EN204-ENERGIA NUCLEAR
AULA 05- Reatores Nucleares Geração III e IV
PROF. DR. JOSÉ RUBENS MAIORINO
Engenharia de Energia-CECS
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;
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
Reatores PWR Evolucionários(G-III)-EPR
AREVA
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 . 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).
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:
Reatores BWR Evolucionários(G-III)-ABWR
GE-HITACHI
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. 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.
https://en.wikipedia.org/wiki/Pebble_bed_modular_reactor
http://www.scielo.org.za/scielo.php?pid=S0038-23532010000300002&script=sci_arttext http://www.world-nuclear.org/info/country-profiles/countries-o-s/south-africa/
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.
https://en.wikipedia.org/wiki/Gas_turbine_modular_helium_reactor http://pbadupws.nrc.gov/docs/ML0224/ML022470282.pdf
