2,236 results on '"Transients"'
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2. RADIATION CHEMISTRY 2010 GORDON RESEARCH CONFERENCE JULY 18-23
3. Dynamic Complexity Study of Nuclear Reactor and Process Heat Application Integration
4. An Implicit Solution Framework for Reactor Fuel Performance Simulation
5. INITIAL RESULTS FROM INVESTIGATIONS TO ENHANCE THE PERFORMANCE OF HIGH TEMPERATURE IRRADIATION-RESISTANT THERMOCOUPLES
6. TWO-PHASE FLOW STUDIES IN NUCLEAR POWER PLANT PRIMARY CIRCUITS USING THE THREE-DIMENSIONAL THERMAL-HYDRAULIC CODE BAGIRA.
7. Selected safety-related events reported in May and June 1982
8. Station blackout in US light-water nuclear reactors
9. Experimental investigation of flow transient critical heat flux at light water reactor conditions
10. Analysis and evaluation of recent operational experience from the Fort St. Vrain HTGR
11. Fuel performance annual report
12. Development of symptoms-oriented operating procedures
13. Modeling transients in PWR steam generator units
14. TRAC-PF1/MOD1 computer code and developmental assessment
15. Selected safety-related events
16. Review of trends in computerized systems for operator support
17. High-Fidelity Space-Time Adaptive Multiphysics Simulations in Nuclear Engineering
18. M0219; FLOT1; PWR flow transient analysis. [CDC6600; FORTRAN IV]
19. VARR2; CRBRP 2-dimensional transient fluid flow analysis. [CDC7600; FORTRAN IV and COMPASS]
20. M0555; ACT1; loss-of-coolant accident analysis. [CDC6600; FORTRAN IV]
21. CHIC-KIN; fast and intermediate power transients. [CDC6600; FORTRAN IV]
22. NALAP; LMFBR transient response to accident. [CDC7600,CYBER76; FORTRAN IV (99%) and COMPASS (1%)]
23. TRAC-PD2/MOD1; best-estimate analysis PWR LOCA. [CDC7600; FORTRAN IV (FTN 4. 5 FORTRAN compiler) with selected COMPASS replacement routines]
24. HEXEREI2; HTGR thermal-hydraulic analysis. [IBM360; FORTRAN IV (99%) and BAL (1%)]
25. NAHAMMER; fluid hammer analysis piping system. [IBM360,370; CDC6600,7600; FORTRAN IV]
26. RELAP3B/MOD110; reactor system transient code. [CDC7600; FORTRAN IV]
27. DEMO4; CRBR reactor and plant transient analysis. [CDC7600; FORTRAN IV]
28. K-TIF; two-fluid PWR downcomer fluid dynamics. [CDC7600; FORTRAN (LRLTRAN and CHAT compiler)]
29. OCTAVIA; pressure vessel failure probabilities. [IBM370,303x; FORTRAN IV]
30. FLASH6; FLASH4; fully-implicit transient simulation. [IBM360,370; CDC6600,7600; FORTRAN IV]
31. RELAP5/MOD1/018; LWR loss of coolant analysis. [CDC CYBER176; CDC7600; FORTRAN IV (90%) and COMPASS (10%)]
32. RELAP4/MOD6; transient thermal-hydraulic study. [IBM360,370; CDC7600; FORTRAN IV (95) and BAL (5) (IBM360), FORTRAN IV (95) and COMPASS (5) (CDC7600)]
33. COMPARE/MOD1A; transient flow with sinks and doors. [CDC7600,CYBER175; FORTRAN IV]
34. Behavior of mixed-oxide fuel elements during an overpower transient
35. Asymmetric flow events in a VEER 1000
36. Interactive nuclear plant analyzer for VVER-440 reactor
37. Fault tree analysis of the EBR-II reactor shutdown system
38. Large break LOCA calculations for the AP600 design
39. Integrated intra-subassembly treatment in the SASSYS-1 LMR systems analysis code
40. Safety aspects of forced flow cooldown transients in modular high temperature gas-cooled reactors
41. Modeling the behavior of metallic fast reactor fuels during extended transients
42. A probabilistic method for evaluating reactivity feedbacks and its application to EBR-II
43. Assessment of core damadge models in SCDAP/RELAP5 during OECD LOFT LP-FP-2
44. Performance analysis of a mixed nitride fuel system for an advanced liquid metal reactor
45. Overview of the Integrated Pressurized Thermal-Shock (IPTS) study
46. Status of High Flux Isotope Reactor (HFIR) post-restart safety analysis and documentation upgrades
47. The MELTSPREAD-1 computer code for the analysis of transient spreading in containments
48. Fast reactor safety testing in Transient Reactor Test (TREAT) in the 1980s
49. IPTS (Integrated Pressurized-Thermal-Shock) study for H. B. Robinson (HBR-HYPO)
50. Simulation of three-dimensional hydrodynamic components with a one-dimensional transient analysis code
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