RADTRAN 6/RadCat 6 user guide.

Weiner, Ruth F.; Hinojosa, Daniel; Heames, T.J.; Farnum, Cathy Ottinger; Kalinina, Elena Arkadievna

doi:10.2172/1096509

Cited by 7 publications

(6 citation statements)

References 16 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…To capture the range of internal dynamics and environmental influences, three independent analysis techniques for evaluating safety, security and safeguards were incorporated into the DPRA analysis. Here, the safety aspects were evaluated in RADTRAN 4 (Weiner et al 2013), an internationally accepted program and code for evaluating the safety risks of transporting radioactive materials; the security aspects were evaluated in STAGE (Dominguez et al 2012), a Sandia-specific application of a commercial modeling and simulation program for evaluating security risks in terms of physical protection system effectiveness; and, the safeguards aspects were evaluated with PRCALC (Yue, Cheng & Bari 2008), a Markov Chain-based code (developed by Brookhaven National Laboratory) for evaluating various risks associated with safeguarding nuclear materials.…”

Section: Analytical Resultsmentioning

confidence: 99%

Using Systems Theory to Address Complex Challenges to International Spent Nuclear Fuel Transportation

Williams

2018

INCOSE International Symp

View full text Add to dashboard Cite

Simply looking at a world map suggests new, more complex set of risks and threats will challenge successful international spent nuclear fuel (SNF) transportation operations. Whether related to multimodal transfers of SNF casks or inconsistency in multijurisdictional control measures, international SNF transportation represents a clear example of new threats and risk stemming from a multifaceted, globalized operating environment. In response to recent work out of Sandia National Laboratories (SNL) suggesting that new, system‐theoretic analysis techniques better ensure safe, secure and safeguarded international transportation of SNF, this paper explores the ability of basic systems theory concepts—interdependence, hierarchy and emergence—to better understand and address these complexities in system analysis.

show abstract

Section: Analytical Resultsmentioning

confidence: 99%

Using Systems Theory to Address Complex Challenges to International Spent Nuclear Fuel Transportation

Williams

2018

INCOSE International Symp

View full text Add to dashboard Cite

show abstract

“…RADTRAN was developed at Sandia National Laboratories to assess the radiological risk of transporting radioactive materials, including nuclear waste and spent nuclear fuel [20,21]. To select input parameters for the RADTRAN code, transportation scenarios for RPV waste were assumed.…”

Section: Transportation Scenariomentioning

confidence: 99%

“…The deposition velocity of other solid-state nuclides was set to 0.01 m s −1 . A deposition velocity of 0.01 m s −1 is often used as being generally representative of the aerodynamic diameter of aerosol particles that can be dispersed over long distances [20,21].…”

Section: Transportation Accident Scenariosmentioning

confidence: 99%

Radiological safety assessment for transportation of reactor pressure vessel during decommissioning of a nuclear power plant in Korea

Kwak,

Kim,

et al. 2024

J. Radiol. Prot.

View full text Add to dashboard Cite

In Korea, decommissioning of NPPs and transportation of the decommissioning waste are expected to expand in the near future. It is necessary to confirm that radiological risks to the public and workers are not significant through radiological safety assessment. The objective of this study is to assess the radiological safety for transportation of RPV waste, which is a major decommissioning waste with relatively high level of radioactivity. It was assumed that the waste would be tranported to the Gyeongju disposal facility by land transportation. First, the source term and transportation method of the RPV waste were determined, and the external dose rates from the waste were calculated using MCNP. Then, transportation scenarios were assumed under both normal and accident conditions. Under the scenarios, radiation doses were calculated using the RADTRAN. Under normal operation scenarios without a transportation accident, assuming 40 shipments per year, the average individual doses for the public ranged from 6.56×10-6 to 2.18×10-2 mSv yr-1. The maximum invidual doses for only a single shipment ranged from 2.43×10-6 to 3.14×10-1 mSv. For cargo handlers and vehicle crew members, the average doses were 2.26×101 mSv yr-1 and 2.95 mSv yr-1, respectively. Under transportation accident scenarios, average individual radiological risks which are product of the radiation doses and the annual accident rates ranged from 1.14×10-11 to 1.61×10-10 mSv yr-1 by transportation route segment when considering the transportation accident rate. Average individual doses assuming transportation accident occurrence ranged from 2.62×10-4 to 1.42×10-3 mSv. The maximum individual dose under accident conditions was 7.99×10-2 mSv. The calculated doses were below the regulatory limits in Korea. However, relatively high doses were observed for cargo handlers and vehicle crew members because of conservative assumptions. This study results can be used as basic data for the radiological safety assessment for the decommissioning waste transportation in the future.

show abstract

“…On the other hand, the potential radiological consequences to receptors T1 to T3 and H from the transportation and handling of SGs and/or the resultant processed objects have been modeled and calculated in this study using the RADTRAN 6 computer code developed by Sandia National Laboratories under the funding of the U.S. Nuclear Regulatory Commission and the U.S. Department of Energy [23]. RADTRAN 6, which simulates the radiation risk based on the measured or calculated dose rate at 1 m from the package, has also been well validated and is frequently used for environmental impact assessments of nuclear installations and transportation risk analysis worldwide [24].…”

Section: Calculation Toolsmentioning

confidence: 99%

“…Thus, the dose rate 1 m from a package containing 1 Bq/g of each radionuclide listed in Table 4 has been derived using the MicroShield ® computer code with regard to the SG in one piece, and a container containing processed (i.e., segmented or smelted) objects [36]. For simplification, each radionuclide is assumed to be homogeneously distributed in the total volume of the SG weighing 540 tons in one piece, defined in Section 3.1, and in the International Organization for Standardization (ISO) 1496/1 container (length 12 m, width 2.4 m, and height 2.5 m), which is widely used in the transportation of low and intermediate level radioactive waste (LILW), containing 20 tons of processed objects [23]. As such, the dose rate 1 m from each package containing each of the 11 key radionuclides for SG transportation at unit activity concentration was derived as shown in Table 4, ranging in the order of 10 −7 -10 −4 (mSv/h ) per (Bq/g).…”

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

View full text Add to dashboard Cite

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.

show abstract

RADTRAN 6/RadCat 6 user guide.

Cited by 7 publications

References 16 publications

Using Systems Theory to Address Complex Challenges to International Spent Nuclear Fuel Transportation

Using Systems Theory to Address Complex Challenges to International Spent Nuclear Fuel Transportation

Radiological safety assessment for transportation of reactor pressure vessel during decommissioning of a nuclear power plant in Korea

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

Contact Info

Product

Resources

About