Determination of spent nuclear fuel assembly multiplication with the differential die-away self-interrogation instrument

Kaplan, A. C.; Henzl, V.; Menlove, H.O.; Swinhoe, Martyn T; Belian, Anthony P.; Flaska, Marek; Pozzi, Sara A.

doi:10.1016/j.nima.2014.04.023

Cited by 13 publications

(15 citation statements)

References 4 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…This effect is not observed in spent fuel, as shown in Figure 7-15. We are interested in applying the early die-away method from [9] and Section 5.1 of this thesis to fresh fuel measurements to ascertain whether or not this relationship exists in experimental results.…”

Section: Fresh Fuel Measurement Resultsmentioning

confidence: 99%

“…The only quantities directly measurable by the DDSI instrument. Previously [9] it was reported that the die-away time of the early time domain (4-52 µs) of the RAD of the DDSI instruments response is quadratically related with the SFA multiplication:…”

Section: Ddsi Methodologymentioning

confidence: 99%

“…time zero in the time correlated distribution) should allow for measurement of the 244 Cm mass and the late doubles gate should allow for measurement of fissile mass. This concept was however modified in later work to account for the fact that the early time-window contains data not only from SF and fastfission events, but also from induced fission events [8,9]. Much of the early research conducted on DDSI utilized the system design in Figure 1-1.…”

Section: The Conceptual Development Of the Ddsi Technique Took Place mentioning

confidence: 99%

“…Such is the case with the DDSI instrument with a rather short detector die-away time of 19 μs and highly multiplicative spent fuel as the typical source [9].…”

Section: Neutron Coincidence Countingmentioning

confidence: 99%

“…It has been shown that there is a correlation between multiplication and early die-away time of the simulated Rossi-alpha distribution from DDSI [9]. It has also been shown that cooling time can be well approximated by total gamma measurements [1].…”

Section: Total Neutron and Gamma Ratesmentioning

confidence: 99%

See 4 more Smart Citations

Utilization of the Differential Die-Away Self-Interrogation Technique for Characterization and Verification of Spent Nuclear Fuel

Trahan¹

2016

View full text Add to dashboard Cite

SINGLE DETECTOR DEFINITION LEFT BANK ***** c ***** 4 atm =-4.99e-4, atm =-7.488e-4, 7.5 atm =-9.359e-4 g/cc 10 atm-1.248e-3 ***** 940-7.488e-4-901 904-905 u=500 imp:n=1 $ He3 tube at 6.0 atm 901 870-2.699 901-902-906 u=500 imp:n=1 $ Al tube 902 920-9.58e-4 902 u=500 imp:n=1 $ air gap around He-3 tube 903 870-2.699-902 906 u=500 imp:n=1 $ Void above each tube 904 940-7.488e-4-901-904 u=500 imp:n=1 $ Lower dead 905 940-7.488e-4-901 905-906 u=500 imp:n=1 $ Upper dead c c SINGLE DETECTOR DEFINITION LEFT BANK NON-DDSI tube c ***** 4 atm =-4.99e-4, 6 atm =-7.488e-4, 7.5 atm =-9.359e-4 g/cc 10 atm-1.248e-3 ***** 950 940-7.488e-4-911 904-905 u=501 imp:n=1 $ He3 tube at 6.0 atm 951 870-2.699 911-912-906 u=501 imp:n=1 $ Al tube 952 920-9.58e-4 912 u=501 imp:n=1 $ air gap around He-3 tube 953 870-2.699-912 906 u=501 imp:n=1 $ Void above tube 954 940-7.488e-4-911-904 u=501 imp:n=1 $ Lower dead 955 940-7.488e-4-911 905-906 u=501 imp:n=1 $ Upper dead c c DETECTOR ASSEMBLY, LEFT BANK 800 0 900 u=2 fill=500 imp:n=1 $ Initial detector # 60 (at left) 811 0-910 u=2 fill=501 imp:n=1 $ NON-DDSI TUBE c Left bank of He-3 tubes, first row 801 like 800 but trcl=(0-3.5 0) u=2 $ 58 802 like 800 but trcl=(0-7.0 0) u=2 $ 56 803 like 800 but trcl=(0-10.5 0) u=2 $ 54 804 like 800 but trcl=(0-14.0 0) u=2 $ 52 805 like 800 but trcl=(0-17.5 0) u=2 $ 50 806 like 800 but trcl=(0-21.0 0) u=2 $ 48 807 like 811 but trcl=(3 12.25 0) u=2 $ 62 DOWN IN OCTOBER c Left bank of He-3 tubes, second row 808 like 800 but trcl=(-3.0 1.75 0) u=2 $ 61 809 like 811 but trcl=(0 7.00 0) u=2 $ 59 DOWN IN OCTOBER 810 like 800 but trcl=(-3.0-5.25 0) u=2 $ 57 812 like 800 but trcl=(-3.0-12.25 0) u=2 $ 53 813 like 800 but trcl=(-3.0-15.75 0) u=2 $ 51 814 like 800 but trcl=(-3.0-19.25 0) u=2 $ 49

show abstract

Section: Fresh Fuel Measurement Resultsmentioning

confidence: 99%

Section: Ddsi Methodologymentioning

confidence: 99%

Section: The Conceptual Development Of the Ddsi Technique Took Place mentioning

confidence: 99%

“…Such is the case with the DDSI instrument with a rather short detector die-away time of 19 μs and highly multiplicative spent fuel as the typical source [9].…”

Section: Neutron Coincidence Countingmentioning

confidence: 99%

Section: Total Neutron and Gamma Ratesmentioning

confidence: 99%

See 3 more Smart Citations

Utilization of the Differential Die-Away Self-Interrogation Technique for Characterization and Verification of Spent Nuclear Fuel

Trahan¹

2016

View full text Add to dashboard Cite

show abstract

Principles of Neutron Multiplicity

Henzlova,

Ensslin,

Favalli

et al. 2024

Nondestructive Assay of Nuclear Materials for Safeguards and Security

View full text Add to dashboard Cite

This chapter describes the extension of the neutron coincidence technique to the measurement of higher orders of correlation (beyond pairs). Successful use of this technique requires more efficient neutron detectors but allows measurement of items with more unknown properties (like impurities). The chapter includes a description of the electronics which is used as well as a mathematical description of the measured quantities and their relation to the properties of interest of the measured item. This is done for both passive methods (using the neutrons emitted from the item) as well as active methods (in which an external neutron source is used to induce fissions in the measured item). The chapter describes how the detectors are characterized and calibrated and presents areas of application and algorithm developments. The section on active counting describes the important concept of item coupling. The chapter concludes with a section on high accidentals multiplicity counting.

show abstract

Spent Fuel Measurements

Kaplan-Trahan,

Belian,

Croce

et al. 2024

Nondestructive Assay of Nuclear Materials for Safeguards and Security

View full text Add to dashboard Cite

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.

show abstract

Determination of spent nuclear fuel assembly multiplication with the differential die-away self-interrogation instrument

Cited by 13 publications

References 4 publications

Utilization of the Differential Die-Away Self-Interrogation Technique for Characterization and Verification of Spent Nuclear Fuel

Utilization of the Differential Die-Away Self-Interrogation Technique for Characterization and Verification of Spent Nuclear Fuel

Principles of Neutron Multiplicity

Spent Fuel Measurements

Contact Info

Product

Resources

About