Nuclear Fuel Cycle Flashcards

1
Q

What is the key decision point in the back end of the nuclear fuel cycle?

A

Following the end of the fuel’s lifetime in the reactor, it can either be reprocessed or stored indefinitely

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2
Q

What are the key steps in the front end of the nuclear fuel cycle?

A

Mining -> Milling & Extraction -> Enrichment -> Fuel fabrication -> Reactor

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3
Q

What are the key stages of milling?

A

Uranium ore is crushed and leached with sulfuric acid
Ammonium diuranate is precipitated from the solvent by using gaseous ammonia
Diuranate is dewatered and roasted to produce U3O8

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4
Q

What is the enrichment factor?

A

The change in molar fraction before and after separation (from feed to product). Analogous to the depletion factor from feed to tails

alpha = Np(1-Nf) / Nf(1-Np)

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5
Q

What is separative work?

A

Thermodynamic work necessary in order to separate isotopes and enrich fissile material. Measured in mass per unit time.

SW = P V(Np) + T V(Nt) - F V(Nf)

Nx = Concentration
V(N) = Value function
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6
Q

What is the value function?

A

V(N) = (2N-1) ln(N/1-N)

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7
Q

What dilemma arises regarding separative work and the tails assay?

A

There is a balance between mass of natural uranium mined and the separative work done (in order to enrich to a particular value). Greater SW is necessary to reduce the tails assay (concentration of fissile material in tails), however, less natural uranium would be needed in order to achieve a particular enrichment

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8
Q

What two enrichment processes are most commonly used?

A

Gaseous diffusion and gas centrifugation

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9
Q

What uranium compound is used for enrichment and what properties of it are desirable for enrichment?

A

Uranium hexafluoride UF6 is used.

UF6 vaporises at moderate temperatures
Fluorine has only one natural isotope (F-19) hence mass difference between molecules is due only to the isotopic mass difference between U235 and U238

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10
Q

Describe the process of gaseous diffusion enrichment

A

Effusion rate is inversely proportional to the square root of the gas molecule’s mass. This gives a theoretical separation factor for a single stage of 1.0043. Multiple separation stages are required in order to achieve 3-5% enrichment

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11
Q

Describe the process of gas centrifugation

A

Centrifugal force creates radial concentration gradient due to molecular mass. As U235 is lighter than U238, U235 is in higher concentration closer to the centre of the centrifuge. A temperature gradient is also applied along the z axis, which causes lighter molecules to rise. The product is collected at the centre of the top of the centrifuge, while the tails are removed at the outer radius at the bottom of the centrifuge.

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12
Q

What properties of gas centrifuges are advantageous over gaseous diffusion plants?

A

Centrifuges utilise a ‘no maintenance’ design
Power consumption is 5% that of equivalent diffusion plant
More compact layout
Lower capital and operating costs
Flexible performance

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13
Q

What occurs to spent fuel rods immediately after they are removed from the reactor?

A

Spent fuel rods are placed in a water tank to cool, as a result of continuous heat emission due to decay heat.

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14
Q

What are the current advantages and disadvantages of geological disposal?

A

Stable, long-term solution to spent fuel management
No need to separate Pu (provides proliferation resistance)
Cheaper in long term than reprocessing, although capital costs are unknown
Difficulty with political and public acceptance (e.g. Yukka Mountain and West Cumbria Country Council)

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15
Q

What is interim storage?

A

On-site fuel rod storage in naturally cooled concrete casks. Typical lifetime ~50 years. Attractive short-term storage but is not sustainable

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16
Q

What are the relative volumetric and radiotoxic distributions of uranium/plutonium and fission products in spent fuel?

A

U/Pu makes up 95% of spent fuel by volume, but fission products make up 98% of radiotoxicity

17
Q

Give an overview of nuclear reprocessing to separate U/Pu from fission products

A

Separated through PUREX solvent extraction. U/Pu have greater solubilities in organic solvents such as TBP and OK than in aqueous solvents. U and Pu can be readily separated from TBP.

18
Q

What organic solvents are used in PUREX solvent extraction?

A

Tri-n-Butyl Phosphate (TBP) and odourless kerosene (OK)