Shuffler instruments for the nondestructive assay of fissile materials

Rinard, P.M.

doi:10.2172/5585772

Cited by 10 publications

(8 citation statements)

References 11 publications

(18 reference statements)

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“…The Cf shuffler technique is well known for the measurement of nuclear material, especially uranium in waste [5]. A moveable Cf source is brought close to an item of interest in a detection chamber for a period of time and then withdrawn into a shielded location.…”

Section: Description and Input Filementioning

confidence: 99%

Examples for Nuclear Safeguards Applications

Hendricks

Swinhoe

Favalli

2022

Monte Carlo N-Particle Simulations for Nuclear Detection and Safeguards

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Four simplified examples of actual safeguard calculations are provided. First is a combined (α,n) and spontaneous fission source in a nuclear fuel assembly in a water tank with fission detectors. Second is an HLNC2 high level neutron coincidence counter for spontaneous fission and (α,n) neutron multiplicity counting. Third is an NaI scintillation detector for a photon pulse-height tally measurement of a photon source from a cylindrical UO2 pellet. Fourth is a Cf shuffler, utilizing a 252Cf spontaneous fission source, used to measure a nuclear material item, with 3He tubes measuring the time-dependent delayed neutron buildup signature. The MCNP output from these calculations provides the data for safeguard analysis.

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Section: Description and Input Filementioning

confidence: 99%

Examples for Nuclear Safeguards Applications

Hendricks

Swinhoe

Favalli

2022

Monte Carlo N-Particle Simulations for Nuclear Detection and Safeguards

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“…Within the family of active neutron NDA techniques, differential die-away (DDA) might also be used if there is a possibility to build a moderating assay chamber at the measurement location. The DDA 37 and 252 Cf Shuffler 38 techniques are a more direct measurement of fissile mass, as they induce fission and detect prompt and delayed neutrons, respectively.…”

Section: Fissile Materials Survey Sensorsmentioning

confidence: 99%

Remote operations and maintenance framework for molten salt reactors

Holcomb

Britton

Varma

et al. 2018

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Remote, highly automated operations and maintenance tools (O&M) are crucial for economically successful deployment of molten salt reactors (MSRs). Liquid-fueled MSRs will have high dose rates within containment following initial start-up due to the proximity of the fuel salt and gaseous fission products. The challenges of performing O&M in high dose environments have long been recognized, and many of the required technology components have been developed for use in similar high radiation environments.To be competitive, future MSRs need to have much lower labor costs than existing nuclear power plants. The advance of digital technologies provides the opportunity to automate maintenance activities. Advances in modeling and simulation (M&S) may enable the role of the operator to be shifted from remote task performance to oversight of automated systems. Dynamically updating a plant's digital twin representation through integrating multiple sensor signals will be key to automating complex process tasks. Since complex, highly automated maintenance in high radiation areas has not been proven, adequate demonstration is required to validate its performance.

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“…We can see the population of delayed neutrons falls off as the time goes by. A conventional way performing the delayed neutron data acquisition is as follows: (1) neutron interrogation in a short time and remove the source, (2) wait until prompt neutrons die away from the system, (3) start the delayed neutron measurement at around I s after the neutron interrogation and measure the delayed neutrons during the time of from 1 s to 2 s and (4) repeat this cycle for a certain time to get a reasonable uncertainty [1]. This conventional system needs a time interval between the interrogation and starting of delayed neutron measurement because of its mechanical driving system of 252 ef source.…”

Section: I I Delayed Neutron Calcula Non For Repeated Cyclesmentioning

confidence: 99%

“…The representative application is the "Shuffler" developed by the Los Alamos National Laboratory (LANL) and this system is very well known for its high measurement accuracy for uranium materials [1]. The delayed neutron measurement has also been used for the fresh fuel inspection in fuel fabrication facilities.…”

Section: Introductionmentioning

confidence: 99%

Delayed neutron measurement in high frequency mode and its application to the determination of fissile content in spent fuel assembly

Lee

Shin

Kim

2011

2011 IEEE Nuclear Science Symposium Conference Record

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Ahstract-The delayed neutron measurement has been used for the fresh fuel inspection and 235U enrichment measurement of uranium materials for many years. The origin of delayed neutron is the beta decay of fission fragments and the population of fission fragments of right after a fission event decreases as time goes by. In the process of optimization of delayed neutron measurement system using a DT neutron generator to determine the fissile content of spent fuel assembly, we could find out that the utilization of delayed neutron can be maximized by performing the data acquisition of delayed neutron in an earlier time after the fission event. Monte Carlo code simulation results show the delayed neutron count rate obtained in a high frequency mode (100 Hz) is 3.25 times bigger than that acquired in a low frequency mode (0.5 Hz). The influence of delayed neutrons by 238U fission on delayed neutron counts is not negligible. Thus the delayed neutron count rate for 64 cases of spent fuel assembly is corrected by considering the 238U influence.To obtain sufficiently large ratios of signal to background for many cases of spent fuel assembly, 10 10 -lOll nls strength of DT neutron generator is needed.

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Shuffler instruments for the nondestructive assay of fissile materials

Cited by 10 publications

References 11 publications

Examples for Nuclear Safeguards Applications

Examples for Nuclear Safeguards Applications

Remote operations and maintenance framework for molten salt reactors

Delayed neutron measurement in high frequency mode and its application to the determination of fissile content in spent fuel assembly

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