using option LOW-MAT. 8) If the card concerns an element that does not exist in nature, setting
= 0.0 cannot provide the natural isotopic composition. Therefore a single isotope will be selected (usually the one with the longest half-life). To avoid confusion, it is suggested to declare explicitly instead the isotope desired. 9) The largest atomic number that can be handled by FLUKA is 100.
MATERIAL 1. 8.988E-5 0.0 1. HYDROGEN LOW-MAT HYDROGEN 1. 11. 296. 0.0 0. HYDROGEN MATERIAL 6. 2.265 0.0 0. CARBON MATERIAL 6. 2.0 0.0 0. GRAPHITE LOW-MAT CARBON 6. -3. 296. 0.0 0. GRAPHITE MATERIAL 41. 8.57 0.0 0. NIOBIUM MATERIAL 48. 8.650 0.0 0. CADMIUM MATERIAL 24. 7.19 0.0 0. CHROMIUM MATERIAL 27. 8.90 0.0 0. COBALT
* Several (name-based) cases are illustrated:
* Hydrogen, pre-defined as material 3, is re-defined as monoisotopic 1-H.
* Command LOW-MAT has been added to force this material to be mapped to
* CH2-bound 1-H for what concerns low energy neutron transport.
* Carbon, pre-defined as material 6.0, is re-defined with a different density,
* and is also redefined with a different name (GRAPHITE), mapped to
* graphite-bound carbon.
* Niobium, Cadmium, Chromium and Cobalt are added to the list.

Previous Index Next