XDOSE: A Tool for Radiological Consequences For Accidental Releases from the Xe-100

Abstract

XDOSE calculates worker and public doses following an airborne release of radioactive material into the atmosphere under postulated accident conditions at a nuclear facility. It is being developed to support radiological consequence assessments for X-energy’s Xe-100 Small Modular Reactor (SMR). The current Canadian nuclear industry tool implements the methods defined in CSA N288.2-M91 which was written to support large CANDU power reactors as opposed to SMRs. Evaluating atmospheric dispersion and doses in the vicinity of buildings is required for the Xe-100 due to the reduced size of its exclusion boundary. XDOSE is being developed to address this technical concern in addition to evaluating dispersion and doses in the far-field. XDOSE is being developed in compliance with CSA Standards N286.7-16 and N288.2:19.

This paper presents the key assumptions and methods utilized in XDOSE. The new model will be applicable to SMRs and existing reactor designs. This tool is expected to reduce conservatisms in the near-field (i.e., < 1 km from the source) relative to the methods in CSA N288.2-M91.