Nuclear Semester 2

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Last updated 4:44 PM on 3/20/26
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65 Terms

1
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Define open fuel cycle

Fuel is used once in reactor, wet interim stored and ultimately dry stored for disposal.

2
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Define partially closed fuel cycle

Fuel is reprocessed to separate U, Pu, U-Pu made into MOx. Main U not recycled.

3
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Define fully closed fuel cycle

Reprocessed U-Pu made into MOx fuel and  U fuel fully recycled.

4
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Chemical formula for yellow cake

U3O8

5
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Explain the process of Uranium mining

  • Ore is crushed and ground

  • Acid leaching is predominantly used (H2SO4)

  • Uranium oxidised to get it into hexavalent form

  • Leaching solution is fltered and concentrated using solvent extraction

  • Precipitated as yellow cake 70-80% using ammonia/magnesia/caustic soda

6
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Explain how to get from yellow cake to fuel ready Uranium

  • Yellow cake (U3O8) to UO3 conversion and purification

  • Conversion of UO3 to UF4

  • UF4 to UF6 (high temp)

  • Enrichment of U235 - leads to significant depleted uranium by-product

  • Back conversion of UF6 to UO2 granule solid for fuel

7
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Give the advantages and disadvantages of a closed fuel cycle

ADV

  • Smaller final waste volumes

  • Lower long term inventories of Pu

  • Reduced requirement for new U mining

DIS

  • Cost

  • U price not increased sufficiently to warrant recycle

  • Nuclear proliferation risk

8
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Explain why open fuel cycles help nuclear proliferation

  • Pu stockpiling due to non recycling

  • If Pu is not separated, fuel cannot be used for nuclear weapons

9
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How long do we have to store spent fuel for?

  • At reactor cooling for 12 months

  • Central pond facility - cooling for reprocessing and handling

  • Long term (decades) usually dry (prior to disposal)

10
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Describe decay heat

  • Created from beta and gamma emissions from fission products

  • Amount and type of fission depend on number of factors

    • Initial enrichment

    • Irradiation time

    • Irradiation history

    • Cooling time

11
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Compare wet and dry storage of fuel

  • Wet store - active system, requiring engineering systems to maintain environment

  • Dry store - passive system requiring no intervention

    • Getting fuel completely dry is difficult

    • New storage racks holding 63 fuel cans in THORP will allow greater storage capacity for wet

    • Number of routes to longer term dry storage being assessed

12
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Generally, how do we dispose of spent fuel?

  • GDF (Geological Disposal Facility)

  • Multiple barriers

  • Secure against unauthorised removal of nuclear material

  • Has to be safe for 1000s of years

13
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Advantages and Disadvantages for solvent extraction

ADV

  • Safety

  • Mature technology

  • Low cost

  • Scale up easy

  • Selectively good

  • High purity achievable

  • Low temp

  • Re-use solvent

  • High HM loading capacity

DIS

  • Degradation of solvent

  • Entrainment

  • Not always CHON only

  • Waste management

14
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What are the general principles of solvent extraction?

  • Use affinity of solute for specific solvent to concentrate solute

  • Reverse operation to recover solute

MIX - SETTLE - SEPARATE

15
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What does PUREX stand for?

Plutonium Uranium Reduction EXtraction

16
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PUREX Flow sheet

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17
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What are the equations for the U and Pu extraction? (reversible)

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18
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Equation for equilibrium constant for Uranium extraction

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19
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Why is the equilibrium constant of U extraction favoured by high NO3-?

Le Chatelier’s principle, higher nitrate core will push equilibrium to the right, run normally at high acid concentrations 3-5 M, runs with high TBP (20-30%)

20
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Describe the partitioning of U and Pu (PUREX)

  • Based on reducing Pu(IV) to Pu(III) which is an inextractable in solvent

  • U remains in the solvent phase, the Pu goes into the aqueous phase

  • The reductant used is uranous nitrate (U(IV)), stabilised by hydrazine

<ul><li><p>Based on reducing Pu(IV) to Pu(III) which is an inextractable in solvent</p></li><li><p>U remains in the solvent phase, the Pu goes into the aqueous phase</p></li><li><p>The reductant used is uranous nitrate (U(IV)), stabilised by hydrazine</p></li></ul><p></p>
21
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Describe the back extraction of U (PUREX)

  • No need to change valence state

  • High back extraction greatly favoured by diltue NO3-

  • Run back extraction using very dilute acid, will shift the reaction towards the release of U complex, run 0.01-0.1M acid in back extraction

<ul><li><p>No need to change valence state</p></li><li><p>High back extraction greatly favoured by diltue NO3-</p></li></ul><ul><li><p>Run back extraction using very dilute acid, will shift the reaction towards the release of U complex, run 0.01-0.1M acid in back extraction</p></li></ul><p></p>
22
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What are the downsides to TBP?

  • Very susceptible to radiolitic breakdown, owning to phospohorus atom

  • Leads to breakdown products that are less efficient, and limits TBP recycle

  • TBP is not very volatile, good for safety perspective but difficult to recycle via thermal separation

23
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Describe pulsed columns

  • Approx 1m of column needed for one theoretical stage

  • Requires large amount of head space but little floor space

  • Moderate solvent inventory

  • Long residence times

24
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Describe mixer settlers

  • Physical and theoretical stages nearly equivalent in efficiency

  • Simple to design and operate

  • Large settler volume

    • long residence time

    • high process inventory

  • Poor geometry for critically (high volume hold up)

  • Tolerant of solids

25
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Describe centrifugal contractors

  • A process intensified PI technology

  • Each unit near one theoretical stage

  • Requires little headroom or floor space, requires remote maintenance capability

  • Small solvent inventory

  • Short residence times

26
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Overview of the PUREX process

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27
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Describe step 1 of the PUREX system (Fuel Dissolution)

  • Shear assembly to expose fuel

  • Dissolve fuel in nitric acid

  • Centrifuge dissolver liquor to remove solids

  • Store clarified liquor for monitoring and feed to solvent extraction

28
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Describe step 2 of the PUREX system (Solvent Extraction)

  • Primary separation

    • Separation of fission products from U/Pu

    • Separation of Pu from U

    • Decontamination of solvents

    • Treatment of fission product stream

29
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Describe primary separation (PUREX)

  • Extract U and Pu into solvent phase

  • Split U and Pu, U in solvent, Pu in aqueous

  • Clean Pu steam of any carried over solvent

30
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Describe Uranium purification (PUREX)

  • Decontamination of U stream from Np

  • Decontamination of solvents

  • Uranium purification

    • Initial U and Np back extraction to aqueous

    • Adjust temperature/conc to ensure U and Np in correct oxidation states

    • Solvent extraction to remove Np from U

    • Back strip with dilute acid to recover U

<ul><li><p>Decontamination of U stream from Np</p></li><li><p>Decontamination of solvents</p></li><li><p>Uranium purification</p><ul><li><p>Initial U and Np back extraction to aqueous</p></li><li><p>Adjust temperature/conc to ensure U and Np in correct oxidation states</p></li><li><p>Solvent extraction to remove Np from U</p></li><li><p>Back strip with dilute acid to recover U</p></li></ul></li></ul><p></p>
31
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Describe Plutonium purification (PUREX)

  • Decontamination of Pu stream from Tc

  • Pu nitrate evaporation

  • Decontamination of solvents

  • Plutonium purification

    • Use NOx to oxidise Pu(III) to Pu(IV)

    • Solvent extraction to separate Pu(IV) from Tc

    • Backwash Pu(III) into acid

    • Clean out any entrained solvent from acid

    • Evaporate to reduce volume for storage

32
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Describe Uranium finishing (PUREX)

  • Steam strip acid to remove entrained solvent

  • Evaporate to remove water and acid

  • Use hot air to breakdown U nitrate to U oxide

  • Cool, blend and store U oxide powder in drums

33
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Describe Plutonium finishing (PUREX)

  • Final conditioning to ensure Pu(IV)

  • Add oxalic acid to precipitate Pu

  • Separate liquid and solids

  • Dry and calcine to convert solids to Pu dioxide

  • Blend, sample and store in cans

  • Wet Pu oxalate is fed continuously to a 2-stage drying calcining furnace

  • Drying/calcination operates at up to 600 degrees celcius in electrically heated furnaces with counter current air flow

34
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Define heterogenous recycling

U, Pu actinides as separate products

35
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Define homogeneous recycling

U, Pu actinides in a single product

36
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Describe homogeneous recycling

GANEX 1st Cycle

  • Solvent extraction process

  • Use of ligand that only extracts Uranium

  • DEHiBA in diluent

  • Still have nitric acid dissolution = head end is the same

  • Uranium is still extracted as a UO2 uranyl ion

GANEX 2nd Cycle

  • EURO-GANEX is a solvent-extraction process aiming to co-separate all transuranic elements

  • For this, a solvent consisting of TODGA and DMDOHEMA in kerosene is used

37
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Define adsorption

Mass transfer from liquid/gas to solid phase

38
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Define leaching

Mass transfer from solid to liquid phase

39
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Define solvent extraction

Mass transfer from one liquid phase to another

40
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Pros and Cons of solvent extraction (SX)

Pros

  • Using the correct ligand is generally straight forwards as long as it dissolves in the solvent

  • High ligand concentration usually okay if solubility/miscibility in solvent/diluent is high

  • Chemicals are usually recoverable

  • Superior when the target species conc in water is >2g/L

Cons

  • Generally unavoidable entrainment of organic and aqueous phases

  • More prone to degradation

41
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Pros and cons of adsorption

Pros

  • Adsorbent regeneration is generally straight forward

  • Less pron to degradation

  • Generally superior for anion separation

  • Superior when the target species conc in water is <2g/L

Cons

  • Attatching the correct ligand to the adsorbent not always easy

  • Cannot have a very high ligand concentraion or physical properties are affected

  • Can last long time but no generally recycled

42
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Define ionic bonding

Complete transfer of valence electrons between bonding partners to create a lattice of cations and anions

43
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Define covalent bonding

Chemical bonds are formed from both bonding partners sharing valence electrons

44
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Define coordinate bonding

Chemical bonds are formed from one bonding partner donating valence electrons

45
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Difference between trans and cis ligands

Trans are on opposite diagonals, cis are on the same side of a complex

46
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Explain HSAB theory

  • Dissolved metal ions in solution are considered lewis acids (capable of accepting a lone pair to form a chemical bond)

  • Likewise, potential ligands are lewis bases (capable of donating a lone electron pair to form a chemical bond

  • Uranyl *UO2 (2+) is slightly unusual, being a polyatomic cation

47
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Describe hard acids and bases

  • High charge density

  • Not very polarizable

  • Bonding interactions more ionic in nature

  • Smaller ionic radius (relative to mass)

48
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Describe soft acids and bases

  • Low charge density

  • Highly polarizable

  • Bonding interactions more covalent in nature

  • Larger ionic radius

49
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Given some examples of soft hard and intermediate acids/bases

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50
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Define and describe chelation

A chelation or cherlating interaction occurs when a single ligand bonds to a metal ion via multiply heteroatoms

Bonding can be very strong, and its sometimes not a helpful for processes such as solvent extraction

Common chelating agent is EDTA

Active ingredient in chemical first-aid sprays found in labs

51
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Describe selective separations

  • Uses a carefully chosen ligand to target specific chemical species

  • Applications usually based on removing just the valuable component of a wastestream

  • Reagents can sometimes be expensive and/or toxic

  • Example : Leaching of gold mind tailings

52
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Describe Non-selective separations

  • Large variety of chemical species transferred from one phase to another

  • Applications usually based on removing hazardous components of a wastestream, prior to discharge to environemnt

  • Example : ion-exchange column to produce potable water

53
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Equation for the distribution coefficient (AKA partition coefficient) for separation processes

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54
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Equation for the separation factor

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55
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What are the requirements of a good organic phase for nuclear separations?

  • Able to extract some components to a larger extent than the rest of the components in the aq phase

  • Reaction should be stable but reversible

  • The compound formation should be easily reversed so that the solvent phase can be reused

  • Density of solvent phase at all times should be different from the aq phase to effect the separation

  • Inexpensive and cost effective with more than one supplier

  • Low toxicity

  • Low viscosity to aid mixing

  • High boiling point

56
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Why is TBP a good ligand for PUREX?

  • P=O bond is strongly polarised meaning electron rich

  • Hydrophobic alkyl groups allow for good solvation in the organic phase

  • Hydrophobic parts of the complex interact with the organic phase and keep the hydrophilic parts contained

57
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Describe acid hydrolysis and radiolysis of TBP

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58
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Describe the degradation of TBP by hydrolysis and radiolysis

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59
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Advantages of CHON ligands

  • Still prone to radiolysis but

  • Degradation products have low affinity compared to other fission products

  • Have relatively low boiling points so no issues residue when spent solvent is incinerated

  • More selective for U/Pu than TBP, overall lower capacity due to solubility limits of the complexes in the organic phase

60
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What is the importance of relative densities of phases?

  • In SX, must always be a density difference between the aqueous and organic phase

  • System must also account for the changes in phase density that occur during mixing, due to mass-transfer

  • Phases being close in density less problematic for mixer/settlers and pulse columns

  • Can be very problematic for centrifugal contract set up

61
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Describe the issues with Iodine-129

  • I129 and I131 are major contaminants in spend nuclear fuel

  • Complex chemical speciation and volatility means radioiodine is present in most stages of fuel recycke

  • Gas and aqueous streams require treatment

  • I129 is most significant dose contributor to plant emissions

62
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What is the solution to I129 issues in separation?

  • Apply HSAB theory to the radioiodine management problem

  • Designing a selective solvent extraction process for non-metals is very difficult

  • Easier to design a solid-phase adsorbent and contact this material with a gaseous or aqueous stream

  • Want the binding to be close to irreversible

  • Radioiodine loaded material can then be processed as solid waste and sent for geological disposal

63
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