Leveraging sub-E0 dose assessment methodology to improve EUV lithography cluster dose performance

2020 ◽  
Author(s):  
Chris F. Robinson ◽  
Cody J. Murray ◽  
Luciana Meli ◽  
Anuja De Silva ◽  
Dario Goldfarb ◽  
...  
Keyword(s):  
Dose Assessment ◽  
Assessment Methodology ◽  
Euv Lithography

Development and Application of Dose Assessment Methodology During IS-LOCA in BWR Plant

2020 ◽  
Author(s):  
Hironobu Iwanami ◽  
Tomoharu Hashimoto ◽  
Motoi Tanaka ◽  
Ryuichi Tayama ◽  
Satoshi Mizuno ◽  
...  
Keyword(s):  
Evaluation Method ◽  
Fission Products ◽  
Emergency Evacuation ◽  
Assessment Model ◽  
Dose Assessment ◽  
Assessment Methodology ◽  
Time Step ◽  
Reactor Water ◽  
Accident Scenario ◽  
Break Area

Abstract A dose assessment methodology was developed for IS-LOCA (Interface System – Loss of Coolant Accident) event, which is one of the design basis accidents in BWR plants, and a dose assessment at site boundary was implemented for the accident scenario by applying the evaluation method. The main objective of the assessment is to review a conventional conservative dose assessment model in the accident scenario. The conventional conservative model is a method due to considering all fission products (FP) in liquid migrate to airborne (i.e. 100%) when reactor water is discharged from piping break area, while the developed new methodology is a method to evaluate transition behavior of fission products precisely by using flash fraction (FF) from liquid to airborne and consider it. As the result of dose assessment, it was confirmed that the calculated dose during IS-LOCA event was about one-fifteith reduced by adopting the new model from the conventional model. The content of this paper includes: • Background and purpose that led to the dose assessment methodology development during IS-LOCA. • An evaluation method by using discharged amount of reactor water at piping break area and flash fraction (FF) from liquid to airborne based on Regulatory guide 1.183 published by U.S. NRC. • Another evaluation method that takes into account the fluctuation due to depressurization of reactor pressure per time step from the start of accident until completion of isolation at piping break area in addition to the above method. • Comparison between dose results at site boundary based on these methods and conventional conservative model. This results will give a precise information for public and it will be useful for making emergency evacuation plan.

PCCP Condition Assessment Methodology: What Is Right for You?

2012 ◽  
Author(s):  
Michael D. Gossett ◽  
Graham E. C. Bell ◽  
Steven R. Fox ◽  
Keith R. Bushdiecker ◽  
Richard Pousard, Jr.
Keyword(s):  
Condition Assessment ◽  
Assessment Methodology

Neutron dose evaluation of Elekta Linac at two energies (10 & 18 MV) by MCNP code and comparison with experimental measurements

2014 ◽  
Vol 6 (1) ◽  
pp. 1006-1015
Author(s):  
Negin Shagholi ◽  
Hassan Ali ◽  
Mahdi Sadeghi ◽  
Arjang Shahvar ◽  
Hoda Darestani ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Measurement Data ◽  
Calculated Data ◽  
High Energy ◽  
Neutron Dose ◽  
Dose Assessment ◽  
Photon Flux ◽  
Dose Equivalent ◽  
Monte Carlo Techniques ◽  
Neutron Dose Equivalent

Medical linear accelerators, besides the clinically high energy electron and photon beams, produce other secondary particles such as neutrons which escalate the delivered dose. In this study the neutron dose at 10 and 18MV Elekta linac was obtained by using TLD600 and TLD700 as well as Monte Carlo simulation. For neutron dose assessment in 2020 cm2 field, TLDs were calibrated at first. Gamma calibration was performed with 10 and 18 MV linac and neutron calibration was done with 241Am-Be neutron source. For simulation, MCNPX code was used then calculated neutron dose equivalent was compared with measurement data. Neutron dose equivalent at 18 MV was measured by using TLDs on the phantom surface and depths of 1, 2, 3.3, 4, 5 and 6 cm. Neutron dose at depths of less than 3.3cm was zero and maximized at the depth of 4 cm (44.39 mSvGy-1), whereas calculation resulted  in the maximum of 2.32 mSvGy-1 at the same depth. Neutron dose at 10 MV was measured by using TLDs on the phantom surface and depths of 1, 2, 2.5, 3.3, 4 and 5 cm. No photoneutron dose was observed at depths of less than 3.3cm and the maximum was at 4cm equal to 5.44mSvGy-1, however, the calculated data showed the maximum of 0.077mSvGy-1 at the same depth. The comparison between measured photo neutron dose and calculated data along the beam axis in different depths, shows that the measurement data were much more than the calculated data, so it seems that TLD600 and TLD700 pairs are not suitable dosimeters for neutron dosimetry in linac central axis due to high photon flux, whereas MCNPX Monte Carlo techniques still remain a valuable tool for photonuclear dose studies.

EXTREME RISK ASSESSMENT METHODOLOGY (ERAM) IN AVIATION SYSTEMS

2015 ◽  
Vol 14 (6) ◽  
pp. 1399-1408 ◽  
Author(s):  
Catalin Cioaca ◽  
Cristian-George Constantinescu ◽  
Mircea Boscoianu ◽  
Ramona Lile
Keyword(s):  
Risk Assessment ◽  
Assessment Methodology ◽  
Extreme Risk ◽  
Risk Assessment Methodology

ASSESSMENT METHODOLOGY FOR NON-COMPLIANT LANDFILLS

2013 ◽  
Vol 12 (2) ◽  
pp. 387-391
Author(s):  
Michaela Bianca Vac Soporan ◽  
Vasile Filip Soporan ◽  
Gheorghe Batrinescu ◽  
Emanuela Cocis
Keyword(s):  
Assessment Methodology
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