scholarly journals Methods for Calculating a Simplified Hydrologic Source Term for Frenchman Flat Sensitivity Studies of Radionuclide Transport Away from Underground Nuclear Tests

2004 ◽  
Author(s):  
A Tompson ◽  
M Zavarin ◽  
C Bruton ◽  
G Pawloski
Keyword(s):  
Source Term ◽  
Radionuclide Transport ◽  
Sensitivity Studies ◽  
Nuclear Tests

scholarly journals Evaluation of the Hydrologic Source Term from Underground Nuclear Tests on Pahute Mesa at the Nevada Test Site: The CHESHIRE Test

2001 ◽  
Author(s):  
G A Pawloski ◽  
A F B Tompson ◽  
S F Carle ◽  
W L Bourcier ◽  
C J Bruton ◽  
...  
Keyword(s):  
Source Term ◽  
Test Site ◽  
Nevada Test Site ◽  
Nuclear Tests

The Hazard Analysis of Plutonium Aerosol Resuspension in Typical Dated Nuclear-Polluted Regions

2011 ◽  
Vol 414 ◽  
pp. 16-21
Author(s):  
Wen Jie Liu ◽  
Ba Yi Hu ◽  
Qing Zhong Li
Keyword(s):  
Radiation Protection ◽  
Source Term ◽  
Hazard Analysis ◽  
Intrinsic Factor ◽  
Short Term ◽  
Radiation Hazards ◽  
Airborne Concentration ◽  
Effective Doses ◽  
Nuclear Tests ◽  
Soil Cleanup

The plutonium material within the nuclear devices would be aerosolized, released from the source-term and deposited in the soil after nuclear tests or accidents. Due to the natural and artificial disturbances the plutonium aerosols deposited in the soil would resuspend into the air. The hazard analysis of plutonium aerosol resuspension in typical dated nuclear-polluted regions is significative for radiation assessment and post-accident depuration in contaminated regions. The analysis shows that the soil eroding is the intrinsic factor of plutonium aerosol resuspension. The airborne contaminated concentration in non-nuclear source-term is much higher than nuclear source-term. The soil cleanup would lead to short-term rise of the airborne concentration. From the estimation of the equivalent dose, it is clear that the radiation hazards of the resuspended particulates in typical dated nuclear-polluted regions are extremely limited. After soil cleanup the annual effective doses of the contaminated regions are far below the radiation protection standards.

Simulation of Radionuclide Release and Subsurface Transport for LILW New Romanian Repository

2001 ◽  
Author(s):  
Liana Didita ◽  
Petre Ilie ◽  
Margarit Pavelescu ◽  
Alexandru Danchiv ◽  
George Martac
Keyword(s):  
Safety Assessment ◽  
Source Term ◽  
Control Period ◽  
Radionuclide Transport ◽  
Assessment Methodology ◽  
Saturated Zone ◽  
Near Surface ◽  
Institutional Control ◽  
Radionuclide Release ◽  
Natural Barrier

Abstract This paper presents the main stages covered in development of the safety assessment methodology for near surface Romanian repository. It also describes the modeling approaches and assumptions used in source term modeling as well as the radionuclides transport through the unsaturated and saturated zones. In the paper, the repository performance is assessed only by the normal evolution scenario and the beginning of the institutional control period. Transport modeling through unsaturated zone emphasizes its behaviour as a natural barrier in radionuclide migration’s way. Only a brief discussion of radionuclide transport through the saturated zone is given in this paper. The discussion is related first to the model’s characteristics, followed by the presentation of the results.

scholarly journals Sensitivity Studies of the Swift Radionuclide Transport Model

1980 ◽  
pp. 763-770
Author(s):  
James E. Campbell ◽  
Brenda S. Langkopf ◽  
Ronald L. Iman ◽  
Mark Reeves
Keyword(s):  
Transport Model ◽  
Radionuclide Transport ◽  
Sensitivity Studies

scholarly journals Hydrologic Source Term Processes and Models for Underground Nuclear Tests at Rainier Mesa and Shoshone Mountain, Nevada National Security Site (Rev. 1.0)

2011 ◽  
Author(s):  
A. F.B. Tompson ◽  
M. Zavarin ◽  
W. W. McNab ◽  
S. F. Carle ◽  
D. E. Shumaker ◽  
...  
Keyword(s):  
National Security ◽  
Source Term ◽  
Nuclear Tests

scholarly journals MELCOR Validation Study on Multi-Room Fire

2020 ◽  
Author(s):  
David L. Y. Louie ◽  
Samir El-Darazi ◽  
Lyndsey M. Fyffe ◽  
James L. Clark
Keyword(s):  
Validation Study ◽  
Source Term ◽  
Sensitivity Study ◽  
Radionuclide Transport ◽  
Aerosol Transport ◽  
Nuclear Facilities ◽  
Code Comparison ◽  
Fire Experiment ◽  
Accident Scenarios ◽  
Fire Accident

Abstract Estimation of radionuclide aerosol release to the environment, from fire accident scenarios, are one of the most dominant accident evaluations at the U.S. Department of Energy’s (DOE’s) nuclear facilities. Of particular interest to safety analysts, is estimating the radionuclide aerosol release, the Source Term (ST), based on aerosol transport from a fire room to a corridor and from the corridor to the environment. However, no existing literature has been found on estimating ST from this multi-room facility configuration. This paper contributes the following to aerosol transport modeling body of work: a validation study on a multiroom fire experiment (this includes a code-to-code comparison between MELCOR and Consolidated Fire and Smoke Transport, a specialized fire code without radionuclide transport capabilities), a sensitivity study to provide insight on the effect of smoke on ST, and a sensitivity study on the effect of aerosol entrainment in the atmosphere (puff and continuous rate) on ST.

scholarly journals Evaluation of the hydrologic source term from underground nuclear tests in Frenchman Flat at the Nevada Test Site: The Cambric test

10.2172/8202 ◽  
1999 ◽  
Author(s):  
W L Bourcier ◽  
C J Bruton ◽  
S F Carle ◽  
A B Kersting ◽  
G A Pawloski ◽  
...  
Keyword(s):  
Source Term ◽  
Test Site ◽  
Nevada Test Site ◽  
Nuclear Tests
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