Historical insights in the development of Best Estimate Plus Uncertainty safety analysis

American Nuclear Society, 2000. In: Proceedings of ANS International Meeting on BE Methods in Nuclear Installations Safety Analysis (November 2000), ANS Order No: 700282, ISBN: 0-89448-658-6.

American Nuclear Society, 2004. In: Proceedings of ANS International Meeting on BE Methods in Nuclear Installations Safety Analysis (November 2004), ANS Order No: 700308, ISBN: 0-89448-681-0.

Boyack, B.E., Wilson, G.E. 2004. Lessons learned in obtaining efficient and sufficient applications of the PIRT process. In: Proceedings of ANS International Meeting on BE Methods in Nuclear Installations Safety Analysis (November 2004), ANS Order No: 700308, ISBN: 0-89448-681-0.

Francesco D’ Auria & Oscar Mazzantini, 2011. The Best Estimate Plus Uncertainty challenge in the current licensing process of present reactors. In: Science and Technology of Nuclear Installations Volume 2011, Article ID 958218.

International Atomic Energy Agency, Safety Reports Series No. SRS-23, Accident Analysis for Nuclear Power Plants.

International Atomic Energy Agency, Specific Safety Guide No. SSG-2, Deterministic Safety Analysis for Nuclear Power Plants.

Technical Program Group, Quantifying reactor safety margins: application of CSAU to a LBLOCA, NUREG/CR-5249 (1989), EG&G Idaho.

Technical Program Group, Quantifying reactor safety margins: application of CSAU to a LBLOCA, Nuclear Engineering and Design (1990), Volume 119, Parts 1–6, pp. 1–117.

USNRC, 1986. NUREG 0630 – Cladding Swelling and Rupture Models for LOCA Analysis.

USNRC, 1989. Regulation Guide 1.157 – Best-Estimate Calculations of Emergency Core Cooling System Performance.

USNRC, 2005. Regulation Guide 1.203 – Transient and Accident Analysis Methods.

USNRC, 2007a. Regulation Guide 1.37 – Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants.

USNRC, 2007b. Regulation Guide 1.7 – Control of Combustible Gas Concentrations in Containment.

USNRC, 2007c. NUGEG 0800 – Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, Chapter 4 – Reactor, Chapter 6 – Engineered Safety Features, Chapter 15 – Accident Analysis.

USNRC, 2007d. Regulation Guide 1.26 – Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants.

USNRC, 2011a. CFR Title 10, Volume 1, Section 1.11 – Protect public health and safety.

USNRC, 2011b. CFR Title 10, Part 50 – Domestic Licensing of Production and Utilization Facilities.

USNRC, 2011c. CFR Title 10, Part 100 – Reactor Site Criteria.