1,701 results on '"FAST reactors"'
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2. Status of post-accident fuel containment studies for a 300-MW(e) GCFR demonstration plant
3. Selected safety-related events reported in May and June 1982
4. Upper internals structures and their effect on HCDA energy mitigation in large LMFBRs
5. New procedure for the safe, economical seismic design of components of nuclear plant facilities at low and moderate seismicity sites
6. Fast reactor safety: the convergence of principles and practice
7. In-pile experiments and analysis of the coolability of UO/sub 2/ debris in sodium
8. Estimated doses and risks resulting from routine radionuclide releases from fast breeder reactor fuel cycle facilities: a summary
9. Alternate approaches to nuclear safety
10. Risk-oriented analysis on the German prototype fast breeder reactor SNR-300
11. Third Specialists Meeting on Reactor Noise
12. Experimental breeder reactor-II: 20 yr of operating experience
13. FY15 Status Report on NEAMS Neutronics Activities
14. BISON and MARMOT Development for Modeling Fast Reactor Fuel Performance
15. Fuel Performance Experiments and Modeling: Fission Gas Bubble Nucleation and Growth in Alloy Nuclear Fuels
16. Toward a mechanistic understanding of radiation effects in materials
17. Coupled hydro-neutronic calculations for fast burst reactor accidents
18. HAA3B; aerosol behavior lognormal model. [IBM370; FORTRAN IV (H)]
19. VENUS2; 2-dimensional coupled neutronics-hydrodynamics. [IBM360,370,303x; CDC7600; FORTRAN IV(H)]
20. PAD; one-dimensional coupled Sn neutronics and hydrodynamics. [CDC7600,6600,6400; FORTRAN IV (RUN compiler)]
21. HAARM3; aerosol behavior log-normal dist model. [CDC6400,7600,CYBER73; FORTRAN IV, FTN4. 5 (CDC7600)]
22. NALAP; LMFBR transient response to accident. [CDC7600,CYBER76; FORTRAN IV (99%) and COMPASS (1%)]
23. DSTRESS; transient fuel model for clad strain. [CDC6600,CYBER175; FORTRAN IV]
24. SOFIRE2 1- and 2-CELL; sodium pool fire 1- and 2-cell analysis. [IBM360; FORTRAN IV]
25. NAHAMMER; fluid hammer analysis piping system. [IBM360,370; CDC6600,7600; FORTRAN IV]
26. ORRIBLE; rod bundle flow and temperature distribution. [IBM360,370/195; FORTRAN IV]
27. A theoretical study on the growth of large sodium vapour bubbles in liquid sodium
28. SOCOOL2; sodium-fuel interaction analysis. [IBM360; UNIVAC1108; FORTRAN IV]
29. PROSA2; probabilistic response surface studies. [IBM370; FORTRAN IV (95%) and Assembly language (5%)]
30. REXCO-H (Release 2); 2-dimensional hydrodynamic response to excursion. [IBM360/195; FORTRAN IV]
31. HAMOC; fluid hammer analysis of piping system. [CDC6600,7600,CYBER74-18; FORTRAN IV]
32. LMFBR aerosol release and transport program quarterly progress report for January--March 1976
33. The EBR-II Probabilistic Risk Assessment: Results and insights
34. Risk management activities at the DOE Class A reactor facilities
35. Embedded computer systems for control applications in EBR-II
36. Plant control impact on IFR power plant passive safety response
37. IFR fuel cycle process equipment design environment and objectives
38. Instrumentation and control improvements at Experimental Breeder Reactor II
39. Probabilistic treatment of rod run-in accident initiators and the reactivity feedback responses in EBR-II
40. Behavior of mixed-oxide fuel elements during an overpower transient
41. Performance of U-Pu-Zr fuel cast into zirconium molds
42. SSC analysis of the GEMs for reactivity control in PRISM
43. Fault tree analysis of the EBR-II reactor shutdown system
44. Integrated intra-subassembly treatment in the SASSYS-1 LMR systems analysis code
45. A PRA case study of extended long term decay heat removal for shutdown risk assessment
46. Modeling the behavior of metallic fast reactor fuels during extended transients
47. Review process and quality assurance in the EBR-II probabilistic risk assessment
48. SAS4A analysis of unprotected loss of flow accidents in a metal fuel reactor
49. A probabilistic method for evaluating reactivity feedbacks and its application to EBR-II
50. Real-time distributed simulation using the Modular Modeling System interfaced to a Bailey NETWORK 90 system
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