International Reactor Innovative and Secure

International Reactor Innovative and Secure (IRIS) is a Generation III+ reactor design made by an international team of companies, laboratories, and universities and coordinated by Westinghouse. IRIS is hoped to open up new markets for nuclear power and make a bridge from Generation III reactor to Generation IV reactor technology. The design is not yet specific to reactor power output. Notably, a 335 MW output has been proposed, but it could be tweaked to be as low as a 100 MW unit.[1]

IRIS is a smaller-scale design for a Pressurized water reactor (PWR) with an integral reactor coolant system layout, meaning the steam generators, pressurizer, control rod drive mechanisms, and reactor coolant pumps are all located within the reactor pressure vessel. This causes it to have a larger pressure vessel than an ordinary PWR despite a lower power rating, the size is more comparable to that of an ABWR.

Many of these design goals coincide with the objectives of the GNEP program launched by the Bush Administration. With large international acceptance, IRIS could be a very large part of GNEP, providing a plant type for user nations.

Contributors

The project has included the work of a number of organizations around the world, this is a list of the major contributors:

Contributor Country Contributions
Industry
Westinghouse USA Overall coordination; leading core design, safety analyses and licensing, commercialization
BNFL UK Fuel cycle
Ansaldo Energia Italy Steam generators design
Ansaldo Camozzi Italy Steam generators fabrication
ENSA Spain Pressure vessel and internals
NUCLEP Brazil Containment
OKBM Russia Testing, desalination and district heating co-gen
LABORATORIES
ORNL USA I&C, PRA, desalination, shielding, pressurizer
CNEN Brazil Transient and safety analyses, pressurizer, desalination
ININ Mexico PRA, neutronics support
LEI Lithuania Safety analyses, PRA, district heating co-gen
ENEA Italy Testing, financial and manpower support
UNIVERSITIES
Politecnico di Milano Italy Safety analyses, shielding, thermal hydraulics, steam generators design, advanced control system
University of California, Berkeley USA Advanced cores, maintenance, security
Tokyo Institute of Technology Japan Advanced cores, PRA
University of Zagreb Croatia Neutronics, safety analyses
University of Pisa Italy Containment analyses, severe accident analyses, neutronics
Polytechnic University of Turin Italy Source term
University of Rome Italy Radwaste system
Georgia Institute of Technology USA Shielding, Fuel Design, and Reactivity Control
POWER PRODUCERS
Eletronuclear Brazil Developing country utility perspective

Reactor Coolant System

The IRIS pressure vessel and systems contained within it

The coolant system consists of a pressurizer, Steam generators, and reactor coolant pumps (RCPs). These are all located within the reactor pressure vessel, making a very small, short loop that forms the primary coolant system, see the figure on the right for the relative locations of the components.

Pressurizer

Unlike ordinary PWRs, the pressurizer is not contained in a separate vessel and connected to the primary side, but rather is the top of the pressure vessel itself. Water line will be at some preset value, and then sprays and boilers within the pressurizer can be used to control pressure and water level. The unique aspect of this is that the pressurizer is of much greater volume than current plants, which helps to keep the pressure constant in accident situations.

Steam Generator

Water from the secondary (the water that is turned into steam and used in the turbine) enters at the bottom of the steam generators, and goes up through a helical coil to the top. The steam generators are once through, and the pressure is greater on the secondary side tubes (no boiling takes place in the tubes). The secondary side water is allowed to flash at the end of the steam generator tube and go out through the steam pipe. There are eight steam generators, as well as eight steam pipes and feedwater pipes.

Reactor Coolant Pumps (RCP)

The decision to put the RCPs on the inside of the vessel was a fairly radical innovation. With the existence of eight separate RCPs as opposed to the 2 or 4 of a typical PWR, when one pump goes out, that pump can be shut down and isolated, not be worked on until the next outage.

Core

It has in the past been proposed to use higher enrichments for IRIS, allowing a longer cycle life, but the design now calls for 4.95% enriched Uranium, which is the same as what is being used in current plants. The fuel is designed for a 3 to 3.5 year life, and half of the core will reloaded in outages. This longer life is accomplished by having a very large core running a relatively low power plant.

Reactivity is controlled almost entirely by control rods and burnable poisons. This eliminates the need for Boron in the primary water, which is a plus for plant chemistry.

Containment

The containment of IRIS is spherical and set to be approximately 22–27 meters across. This is compared to 58 meters high and 40 meters in diameter for a typical 600 MW PWR. Additionally, two thirds of the containment will be underground, giving it a lower profile, in addition to its already very small footprint. While the containment will be smaller than typical plants, it will also be rated for a higher maximum pressure, increasing costs.

Advantages

Most of the advantages of the new IRIS design are safety related, although Westinghouse claims that IRIS will be able to deliver power at competitive rates as well.

Due to Economies of scale, modern nuclear plants tend to be built with larger electrical outputs, such as the European Pressurized Reactor, which has scaled up power to 1600 MW in new plants. IRIS, on the other hand, is built to be used in countries where there are not extremely large electric power grids, mainly developing nations. Due to limitations on power of individual power stations versus total grid size, plants whose power is over a certain percentage of grid size are infeasible in such situations.

Due to simplifications and greater safety, it is believed by Westinghouse that in spite of its size, analysis estimated a target total cost of electricity at about 4 ¢/kWh. Given its small power and physical size, it is expected that multi-unit sites could be operated efficiently, Westinghouse estimates that a 3-unit site could be built in 9 years with a maximum cash outflow of 300 M$. One cost saver, for instance, is the need for only one control room, from which all units at a multi-unit site can be controlled.

Aside from economics, these are a few other advantages that the IRIS has:

Disadvantages and Criticisms

Compared to Generation III reactors, there are a lot more innovations that may require further investment and research. All the advantages of the reactor can't be proved until a plant is actually built.

Other criticisms are common for the entirety of the GNEP plan. These criticisms relate to the possible lack of demand for such a small power plant, and skepticism of the economics.

See also

References