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Passive Neutron Assay of Uranium Mass Measurements in Scraps and Wastes PowerPoint Presentation

Passive Neutron Assay of Uranium Mass Measurements in Scraps and Wastes

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### Passive Neutron Assay of Uranium Mass Measurements in Scraps and Wastes

V. Nizhnik, M. Pickrell SGTS/TND

Conventional Passive Multiplicity and Wastes

- Passive multiplicity is based on a theoretical hierarchy called the Point Model
- So named, because it is a zero dimensional.
- Therefore, spontaneous fission, multiplication, and alpha-n production are UNIFORM across the sample.
- Therefore, the sample nuclear material is evenly distributed in a homogenous matrix.

The Modification Necessary to Measure Uranium Wastes and Wastes

- What happens when the material is not uniform and evenly distributed?
- The conventional method develops a bias error.

- This work developed a modification of the Point Model / Passive Multiplicity equations to analyze non-uniform, inhomogeneous samples.
- Applied to uranium wastes with metal ingots mixed with diffuse oxide powder.

Passive Multiplicity (PM) Assumptions Kill this slide and Wastes

- Homogeneous distribution of nuclear material through an item matrix material
- The same chemical form of Uranium material in the item, i.e. uniform (a,n)-neutron production rate in the item volume
- Uniform physical property of uranium material (mostly concerns material density)
- If item properties are in compliance with listed statement:
- all the neutrons are equal in the term of multiplication
- Alpha parameter is the same for any point of item material
Then Passive Multiplicity Analysis can be applied for precise U mass analysis

Wastes: “Close Look” Example and Wastes

Uranium Metal Production Process

Ideal Case

UF4 + 2 Mg Umetal + 2 MgF2

Product: Single U metal piece and burnt matrix material; both of known mass

In reality

UF4 + 2 Mg

X·Uchunks + Y·UF4 + Z·MgF2 + W·Mg

Product: Number of U metal chunks, un-burnt UF4 in un-burnt Mg+MgF2 matrix. Their mas ratios are unknown.

- Impact on Neutron Multiplicity:
- Non-homogeneous distribution of U material
- Multi-component chemical composition
- Unknown mass ratio for uranium material components
- Non-uniform (a,n)-neutron production rate
- Spatial dependent neutron multiplication

Passive Multiplicity and Wastes

Conventional Passive Multiplicity Equations

Long Crocs

Modified Passive Multiplicity

Assumptions and known parameters:

Assign: x –U metal fraction in total U mass in item

Then: (1-x) – fraction of UF4 in total U mass in item

U metal chunks are pure: no (a,n)-neutrons production (a = 0)

Dispersed un-burnt UF4 material in Mg+MgF2 matrix is non-multiplying media due to low density (M = 1)

Alpha value for UF4 is known, based on U isotopic information

Modified Passive Multiplicity and Wastes

UF4 term

U metal term

M – multiplication in the metal chunks

x – U metal fraction in total U mass in item

mU – total U mass in measured item

- Corrects for non-uniform distribution of multi-component Uranium material
- Determines total Uranium mass in measured item
- Determines U mass in metal and UF4 form
- Determines neutron Multiplication in metal phase (gives information on average metal chunks size)

Example of U Waste Measurements and Wastes

- Counter:
- Efficiency 55%: allows fast acquisition of neutron multiplicity data with good statistics
- Size of the measurement cavity: d=20cm, h=42cm
- Items:
- 34 Uranium waste items with various Gross Weight (up-to 30kg)
- Packed in Poly bags to fit in the measurement cavity
- Target total uncertainty:
- Not more than 2.3% for 1 Sigma confidential interval

Plutonium Scrap Multiplicity Counter

Rejection of Cosmic Rays Bursts and Wastes

Cosmic rays prompt neutron “bursts” when interacting with High-Z (Uranium) material nuclei; they produce high multiplicities of detected neutron and affect counting rates.

Cycle-by-Cycle Multiplicity Distribution

Rejected by RSD based rejection logic

Good Cycle

Bad Cycle

Good Cycle

Rejected by Multiplicity Distribution analysis logic

Analysis with Modified PM and Wastes

Theoretical bias of Conventional vs Modified PM for NU

U metal average multiplication: M=1.05

UF4 Alpha value a=3.85

Conventional vs Modified Method Results

Measurement of a batch of uranium waste items (individual item U mass and Total U mass)

Relative content of UF4(1-x)

Bias of Total U mass in the measured batch

Theoretical Bias

The bias is higher in case of analysis of enriched Uranium since values of Multiplication in metal phase and Alpha in UF4 phase are higher then for natural Uranium

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