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14 декабря, 2021
The problem description is in one file*, the input file. This file contains geometry description (cells defined with surfaces), materials, neutron source, calculation * Note that the neutron source may be defined in a separate file.
Table 5.1. Main units used in MCNP.
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type (critical or standard), etc. This file has a special format. It contains delimiters, data entries (or cards) and comments. Each line is limited to 80 characters; but a single data entry may lie on more than one line if each of these lines (except the last one) ends with an & (ampersand). MCNP is case insensitive.
The general structure of the input file is:
Title line
Cell cards
Blank line delimiter
Surface cards
Blank line delimiter
Data cards
Blank line terminator
Comments can be inserted on separate lines: the line must begin with a ‘c’ followed by at least one blank. They can also be placed at the end of a data entry: after a $ (dollar sign).