Simulation of the modified K reactor supplementary safety system

Conference · Tue Jan 01 00:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States)

OSTI ID:7073770

Paik, I K; Canas, L R ^[1]; Peterson, P F ^[2]

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1. Westinghouse Savannah River Co., Aiken, SC (United States)
2. Univ. of California, Berkeley (United States)

The supplementary safety system (SSS) of the K reactor provides a second line of defense to shut down the reactor if the safety and control rods fail to scram. The SSS was originally designed to inject a neutron poison solution (ink) into the reactor tank via spargers. Recently, concerns arose that the ink inventory might run out before the ink front returned to the moderator during a loss-of-ac-power transient in which the coolant pumps coast down. Thus, a new system has been added to inject additional ink through the pump suctions so that ink will arrive in the core before depletion of the sparger ink. The MODFLOW code was developed to calculate the moderator flow distribution in Savannah River site (SRS) reactors, including the effects of inertia and stratification from buoyancy forces.

• OSTI ID: 7073770
• Report Number(s): CONF-911107-; CODEN: TANSA; TRN: 92-030829
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 63; Conference: 1991 Winter meeting of the American Nuclear Society (ANS) session on fundamentals of fusion reactor thermal hydraulics, San Francisco, CA (United States), 10-15 Nov 1991; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
ENGINEERED SAFETY SYSTEMS
COMPUTERIZED SIMULATION
RELIABILITY
K REACTOR
AC SYSTEMS
BLACKOUTS
COMPUTER CODES
CONTROL ELEMENTS
ECCS
ELECTRICAL TRANSIENTS
FINITE DIFFERENCE METHOD
FLOW MODELS
HEAT TRANSFER
HYDRAULICS
M CODES
MODERATORS
PUMPS
RADIOACTIVE AEROSOLS
RADIOACTIVITY TRANSPORT
REACTOR PROTECTION SYSTEMS
SAFETY INJECTION
SAVANNAH RIVER PLANT
SCRAM
SPARGERS
AEROSOLS
COLLOIDS
DISPERSIONS
ENERGY TRANSFER
FLUID MECHANICS
HEAVY WATER MODERATED REACTORS
ITERATIVE METHODS
MATHEMATICAL MODELS
MECHANICS
NATIONAL ORGANIZATIONS
NUMERICAL SOLUTION
POWER SYSTEMS
PRODUCTION REACTORS
REACTOR COMPONENTS
REACTOR SHUTDOWN
REACTORS
SHUTDOWN
SIMULATION
SOLS
SPECIAL PRODUCTION REACTORS
TRANSIENTS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
VOLTAGE DROP
220900* - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors