EN3435: Introdução a Engenharia Nuclear

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Júlia Palmeira Silveira
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1 EN3435: Introdução a Engenharia Nuclear AULA 07- Geração de Potência Nuclear: Reatores geração III e IV PROF. DR. JOSÉ RUBENS MAIORINO Engenharia de Energia-CECS

2 Reatores de Geração III As características principais dos reatores de terceira geração são: 1. Padronização no projeto para cada tipo de reator, com a finalidade de agilizar o licenciamento, de diminuir os custos capitais e de reduzir os tempos de construção(economicidade); 2. Desenho e projeto simplificado para que sejam mais simples de serem operados e menos vulneráveis à falhas operacionais; 3. Maior disponibilidade (availability) e aumento da vida útil para até 60 anos; 4. Minimização da possibilidade de fusão do núcleo; 5. Sistemas de segurança avançados; 6. Maiores taxas de queima para minimizar a quantidade de rejeitos; 7. Utilização de venenos queimáveis para aumentar a vida do combustível

3 Principais Projetos de Reatores G-III e G-III+

4 Características Principais dos Reatores G-III

5 Reatores PWR Evolucionários(G-III)-AP-600/1000 (WESTINGHOUSE) AP-600/1000- Westinghouse (US) has a new series of Advanced Passive PWRs, available in two models the AP600 with 600 MWe net electric output (619 MWe gross), and the AP1000 at 1117 MWe net electric output (1200 MWe gross). The AP600 is a Gen III design approved by the NRC in 1998, but no units were built. The AP1000 is a Gen III+ design, based on the AP600, with higher power. For both, the reactor vessel is the same as that for a standard Westinghouse three-loop plant, with nozzles adjusted to accommodate the two loops of the new designs. The internals are also standard, with minor modifications. The safety systems for both AP600 and AP1000 include passive safety injection, passive residual heat removal, and passive containment cooling. The passive safety systems are significantly simpler than conventional PWR safety systems. They have typically three times fewer remote valves than active systems, and they contain no pumps. This type of design is less expensive to build than a conventional PWR due to a significant reduction in the number of pipes, wires, valves, and associated components

6 AP 1000

7 Reatores PWR Evolucionários(G-III)-EPR AREVA

8 Reatores PWR Evolucionários(G-III+)- IRIS Westinghouse

Reator VVER Avançado Russo(G-III)- AES-92 ROSATOM The AES-92 is an advanced PWR of Russian design with 1000 MWe net electric output (1068 MWe gross electric output), also designated NPP-92 or V-392.

10 Reator VVER Avançado Russo(G-III)- AES-92 ROSATOM The AES-92 is an advanced PWR of Russian design with 1000 MWe net electric output (1068 MWe gross electric output), also designated NPP-92 or V-392. The AES-92 is based on the well-known VVER-1000 (from Vodo-Vodyanoi Energetichesky Reactor, (Водо-водяной энергетический реактор)literally translated as Water-Water Energetic Reactor ), of which there are 10 operating units in Russia (Balakovo-1 to 4, Kalinin-1 to 3, Novovoronezh-5, Rostov 1 and 2), 13 in the Ukraine (Khmelnitski-1 and 2, Rovno-3 and 4, South Ukraine-1 to 3, Zaporozhe-1 to 6), two in the Czech Republic (Temelin-1 and 2), two in Bulgaria (Kozloduy-5 and 6) and two in China (Tianwan-1 and 2).

13 Reator Evolucionário Coreano(G-III)-APR-1400 KEPCO/ The APR-1400 (for Advanced Power Reactor 1400 [MWe]) is an advanced pressurized water nuclear reactor designed by the Korea Electric Power Corporation (KEPCO). Originally known as the Korean Next Generation Reactor (KNGR), this Generation III reactor was developed from the earlier OPR-1000 design and also incorporates features from the US Combustion Engineering (C-E) System 80+ design. Currently there is one unit in operation (Shin Kori unit 3) and seven units under construction, four in the United Arab Emirates at Barakah and three in South Korea: one at Shin Kori and two at Shin Hanul. Two more units are planned with construction yet to commence at Shin Kori. (Fonte:

16 Reatores BWR Evolucionários(G-III)-ABWR GE-HITACHI

21 Reator CANDU Avançado(G-III+)-ACR-1000 ATOMIC ENERGY CANADA The Advanced CANDU Reactor (ACR) is a Generation III+ nuclear reactor design and is a further development of existing CANDU reactors designed by Atomic Energy of Canada Limited. The ACR is a light-water-cooled reactor that incorporates features of both pressurized heavy water reactors (PHWR) and advanced pressurized water reactors(apwr) technologies. It uses a similar design concept to the steam-generating heavy water reactor(sghwr). The design uses low enriched uranium (LEU) fuel, ordinary (light) water coolant, and a separate heavy water moderator. The reactivity regulating and safety devices are located within the low pressure moderator. The ACR also incorporates characteristics of the CANDU design, including on-power refueling with the CANFLEX fuel; a long prompt neutron lifetime; small reactivity holdup; two fast, totally independent, dedicated safety shutdown systems; and an emergency core cooling system (although all generation 2, 3, and 3+ designs have this feature). The compact reactor core reduces core size by half for the same power output over the older design. The fuel bundle is a variant of the 43-element CANFLEX design (CANFLEX-ACR). The use of LEU fuel with a neutron absorbing center element allows the reduction of coolant void reactivity coefficient to a nominally small, negative value. It also results in higher burnup operation than traditional CANDU designs. The current size for the ACR-1000 is approximately 1200MWe.

Pebble Bed Modular Reactor(PBMR) South Africa The Pebble Bed Modular Reactor (PBMR) is a particular design of pebble bed reactor under development by South African company PBMR (Pty) Ltd since 1994.

24 Pebble Bed Modular Reactor(PBMR) South Africa The Pebble Bed Modular Reactor (PBMR) is a particular design of pebble bed reactor under development by South African company PBMR (Pty) Ltd since The project entails the construction of a demonstration power plant at Koeberg near Cape Town (now postponed indefinitely) and a fuel plant at Pelindaba near Pretoria

GT-MHR(Gas Turbine ModularHelium Reactor ) General Atomics The Gas Turbine Modular Helium Reactor (GT-MHR) is a power reactor design under development by a group of Russian enterprises (OKBM

27 GT-MHR(Gas Turbine ModularHelium Reactor ) General Atomics The Gas Turbine Modular Helium Reactor (GT-MHR) is a power reactor design under development by a group of Russian enterprises (OKBM Afrikantov,Kurchatov Institute, VNIINM and others), an American group headed by General Atomics, French Framatome and Japanese Fuji Electric. It is a helium cooled, graphite moderated reactor and uses TRISO fuel compacts in a prismatic core design. The reactor can also be used for hydrogen or other high temperature applications, it can generate 285 MWe of electricity per modulus.

31 Generation IV reactors (Gen IV) are a set of nuclear reactor designs currently being researched for commercial applications, with depending on the particular design, Technology readiness levels varying between the level requiring a demonstration, to economical competitive implementation. Most of these designs, are generally not expected to be available for commercial construction before REATORES DE GERAÇÃO IV

32 Nasceram duas iniciativas a nível internacional: GIF: Forum Internacional para os reatores de Geração IV, liderado pelos EUA e criado em 2001 pelo DOE. INPRO: International Project on Innovative Nuclear Reactor and Fuel Cycle, lançado em 2000 pela IAEA Iniciativas internacionais Baseadas nos conceitos de: Energia sustentável Energia competitiva Segurança Não proliferação Proteção física

33 Conceitos de Reatores de Geração IV GIF

36 Accelerator Driven Systems (ADS)

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