Para el que quiera entretenerse...algunos de los informes mas importantes en temas de seguridad elaborados por el NRC...

1982 NUREG/CR-2255, “Expert Estimation of Human Error Probabilities in Nuclear Power Plant Operations: A Review of Probability Assessment and Scaling,” W.G. Stillwell et al.

1983 NUREG/CR-2743, “Procedures for Using Expert Judgment to Estimate Human Error Probabilities in Nuclear Power Plant Operations,” D.A. Seaver and Stillwell, W.G.

1984 NUREG/CR-3688, “Generating Human Reliability Estimates Using Expert Judgment,” M.K. Comer et al.

1987 NUREG/CR-4550, “Analysis of Core Damage Frequency From Internal Events: Expert Judgment Elicitation, Part 1 Expert Panel Results.”

1987 NUREG/CR-4982, “Severe Accidents in Spent Fuel Pools in Support of Generic Safety Issue 82,” V.L. Sailer et al.

1987 NUREG/CR-4962, “Methods for the Elicitation and Use of Expert Opinion in Risk Assessment,” A. Mosleh et al.

1990 NUREG/CR-5424, “Eliciting and Analyzing Expert Judgment, A Practical Guide,” M.A. Meyer and Booker, J.M.

1990 NUREG-1150, “Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants”

1990 NUREG/CR-5411, “Elicitation and Use of Expert Judgment in Performance Assessment For High-level Radioactive Waste Repositories,” E.J. Bonano et al.

1996 NUREG-1563, “Branch Technical Position on the Use of Expert Elicitation in the HighLevel Radioactive Waste Program,” J.P. Kotra et al.

1997 NUREG/CR-6372, “Recommendations for Probabilistic Seismic Hazard Analysis: Guidance on Uncertainty and Use of Experts,” R.J. Budnitz et al.

2000 NUREG-1624, “Technical Basis and Implementation Guidelines for A Technique for Human Event Analysis (ATHEANA),” S. Cooper et al.

2008 NUREG-1829, “Estimating Loss-of-Coolant Accident (LOCA) Frequencies Through the Elicitation Process,” R. Tregoning et al.

2012 NUREG-2117, “Practical Implementation Guidelines for SSHAC Level 3and 4 Hazard Studies,” A.M. Kammerer and Ake, J.P.


Como veis, esta el que citaba Gundersen en su video...aqui lo teneis.

severe accidents in spent fuel pools in support of generic safety issue 82

En dicho documento se relatan muchos datos que afectan a la famosa piscina del reactor 4:



This investigation provides an assessment of the likelihood and consequences
of a severe accident in a spent fuel storage pool - the complete
draining of the pool. Potential mechanisms and conditions for failure of the spent fuel, and the subsequent release of the fission products, are identified.
Two older PWR and BWR spent fuel storage pool designs are considered
based on a preliminary screening study which tried to identify vulnerabilities.
Internal and external events and accidents are assessed. Conditions
which could lead to failure of the spent fuel Zircaloy cladding as a result of cladding rupture or as a result of a self-sustaining oxidation reaction are presented. Propagation of a cladding fire to older stored fuel assemblies is evaluated. Spent fuel pool fission product inventory is estimated and the releases and consequences for the various cladding failure scenarios are provided.
Possible preventive or mitigative measures are qualitatively evaluated.
The uncertainties in the risk estimate are large, and areas where additional
evaluations are needed to reduce uncertainty are identified.

__________________