Last edited by Grolkree
Sunday, May 17, 2020 | History

2 edition of Slowpoke-2 Reactor with Low Enrichment Uranium Oxide Fuel. found in the catalog.

Slowpoke-2 Reactor with Low Enrichment Uranium Oxide Fuel.

Atomic Energy of Canada Limited.

Slowpoke-2 Reactor with Low Enrichment Uranium Oxide Fuel.

by Atomic Energy of Canada Limited.

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  • 13 Currently reading

Published by s.n in S.l .
Written in English


Edition Notes

1

SeriesAtomic Energy of Canada Limited. AECL -- 8840
ContributionsTownes, B., Hilborn, J.
ID Numbers
Open LibraryOL21968996M

  2/ThF4/UF4 fuel in molten salt breeder reactor (MSBR). Th and U are the best ‘fertile’ and ‘fissile’ materials respectively for thermal neutron reactors and ‘thermal breeding’ has been demonstrated for (Th, U)O2 fuel in the Shippingport light water breeder reactor (LWBR)   SLOWPOKE The 5 kW (thermal) SLOWPOKE-1 (Safe LOW POwer Critical(K) Experiment) research reactor was developed by AECL at Chalk River, and first went critical in May (See SLOWPOKE history). The reactor was dismantled and rebuilt at the Environmental Science and Engineering Institute of the University of Toronto. It was later uprated to a

  The Front End of the Nuclear Fuel Cycle: Current Issues Nuclear power contributes roughly 20% of the electrical generation in the United States. Uranium is the fundamental element in fuel used for nuclear power production. The nuclear fuel cycle is the cradle-to-grave life cycle from extracting uranium ore from the earth through power The nuclear fuel cycle: industrial processes which involve the production of electricity from uranium in nuclear power reactors. Electricity is created by using the heat generated in a nuclear reactor to produce steam and drive a turbine connected to a generator. Fuel removed from a reactor, after it has reached the end of its useful life, can be reprocessed to produce new ://

How Does it Work? The McMaster Nuclear Reactor is a medium flux nuclear fission reactor with a light water moderator and an open pool design. To better understand what this means, it is necessary to first explore some of the basic concepts associated with nuclear fission and fission based reactors prior to undertaking a more in-depth examination of the components that make up a nuclear :// Since most reactor types require U fuel with a low enrichment, uranium oxide is converted into gaseous uranium hexafluoride (UF 6) and raised to the desired enrichment level in isotope enrichment plants. This produces depleted uranium with a U content of approx. %, which is first stored and can later be used as a fuel, e.g., in fast


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Slowpoke-2 Reactor with Low Enrichment Uranium Oxide Fuel by Atomic Energy of Canada Limited. Download PDF EPUB FB2

The critical mass of uranium in the SLOWPOKE-2 design is approximately kg of low-enriched uranium (LEU) or kg of high-enriched uranium (HEU). Originally designed to operate with HEU (93% at enrichment), AECL redesigned the SLOWPOKE-2 to use % at U LEU, as described in the previous :// SLOWPOKE-2 (LEU core) is a pool-type nuclear reactor with a maximum nominal thermal power of 20 kW.

It uses a pelletized uranium oxide fuel (% enrichment) and provides a useful high neutron PIERRE, J.R.M., Low Enrichment Uranium (LEU)-Fuelled SLOWPOKE-2 Nuclear Reactor Simulation with the Monte Carlo based MCNP-4A Code, Master of Engineering Thesis, Royal Military College of SLOWPOKE (Safe LOW-POwer Kritical Experiment) was designed by Atomic Energy of Canada Limited, where prototype (SLOWPOKE-1) and commercialized (SLOWPOKE-2) versions exists.

The core thermal power of SLOWPOKE-2 is 20 kW, and rod-type fuel made of UO 2 meat and Zircaloy-4 cladding is currently used (Townes and Hilborn, ). The low enriched uranium UO2 fuel performance in MTR MW reactor is investigated in this paper with One Neutronic Trap (ONT) and Three Neutronic Traps (TNTs) to increase the scientific The enrichment process requires the uranium to be in a gaseous form.

This is achieved through a process called conversion, where uranium oxide is converted to a different compound (uranium hexafluoride) which is a gas at relatively low temperatures. The uranium hexafluoride is fed into centrifuges, with thousands of rapidly-spinning vertical Newly fabricated uranium oxide fuel contains up to 3%–5% U and the rest is U.

Nuclear reactions in the reactor burn up part of the uranium and produce radionuclides. Eighty per cent of U consumed is burned by fission reactions and 20% by neutron capture to U. U is then burned by neutron capture to Np, 25% of which is Nuclear forensic analysis was conducted on two uranium samples confiscated during a police investigation in Victoria, Australia.

The first sample, designated NSR-F, was a depleted uranium Uranium dioxide is the primary raw material for nuclear fuel, though between mining the ore and the production of fuel rods it is temporarily converted into the more volatile uranium hexafluoride for enrichment.

After the enriched uranium is returned to the uranium dioxide form it is made into ceramic pellets which are then sealed into the The Low Enriched Uranium UO 2 fuel performance in low-power research reactors is assessed in this paper.

The usability of this fuel has been demonstrated in some research reactors in the world (SLOWPOKE-2). The fuel proved to be usable in the miniature neutron source low-power research reactors when about 50 fuel rods were substituted by as many dummy rods, while in SLOWPOKE   @article{osti_, title = {Analysis and modeling of fission product release from various uranium-aluminum plate-type reactor fuels}, author = {Taleyarkhan, R.P.}, abstractNote = {This articles provides a perspective overview and analysis of volatile of fission-product release data obtained for uranium-aluminum (U-Al) reactor fuels, U-Al[sub x] (alloy and dispersed), U[sub 3]O[sub 8]-Al The AGR-2 irradiation experiment included TRISO fuel particles with kernels containing both uranium oxide and uranium carbide, called UCO, where uranium carbide is included with the commonly-used uranium oxide in the kernel to provide a getter for oxygen liberated during fission and limit CO ://   75% uranium oxide, i.e.

kg per tonne. Uranium is a metal that oxidises very quickly when it comes into contact with oxygen in the air and changes into uranium oxide. From the uranium mine to waste disposal 7> The nuclear fuel cycle From the uranium mine to waste disposal 7> The nuclear fuel @article{osti_, title = {Summary report on the HFED (High-Uranium-Loaded Fuel Element Development) miniplate irradiations for the RERTR (Reduced Enrichment Research and Test Reactor) Program}, author = {Senn, R.L.}, abstractNote = {An experiment to evaluate the irradiation characteristics of various candidate low-enriched, high-uranium content fuels for research and test reactors was However, this effect is much smaller than in uranium fuel.

Thus, thorium reactor cores are more manageable than uranium cores because, over the lifetime of the core, the variations in reactivity and power distribution (power peaking) are less. Further, at low average fluxes and low burn-up, the in situ breeding is also better than for uranium :// Uranium enrichment estimates were obtained for all cases including the bulk uranium samples shielded by lead.

Further refinement of this technique is needed to make it a more powerful tool for non Page - SR Bernard and EG Struxness, A Study of the Distribution and Excretion of Uranium in Man, An Interim Report, ORNL ().

Appears in 15 books from Page 85 - Development of the Continuous Method for the Reduction of Uranium Hexafluoride with Hydrogen —   Heavy water (deuterium oxide) is highly efficient because of its low neutron absorption and affords the highest neutron economy of all commercial reactor systems.

As a result chain reaction in the reactor is possible with natural uranium The Scalable LIquid Metal cooled small Modular (SLIMM) reactor with uranium nitride fuel enrichment of % had been developed for generating 10– MW th continuously, without refueling for ∼66 and full power years, respectively.

Natural circulation of in-vessel liquid sodium (Na) cools the core of this fast energy spectrum reactor during nominal operation and after shutdown The choice of 20 percent as a target enrichment for research reactors is not obvious, because plutonium production within the fuel itself increases as the fuel enrichment decreases, and there is no sharp boundary in Figure to determine a threshold for uranium enrichment.

For example, a MW natural-uranium-fueled reactor makes about 8 kg. Enrichment is also an important step in the civil nuclear fuel cycle, in producing low enriched uranium (LEU) for use as fuel for nuclear reactors to generate electricity. However, the same equipment used to produce LEU for nuclear reactor fuel can also be used to produce HEU for ://The decay characteristics of spent fuel, high-level waste, and fuel-assembly structural material (cladding) waste are presented in the form of ORIGEN2 output tables for (1) a pressurized water reactor operating on a once-through cycle with low-enrichment uranium feed, (2) a boiling-water reactor operating on a once-through cycle with low-enrichment uranium feed, and (3) a liquid-metal fast    Fuel Development The key factor in enabling the conversion of a research reactor lies in the availability of a fuel with much greater uranium content, to compensate for the reduction in the content of U in the LEU material.

HEU fuels in plate-type fuel are usually dispersion fuels with densities ranging from to g/cm3. Hydride