Quantifying reactor safety margins part 1: An overview of the code scaling, applicability, and uncertainty evaluation methodology

Abstract

In August 1998, the Nuclear Regulatory Coml,lission (NRC) approved the final version of a revised rule on the acceptance of emergency core cooling systems (ECCS) entitled 'iEmergency Core Cooling System: Revisions to Acceptance Criteria."" The revised rule states an alternate ECCS performance analysis, based on best-estimate methods, may be used to provide more realistic estimates of plant safety margins, provided the licensee quantifies the uncertainty of the estimates and * Ttlis work WJS fuIIdd hy the US Nuclc,lr l{cg[ll,]~ory Cornlniss ion (NRC), of Tit c of Nll(.

Development of HyPEP, A Hydrogen Production Plant Efficiency Calculation Program

“…A more rigorous approach exists but it involves man-years of effort and is suited more for final safety analysis. (Boyack 1990) …”

Updated TRAC analysis of an 80% double-ended cold-leg break for the AP600 design

“…The format and period definitions of the LBLOCA in AP600 closely follow those of Ref. 11. These'time periods, term'ed blowdown, reffl, reflood, and long-term cooling are defined by the start of accumulator injection and by the core and lower plenum liquid mass fraction behaviors (Fig.…”

Generation IV Nuclear Systems: State of the Art and Current Trends with Emphasis on Safety and Security Features

“…PIRT was developed in the late 1980s, for the qualification of deterministic safety codes for Light Water Reactors [32,33]. It is a systematic way of gathering information from experts on a specific subject, and ranking the importance of the information, in order to meet some decision-making goal [34].…”