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A deterministic model for criticality and rod worth analysis of the DNRR research reactor with HEU fuel
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This paper presents the development and verification of a deterministic model using the SRAC code system for analysing the criticality and control rod worth of the Dalat Nuclear Research Reactor (DNRR). Numerical calculations were performed based on seven core configurations established experimentally during the startup period of the DNRR.
Nội dung trích xuất từ tài liệu:
A deterministic model for criticality and rod worth analysis of the DNRR research reactor with HEU fuel
Nội dung trích xuất từ tài liệu:
A deterministic model for criticality and rod worth analysis of the DNRR research reactor with HEU fuel
Tìm kiếm theo từ khóa liên quan:
Control rod worth SRAC code system Dalat Nuclear Research Reactor Numerical calculations Various nuclear data librariesTài liệu liên quan:
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