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731 results on '"Reactor Pressure Vessel"'

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1. Assessment of VVER 1000 core degradation for bounding cases with ASTEC 2.1.1.0

2. On the quench of a debris bed in the lower head of a Nordic BWR by coolant injection through control rod guide tubes

3. Prandtl number effect on thermal behavior in volumetrically heated pool in the high Rayleigh number region

4. Model development for fragment-size distribution based on upper-limit log-normal distribution

5. Structural assessment of radiation damage in light water power reactor concrete biological shield walls

6. Analysis of a steam line break accident of a generic SMART-plant with a boron-free core using the coupled code TRACE/PARCS

7. Determination of pressure loss coefficient of the hot duct break of the CEA ALLEGRO 2009 concept using a CFD technique

8. Influences of some engineered factors on IVR-ERVC limits

9. CAP1400 IVR related design features and assessment

10. Exemplification of AC2’s multidimensional capabilities to the application of large pools within the frame of the German EASY project

11. BWR-4 ATWS modeling with RELAP5-S3K

12. Failure domain analysis and uncertainty quantification using surrogate models for steam explosion in a Nordic type BWR

13. A sensitivity study of MELCOR nodalization for simulation of in-vessel severe accident progression in a boiling water reactor

14. Effects of neutron irradiation on magnetic properties of reactor pressure vessel steel

15. Numerical analysis of the ROCOM boron dilution benchmark experiment using the CUPID code

16. Modular system for probabilistic fracture mechanics analysis of embrittled reactor pressure vessels in the Grizzly code

17. Precipitation profile and dryout concentration of sea-water pool-boiling in 5 × 5 bundle geometry

18. Safety cases for design-basis accidents in LWRs featuring passive systems

19. Water-jacket reactor cavity cooling system concept to mitigate severe accident consequence of high temperature gas-cooled reactor

20. Experimental and numerical investigation of sloshing behavior in annular region separated by several cylinders related to fast reactor design

21. A miniature integrated nuclear reactor design with gravity independent autonomous circulation

22. Jet impingement model for system analysis code to enhance mixing behavior prediction in downcomer during DVI line break accident

23. A margin missed: The effect of surface oxidation on CHF enhancement in IVR accident scenarios

24. Measurement of the residual stresses in a PWR Control Rod Drive Mechanism nozzle

25. An analysis of radiological releases during a station black out accident for the APR1400

26. Ablation and thermal stress analysis of RPV vessel under heating by core melt

27. On the characteristics of the flow and heat transfer in the core bypass region of a PWR

28. Assessment of a lower head molten pool analysis module using LIVE experiment

29. Identification of ductile damage parameters for pressure vessel steel

30. Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 2. Creep deformation and failure of the reactor pressure vessel

31. Effect of different conditions on heat transfer characteristics of molten Zr-Stainless steel pool with water injection

32. Mechanistic critical heat flux prediction for in-vessel retention conditions

33. A new correlation for CCFL at full scale PWR excluding the Hutze effect in UPTF data

34. Investigation of neutron noise in a micro-scale, natural circulation molten salt fission battery system

35. Reactor cell neutron dose for the molten salt breeder reactor conceptual design

36. Mathematical model for predicting the vibration performance of a core barrel considering the interaction of seismic load and fluid force

37. Design optimization of a closure head for a PWR reactor pressure vessel

38. Features of heat and deformation behavior of a VVER-600 reactor pressure vessel under conditions of inverse stratification of corium pool and worsened external vessel cooling during the severe accident. Part 1. The effect of the inverse melt stratification and in-vessel top cooling of corium pool on the thermal loads acting on VVER-600’s reactor pressure vessel during a severe accident

39. Investigation of various reactor vessel auxiliary cooling system geometries for a hybrid micro modular reactor

40. Comparative study with two reduced test facilities for air-cooled RCCS scaling law

41. Core design of ma-transmutation fast reactor with zirconium hydride target

42. External function for GOTHIC code to estimate critical heat flux conditions for in-vessel retention assessment

43. Enhanced safety characteristics of SMART100 adopting passive safety systems

44. Baffle jetting modelling

45. Thermo-mechanical behavior of an ablated reactor pressure vessel wall in a Nordic BWR under in-vessel core melt retention

46. Study of rescue measure of Kuosheng BWR power plant to cope with Fukushima-type accident

47. Nuclear energy system’s behavior and decision making using machine learning

48. Study on the reactor core barrel instantaneous characteristics in case of Loss of Coolant Accident (LOCA) scenarios for loop-type PWR

49. Preliminary forensic engineering study on aggravation of radioactive releases during the Fukushima Daiichi accident

50. Experimental investigation of 3-D ERVC process for IVR strategy – CHF limits and visualization of boiling phenomena

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