1,600 results on '"failures"'
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2. RBMK pressure tube rupture assessment
3. BEHAVE-SST; overpower transient fuel mechanics. [CDC7600; FORTRAN IV]
4. PECS3; probabilistic evaluation cladding life. [CDC7600; FORTRAN IV]
5. FRAP-T4; FRAP-T; transient analysis of oxide fuel rods. [CDC7600; IBM360; FORTRAN (99%) and Assembly language (1%). The Assembly language is used in a few of the INEL Environmental Routines]
6. Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests
7. SSC analysis of the GEMs for reactivity control in PRISM
8. SAS4A analysis of unprotected loss of flow accidents in a metal fuel reactor
9. The characterization and monitoring of metallic fuel breaches in EBR-2
10. Comparison of SCDAP/RELAP5/MOD3 to TRAC-PF1/MOD1 for timing analysis of PWR fuel pin failures
11. Behavior of low-burnup metallic fuels for the integral fast reactor at elevated temperatures in ex-reactor tests
12. The characterization and monitoring of metallic fuel breaches in EBR-2
13. Whole-Pin Furnace system: An experimental facility for studying irradiated fuel pin behavior under potential reactor accident conditions
14. Recent progress in the development of metallic fuel
15. Thermal-hydraulic impact of failure of highly irradiated fuel pins on LMR passive safety
16. Run - Beyond - Cladding - Breach (RBCB) test results for the Integral Fast Reactor (IFR) metallic fuels program
17. Consequences of metallic fuel-cladding liquid phase attack during over-temperature transient on fuel element lifetime
18. In-vessel retention of core debris in integral fast reactor severe accident sequences
19. M8 power calibration (M8CAL) hodoscope report
20. Validation of the integrated SASSYS/SAS4A-FPIN2 model for the transient analysis of metallic fuel elements
21. Current status of the Run-Beyond-Cladding Breach (RBCB) tests for the Integral Fast Reactor (IFR). Metallic Fuels Program
22. Fuel-element failures in Hanford single-pass reactors 1944--1971
23. Timing analysis of PWR fuel pin failures
24. Timing analysis of PWR fuel pin failures
25. Probabilistic treatment of a long-term shutdown event with peak xenon and failed rods. Task: PRA
26. System 80+{trademark} Standard Design: CESSAR design certification. Volume 12: Amendment I
27. Acceptance of failed SNF (spent nuclear fuel) assemblies by the Federal Waste Management System
28. A model for predicting coolant activity behaviour for fuel-failure monitoring analysis
29. Sodium boiling dryout correlation for LMFBR fuel assemblies
30. Mechanistic modeling of Zircaloy deformation and fracture in fuel element analysis
31. Deformation and fracture characteristics of spent Zircaloy fuel cladding
32. Results of transient overpower events on breached and unbreached fuel pins
33. Mechanical properties of transient-tested irradiated fast-reactor cladding. [811/sup 0/ to 1644/sup 0/K; 5. 8 x 10/sup 22/ n/cm/sup 2/]
34. TS-1 and TS-2 transient overpower tests on FFTF fuel
35. Neutronic and thermal design considerations for heat-pipe reactors
36. Evaluating the loss of a LWR spent fuel or plutonium shipping package into the sea. [Radioecological effects]
37. An evaluation of LMR design options for reduction of sodium void worth
38. Fuel pin failure models and fuel-failure thresholds for core disruptive accident analysis
39. Zircaloy cladding deformation in a steam environment with transient heating
40. FUEL ELEMENT LOCATION IN THE ML-1 REACTOR
41. SUMMARY AND EVALUATION OF STARTUP AND OPERATING EXPERIENCE AT INDIAN POINT STATION
42. Power cycling of fuel specimens clad with thin-wall stainless steel
43. Observation of fuel failure behavior during in-pile meltdown tests using high-speed photography and a transparent autoclave
44. Slug-Burst Detection in the G3 Reactor; La detection de rupture de gaine au reacteur G3
45. Late-stage accident behavior of a highly disrupted LMR oxide fuel bundle
46. Thermal-hydraulic effect of grid spacers and cladding rupture during reflood
47. Spent fuel assembly source term sensitivity parameters
48. Status of the Monticello nuclear generating plant lead plant license renewal program
49. Analysis of the light-water flooding of the HFBR thimble tubes
50. Run-beyond-clad-breach oxide testing in EBR-2
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