DOCSLIB.ORG
Explore
Sign Up
Log In
Upload
Search
Home
» Tags
» CANFLEX
CANFLEX
Fuel Cycle Flexibility in CANDU P.G
NPR81: South Korea's Shifting and Controversial Interest in Spent Fuel
THE NEXT GENERATION CANDU 6 J.M. HOPWOOD XA0053559 Atomic Energy of Canada Ltd, Mississauga, Ontario, Canada
Radiation Safety Information Computational Center
Tritium Resources Available for Fusion Reactors 1: Nuclear Energy Hervé Nifenecker
Enrichment Effects on Candu-Seu Spent Fuel Monte Carlo Shielding Analysis
A AECL EACL AECL Research EACL Recherche
Plutonium Management in the Medium Term
NRC Regulatory History of Non-Light Water Reactors (1950-2019)
Advanced Nuclear Reactor Safety Issues and Research Needs Advanced Nuclear
Management and Storage of Research Reactor Spent Nuclear Fuel Proceedings Series
Bringing the Canflex Fuel Bundle to Market
Comparison of Fuel Temperature Characteristics Between Standard 37-Element and CANFLEX Fuel Bundles
System Reports 4
EC6 and CANMOX Advanced Fuel Technology for Plutonium Reuse Utility-Proven Technology Provides Safe, Timely and Affordable Waste Solutions Sites Using CANMOX™ Fuel
Alternatives for Additional Spent Fuel Storage in South Korea
A Preliminary Analysis of the Reactor-Based Plutonium Disposition Alternative Deployment Schedules
NUCLEAR WASTE MANAGEMENT TECHNICAL SUPPORT DOCUMENT NEW NUCLEAR - DARLINGTON ENVIRONMENTAL ASSESSMENT NK054-REP-07730-00027 Rev 000
Top View
Demonstration Irradiation of CANFLEX in a CANDU 6 Power Reactor
Fuel-Management Simulations for Once-Through Thorium Fuel Cycle in Candu Reactors
Environmental Assessment: Industry Perspective" (Uranium Saskatchewan, Canada)
Trends Towards Sustainability in the Nuclear Fuel Cycle Trends Towards Sustainability in the Nuclear Fuel Cycle
Increasing CANDU Operating Margins with CANFLEX Fuel
Canflex-Ru Fuel Development Program As Xa9953260 One Option of Advanced Fuel Cycles Ev Korea
Koreas CANDU Fuel R and D Program
Use of Reprocessed Uranium
Data Requirements and Maintenance of Records for Spent Fuel Management: a Review
PRPP/SSC Compendium Report
Thesis Outline
2002 Ans Annual Meeting
DEMONSTRATION IRRADIATION of XA9953255 CANFLEX in PT. LEPREAU W. INCH Chalk River Laboratories, Atomic Energy of Canada Limited
Structural Behaviour of Fuel Assemblies for Water Cooled Reactors
S309 Reviewers Guidance for New Nuclear Power Plant Environmental Impact Statements: Final
Technical and Economic Limits to Fuel Burnup Extension Proceedings of a Technical Committee Meeting Held in San Carlos De Bariloche, Argentina, 15–19 November 1999
A Preliminary Analysis of the Reactor-Based Plutonium Disposition Alternative Deployment Schedules
Analysis on Experimental Results of CANDU Fuel Void Reactivity KAERI
VOL 28 Ns 22
Structure Materials for Innovative Nuclear Systems (SMINS-2), Workshop Proceedings, Daejon, Republic of Korea, 31 August-3Septem
Some Considerations in the Canflex-Nu Fuel Design1
Chapter 2. Description of Technology Alternatives
Research Reactor Modernization and Refurbishment
Management of Technical Information Department