Sentences with phrase «cooled fast reactors»

The R&D programs for LMFTs is probably far more modest than for the MSR, and ditto for grtaphite gas cooled fast reactors.

As a result of numerous fires from leaking systems, operating sodium - cooled fast reactors to date have been shut down more than they have run.

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).

The better half of table salt, this element cools a fast reactor nicely and also ensures there is no perpetual chain reaction.

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.

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.

Each company has so far been developing its own sodium - cooled fast reactor models.

The TWR is a liquid sodium - cooled fast reactor that uses depleted or natural uranium as fuel.

IFR was a sodium - cooled fast reactor with inherently - safe fuel rods made of «spent» fuel (article by Dr. Till).

Fast reactor concepts are typically classified by their coolant — i.e., sodium - cooled fast reactor (SFR); lead - or lead - bismuth eutectic (LBE)- cooled fast reactor (LFT); and gas - cooled fast reactor (GFR).

Not exact matches

In the 1980s this research was directed toward a fast reactor (dubbed the advanced liquidmetal reactor, or ALMR), with metallic fuel cooled by a liquid metal, that was to be integrated with a high - temperature pyrometallurgical processing unit for recycling and replenishing the fuel.

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 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.

The water around the reactor core serves as three things: a neutron moderator, meaning it slows down the fast neutrons released during fission, which then sustain the chain reaction; a cooling agent; and a radiation shield.

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.

RIAR's reactors provide a full range of capabilities to test fuel and materials of all types of existing power reactors as well as advanced and innovative ones: water - cooled thermal reactors, including those with boiling and pressurized water, gas - cooled, fast and other types of reactors.

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

Engineers will agnostically build tar sand refineries, or solar power plants, or arctic drilling rigs, or windmills, or lead cooled liquid metal fast breeder reactors.

The EM2 concept is for a modular, 240 - 265 MWe helium cooled, fast neutron, high temperature reactor operating at 850 °C.

As well as the BN series of reactors, Russia is also developing the lead - cooled BREST fast reactor, the lead - bismuth cooled SVBR and a multi-purpose fast neutron research reactor, the MBIR.

DOE selected the Sodium - cooled Fast Reactor (SFR) as the GenIV reactor type to go forward.