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By C.J. Joachain

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3. Proliferation-resistance The potential linkage between peaceful use of nuclear energy and the proliferation of nuclear weapons has been a continuing societal concern. To ensure the absence of un-declared nuclear material and activities or diversion of nuclear mater ial for weapons purposes, an international non-proliferation regime has been developed. This regime consists of the following components: • An international institutional framework for non-proliferation based on the Non-Proliferation Treaty and comprehensiv e IAEA safeguards agreements and protocols; International verification measures (the IAEA Safeguards system plus regional and bilateral agreements) to provide credible assurance of the non-diversion of nuclear material and of the absence of undeclared nuclear material and activities; Export controls on nuclear materials, specified facilities, equipment and other materials, including dual-use technologies and materials; and National physical protection measures and material accounting and controls measures, as well as IAEA recommendations on physical protection.

Tables 6 and 7 of this report lists the computer codes used for linear and non-linear stability analysis. These codes have neutron kinetics models ranging from point kinetics to full 3-D kinetics. Computational fluid dynamic (CFD) codes can also serve as valuable tools for the analysis of natural circulation flows. CFD codes are particularly well suited for analysing single-phase fluid flow inside complex geometries. ANNEX 20 provides an excellent overview of the use of CFD codes in nuclear power plant applications.

The transport equations implemented in typical thermal hydraulic system analysis codes are described in ANNEX 6. Figure 20 presents a summary of the many different formulations used in thermal hydraulic safety analysis codes. They range from very simple 3-equation homogeneous equilibrium models to advanced full non-equilibrium models using 6 balance equations. New codes, such as NRC’s TRACE code are also under development. As demonstrated in ANNEX 9 and ANNEX 19, neutron kinetics can have a large impact on the stability of two-phase natural circulation flows, particularly during BWR operations.

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