Behavior of irradiated PWR [Presssurized Water Reactor] fuel under a simulated RIA [Reactivity Initiated Accident] condition: [results of NSRR [Nuclear Safety Research Reactor] test MH-3].

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TextLanguage: en Language: en Language: ni Publication details: Tokai, Ibaraki : JAERI, 1995.Description: iv, 179 p. : il

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Books	Centro de Información Eduardo Savino	JAERI-Research-95-087 (Browse shelf(Opens below))	Available	47280

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Previous	JAERI-Research-95-079 Study of density limit in JT-60 joule heated plasmas.	JAERI-Research-95-080 Experimental data report for test TS-5 reactivity initiated accident test in the NSRR with pre-irradiated BWR fuel rod.	JAERI-Research-95-081 Compilation report of VHTRC temperature coefficient benchmark calculations.	JAERI-Research-95-087 Behavior of irradiated PWR [Presssurized Water Reactor] fuel under a simulated RIA [Reactivity Initiated Accident] condition: [results of NSRR [Nuclear Safety Research Reactor] test MH-3].	JAERI-Research-95-088 Oxidation characteristics of oxide dispersion strengthened [ODS] alloy.	JAERI-Research-95-089 Numerical prediction of turbulent heat transfer augmentation in an annular fuel channel with two-dimensional square ribs.	JAERI-Research-96-003 OECD/NEA Burnup credit criticality benchmark: result of phase IIA.	Next

Bibliografía: p.28-30

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