Nuclear fuels
Resource Information
The concept Nuclear fuels represents the subject, aboutness, idea or notion of resources found in Indiana State Library.
The Resource
Nuclear fuels
Resource Information
The concept Nuclear fuels represents the subject, aboutness, idea or notion of resources found in Indiana State Library.
- Label
- Nuclear fuels
- Authority link
- (EG-IN)592459
81 Items that share the Concept Nuclear fuels
Context
Context of Nuclear fuelsSubject of
- A review and evaluation of available critical experiment-data for HTGR-non-proliferation fuel cycles
- Allocation of uranium enrichment services to fuel foreign and domestic nuclear reactors, Energy Research and Development Administration, Department of State : report to the Committee on Foreign Affairs, House of Representatives
- An assessment of U.S. domestic capacity for producing reactor-grade thorium dioxide and controlling associated wastes for effluents
- Analysis of alternative light water reactor (LWR) fuel cycles
- Analytical methods for fissionable material determinations in the nuclear fuel cycle
- Assessment of carbon-14 control technology and costs for the LWR fuel cycle
- Atomic energy : uranium supply for TRIGA reactor : agreement between the United States of America and and the Socialist Republic of Romania, effected by exchange of notes dated at Washington February 13, 1978
- Certain actions that can be taken to help improve this Nation's uranium picture, Energy Research and Development Administration : report to the Congress
- Concept evaluation of a nuclear design for electronuclear fuel production : evaluation of ORNL's proposed TMF-ENFP
- Conventions on Early Notification of a Nuclear Accident and on Assistance in the Case of a Nuclear Accident or Radiological Emergency : message from the President of the United States transmitting two conventions ... both adopted in Vienna at a special session of the General Conference of the International Atomic Energy Agency on September 26, 1986, and signed by the United States on that date
- Depleted uranium valuation
- Deposition of silicon carbide coatings on particles in a fluidized bed using silane and tetramethylsilane : a feasibility study
- Description of alternative steady-state fuel cycles
- Detection of hydrogen buildup in initially pure nonhydrogenous liquids
- Development of interagency relationship in the regulation of nuclear materials and facilities : Nuclear Regulatory Commission, Energy Research and Development Administration : report to the Senate Committee on Government Operations
- Development of nuclear power fuel cycles : report
- Environmental analysis of the uranium fuel cycle
- Environmental and radiological safety studies : interaction of 238PuO2
- Environmental impact statement for Hot Fuels Engineering Laboratory
- European reactions to the international nuclear fuel cycle evaluation
- Evaluation of MHTGR fuel reliability
- Examination of fast reactor fuels and FBR analytical quality assurance standards and methods
- Examination of fast reactor fuels, FBR analytical quality assurance standards and methods, and analytical methods development -- irradiation tests
- Export of nuclear fuel to India : hearings and markup before the Committee on International Relations, House of Representatives, Ninety-fifth Congress, second session, May 23, June 8 and 14, 1978
- Fort St. Vrain MEU program : final report
- Fuel cycle programs
- GCFR fuel cycle information for the ORNL nonproliferation study
- HTGR fuels and core development program
- Hydrogen pellet fueling experiment on the ISX-A tokamak
- In-pile observation of fuel and clad relocation during LMFBR core-disruptive accidents
- Interim design report : fuel particle crushing
- Interim development report, engineering-scale HTGR fuel particle crusher
- Interlaboratory reaction rate program : 11th progress report, November 1975-October 1976
- LWR spent fuel disposition capabilities : 1976-1985
- LWR spent fuel disposition capabilities, 1977-1986
- Mass flows for LMFBRs fueled with various types of plutonium and fertile material
- Molten-salt reactors for efficient nuclear fuel utilization without plutonium separation
- Monte Carlo-based validation of the ENDF/MC2-II/SDX cell homogenization path
- Neutronic experiment planning for the fuels refabrication and development program
- Non-proliferaton cycles, Core design plans
- Nuclear fuel export to India : hearing before the Subcommittee on Arms Control, Oceans, and International Environment of the Committee on Foreign Relations, United States Senate, Ninety-fifth Congress, second session ... May 24, 1978
- Nuclear fuels
- Nuclear fuels policy : report of the Atlantic Council's Nuclear Fuels Policy Working Group
- Nuclear proliferation and reprocessing : hearing before the Subcommittee on International Security and Scientific Affairs of the Committee on International Relations, House of Representatives, Ninety-fourth Congress, second session, June 7, 1976
- Nuclear reactor fuel elements; metallurgy and fabrication
- Overview of nuclear export policies of major foreign supplier nations : study by the staff of the U.S. General Accounting Office
- Preliminary estimates of the charge for spent fuel storage and disposal services
- Program ELM : a tool for rapid thermal-hydraulic analysis of solid-core nuclear rocket fuel elements
- Proliferation resistance design of a plutonium cycle : (proliferation resistance engineering program, PREP)
- Proliferation-resistant nuclear fuel cycles
- Proposed plan for critical experiments supporting thorium fuel cycle development
- Report on strategic special nuclear material inventory differences
- Report to the LMFBR Steering Committee on resources, fuel and fuel cycles, and proliferation aspects
- Reprocessing of nuclear fuels and plutonium breeder commercialization : implications of deferral
- Resolutions of disapproval pertaining to the shipment of nuclear fuel to India : hearings and markup before the Committee on Foreign Affairs, House of Representatives, Ninety-sixth Congress, second session, June 26, July 23, and September 10, 1980
- Rover process verification studies : sintered metal filters blowback system
- Rover process verification studies : transport of dry solids
- STARBUCS : a prototypic SCALE control module for automated criticality safety analyses using burnup credit
- Safety evaluation report for the National Enrichment Facility in Lea County, New Mexico : docket no. 70-3103, Louisiana Energy Services
- Sources of neutronics data involving thorium or 233U and light water moderation
- THO2-based pellet fuels, their properties, methods of fabrication, and irradiation performance : a critical assessment of the state of thetechnology and recommendations for further work
- TRISO-coated particle fuel phenomenon identification and ranking tables (PIRTs) for fission product transport due to manufacturing, operations, and accidents
- TRISO-coated particle fuel phenomenon identification and ranking tables (PIRTs) for fission product transport due to manufacturing, operations, and accidents
- Technical specifications for the pool critical assembly
- The General Atomic HTGR fuel reprocessing pilot plant : results of initial sequential equipment operations
- The General Atomic reprocessing pilot plant : description and results of initial testing
- The economy and utilization of thorium in nuclear reactors : technical annexes 1 and 2
- The energy content of nuclear fuels : technical comparisons and computations report
- The gravimetric determination of carbon in uranium-plutonium carbide materials
- The status and development potential of plate-type fuels for research and test reactors
- Thorium fuel-cycle alternatives
- Thorium production technology
- U.S. commercial nuclear power : historical perspective, current status, and outlook
- Uniframe interim development design report
- Uranium and nuclear fuel
- Uranium and thorium
- Uranium dioxide: : properties and nuclear applications
- Uranium enrichment : a speech
- Uranium enrichment policy : hearing before the Subcommittee on Energy Research and Development of the Committee on Energy and Natural Resources, United States Senate, Ninety-fifth Congress, second session ... February 9, 1978
- Uranium production technology
- Verification of the LWRARC code for light-water-reactor afterheat rate calculations
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<div class="citation" vocab="http://schema.org/"><i class="fa fa-external-link-square fa-fw"></i> Data from <span resource="http://link.library.in.gov/resource/geh_1jpqFKQ/" typeof="CategoryCode http://bibfra.me/vocab/lite/Concept"><span property="name http://bibfra.me/vocab/lite/label"><a href="http://link.library.in.gov/resource/geh_1jpqFKQ/">Nuclear fuels</a></span> - <span property="potentialAction" typeOf="OrganizeAction"><span property="agent" typeof="LibrarySystem http://library.link/vocab/LibrarySystem" resource="http://link.library.in.gov/"><span property="name http://bibfra.me/vocab/lite/label"><a property="url" href="http://link.library.in.gov/">Indiana State Library</a></span></span></span></span></div>
