US NRC discussion of options to revise radiation protection recommendations

2012 ◽  
Vol 41 (3-4) ◽  
pp. 313-317
Author(s):  
D.A. Cool
Keyword(s):  
Radiation Protection ◽  
Nuclear Regulatory Commission ◽  
Radiological Protection ◽  
Policy Paper ◽  
Occupational Dose ◽  
Wide Range ◽  
Other Information ◽  
Dose Limits ◽  
Key Issues ◽  
Regulatory Commission

The Nuclear Regulatory Commission (NRC) is continuing the process of engaging stakeholders on issues associated with possible changes to the radiation protection regulations contained in 10 CFR Part 20, and other parts of the NRC regulations, to increase alignment with international recommendations. The Commission is particularly seeking to explore implications, as appropriate and where scientifically justified, of greater alignment with the 2007 Recommendations of the International Commission for Radiological Protection. Other information from national and international sources is also being considered. Given that the NRC regulations provide adequate protection, the discussion has been focusing on discerning the benefits and burdens associated with revising the radiation protection regulatory framework. NRC, through three Federal Register Notices, has officially solicited comments on a series of key issues, and has conducted a series of facilitated workshops to encourage feedback from a wide range of stakeholders. The issues include the use of updated scientific methodologies and terminology, the occupational dose limits, and the use of the concepts of constraints in optimisation. NRC staff provided a policy paper with recommendations to the Commission on April 25, 2012 (NRC, 2012).

Operational Readiness of the ES-3100 Type B Shipping Container for Fissile Materials

2009 ◽  
Author(s):  
Jeffrey G. Arbital ◽  
Kenneth E. Sanders
Keyword(s):  
Competent Authority ◽  
Nuclear Regulatory Commission ◽  
Lessons Learned ◽  
Department Of Energy ◽  
Radioactive Material ◽  
Fissile Material ◽  
Shipping Container ◽  
Other Information ◽  
Enriched Uranium ◽  
Regulatory Commission

The U. S. Department of Transportation (DOT) Specification 6M containers had been the workhorse bulk Highly Enriched Uranium (HEU) shipping containers for the U. S. Department of Energy (DOE) and many other shippers for over 20 years. This DOT specification container was terminated for shipment of radioactive material on September 30, 2008. The anticipation of this action prompted DOE to develop and implement the ES-3100 shipping container as a replacement for the 6M. The ES-3100 was first licensed in April 2006. Since then, the license has been revised nine times. The ES-3100 was operationally ready for use at several sites by September 2007, and is now in being used on a regular basis for materials that had been shipped in the DOT 6M. The ES-3100 has also been certified for air transport, in support of foreign research reactor fuel supply and international nonproliferation efforts. This container has a Certificate of Compliance (CoC) from the U. S. Nuclear Regulatory Commission (NRC) and a Competent Authority Certificate from the DOT. The utility of the ES-3100 continues to grow. The ES-3100 CoC allows many forms of fissile material to be shipped, and continues to be amended to authorize additional contents for a variety of shippers. This paper will identify the currently certified contents for the ES-3100 and the planned certificate amendments to expand the content basis, as well as the approach to add new contents to the CoC. The path to becoming a user of the ES-3100 will be outlined. Operational requirements for this container, handling tools and non-standard operating tools needed for the use of this container will be covered. Readiness requirements, maintenance issues, training, and lessons learned will also be discussed. This paper will provide the information necessary for organizations to obtain ES-3100 containers, the special tools, adequate training, and any other information that would be helpful for a site to be able to use this fissile, radioactive material shipping container system.

Effective dose: a radiation protection quantity

2012 ◽  
Vol 41 (3-4) ◽  
pp. 117-123 ◽  
Author(s):  
H-G. Menzel ◽  
J. Harrison
Keyword(s):  
Effective Dose ◽  
Radiation Protection ◽  
Scientific Information ◽  
Scientific Data ◽  
Whole Body ◽  
Practical Implementation ◽  
Radiological Protection ◽  
Stochastic Effects ◽  
Weighting Factors ◽  
Dose Limits

Modern radiation protection is based on the principles of justification, limitation, and optimisation. Assessment of radiation risks for individuals or groups of individuals is, however, not a primary objective of radiological protection. The implementation of the principles of limitation and optimisation requires an appropriate quantification of radiation exposure. The International Commission on Radiological Protection (ICRP) has introduced effective dose as the principal radiological protection quantity to be used for setting and controlling dose limits for stochastic effects in the regulatory context, and for the practical implementation of the optimisation principle. Effective dose is the tissue weighted sum of radiation weighted organ and tissue doses of a reference person from exposure to external irradiations and internal emitters. The specific normalised values of tissue weighting factors are defined by ICRP for individual tissues, and used as an approximate age- and sex-averaged representation of the relative contribution of each tissue to the radiation detriment of stochastic effects from whole-body low-linear energy transfer irradiations. The rounded values of tissue and radiation weighting factors are chosen by ICRP on the basis of available scientific data from radiation epidemiology and radiation biology, and they are therefore subject to adjustment as new scientific information becomes available. Effective dose is a single, risk-related dosimetric quantity, used prospectively for planning and optimisation purposes, and retrospectively for demonstrating compliance with dose limits and constraints. In practical radiation protection, it has proven to be extremely useful.

Verification of New Capabilities of Deterministic Load Module of FAVOR 09.1

2010 ◽  
Author(s):  
Shengjun Yin ◽  
Terry L. Dickson ◽  
Paul T. Williams ◽  
B. Richard Bass
Keyword(s):  
Computational Study ◽  
National Laboratory ◽  
Nuclear Regulatory Commission ◽  
Pressurized Water ◽  
Oak Ridge ◽  
Problem Class ◽  
Wide Range ◽  
Significant Generalization ◽  
Water Reactors ◽  
Regulatory Commission

This paper describes a computational study conducted by the Probabilistic Pressure Boundary Integrity Safety Assessment (PISA) program at Oak Ridge National Laboratory (ORNL) in support of the Nuclear Regulatory Commission (NRC) sponsored verification of the new capabilities of the latest version of Fracture Analysis of Vessels – Oak Ridge (FAVOR) 09.1. The v09.1 version of FAVOR represents a significant generalization over previous versions, because the problem class for FAVOR has been extended to encompass a broader range of transients and vessel geometries. FAVOR, v09.1, provides the capability to perform both deterministic and risk-informed fracture analyses of boiling water reactors (BWRs) as well as pressurized water reactors (PWRs) subjected to heat-up and cool-down transients. In this study, deterministic solutions generated with the FAVOR v09.1 code for a wide range of representative internal/external surface-breaking flaws and embedded flaws subjected to selected thermal-hydraulic transients were benchmarked with the solutions obtained from ABAQUS (version 6.9-1) for the same transients. Based on the benchmarking analyses, it is concluded that the deterministic module implemented into FAVOR, v09.1, satisfies the criteria described in the FAVOR software design documentation.

Radiation Safety

2018 ◽  
Author(s):  
Erin M. Maddy ◽  
Kevin Abnet ◽  
Geoffrey Scriver ◽  
Mrinal Shukla
Keyword(s):  
Best Practices ◽  
Radiation Protection ◽  
Human Body ◽  
Radiation Safety ◽  
Radiological Protection ◽  
Surgical Practice ◽  
Anesthesia Practice ◽  
Dose Limits ◽  
Effects Of Radiation

Exposure to ionizing radiation is increasing in modern anesthesia practice, due to both the number of procedures facilitated and the expanding role of imaging in surgical practice. International Commission on Radiological Protection (ICRP) recommends that physicians who assist with radiation procedures be educated on the basics of radiation including units, effects of radiation exposure, and radiation protection for both providers and patients. This chapter will mirror the recommendations of the ICRP and include an introduction to radiation production, terminology, units, effects on the human body, dose limits, best practices for radiation protection, and safety infrastructure.

scholarly journals Applied Demography In Action: A Case Study of “Population Identification.”

2008 ◽  
Vol 35 (1) ◽  
pp. 133 ◽  
Author(s):  
David A. Swanson
Keyword(s):  
Nuclear Regulatory Commission ◽  
Nuclear Waste Repository ◽  
Graduate Studies ◽  
Wide Range ◽  
The Us ◽  
High Level Nuclear Waste ◽  
Regulatory Commission ◽  
High Level

This case study deals with a problem quite different than the typical one facing most applied demographers. It involves the identification of a “population” using a set of criteria established by a regulatory agency. Specifically, criteria established by the US Nuclear Regulatory Commission for purposes of Site Characterization of the High Level Nuclear Waste Repository proposed for Yucca Mountain, Nevada. Consistent with other recent studies, this one suggests that a wide range of skills may be needed in dealing with problems posed to applied demographers by clients and users in the 21st century. As such, budding applied demographers, especially those nearing completion of their graduate studies, should consider adopting a set of skills beyond traditional demography.

EVALUATION OF OCCUPATIONAL RADIATION EXPOSURE IN A RADIO-DIAGNOSTIC FACILITY IN KATSINA- NIGERIA

2020 ◽  
Vol 4 (2) ◽  
pp. 722-729
Author(s):  
Usman Sani ◽  
Bashir Gide Muhammad ◽  
Dimas Skam Joseph ◽  
D. Z. Joseph
Keyword(s):  
Radiation Dose ◽  
Radiation Exposure ◽  
Short Exposure ◽  
Skin Dose ◽  
Continuous Training ◽  
Short Exposure Time ◽  
Occupational Dose ◽  
Dose Limits ◽  
Radiation Workers ◽  
Occupational Radiation

Poor implementation of quality assurance programs in the radiation industry has been a major setback in our locality. Several studies revealed that occupational workers are exposed to many potential hazards of ionizing radiation during radio-diagnostic procedures, yet radiation workers are often not monitored. This study aims to evaluate the occupational exposure of the radiation workers in Federal Medical Centre Katsina, and to compare the exposure with recommended occupational radiation dose limits. The quarterly readings of 20 thermo-luminescent dosimeters (TLDs') used by the radiation workers from January to December, 2019 were collected from the facility's radiation monitoring archive, and subsequently assessed and analyzed. The results indicate that the average annual equivalent dose per occupational worker range from 0.74 to 1.20 mSv and 1.28 to 2.21 mSv for skin surface and deep skin dose, measured at 10 mm and 0.07 mm tissue depth respectively. The occupational dose was within the recommended national and international limits of 5 mSv per annum or an average of 20 mSv in 5 years. Therefore, there was no significant radiation exposure to all the occupational workers in the study area. Though, the occupational radiation dose is within recommended limit, this does not eliminate stochastic effect of radiation. The study recommended that the occupational workers should adhere and strictly comply with the principles of radiation protection which includes distance, short exposure time, shielding and proper monitoring of dose limits. Furthermore, continuous training of the radiation workers is advised.

MINIMIZING THE EXPOSURE TO THE EYE LENS OF RADIOLOGIC TECHNOLOGISTS ASSISTING PATIENTS DURING CHEST X RAYS: A PHANTOM STUDY

2021 ◽  
Vol 193 (1) ◽  
pp. 43-54
Author(s):  
Yasuda Mitsuyoshi ◽  
Funada Tomoya ◽  
Sato Hisaya ◽  
Kato Kyoichi
Keyword(s):  
Radiation Protection ◽  
Phantom Study ◽  
International Commission ◽  
Eye Lens ◽  
Radiological Protection ◽  
X Rays ◽  
Radiologic Technologists ◽  
Maximum Reduction ◽  
The Right

Abstract As chest x rays involve risks of patients falling, radiologic technologists (technologists) commonly assist patients, and as the assistance takes place near the patients, the eye lenses of the technologists are exposed to radiation. The recommendations of the International Commission on Radiological Protection suggest that the risk of developing cataracts due to lens exposure is high, and this makes it necessary to reduce and minimize the exposure. The present study investigated the positions of technologists assisting patients that will minimize exposure of the eye lens to radiation. The results showed that it is possible to reduce the exposure by assisting from the following positions: 50% at the sides rather than diagonally behind, 10% at the right side of the patient rather than the left and 40% at 250 mm away from the patient. The maximum reduction with radiation protection glasses was 54% with 0.07 mmPb and 72% with 0.88 mmPb.

scholarly journals Analysis of the Technological Evolution of Materials Requirements Included in Reactor Pressure Vessel Manufacturing Codes

2021 ◽  
Vol 13 (10) ◽  
pp. 5498
Author(s):  
Alvaro Rodríguez-Prieto ◽  
Mariaenrica Frigione ◽  
John Kickhofel ◽  
Ana M. Camacho
Keyword(s):  
Sustainable Development ◽  
Pressure Vessel ◽  
Nuclear Regulatory Commission ◽  
Green Energy ◽  
Reactor Pressure Vessel ◽  
Technical Literature ◽  
Pressurized Water ◽  
Water Reactors ◽  
Regulatory Commission ◽  
Reactor Pressure

The growth of green energy technologies within the frame of the 7th Sustainable Development Goal (SDG) along with the concern about climatic changes make nuclear energy an attractive choice for many countries to ensure energy security and sustainable development as well as to actively address environmental issues. Unlike nuclear equipment (immovable goods), which are often well-catalogued and analyzed, the design and manufacturing codes and their standardized materials specifications can be considered movable and intangible goods that have not been thoroughly studied based on a detailed evaluation of the scientific and technical literature on the reactor pressure vessel (RPV) materials behavior. The aim of this work is the analysis of historical advances in materials properties research and associated standardized design codes requirements. The analysis, based on the consolidated U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.99 Rev.2 model, enables determination of the best materials options, corresponding to some of the most widely used material specifications such as WWER 15Kh2MFAA (used from the 1970s and 1980s; already in operation), ASME SA-533 Grade B Cl.1 (used in pressurized water reactor-PWR 2nd–4th; already in operation), DIN 20MnMoNi55 and DIN 22NiMoCr37 (used in PWR 2nd–4th) as well as ASTM A-336 Grade F22V (current designs). Consequently, in view of the results obtained, it can be concluded that the best options correspond to recently developed or well-established specifications used in the design of pressurized water reactors. These assessments endorse the fact that nuclear technology is continually improving, with safety being its fundamental pillar. In the future, further research related to the technical heritage from the evolution of materials requirements for other clean and sustainable power generation technologies will be performed.

scholarly journals Molecular survey of vector-borne diseases in two groups of domestic dogs from Lisbon, Portugal

2021 ◽  
Vol 14 (1) ◽  
Author(s):  
Ana Mafalda Dordio ◽  
Relja Beck ◽  
Telmo Nunes ◽  
Isabel Pereira da Fonseca ◽  
Jacinto Gomes
Keyword(s):  
Clinical Status ◽  
Molecular Methods ◽  
Hepatozoon Canis ◽  
Clinical Approach ◽  
Limited Information ◽  
Vector Borne Diseases ◽  
Wide Range ◽  
Other Information ◽  
Southern Portugal ◽  
Vector Borne

Abstract Background Canine vector-borne diseases (CVBDs) are caused by a wide range of pathogens transmitted by arthropods. They have been an issue of growing importance in recent years; however, there is limited information about the vector-borne pathogens circulating in Portugal. The aim of the present study was to detect canine vector-borne bacteria and protozoa of veterinary and zoonotic importance using molecular methods. Methods One hundred and forty-two dogs from Lisbon, southern Portugal, were tested: 48 dogs from a veterinary hospital clinically suspected of vector-borne diseases and 94 apparently healthy dogs from shelters. Anaplasma spp./Ehrlichia spp., Babesia/Theileria spp., Hepatozoon spp., and Mycoplasma spp. infections were detected by PCR from blood samples and examined under light microscopy. Other information including clinical status and diagnostic test results were collected for each animal. Results Infections were detected by PCR in 48 (33.80%) dogs. Single infections were found in 35 dogs (24.64%), and co-infections were found in 13 (9.15%) dogs. Twenty-nine (20.42%) dogs were positive for Hepatozoon spp., 15 (10.56%) for Mycoplasma spp., 11 (7.75%) for Anaplasma spp./Ehrlichia spp., and six (4.21%) for Babesia spp. DNA sequencing was used to identify Babesia vogeli (2.81%), Babesia canis (1.40%), Hepatozoon canis (20.42%), Mycoplasma haematoparvum (2.11%), Mycoplasma haemocanis (8.45%), Anaplasma platys (7.04%), and Ehrlichia canis (0.70%). Conclusions This is the first molecular identification of B. canis and M. haematoparvum in dogs from southern Portugal. This study highlights the importance of molecular methods to identify CVBD pathogens in endemic areas and helps to guide the clinical approach of veterinarians in practice.

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