Measuring spent fuel assembly multiplication in borated water with a passive neutron albedo reactivity instrument

Tobin, Stephen J; Peura, P.; Bélanger-Champagne, C.; Moring, Mikael; Dendooven, P.; Honkamaa, Tapani

doi:10.1016/j.nima.2018.04.044

Cited by 5 publications

(2 citation statements)

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“…Neutron emission is an important observable for nuclear safeguards applications to verify the plutonium content in SNF and reprocessed raffinates. Examples of passive NDA methods measuring the neutron emission of SNF assemblies are the FORK type of detectors (Rinard and Bosler, 1988) and the more advanced Differential Die-Away Self-Interrogation (DDSI) (Kapklan et al, 2020) and Passive Neutron Albedo Reactivty (PNAR) (Tobin et al, 2018) systems. They are based on the neutron emission from spontaneous fission of 244 Cm as primary neutron source.…”

Section: Introductionmentioning

confidence: 99%

An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation

et al. 2023

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A method to determine the neutron production rate of a spent nuclear fuel segment sample by means of non-destructive assay conducted under standard controlled-area conditions is described and demonstrated. A neutron well counter designed for routine nuclear safeguards applications is applied. The method relies on a transfer procedure that is adapted to the hot cell facilities at the Laboratory for High and Medium level Activity of SCK CEN in Belgium. Experiments with 252Cf(sf) sources, certified for their neutron emission rate, were carried out at the Joint Research Centre to determine the characteristics of the detection device. Measurements of a segment of a spent nuclear fuel rod were carried out at SCK CEN resulting in an absolute and non-destructive measurement of the neutron production rate avoiding any reference to a representative spent nuclear fuel sample to calibrate the device. Results of these measurements were used to study the performance of depletion codes, i.e., ALEPH2, SCALE, and Serpent2. The study includes a code-to-code and code-to-experiment comparison using different nuclear data libraries.

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Section: Introductionmentioning

confidence: 99%

An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation

et al. 2023

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“…The ratio of the measured neutron flux in the two configurations, high multiplication divided by low multiplication, is called the PNAR Ratio and is a measure of the multiplication in the fuel assembly for which the fissile content creates the chain reaction. The PNAR concept was originally proposed in 1982 by Lee and Lindquist [6] and the method has recently been discussed in more detail in several publications [7][8][9][10].…”

Section: Introductionmentioning

confidence: 99%

Passive neutron albedo reactivity measurements of spent nuclear fuel

Tupasela

Dendooven

Tobin

et al. 2021

Nuclear Instruments and Methods in Physics Research Section A:

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Spent Fuel Measurements

Kaplan-Trahan,

Belian,

Croce

et al. 2024

Nondestructive Assay of Nuclear Materials for Safeguards and Security

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This chapter describes the methods used to measure spent nuclear fuel. The first section describes the properties of typical reactor fuel: geometry, burnup, initial enrichment, and cooling time. Neutron multiplication in the assembly is discussed. The measurement methods are divided into gamma-based methods, neutron-based methods, and other methods. A particularly important gamma-based method is passive gamma emission tomography. The neutron-based methods range from the relatively simple passive neutron fork, passive neutron albedo reactivity and differential dieaway to the complex active methods. The other methods are Cerenkov viewing devices, curium/plutonium ratio and calorimetry.

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Measuring spent fuel assembly multiplication in borated water with a passive neutron albedo reactivity instrument

Cited by 5 publications

References 8 publications

An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation

An absolute measurement of the neutron production rate of a spent nuclear fuel sample used for depletion code validation

Passive neutron albedo reactivity measurements of spent nuclear fuel

Spent Fuel Measurements

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