Reevaluation of neutron flux characterization parameters for NIST RT-2 facility

Sahin, Dagistan Nmn; Radulović, Vladimir; Lindstrom, Richard M.; Trkov, A.

doi:10.1007/s10967-014-3076-3

Cited by 7 publications

(2 citation statements)

References 12 publications

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“…This method has been highly touted as an accurate method of Instrumental NAA (INAA) [13] and has been implemented at several facilities around the world. Recent research using the reactor at the National Institute of Standards and Technology (NIST) has shown that limitations exist with this methodology when considering a highly thermalized reactor spectrum [14]. It was found that owing to the low-energy resonances in many non-1/v isotopes, the K 0 method yields incorrect reaction rates for highly thermalized fluxes.…”

Section: B Estimation Of Effective Fission-product Yields Via Origenmentioning

confidence: 99%

Quantification of Trace-Level Fissile Samples via Short-Lived Delayed Gamma Spectroscopy

Skutnik

Knowles

Glasgow

2019

IEEE Trans. Nucl. Sci.

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We describe a generalized means of isotopic assay and quantification of multicomponent fissile mixtures based on the observation of short-lived fission-product gamma signatures. Given that the characteristic mass yield curves differ for individual fissile species, this can be used to construct an overdetermined system of equations corresponding to the observed photopeak yields, the solution of which yields information on the individual isotopic masses of parent fissile isotopes within the system. This method is then demonstrated for single-isotope samples of 233 U, 235 U, and 239 Pu; binary fissile mixtures of U and Pu; and trace fissile samples contained within intact typical environmental sampling media, each irradiated and measured using the High Flux Isotope Reactor at the Oak Ridge National Laboratory. Our findings indicate that this method can reliably be used to quantify nanogram-level fissile masses in binary mixtures with uncertainties on the order of 2%-7%. Finally, observed discrepancies with individual fission-product indicators and likely sources of bias are discussed.

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Section: B Estimation Of Effective Fission-product Yields Via Origenmentioning

confidence: 99%

Quantification of Trace-Level Fissile Samples via Short-Lived Delayed Gamma Spectroscopy

Skutnik

Knowles

Glasgow

2019

IEEE Trans. Nucl. Sci.

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“…There are also measurements that provide additional validation of the calculations used for operational and safety support. Measurements of neutron flux can be based on foil irradiations such as those used in the past to make measurements in the RT-2 rabbit facility in order to facilitate its use for activation analysis (Lindstrom, 2008 andŞahin, 2014). This provides a local measurement as opposed to a global measurement such as reactivity and is important as the most significant change in the reactor due to the replacement of the HEU with LEU is a shift of the peak flux distribution from the outer core to the inner core.…”

Section: Other Testsmentioning

confidence: 99%

A reload and startup plan for conversion of the NIST research reactor

Diamond¹

2016

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The National Institute of Standards and Technology operates a 20 MW research reactor for neutron-based research. The heavy-water moderated and cooled reactor is fueled with highenriched uranium (HEU) but a program to convert the reactor to low-enriched uranium (LEU) fuel is underway. Among other requirements, a reload and startup test plan must be submitted to the U.S. Nuclear Regulatory Commission (NRC) for their approval. The NRC provides guidance for what should be in the plan to ensure that the licensee has sufficient information to operate the reactor safely. Hence, a plan has been generated consisting of two parts.

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Nuclear analysis at NBS and NIST

Lindstrom

2018

J Radioanal Nucl Chem

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Reevaluation of neutron flux characterization parameters for NIST RT-2 facility

Cited by 7 publications

References 12 publications

Quantification of Trace-Level Fissile Samples via Short-Lived Delayed Gamma Spectroscopy

Quantification of Trace-Level Fissile Samples via Short-Lived Delayed Gamma Spectroscopy

A reload and startup plan for conversion of the NIST research reactor

Nuclear analysis at NBS and NIST

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