Evaluation of severe accident risks: Quantification of major input parameters: MAACS (MELCOR Accident Consequence Code System) input

Sprung, J.L.; Jow, H-N; Rollstin, J.A.; Helton, Jon C.

doi:10.2172/6360728

Cited by 7 publications

(6 citation statements)

References 3 publications

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“…The inhalation and skin protection factors for sheltering come from NUREG/CR-4551, Vol.2 Rev.1 Part 7 and are consistent with SOARCA. 7 The study assumed that evacuees disappear as soon as the evacuation begins. Normal activities were assumed to occur outside with no shielding.…”

Section: A5 Cohort Types and Sheltering Coefficientsmentioning

confidence: 99%

Analysis of dose consequences arising from the release of spent nuclear fuel from dry storage casks.

Durbin¹,

Morrow²

2013

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The resulting dose consequences from releases of spent nuclear fuel (SNF) residing in a dry storage casks are examined parametrically. The dose consequences are characterized by developing dose versus distance curves using simplified bounding assumptions. The dispersion calculations are performed using the MELCOR Accident Consequence Code System (MACCS2) code. Constant weather and generic system parameters were chosen to ensure that the results in this report are comparable with each other and to determine the relative impact on dose of each variable. Actual analyses of site releases would need to accommodate local weather and geographic data. These calculations assume a range of fuel burnups, release fractions (RFs), three exposure scenarios (2 hrs and evacuate, 2 hrs and shelter, and 24 hrs exposure), two meteorological conditions (D-4 and F-2), and three release heights (ground level -1 meter (m), 10 m, and 100 m). This information was developed to support a policy paper being developed by U.S. Nuclear Regulatory Commission (NRC) staff on an independent spent fuel storage installation (ISFSI) and monitored retrievable storage installation (MRS) security rulemaking. iv This page intentionally blank v

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Section: A5 Cohort Types and Sheltering Coefficientsmentioning

confidence: 99%

Analysis of dose consequences arising from the release of spent nuclear fuel from dry storage casks.

Durbin¹,

Morrow²

2013

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“…Later years harvests are thus predominantly contaminated due to root uptake. However, Sprung et al (1990), indicate that of the radionuclides deposited onto soil, less than 1% will be consumed by man as a result of long-term root uptake. Since this amount is far less than that consumed from the first year harvest, subsequent years harvests will not be considered.…”

Section: Concentration In Following Years Cropmentioning

confidence: 99%

Development of an Ingestion Pathway Model for AXAIRQ

Simpkins¹

1999

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DISCLAIMER This LIST OF TABLES (Simpkins 1995b, Pillinger andHuang 1986) is used to predict the worst-case dose following a hypothetical acute atmospheric release of radionuclides. The model calculates dose due to inhalation, plume shine, and ground shine pathways. The addition of an ingestion model would provide completeness of pathway analysis. Further, as the DOE begins the proposed transition to regulation by the U.S. Nuclear Regulatory Commission (NRC) (Buhl et al. 1997), the addition of an ingestion model in the accident dose model will become necessary to comply with certain NRC regulations (USNRC 1995). OBJECTIVEThe purpose of this research was to develop, implement, and verify an ingestion model for the accident dose code AXAIRQ. BACKGROUND AXAIRQAXAIRQ calculates a predictive dose for both individuals and the population surrounding SRS. It is used predominantly for safety-related documentation and follows the recommendations in USNRC Regulatory Guide 1.145 (USNRC 1982). AXAIRQ uses the Gaussian plume model to describe the hypothetical transport of radionuclides from the release site to the area of interest. The Gaussian plume model, exposure pathways, and method of dose reporting are discussed in more detail below.Prior to running AXAIRQ, the hypothetical accident parameters must be entered into the code. Input requirements include, but are not limited to, the location of the release, classification of the release as resulting from a stack or vent, mixing height, and the quantity of each radionuclide released. The release is assumed to occur over a m i k u m 2 hour period. A calendar year for the postulated release is necessary to estimate population dose. The user has the option of including deposition and depletion of the plume, as well as the distances from the release at which to calculate dose (Simpkins 1995a AXAIN95 reads the user input data, data files, and dose factors. AXAIN95 determines the minimum distance from release location to site boundary in each of the sixteen sectors. Additionally, AXAIN95 determines the percentage of total time the wind is blowing in a given direction, stability class, and wind speed category. The above information is written into temporary files for access by subsequent modules.AXATERL constructs an array of concentric rings (out to 50 miles) around the release point representing the maximum relative terrain height. Data is read from an Oak Ridge National Laboratory data base. .. . AXAPOP89calculates the projected 50 mile offsite population, based 'on year of release, according to sector and *distance from the release.AXAMET95 calculates the relative air concentrations for all user-specified sectors and distances. Depletion factors are also calculated. PRIMUSL determines the radionuclide daughter ingrowth for all nuclides specified. AXADOS95 calculates individual and population doses by radionuclide and pathway. Diagrams of the subroutines for each module can be found in Simpkins (1995b). Models UsedCalculating dose following a hypothetical acute atmospheric releas...

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“…c -7 The assumptions utilized in NRC (1990) are given in Sprung et al (1990). A 51-year halflife for the lo-' m-' term of the summation has been ignored in the present analysis.…”

Section: C-6mentioning

confidence: 99%

Site restoration: Estimation of attributable costs from plutonium-dispersal accidents

Chanin¹,

Murfin²

1996

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Evaluation of severe accident risks: Quantification of major input parameters: MAACS (MELCOR Accident Consequence Code System) input

Cited by 7 publications

References 3 publications

Analysis of dose consequences arising from the release of spent nuclear fuel from dry storage casks.

Analysis of dose consequences arising from the release of spent nuclear fuel from dry storage casks.

Development of an Ingestion Pathway Model for AXAIRQ

Site restoration: Estimation of attributable costs from plutonium-dispersal accidents

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