RADTRAN 6 Technical Manual

Weiner, Ruth F.; Neuhauser, K.S.; Heames, T.J.; O'Donnell, Brandon M.; Dennis, Matthew L.

doi:10.2172/1323552

Cited by 5 publications

(4 citation statements)

References 22 publications

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“…Equations ( 14) to ( 16) are the equations in use today in important plume and dosimetry software models developed for radiological response. The FRMAC (Beal et al 2020), RESRAD family of codes (Yu et al 2001), and RADTRAN (Weiner et al 2014), for instance, use eqns ( 14) and ( 15) with revised coefficients. Marshall et al (2018) applied a relative weighting method favoring the long-term data in determining the goodness-of-fit for the Anspaugh models that "reaffirm their deficiencies in the short-lived timeframe wherein the dynamics of particulate dispersion dominate the resuspension process."…”

Section: Use Of Resuspension Equations In Plume and Dosimetry Softwar...mentioning

confidence: 99%

A Review of the Resuspension of Radioactively Contaminated Particles by Vehicle and Pedestrian Traffic—Current Theory, Practice, Gaps, and Needs

Kaminski,

Daiyega,

Magnuson

2024

Health Physics

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The resuspension of radioactively contaminated particles in a built environment, such as from urban surfaces like foliage, building exteriors, and roadways, is described empirically by current plume and dosimetry models used for hazard assessment and long-term risk purposes. When applying these models to radiological contamination emergencies affecting urban areas, the accuracy of the results for recent contamination deposition is impacted in two main ways. First, the data supporting the underlying resuspension equations was acquired for open, quiescent conditions with no vehicle traffic or human activities, so it is not necessarily representative of the urban environment. Second, mechanical disturbance by winds in urban canyons and during emergency operations caused by vehicle traffic and human activities are not directly considered by the equations. Accordingly, plume and dosimetry models allow the user to input certain compensating values, but the models do not necessarily supply users instructions on what values to use. This manuscript reviews the available literature to comprehensively and consistently pool data for resuspension due to mechanically induced resuspension applicable to urban contamination. Because there are few studies that directly measured radioactive resuspension due to vehicles and pedestrians, this review novelly draws on a range of other studies involving non-radioactive particles, ranging from outdoor air pollution emissions to indoor allergen transport. The results lead to tabulated, recommended values for specific conditions in the emergency phase to help users of plume and dosimetry models maintain the conservativeness needed to properly capture the potential radiation dose posed by mechanically induced resuspension. These values are of benefit to model users until better data are available. The results also suggest the types of data that may result in improved plume and dose modeling.

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Section: Use Of Resuspension Equations In Plume and Dosimetry Softwar...mentioning

confidence: 99%

A Review of the Resuspension of Radioactively Contaminated Particles by Vehicle and Pedestrian Traffic—Current Theory, Practice, Gaps, and Needs

Kaminski,

Daiyega,

Magnuson

2024

Health Physics

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“…As this scenario had both safety implications during the derailment and security implications during the subsequent attack, a multi-simulator DET was constructed to model the scenario. RADTRAN 24 was used to model the safety elements (Phase 1) and STAGE 25 modeled the security elements (Phase 2).…”

Section: State-of-the-art Det 2s Analysismentioning

confidence: 99%

Development of a leading simulator/trailing simulator methodology as part of an integrated safety-security analysis for nuclear power plants

Cohn

Noel

Osborn

et al. 2022

Proceedings of the Institution of Mechanical Engineers, Part O:

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Nuclear power plant (NPP) risk assessment is broadly separated into disciplines of nuclear safety, security, and safeguards. Different analysis methods and computer models have been constructed to analyze each of these as separate disciplines. However, due to the complexity of NPP systems, there are risks that can span all these disciplines and require consideration of safety-security (2S) interactions which allows a more complete understanding of the relationship among these risks. A novel leading simulator/trailing simulator (LS/TS) method is introduced to integrate multiple generic safety and security computer models into a single, holistic 2S analysis. A case study is performed using this novel method to determine its effectiveness. The case study shows that the LS/TS method avoided introducing errors in simulation, compared to the same scenario performed without the LS/TS method. A second case study is then used to illustrate an integrated 2S analysis which shows that different levels of damage to vital equipment from sabotage at a NPP can affect accident evolution by several hours.

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“…The small differences in the general PDFs for radionuclides (except receptor S 3 ) can be ascribed to the comparable dose coefficients for intake among actinides (i.e., 1.1 × 10 −7 to 2.5 × 10 −7 Sv/Bq for ingestion and 2.1 × 10 −5 to 4.7 × 10 −5 Sv/Bq for inhalation) and the dominance of internal exposure for the respective receptors. In addition, irregularities of the general PDFs among the actinides observed for receptor S 3 (i.e., scrap transfer worker) result from the fact that direct radiation becomes the only applicable exposure pathway due to the general assumption of negligible portions of releasable radionuclides under normal transfer conditions [33]. On the other hand, the higher values of general PDFs for receptor M 4 (i.e., slag worker) than other receptors, can be attributed to the longer exposure time, higher external dose conversion factor due to larger dimensions of objects, shorter distance from the receptor, and the higher slag-partitioning factor of actinides, as shown in Table 2 [19].…”

Section: General Pathway Dose Factors For Processing Of Dismantled St...mentioning

confidence: 99%

Calculation of Potential Radiation Doses Associated with Predisposal Management of Dismantled Steam Generators from Nuclear Power Plants

2020

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Although the generation of large components from nuclear power plants is expected to gradually increase in the future, comprehensive studies on the radiological risks of the predisposal management of large components have been rarely reported in open literature. With a view to generalizing the assessment framework for the radiological risks of the processing and transport of a representative large component—a steam generator—12 scenarios were modeled in this study based on past experiences and practices. In addition, the general pathway dose factors normalized to the unit activity concentration of radionuclides for processing and transportation were derived. Using the general pathway dose factors, as derived using the approach established in this study, a specific assessment was conducted for steam generators from a pressurized water reactor (PWR) or a pressurized heavy water reactor (PHWR) in Korea. In order to demonstrate the applicability of the developed approach, radiation doses reported from actual experiences and studies are compared to the calculated values in this study. The applicability of special arrangement transportation of steam generators assumed in this study is evaluated in accordance with international guidance. The generalized approach to assessing the radiation doses can be used to support optimizing the predisposal management of large components in terms of radiological risk.

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RADTRAN 6 Technical Manual

Cited by 5 publications

References 22 publications

A Review of the Resuspension of Radioactively Contaminated Particles by Vehicle and Pedestrian Traffic—Current Theory, Practice, Gaps, and Needs

A Review of the Resuspension of Radioactively Contaminated Particles by Vehicle and Pedestrian Traffic—Current Theory, Practice, Gaps, and Needs

Development of a leading simulator/trailing simulator methodology as part of an integrated safety-security analysis for nuclear power plants

Calculation of Potential Radiation Doses Associated with Predisposal Management of Dismantled Steam Generators from Nuclear Power Plants

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