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Active fuel length
Institute for Clinical and Economic Review
小型飛翔体/海外 [Format 2] Technical Catalog Category
A 50-100 Kwe Gas-Cooled Reactor for Use on Mars
Advances in Small Modular Reactor Technology Developments
Self-Sustaining Thorium Boiling Water Reactors
Latest Fusion R&D Activities at INEST
Control Rod Safety Management in Nuclear Power Plant
NRC Collection of Abbreviations
Irradiation Performance of Fast Reactor Fuels
Understanding Non-Hodgkin Lymphoma
Fundamentals of Boiling Water Reactor (Bwr)
A Graphite Isotope Ratio Method Primer—A Method for Estimating Plutonium Production in Graphite Moderated Reactors
NUCLEAR TECHNOLOGY REVIEW 2011 the Following States Are Members of the International Atomic Energy Agency
AP1000 European 4. Reactor Design Control Document
Consequences of Fuel Failure on Criticality Safety of Used Nuclear Fuel
Nuclear Science and Technology
Feature Article
Impact Investigation of Reactor Fuel Operating Parameters on Reactivity for Use in Burnup Credit Applications
Top View
Accuracy of the Nuclide Concentrations Calculated by CASMO-4
Determination of Pu Accumulated in Irradiated Fuels by Non-Destructive Isotopic Correlation Technique *
U-232 and the Proliferation- Resistance of U-233 in Spent Fuel
Ersec Book Ucar Neutronics
Basic Research Needs Workshop on Compact Accelerators for Security and Medicine Tools for the 21St Century
AMES-DISSERTATION.Pdf (6.866Mb)
Nuclear Fission Power and Propulsion
High-Fidelity Multi-Physics Coupling for Determination of Hydride Distribution
CHARACTERISTICS of FAST NEUTRON POWER REACTORS by M.-Th
Radiation Treatment Using Hadrons (Negative Pions, Neutrons, Proton, O and Heavier Ions)
A Conversion Proposal for Iran's IR-40 Reactor with Reduced
Mechanical Elements Operating in Sodium and Other Alkali Metals Volume II Experience Survey
Reactor AP1000 Design Control Document
Controversies in Medical Physics: a Compendium of Point/Counterpoint Debates Volume 2
Benchmark on Kinetic Parameters in the CROCUS Reactor
Technological Lessons from the Fukushima Dai-Ichi Accident
Potential of Thorium Based Fuel Cycles to Constrain Plutonium and Reduce Long Lived Waste Toxicity
The UK's Nuclear Future. Industrial Strategy
R&D and Innovation Needs for Decommissioning of Nuclear
Fusion Neutron Sources
Radiation Protection and Safety in Medical Uses of Ionizing Radiation Jointly Sponsored By
Tier 2 Chapter 4 – Reactor – Section 4.3 Nuclear Design
Evaluation Guide for the Evaluated Spent Nuclear Fuel Assay Database (SFCOMPO) Unclassified NEA/NSC/R(2015)8
High-Temperature XAFS Measurement of Molten Salt Systems
Thorium Fuel Cycle — Potential Benefits and Challenges
Studsvik Report STUDSVIK/ES-95/10
JAERI-Research 95-087 BEHAVIOR of IRRADIATED PWR FUEL
Dosimetry of Small Static Fields Used in External Beam Radiotherapy
Plutonium Discharge Rates and Spent Nuclear Fuel Inventory Estimates for Nuclear Reactors Worldwide
Advanced Large Water Cooled Reactors a Supplement to the IAEA’S Advanced Reactor Information System (ARIS)
Reactor Physics Scoping and Characterization Study on Implementation of TRIGA Fuel in the Advanced Test Reactor
DESIGN and FUEL MANAGEMENT of PWR CORES to OPTIMIZE the ONCE-THROUGH FUEL CYCLE by Edward K
Detailed Radiation Dose Rate Evaluations of Commercial Spent Nuclear Fuel Canisters
"Fuel Fragmentation, Relocation, and Dispersal During the Loss-Of
Mtg Materials
Studies of Nuclear Fuel Performance Using On-Site Gamma-Ray Spectroscopy and In-Pile Measurements
Pin-Wise Loading Optimization and Lattice–To-Core Coupling for Isotopic Management in Light Water Reactors
Fuel Cycle Analysis of the SABR Subcritical Transmutation Reactor
[Boiling-Water Reactor] Fuel Assemblies
FY 2013 Volume 5