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DOE OSTI2024

Qualitative and Quantitative Evaluation for Representative Human Reliability Analysis Methods

The Korea Institute of Nuclear Safety (KINS) is the regulatory expert organization established by the Korean government to strengthen the nation’s technical capabilities relating to nuclear safety regulation. KINS oversees the technical aspects of nuclear safety regulation, including safety reviews, inspections, education, and safety research—all conducted based on technical knowledge and accumulated regulatory experience. In 2023, KINS requested that Idaho National Laboratory (INL) validates representative human reliability analysis (HRA) methods used throughout the world, thus affording KINS with a basis for determining an HRA method adequate for its domestic regulatory purposes. The present paper mainly examines INL’s efforts in this regard. The resulting INL study covered four representative HRA methods widely used by nuclear utilities and regulatory institutes. These methods were qualitatively evaluated by applying specific evaluation criteria and determining how well each method reflected critical HRA issues. For this assessment, INL benchmarked the Halden International HRA Empirical Study. Using the Halden empirical data, along with information on human failure events (HFEs), the present study employed the selected HRA methods to estimate human error probabilities (HEPs) for the HFEs. It also performed statistical analyses to compare the HEPs predicted via the HRA methods against those from the Halden empirical data.

99 - GENERAL AND MISCELLANEOUS↗

DOE OSTI2024

Absolute decay counting of 146 Sm with 4π cryogenic microcalorimetry

We present a methodology for absolute activity counting of long-lived isotopes based on cryogenic Decay Energy Spectroscopy. A 146 Sm source was produced at the TRIUMF Laboratory and then processed and purified at Lawrence Livermore National Laboratory, yielding a pure sample. The source was embedded within a 4π thermal absorber coupled to a magnetic microcalorimeter achieving nearly 100% counting efficiency. Experimental uncertainties were studied and modeled, including thermal coupling of the source to the absorber, pulse pile-up, trigger, and event selection efficiencies. Here, the absolute activity of the pure 146 Sm source was measured to better than 1% uncertainty.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2021

Material Identification Using Dual Energy X-ray Absorptiometry

Two implementations of dual energy X-ray absorptiometry were studied to identify materials using X-ray attenuation data taken with the Digital Radiography and Computed Tomography (DRCT) systems that were developed for the Recovered Chemical Materiel Directorate (RCMD). Maitrejean et al.’s approach utilizes eigen effects through Principal Component Analysis, while Osipov et al.’s approach proposed a physics-based method. Both approaches approximate mass attenuation coefficients of materials as a linear combination of basis functions (eigen effects) or physics-based equations. A set of coefficients {a 1 , a 2 , a 3 } or {B, D} were found by parameter optimization in EXCEL Solver. The identification parameters, {$\frac{a_{2}}{a_{1}}$, $\frac{a_{3}}{a_{1}}$} or estimated effective atomic number $\hat{Z}$ from {B, D}, were calculated to identify material of an aluminum 8 step wedge and a steel 8 step wedge in X-ray radiography images taken by a DRCT system. Maitrejean et al.’s approach was unable to provide reliable $\frac{a_{3}}{a_{1}}$ ratio values for identification of materials. Osipov et al.’s approach was found to be more robust in identify materials with a semi-empirical formula derived from test results in this study.

36 MATERIALS SCIENCE↗

DOE OSTI2020

Application of Gaussian Bayes classifier to differentiate chlorine-based chemical agents

The Portable Isotopic Neutron Spectroscopy (PINS) is a commercialized system developed by Idaho National Laboratory (INL) to examine chemical warfare agents (CWA) non-destructively, utilizing Prompt Gamma Neutron Activation Analysis (PGNAA) techniques. The PINS system takes advantage of a high-resolution gamma-ray spectrum from a mechanically-cooled high-purity germanium (HPGe) detector. One of the difficult technical challenges is to discriminate the chlorine-based chemical agents. Especially, CN, CNB, CNS and CG have similar chemical compositions to make it hard to discriminate them with a higher confidence. Current identification algorithms for PINS systems with 252-Cf sources have been improved and updated continuously as more field data became available, and new algorithms was studied to complement the current algorithms by adopting the Gaussian Bayes classifier. These new algorithms were intended to be applied to a subset of chlorine-based chemical agents, and their main goal is discriminate CN, CNB, CNS and CG with their ratios of the chlorine neutron inelastic 1763keV peak to the chlorine thermal neutron capture 1959keV peak, which is referred to as the “Cl i/c” or “clic” ratio in this study. The Cl i/c ratios were assumed to follow Gaussian distributions with the means and the standard deviations unique to their corresponding chemical agents. The prior probabilities of these four chemical agents were optimized with a collection of field data to achieve the best performance in terms of precision or positive predictive value (PPV). Finally, their posterior probabilities as functions of the Cl i/c ratio were implemented in the current version of PINS analysis software in order to be tested with more field data.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗

DOE OSTI2019

Application of artificial neural network to prompt gamma neutron activation analysis for chemical warfare agents identification

The Portable Isotopic Neutron Spectroscopy (PINS) is a commercialized system developed by Idaho National Laboratory (INL) to examine chemical warfare agents (CWA) non-destructively, utilizing Prompt Gamma Neutron Activation Analysis (PGNAA) techniques. The PINS system takes advantage of a high-resolution gamma-ray spectrum from a mechanically-cooled high-purity germanium (HPGe) detector, and gamma-ray peak analysis provides input to its chemical identification logic with a probabilistic decision tree (PDT). The effectiveness of the chemical identification algorithm is determined by the availability of a wide range of data to train the algorithm to identify chemical-fills with accuracy. INL has a collection of gamma-ray spectra of various chemical-fills from the field-deployed PINS systems over the years, and it was envisaged to leverage such a database with the Artificial Neural Network (ANN) technique. Therefore, an ANN-based chemical identification algorithm was developed as an independent verification of the current algorithm. The ANN-based algorithm’s performance was evaluated against the U.S. Army blind test data, and results were presented and discussed in this study.

38 RADIATION CHEMISTRY, RADIOCHEMISTRY, AND NUCLEA↗

DOE OSTI2019

Simulation-based Design of a Shadow Shield for the MIND Backpack System

Modeling and simulation is a cost- and time-saving method to study conceptual designs of radiation detection systems. MCNP radiation transport code has been an indispensable tool in development of radiation detection systems, and the PINS systems have also utilized MCNP modeling and simulation in the system development. MCNP models of the PINS systems have been used to understand detector responses and to fill the gap in experimental data. Recently, the MIND backpack system was announced to be developed, and its prototype design was required to conduct laboratory tests and demonstrations. A shadow shield is the component to be designed by Idaho National Laboratory in order to maximize the performance of a backpack system while meeting the sponsor’s requirements. MCNP modeling and simulation was utilized to find the best specification of a shadow shield. This study was performed to down-select a shadow shield design for the MIND system. A total of 24 designs for a shadow shield were identified to build MCNP models, and their simulation results were used to prioritize each design. As a quantitative performance metric, an equation of Figure-of-Merit was introduced in the decision making analysis. In addition, the Analytic Hierarchy Process was adopted to prioritize and recommend best performing shadow shield designs.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗

DOE OSTI2019

Determination of the Deuterium-Tritium (D-T) Generator Neutron Flux using Multi-foil Neutron Activation Analysis Method

The deuterium-tritium (D-T) neutron flux from a Thermo-Fisher™ MP320 neutron generator was determined experimentally in this study. Fast neutron flux from a neutron generator can be measured indirectly using multi-foil activation analysis. Two sets of 12 activation foils each were prepared to cover a broad energy range of fast neutrons (1 – 15 MeV), and spectral peak analysis was performed on each activated foil with a mechanically-cooled HPGe detector. A non-negative solution of a linear least squares problem was solved to find a neutron flux energy distribution. The neutron yields of the high-yield (60 µA-90 kV) and low-yield (30 µA-70 kV) settings were determined to be 1.73×108 n/s and 2.28×107 n/s, respectively. Uncertainties on these neutron yields were estimated using the BC400 scintillator count rates whose fluctuations throughout the irradiations were described by the standard deviations of 10.6 and 8.5%, respectively. Linear relationships between the MP320’s neutron flux and a BC400 scintillator as well as a SWENDI-2 neutron dose meter were also derived to utilize them as on-line neutron flux monitors in the future.

07 ISOTOPE AND RADIATION SOURCES↗

DOE OSTI2019

Experimental Validation of MCNP Models for PINS Shadow Shield Mockups

MCNP has been regarded as an indispensable tool in development of radiation detection systems, and it is cost effective, thanks to advances in computing power, to simulate various conceptual designs without even fabricating them. Development of various PINS systems have also benefited from MCNP modeling and simulation. MCNP models of PINS systems have been frequently used to understand detector responses and to fill the gap in experimental data. Recently, a backpack version PINS system was announced to be developed. When the neutron generator and the HPGe detector are built by external vendors, the shadow shield is the component to be designed to maximize the performance while meeting the sponsor’s requirements. In order to utilize MCNP modeling and simulation to find the best specification of the shadow shield, a campaign of PINS lab measurements with a few shadow shield mockups has been conducted to validate MCNP simulation results. This study is intended to validate MCNP simulations and models in preparation of another more extensive simulation study. Validation of neutron flux is also discussed later in this report even though neutron counts were not measured experimentally.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗