Reactor Research
FUKUSHIMA
NEW Tanaka_lessonslearned_88_PJA8809B-01
Chart of radiation releases by reactor and isotopes
NEI Report On Fukushima Disaster
The Geology of Fukushima (with many diagrams) http://fukushima.over-blog.fr/m/article-88575278.html
General
New DOE_Monju_098b7ef980003e20
New Standard Technical Specifications for GE BWR
NRC Technical Specifications For Various Reactor Models
Economic Undertow – Technical document on melted fuel, recriticality and explosion potentials
Maintenance Management and New Inspection Program JAEAinspection_jnesel-tt-008
NUCLEAR GENERATING STATION PLUME AND POST-PLUME EXERCISES AND INCIDENTS LIBRARY OF PRESS RELEASES Nuclear Power Plant Material
ORNL document – Reactor Operating Experiences 1972-1974 (details on reactor behavior in various accident scenarios)
ANSN – Training course long term BWR safety
Recirculation Line Break and Annulus Pressurization Loads for BWRs ML101590626
GE_ABWR_design_ML11126A109 (ABWR are newer designs than Daiichi)
IAEA_hydrogen_accidents_TE_1661_Web
IAEA cn200_final-fukushima-mission_report
SENSORS – Weed Instrumentation – details on types of sensors and instruments used at Fukushima
BWR containment manual ML11263A359
TIPS Transversing Incore Probes information – http://www.oecd-nea.org/science/rsd/ic96/5-3.pdf
Severe Accident Recriticality Analysis
CONTAINMENT
New Primany_Secondary_ContainmentFailures_BWR_5835351
FAILURE MODES OF THE BWR REACTOR VESSEL BOTTOM HEAD
OCRD – Role of BWR Secondary Containments in Severe Accident Mitigation (PDF version here)
Oyster creek sand bed_containmentML091140361
CODE FOR CONCRETE REACTOR VESSELS AND CONTAINMENTS
NRC Report On Brunswick NPP Torus ML020110289
containment core melt BWR 6250306
CONTAINMENT – M Raghab – Containment Structures
VALVES & VENTING
New Nuclear_Valves_Nuclear A4 UK English – web ready
VENTING – Westinghouse – Passive Hardened Vents for BWRs
VENTING – Excelon – reactor safety relief valves
VALVES – ORNL – Check valves: Oak Ridge’s new diagnostics.
FUEL
http://edocket.access.gpo.gov/2006/E6-17937.htm
Fuel research – http://article.nuclear.or.kr/jknsfile/v41/JK0410163.pdf
Union of Concerned Scientists – UCS fuel cladding failure analysis
SPENT FUEL POOLS
New EPR_2.I.1.6 – Design of Pool Liners (Except IRWST) – v2
New EPRfuelpools
New USdrystorageSpentfuelResearch_eds_rpt
Safety and Security of Commercial Spent Fuel – lots of details about fuel pool specifications and design.
http://www.princeton.edu/sgs/publications/sgs/pdf/5_1albright.pdf
Stress Corrosion Cracking Spent Fuel 1431
IAEA_SFP_chemistry_te_0944_scr
Station Black Out & LOCA
Station Blackout model and details
Corrosion
CORROSION MECHANISMS AND THEIR CONSEQUENCES FOR NUCLEAR POWER PLANTS WITH LIGHT WATER REACTORS
NUCLEAR REACTOR CORIUM INFORMATION
NRC corium melt in BWR – Liner Failure By Corium Melt
Argonne National Lab –Corium Coolability under ex-vessel accident conditions for LWRs
Oak Ridge National Lab – Identification and Assessment of BWR In-Vessel Severe Accident Mitigation Strategies
Idaho National Lab – A Heat Transfer Model for a Stratified Corium-Metal Pool in the Lower Plenum of a Nuclear Reactor
Notes on the corium/containment manual – Nancy
NRC – Reactor Safety Course – section on containment and corium in the BWR reactor
Assessment and Development of Molten Corium Concrete Interaction Models for the Integral Code ASTEC
REACTOR FLOODING (mostly US documentation)
57465620-Bernard-Shanks-Flood-Risk-Editorial
EditedPerkinsReportML12188A239
Nuclear Power Whistleblowers Charge Federal Regulators With Favoring Secrecy Over Safety
Possible Fort Peck Dam Failure Major Threat To Missouri Flooding _ Plains Daily