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To construct and operate a nuclear research reactor, the licensee is required   to obtain the authorization from the regulatory body. One of the tasks of the   regulatory authority is to verify that the safety analysis fulfils safety   requirements. Historically, the compliance with safety requirements was   assessed using a deterministic approach and conservative assumptions. This   provides sufficient safety margins with respect to the licensing limits on   boundary and operational conditions. Conservative assumptions were introduced   into safety analysis to account for the uncertainty associated with lack of   knowledge. With the introduction of best estimate computational tools, safety   analyses are usually carried out using the best estimate approach. Results of   such analyses can be accepted by the regulatory authority only if appropriate   uncertainty evaluation is carried out. Best estimate computer codes are   capable of providing more realistic information on the status of the plant,   allowing the prediction of real safety margins. The best estimate plus   uncertainty approach has proven to be reliable and viable of supplying   realistic results if all conditions are carefully followed. This paper,   therefore, presents this concept and its possible application to research   reactor safety analysis. The aim of the paper is to investigate the   unprotected loss-of-flow transients "core blockage" of a miniature neutron   source research reactor by applying best estimate plus uncertainty   methodology. The results of our calculations show that the temperatures in   the core are within the safety limits and do not pose any significant threat   to the reactor, as far as the melting of the cladding is concerned. The work   also discusses the methodology of the best estimate plus uncertainty approach   when applied to the safety analysis of research reactors for licensing   purposes

Application of best estimate plus uncertainty in review of research reactor safety analysis