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Nuclear reactor core
2012/054167 Al
Design and Analysis of a Nuclear Reactor Core for Innovative Small Light Water Reactors
Sensitivity and Uncertainty Analysis of Multiphysics Nuclear Reactor Core Depletion
Nuclear Energy and the Three Mile Island Unit Two Accident Lesson Plans and Resource Guide
Fact Sheet on U.S. Nuclear Powered Warship (NPW) Safety
Research Reactor Core Conversion Guidebook
Compare and Contrast Major Nuclear Power Plant Disasters: Lessons Learned from the Past
Module04 Design of a Nuclear Reactor
Nuclear Reactor Core Model for the Advanced Nuclear Fuel Cycle Simulator FANCSEE
Nuclear Energy of the Future: What Research for Which Objectives?
Direct Meta-Analyses Reveal Unexpected Microbial Life in the Highly Radioactive Water of an Operating Nuclear Reactor Core
Methods of Utilization of Information From
Thermo-Hydraulics of Nuclear Reactors
Data Base on the Behavior of High Burnup Fuel Rods with Zr-1%Nb Cladding and U0 2 Fuel (VVER Type) Under Reactivity Accident Conditions
Thermal Hydraulic Analysis of a Nuclear Reactor Due to Loss of Coolant Accident with and Without Emergency Core Cooling System
Sensitivity of VVER-1000 Spent Fuel Pin Nuclide Inventory to Operational Parameters
Tools for the Automatic Design of Nuclear Reactor Core Configurations for Fuel Reload, (Re)Arranging New and Partly Spent Fuel
The Nuclear Accident at the Chernobyl Reactor in 1986 Shocked the World
Top View
Research Reactors in France
In Core Instrumentation for Online Nuclear Heating Measurements of Material Testing Reactor Abstract
Fault-Event Trees Based Probabilistic Safety Analysis of a Boiling Water Nuclear Reactor’S Core Meltdown and Minor Damage Frequencies
Generating Records
Nuclear Reactor Core Modelling in Multifunctional Simulators
Nuclear Reactor Theory
Nuclear Reactor with Scrammable Part Length
In-Core Fuel Management Programs for Nuclear Power Reactors
In-CORE NUCLEAR FUEL MANAGEMENT OPTIMIZATION of VVER1000 USING PERTURBATION THEORY
Research Reactors in Latin America and the Caribbean
The Japanese Nuclear Incident: Technical Aspects
The Future of the Nuclear Fuel Cycle— Overview, Conclusions, and Recommendations 1 Chapter 2
Neutron Shielding for Small Modular Reactors
Annual Report 2017 Rosenergoatom 4 — 5
Evaluation of Nuclear Power As a Proposed Solution to Global Warming, Air Pollution, and Energy Security
2011 September Boiling Water Reactor Generic Fundamentals
Nuclear Power Each Year? If Not, Then 11 Reactors—The Most of Any It’S About Time You Get to Know Nuclear
Counterfeit/Obsolete Equipment and Nuclear Safety Issues of VVER-1000 Reactors at Kudankulam, India
Analysis of Nuclear Characteristics of Chernobyl Reactor by WIMS-ATR Code
A Simplified Nuclear Reactor Core Simulator Model A
Nuclear Reactor Physics, Engineering and Safety
Nuclear Power
Geant4 in a New Role - Reactor Physics
Method for Operating a Nuclear Reactor with Scrammable Part Length
Topical Issues in Nuclear Installation Safety Topical Issues in Nuclear Installation Safety
Innovative Technologies for Nuclear Fuel Cycles and Nuclear Power the Originating Section of This Publication in the IAEA Was
Monte Carlo Investigation of the UK's First EPR Nuclear Reactor Startup
Nuclear Power Reactor Core Melt Accidents
Three-Dimensional Kinetics Analysis of Large LMFBR Cores With<Br
Multi-Physics Approach for Nuclear Reactor Analysis Using Thermal
Did You Hear the One About MIT's Little Nuclear Reactor? by Grace Talusan, Boston Magazine, August 2011
Threats of Nuclear Power and Plans for the Future
A CONTRASTIVE ANALYSIS of FOUR CRITICAL NUCLEAR REACTOR CORE SAFETY SYSTEMS and THEIR HISTORICAL and FUTURE IMPLICATIONS by JOSE
IN-CORE FUEL MANAGEMENT for the COURSE on OPERATIONAL PHYSICS of for a Nuclear Electric Power Station
The Technological and Economic Future of Nuclear Power Energiepolitik Und Klimaschutz Energy Policy and Climate Protection