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Development of GSA-GCL code version 2 to evaluate radioactivity concentration limit for low level radioactive waste disposal (Contract research)

Takeda, Seiji ; Sawaguchi, Takuma ; Sasaki, Toshihisa*; Kimura, Hideo

The upper bound of radioactivity concentration during disposal means the maximum concentration of radionuclides of waste repository allowable in a license application for that repository. For transuranium (TRU) and uranium wastes, it is necessary to amend the law to set the upper bound of radioactivity concentration for three concepts to dispose of low-level waste categories: near surface disposal without an artificial barrier (trench disposal), near surface disposal with an artificial barrier (concrete vault disposal), and intermediate depth disposal. We developed an assessment code (GSA-GCL ver.2) to derive the upper bound of radioactivity concentration for TRU and uranium wastes, according to geological and artificial barrier features in three disposal concepts. This document summaries descriptions of the capabilities and structure of GSA-GCL ver.2 code, mathematical models, user information for execution of the code system (users' manual), input and output file system and the result of verification for the models in this code. We provide the evaluated result of the upper bounds of radioactivity concentration for radionuclides in TRU wastes, which reflects to the regulation report on the result for three concepts to dispose of low-level waste categories, reviewed by Nuclear Safety Commission of Japan in May 2007.

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