Sandia National Laboratories have a proud history of research programs to improve the understanding and safety of nuclear power plants during severe accidents. For over 25 years, the MELCOR severe accident code has been developed to examine these situations and increase the safety of the nuclear fleet. This work consisted of integrated experimental and numerical simulation programs to investigate the response of spent nuclear fuel during a complete loss of coolant accident with a primary emphasis on the validation of MELCOR. This report summarizes the efforts made to simulate these accidents with nearly-prototypic boiling water reactor fuel assemblies and the corresponding numerical predictions.

This document provides general guidance for the design and analysis of bolted joint connections. An overview of the current methods used to analyze bolted joint connections is given. Several methods for the design and analysis of bolted joint connections are presented. Guidance is provided for general bolted joint design, computation of preload uncertainty and preload loss, and the calculation of the bolted joint factor of safety. Axial loads, shear loads, thermal loads, and thread tear out are used in factor of safety calculations. Additionally, limited guidance is provided for fatigue considerations. An overview of an associated Mathcad © Worksheet containing all bolted joint design formulae presented is also provided.

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