SciTech Connect

Title: Accident sequences simulated at the Juragua nuclear power plant

Accident sequences simulated at the Juragua nuclear power plant Different hypothetical accident sequences have been simulated at Unit 1 of the Juragua nuclear power plant in Cuba, a plant with two VVER-440 V213 units under construction. The computer code MELCOR was employed for these simulations. The sequences simulated are: (1) a design-basis accident (DBA) large loss of coolant accident (LOCA) with the emergency core coolant system (ECCS) on, (2) a station blackout (SBO), (3) a small LOCA (SLOCA) concurrent with SBO, (4) a large LOCA (LLOCA) concurrent with SBO, and (5) a LLOCA concurrent with SBO and with the containment breached at time zero. Timings of important events and source term releases have been calculated for the different sequences analyzed. Under certain weather conditions, the fission products released from the severe accident sequences may travel to southern Florida.
Authors:
Publication Date:
OSTI Identifier:665976
Report Number(s):ORNL/CP--98752; CONF-981011--
ON: DE98007183; TRN: 99:000284
DOE Contract Number:AC05-96OR22464
Resource Type:Technical Report
Data Type:
Resource Relation:Conference: American Nuclear Society international topical meeting on safety of operating reactors, San Francisco, CA (United States), 11-14 Oct 1998; Other Information: PBD: [1998]
Research Org:Oak Ridge National Lab., TN (United States)
Sponsoring Org:Department of Defense, Washington, DC (United States)
Country of Publication:United States
Language:English
Subject: 22 NUCLEAR REACTOR TECHNOLOGY; 21 NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS; JURAGUA-1 REACTOR; M CODES; DESIGN BASIS ACCIDENTS; LOSS OF COOLANT; OUTAGES; COMPUTERIZED SIMULATION; SOURCE TERMS; RADIONUCLIDE MIGRATION; THEORETICAL DATA