The term generations in the context of power stations represents a significant technical advancement with regards to performance, cost, economics, sustainability or safety in comparison to the previous generation.
Generation I power stations housed the prototype and power reactors which launched civil nuclear power. Derived from experimental and military reactors and developed in the 1950-60’s, the first generation consisted of both commercial and non-commercial power producing reactors.
The UK, France, Belgium, Canada, USSR and USA all developed Generation I reactors.
Some examples and designs, not limited, within these countries are:
Origin UK UK France France France Belgium
Reactor Calder Hall-1 Dounreay(DFR) Marcoule G1-G3 Brennilis Chooz-A BR3
Type Magnox GCR FBR UNGG GCR HW GCR PWR PWR
Active 1956-2003 1959-1977 1956-1984 1967-1985 1967-1991 1962-1987
Origin Canada USSR USSR USA USA USA
Reactor NPD Obninsk AM-1 BR-5/10 Shippingport Dresden-1 Fermi-1
Type CANDU PHWR RBMK SFR PWR BWR SFR
Active 1962-1987 1954-2002 1959-2002 1957-1982 1960-1978 1963-1972
Generation I safety systems were active because they relied on active electrical and mechanical control of the equipment.
Generation II power stations are what make up the majority of the 400+ global commercial reactors currently active today. They are heirs to the development of the first generation reactors with active safety systems.
Uranium enrichment became readily available for civilian purposes, allowing the use of ordinary water as the moderator to slow down the neutrons. This meant that the bulk of the reactors within this generation are Light Water Reactors (LWR), developed and well established largely from the USA, with the main types being the Pressurised Water Reactors (PWR) and Boiling Water Reactors (BWR).
The UK continued with the Generation I Magnox design, with the last of this type to decommission at Wylfa Nuclear Power Station in December 2015. The UK also commercialised the Advanced Gas-cooled Reactor (AGR), developed from Magnox and AGR prototypes in the 1960’s; Plagued with problems they then switched to LWR.
France developed a chain of Fast Breed Reactors (FBR) from the prototype Rapsodie, and substituted their Gas Cooled Reactor (GCR) designs for the more favourable PWR. After obtaining a licence from the USA for the imported Chooz-A reactor, the French and Belgians built and exploited the PWR design. This resulted in both France and Belgium developing their own individual designs.
Canada continued with their CANDU design which is a Pressurized Heavy Water Reactor (PHWR), one of the only Generation II technologies marketed that wasn’t light water.
The USSR, later Russia, favoured the RBMK, a design that ultimately caused the Chernobyl disaster but has been retro-upgraded since. They also developed a new Water-Water Energy Reactor (VVER) which is similar to a PWR.
USA incorporated the PWR or BWR designs, which are currently the only types in commercial operation within the states.
South Korea developed their own Generation II design, the OPR-1000 (KSPN) PWR; based on USA and French designs.
There are currently over 30 countries operating commercial Generation II power stations, incorporating different reactor designs of PWR, BWR, CANDU, RBMK, VVER and AGR.
Generation II+ reactors are Generation ii reactor designs, post 2000, that have received significant upgrades such as instrumentation, size, simpler designs, longer life and an active/passive safety system combination.
Passive safety systems are based on energy transfer which results in less dependability on active systems and operator input.
An example of a generation II+ would be the French modified Ao II-1, CPR-1000 PWR reactor at the Chinese Ling Ao Nuclear Power Plant.
Generation III power stations are an advancement on the Generation II LWR technology with improved performance, design lifetimes, modularized and standardization, fuel technology and passive safety systems.
Throughout the 80’s and 90’s the nuclear power market suffered a crash and so few new plants were constructed in Europe and North America. Development continued, and this meant that Asia mostly invested within this generation.
The USA AP-600 (Advanced Passive) PWR was one of the first Generation III designs but took no orders.
USA designed and with Japan produced the Advanced Boiling Water Reactor (ABWR), evolved from the BWR it was the first operational Generation III.
Another ABWR was the System 80+, which was never promoted for sale but its design features used in the APR-1400.
The Koreans developed the APR-1400, an advanced PWR based on the OPR-1000.
China improved the CPR-1000, resulting in the ACPR-1000, which they then merged with the similar ACP1000 design to give the Hualong-1(HPR-1000) that’s soon to be operational.
Russia incrementally improved safety with a full containment structure on the VVER-1000, as well as a FBR.
Canada continued development of the PHWR with the Enhanced CANDU-6 (EC6)
Some examples and designs, not limited, within this generation are:
Origin Japan Korea China China Russia Russia
Reactor KK-6 Shin Kori 3 Yangjiang 5 Fuqing 5 Bushehr-1 Beloyarsk-4
Type ABWR APR-1400 ACPR-1000 HPR-1000 VVER-1000/446 BN-800 FBR
Active 1996-Present 2016-Present 2015-Present 2019-Present 2013-Present 2014-Present
Generation III+ power stations are an evolutionary development of the Generation III reactors offering significant improvements in safety and passive systems. A lot of this Generation has just passed certification or is still in development.
Some designs, not limited within this generation are:
Origin Russia Canada USA USA Europe Korea
Reactor VVER-1200 ACR-1000 AP-1000 ESBWR EPR APR+
Type PWR PHWR PWR BWR PWR PWR
Based on VVER-1000 CANDU PWR ABWR N4/Konvoi APR-1400
Generation IV power stations are concept innovative designs that are being coordinated at a global level by the Generation-IV International Forum (GIF); a 14-member consortium that carries out the research and development needed to establish the performance and feasibility capabilities of next generation nuclear energy systems.
Research includes work on a range of areas including the fuel cycle, specifically closed, as well as the reactor components and passive safety.
A passive system in the context of a Generation IV power plant design is used as a key measurement to help avoid accidents, reduce reliance on operator action and mitigate the consequences of potential accidents to achieve the highest level of safety.
Development towards FBR aims to minimise end radioactive waste through burning if the actinides within the core. These actinides are usually separated in previous generations from spent fuel, one of which being pure bomb grade Plutonium, which is at no point separated from the other components of the spent fuel with this process, and therefore an unattractive material source for atomic bomb programs.
With burning and removal of the minor actinides, the radioactivity of the ultimate waste will therefore decay more rapidly and give a reduced radiotoxicity, as well as a reduction on heat generation.
Guiding principles to outline goals are that systems should be challenging and stimulate innovation; they should be responsive to energy needs worldwide; and concepts must define complete nuclear energy systems and not just reactor technologies.
The 6 system concepts chosen for development from GIF from a wide range of designs as exhibiting the greatest potential for advancement are:
(VHTR) - Very high-temperature gas-cooled reactor
(SFR) - Sodium-cooled fast reactor
(GFR) - Gas-cooled fast reactor
(LFR) - Lead-cooled fast reactor
(MSR) - Molten salt reactor
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