Published 2014
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Study of a loss of coolant accident of a PWR reactor through a Full Scope Simulator and computational code RELAP
Description
The present paper proposes a study of a loss of coolant accident of a PWR reactor through a Full Scope Simulator and computational code RELAP. To this end, it considered a loss of coolant accident with 160 cm2 breaking area in cold leg of 20 circuit of the reactor cooling system of nuclear power plant Angra 2, with the reactor operating in stationary condition, to 100% power. It considered that occurred at the same time the loss of External Power Supply and the availability of emergency cooling system was not full. The results obtained are quite relevant and with the possibility of being used in the planning of future activities, given that the construction of Angra 3 is underway and resembles the Angra 2. (author)
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46034938.pdf
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Additional details
Additional titles
- Original title (Portuguese)
- Estudo do acidente com perda de refrigerante de um reator PWR atraves de um simulador de escopo completo e do codigo computacional RELAP
Publishing Information
- Imprint Pagination
- 77 p.
- Report number
- INIS-BR--14957
INIS
- Country of Publication
- Brazil
- Country of Input or Organization
- Brazil
- INIS RN
- 46034938
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Thesis
- Descriptors DEI
- ANGRA-2 REACTOR; BENCHMARKS; LOSS OF COOLANT; OUTAGES; POWER SUPPLIES; R CODES; REACTOR ACCIDENT SIMULATION; SIMULATORS
- Descriptors DEC
- ACCIDENTS; ANALOG SYSTEMS; COMPUTER CODES; ELECTRONIC EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FUNCTIONAL MODELS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS