3-D thermal stress analysis of hot spots in reactor piping using bem.

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TextLanguage: en Publication details: Ibaraki-ken : Japan Atomic Energy Research Institute, 1994.Description: 66 p

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Item type	Home library	Call number	Status	Barcode
Books	Centro de Información Eduardo Savino	JAERI-Research 94-007 (Browse shelf(Opens below))	Available	45062

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Previous	JAERI-Research-96-031 Numerical simulations of heat transfer in an annular fuel channel with three-dimensional spacer ribs set up periodically under a fully developed turbulent flow.	JAERI-Research 94-001 Transport studies of tokamak plasmas in JT-60 device.	JAERI-Research 94-006 Behavior of pre-irradiated fuel under a simulated ria condition [results of NSRR test JM-3].	JAERI-Research 94-007 3-D thermal stress analysis of hot spots in reactor piping using bem.	JAERI-Research 94-008 Thermal durability of modified synroc material as reactor fuel matrix.	JAERI-Research 94-011 Onset of elms in JT-60U.	JAERI-Research 94-013 Stability analysis of external kink mode for iter l-mode profile plasmas.	Next

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