Sentences with phrase «cooled reactor designs»

«Yet newer helium - cooled reactors designs have proved attractive — at least in China.

Not exact matches

In the event of a breakdown of pumps that supply the reactor with fresh cooling water, the torus design is supposed to provide additional cooling.

In its efforts to develop safer, cheaper, and more efficient nuclear reactors, the Idaho National Laboratory has researched half a dozen next - generation reactor designs; these two (the sodium - cooled fast reactor and the very - high - temperature reactor) are the most promising.

Their efforts focus on two new designs: the very - high - temperature reactor (VHTR) and the sodium - cooled fast reactor (SFR).

There are some 50 modular designs being developed globally, and while many are traditional light water reactors, which use water to cool the reactor core, others gain efficiency by using coolants such as gas, which allow reactors to reach higher temperatures.

Christos G. Takoudis's interdisciplinary team plans to wield a unique atomic layer deposition / chemical vapor deposition (ALD / CVD) hybrid reactor that can lay down novel thin - film cell materials and structures that run cooler by design.

In addition to its unique fuel cycle, the TerraPower design employs a high - temperature, liquid metal core cooling technology suited to a breeder reactor with «fast» neutron activity, rather than today's predominant reactors whose water cooling systems slow neutrons.

Novel designs with alternative cooling fluids other than water, such as Transatomic Power's molten salt — cooled reactor or the liquid lead — bismuth design from Hyperion Power, are in development.

As the recent meltdown in Fukushima showed, the design of these reactors» systems, such as the donut - shaped «suppression pool» of water meant to cool the reactor in a crisis, showed flaws — flaws identified by regulators decades ago.

Until now, U.S. safety regulations have been based on ensuring plants are designed to withstand certain specified failures or abnormal events, or «design - basis - events» — such as equipment failures, loss of power, and inability to cool the reactor core — that could impair critical safety functions.

Novel design The trouble with fast reactors has largely been related to what's used to cool them — liquid sodium in the case of GE's PRISM and many others.

PRISM is a sodium - cooled, high - energy neutron (fast) reactor design that uses a series of proven, safe and mature technologies developed in the U.S. and abroad.

Prism is a sodium - cooled fast neutron reactor design built on more than 30 years of development work, benefitting from the operating experience of the EBR - II prototype integral fast reactor which operated at the USA's Idaho National Laboratory — formerly Argonne National Laboratory — from 1963 to 1994.

After removal from the reactor core, spent fuel assemblies are placed in dedicated spent fuel storage racks in the below ground spent fuel pool, which contains four times more water volume for cooling per fuel assembly than current designs.

The NuScale Power Module ™ and power plant design enhances the intrinsic physical protection and security of the plant through the elegantly simple design, elimination of large break loss of coolant accidents, and full reliance on passive systems to cool the reactors and spent fuel for extended periods without the need for AC power, DC power or additional water following an upset condition.

The NuScale design also has unique safety characteristics: under abnormal conditions, the reactor can shut itself down and cool itself for indefinite periods without the need for human intervention, water addition or external electricity supplies.

The PRISM reactor vessel auxiliary cooling system can maintain reactor temperatures well below design limits using natural circulation to remove heat from the reactor module.

SMR - 160 is a conventional fission reactor, using water as the cooling medium, and is designed with six decades of world - wide industrial operating experience with pressurized water reactors.

GE Hitachi Nuclear Energy have developed the sodium - cooled fast reactor PRISM to advanced conceptual design, and the design is ready to start undergoing the regulatory process.

Both GEH and ARC have developed reactor designs based on the Experimental Breeder Reactor - II (EBR - II) integral sodium - cooled fast reactor prototype at the Argonne National Laboratory.

Both aSMR designs share fundamental features, such as high energy neutrons, liquid sodium cooling and metallic fuel, which provide inherent safety performance and more economically competitive plant architecture compared to traditional water - cooled reactors.

GEH and ARC Nuclear have each developed advanced reactor designs based on the EBR - II, an integral sodium - cooled fast reactor prototype which was developed by Argonne National Laboratory and operated successfully for more than 30 years at Idaho Falls, Idaho.

But the cooling system for both the reactor cores and the onsite - stored spent fuel rods was not designed to withstand a «once - in - a-millennium» tsunami.

To my mind, the Fukushima failure also builds the case for the kind of push under way in China, which is moving forward with construction of the first two of a new generation of nuclear reactors — cooled by helium, not water, and designed in a way that can not produce a meltdown of the fuel.

The Xiapu reactor will be a demonstration of that sodium - cooled pool - type fast reactor design.

This makes very good sense to me, the cost would drop dramatically if we changed our regulation environment for nuclear, the new passive cooling reactors are much much safer than older reactor designs, and regional storage (which we have de facto anyway) solves the waste problem.

[4]» [4] The NuScale design claims to enable the reactor to safely shut down and self - cool indefinitely, with no operator action, no AC or DC power, and no additional water.

New reactor designs, especially in France, have improved safety further, with multiple backup cooling systems.

One design, by MIT professor Charles Forsberg, called the AHTR, combines a flouride - salt - cooled reactor with a gas turbine; one variation on it incorporates injecting gas to the turbine for high temperature turbine generation, so that the power plant can operate for both baseload and peak power.