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Pressurizer / Small modular reactor / Reactor protection system / Loss-of-coolant accident / Boiling water reactor safety systems / B&W mPower / Nuclear technology / Energy / Nuclear safety


Pressurized Water Small Modular Reactor (SMR), Design Basis Accident Analysis using the ASTEC code 1 2
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Document Date: 2015-02-07 16:50:28

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File Size: 352,25 KB

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City

Washington / DC / Portorož / Article / Vienna / Bologna / /

Company

ASTEC / Westinghouse / RELAP-GOTHIC / M. Di Giuli1 Nuclear Engineering Laboratory / /

Continent

Europe / /

Country

United States / Italy / Slovenia / /

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Event

Business Partnership / Natural Disaster / /

Facility

Reactor Cooling System / SPES3-IRIS facility / IRIS reactor / Reactor Vessel / Dept. DIN University of Bologna / Reactor Containment / University of Zagreb / Pressurized Water Small Modular Reactor / SPES3 facility / /

IndustryTerm

passive systems / non-electrical nuclear energy applications / sub-systems / electricity demand / leak restriction devices / non-condensable gas effects / reactor systems / main and auxiliary systems / passive safety systems / safety systems / /

NaturalFeature

Core inlet / Steam inlet / /

Organization

Dept. DIN University of Bologna / IRSN / University of Zagreb / International Atomic Energy Agency / DVI DEG / /

Person

IRIS RESPONSE TO TRANSIENTS / Monte Sole / /

Position

CPA / hydrostatic head / RT / /

Product

EBT injection / Direct Vessel Injection / RELAP5 / RELAP GOTHIC injection / v2r2 Pressurizer / /

RadioStation

4504 Core / Core / 423 RT 08 / 293 Core / WCAP-17524 / 526 RT 09 / /

Technology

CAV / condensation / Technology of Nuclear Installations / /

SocialTag