Abstract
The improvement of the dose evaluation method for criticaiity accidents is important to rationalize design of the nuclear fuel cycle facilities. The source spectrums of neutron and gamma ray of a criticaiity accident depend on the condition of the source, its materials, moderation, density and so on.The comparison of the dose evaluation methods for a criticaiity accident is made. Some methods, which are combination of criticaiity calculation and shielding calculation, are proposed. Prompt neutron and gamma ray doses from nuclear criticaiity of some uranium systems have been evaluated as the Nuclear Criticaiity Slide Rule. The uranium metal source (unmoderated system) and the uranyl nitrate solution source (moderated system) in the rule are evaluated by some calculation methods, which are combinations of code and cross section library, as follows:(a) SAS1X (ENDF/B-IV)(b) MCNP4C (ENDF/B-VI) - ANISN (DLC23E or JSD120)(c) MCNP4C - MCNP4C (ENDF/B-VI)They have consisted of criticaiity calculation and shielding calculation.These calculation methods are compared about the tissue absorbed dose and the spectrums at 2m from the source.
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