7,657 results on '"FAST reactors"'
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2. Containment margins in FFTF for postulated failure of in-vessel post-accident heat removal
3. Low-temperature swelling in LWR internal components: a computational assessment
4. Transition Analysis of Promising U.S. Future Fuel Cycles Using ORION
5. Evaluation of Waste Arising from Future Nuclear Fuel Cycle
6. Progress towards developing neutron tolerant magnetostrictive and piezoelectric transducers
7. NRC ARDC Guidance Support Status Report
8. Accelerated Irradiations for High Dose Microstructures in Fast Reactor Alloys
9. Pulsed magnetic welding of breeder reactor fuel pin end closures
10. FBR core design with the composite fuel assembly
11. U. S. program for large sodium/water reaction tests. [LMFBR]
12. ERDA's integrated safeguards system program
13. Relative safeguards risks of advanced reactor concepts. [Material diversion in fuel cycle for seven reactor concepts]
14. Planning for the nuclear future. [Overview of ERDA's nuclear energy program]
15. Status of post-accident fuel containment studies for a 300-MW(e) GCFR demonstration plant
16. Uncertainties in fast breeder reactor fuel pin cladding stress and strain calculations
17. Use of DRACS to Enhance HTGRs Passive Safety and Economy
18. Immobilization of Cesium Traps from the BN-350 Fast Reactor (Aktau, Kazakhstan)
19. A Study of Fast Reactor Fuel Transmutation in a Candidate Dispersion Fuel Design
20. Sustained Recycle in Light Water and Sodium-Cooled Reactors
21. Implications of Fast Reactor Transuranic Conversion Ratio
22. Analyzing Losses: Transuranics into Waste and Fission Products into Recycled Fuel
23. An overview of modeling methods for thermal mixing and stratification in large enclosures for reactor safety analysis
24. FUEL CYCLE ISOTOPE EVOLUTION BY TRANSMUTATION DYNAMICS OVER MULTIPLE RECYCLES
25. Benchmark Development in Support of Generation-IV Reactor Validation (IRPhEP 2010 Handbook)
26. On the Criticality Safety of Transuranic Sodium Fast Reactor Fuel Transport Casks
27. BENCHMARK EVALUATION OF THE INITIAL ISOTHERMAL PHYSICS MEASUREMENTS AT THE FAST FLUX TEST FACILITY
28. Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design
29. Proliferation resistance for fast reactors and related fuel cycles: issues and impacts
30. Innovative Fast Reactors: Impact of Fuel Composition on Reactivity Coefficients
31. Nuclear Data for Innovative Fast Reactors: Impact of Uncertainties and New Requirements
32. Mitigation of Severe Accident Consequences Using Inherent Safety Principles
33. Dry Processing of Used Nuclear Fuel
34. Fast Reactor Fuel Type and Reactor Safety Performance
35. Fate of Noble Metals during the Pyroprocessing of Spent Nuclear Fuel
36. Dynamic Analysis of Fuel Cycle Transitioning
37. Fast Reactor Subassembly Design Modifications for Increasing Electricity Generation Efficiency
38. Design Considerations for Economically Competitive Sodium Cooled Fast Reactors
39. Experiments Performed in Substantiation of the Conditioning of BN-350 Spent Cesium Traps Using Lead or Lead-Bismuth Alloy Filling Technology
40. Use of Multiple Reheat Helium Brayton Cycles to Eliminate the Intermediate Heat Transfer Loop for Advanced Loop Type SFRs
41. The Industrial Sodium Cooled Fast Reactor
42. Minor Actinide Recycle in Sodium Cooled Fast Reactors Using Heterogeneous Targets
43. Behavior of 241Am in fast reactor systems - a safeguards perspective
44. Testing of the dual slab verification detector for attended measurements of the BN-350 dry storage casks
45. On the extension of modern best-estimate plus uncertainy methodologies to future fast reactor and advanced fuel licensing - initial evaluation of issues
46. Clad and duct materials property needs for sodium fast reactors: US perspective
47. Implications for advanced safeguards derived from PR&PP case study results
48. Initial Comparison of Direct and Legacy Modeling Approaches for Radial Core Expansion Analysis
49. Regulatory Technology Development Plan - Sodium Fast Reactor: Mechanistic Source Term – Trial Calculation
50. FY16 Status Report on NEAMS Neutronics Activities
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