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Journal Articles

Scaling issues for the experimental characterization of reactor coolant system in integral test facilities and role of system code as extrapolation tool

Mascari, F.*; Nakamura, Hideo; Umminger, K.*; De Rosa, F.*; D'Auria, F.*

Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.4921 - 4934, 2015/08

JAEA Reports

Heat Loss and Fluid Leakage Tests of the ROSA-III Facility

; Tasaka, Kanji;

JAERI-M 9834, 42 Pages, 1981/12

JAERI-M-9834.pdf:0.92MB

no abstracts in English

JAEA Reports

Experiment Data of ROSA-III Integral Test RUN 710; Full ECCS Actuation,without Heat Generation in Channel A

Koizumi, Yasuo; Tasaka, Kanji; ; ; Soda, Kunihisa; ; ; ; ;

JAERI-M 9249, 122 Pages, 1981/01

JAERI-M-9249.pdf:3.05MB

no abstracts in English

Oral presentation

Scaling rationale design and extrapolation problem for ITF and SETF

Mascari, F.*; Nakamura, Hideo; De Rosa, F.*; D'Auria, F.*

no journal, , 

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