Derivation of Geometry Factors for Internal Gamma Dose Calculations for a Cylindrical Radioactive Waste Package

2002 ◽  
Vol 140 (3) ◽  
pp. 279-287 ◽  
Author(s):  
Brent J. Lewis ◽  
Aamir Husain
Keyword(s):  
Radioactive Waste ◽  
Gamma Dose ◽  
Dose Calculations ◽  
Waste Package

Accuracy of Cloudshine Gamma Dose Calculations in the CAP-88 Dispersion Model

2017 ◽  
Vol 112 (4) ◽  
pp. 414-419 ◽  
Author(s):  
Michael W. McNaughton ◽  
Jessica M. Gillis ◽  
Elizabeth Ruedig ◽  
Jeffrey J. Whicker ◽  
David P. Fuehne
Keyword(s):  
Dispersion Model ◽  
Gamma Dose ◽  
Dose Calculations

Development of nuclear criticality safety controls on intermediate-level waste packages

2012 ◽  
Vol 76 (8) ◽  
pp. 2949-2956 ◽  
Author(s):  
T. W. Hicks ◽  
P. Wood ◽  
D. Putley ◽  
T. D. Baldwin
Keyword(s):  
Radioactive Waste ◽  
Waste Management ◽  
Neutron Transport ◽  
Intermediate Level ◽  
Fissile Material ◽  
Radioactive Waste Management ◽  
Waste Package ◽  
Operational Phase ◽  
Nuclear Criticality Safety ◽  
Enriched Uranium

AbstractIntermediate-level wastes (ILW) include substantial quantities of fissile material and controls are required to ensure that its storage, transport and disposal does not present a nuclear criticality hazard. This paper describes the Radioactive Waste Management Directorate's research to develop package fissile material limits (in the form of screening levels) for four different categories of ILW, defined according to uranium or plutonium composition: (1) irradiated natural and slightly enriched uranium (uranium containing up to 1.9 wt.% 235U); (2) low-enriched uranium (uranium containing up to 4 wt.% 235U); (3) high-enriched uranium (uranium containing up to 100 wt.% 235U); and (4) separated plutonium (plutonium containing up to 100 wt.% 239Pu).The derivation of package screening levels was supported by neutron transport calculations that addressed conditions during waste package transport to a geological disposal facility (GDF), during the GDF operational phase and after GDF closure. The analysis included consideration of combinations of events and processes that could result in fissile material accumulation and concentration after GDF closure, when waste packages have deteriorated sufficiently for fissile material to be mobilized. The results of the calculations have provided input to Radioactive Waste Management Directorate's decision making on setting waste package screening levels.

scholarly journals Assessment of Gamma Dose Rate for Hypothetical Radioactive Waste Container

2017 ◽  
Vol 04 (01) ◽  
Author(s):  
Sabeeha JB ◽  
Mohammed GHK ◽  
Battawi SM ◽  
Falah SHHU ◽  
Ahmad JH ◽  
...  
Keyword(s):  
Radioactive Waste ◽  
Dose Rate ◽  
Gamma Dose ◽  
Gamma Dose Rate ◽  
Waste Container

scholarly journals Photoneutron and capture gamma dose calculations for a radiotherapy room made of high density concrete

2011 ◽  
Vol 26 (2) ◽  
pp. 147-152 ◽  
Author(s):  
Asghar Mesbahi ◽  
Hosein Ghiasi ◽  
Rabee Mahdavi
Keyword(s):  
Analytical Methods ◽  
Gamma Ray ◽  
Gamma Dose ◽  
High Density ◽  
Dose Calculations ◽  
Average Difference ◽  
Dose Equivalent ◽  
Entrance Door ◽  
Therapy Room ◽  
The Difference

Neutron and capture gamma ray dose equivalent along the maze and entrance door of a radiation therapy room made of high density concrete was calculated using analytical and Monte Carlo methods. The room geometry and the 18 MV photon beam of a Varian 2100C/D linac were simulated using MCNPX MC code. Four analytical methods including Kersey, French, McCall, and Wu-McGinley methods were used in the current study. Average difference of 13-30% was seen between analytical and MC methods along the maze for photoneutron calculations. The difference between Wu-McGinley and MC methods was about 17% for capture gamma ray calculations. It was concluded that the analytical methods overestimate both neutron and capture gamma ray dose equivalents compared to MC. Moreover, it was shown that the analytical methods can be used as conservative estimators for neutron and capture gamma calculations.

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