Ecological radiation protection criteria for nuclear power

Atomic Energy ◽  
1993 ◽  
Vol 74 (4) ◽  
pp. 300-306 ◽  
Author(s):  
I. I. Kryshev
Author(s):  
Liming Huang ◽  
Shouhai Yang ◽  
Jie Liu

Radiation safety is an important part of safety assessment of spent fuel dry storage technology. This paper describes the radiation protection design of PWR spent fuel dry storage facility for radiation safety completed by China General Nuclear Power Corporation. Considering the special site conditions, Monte Carlo method is used to complete the precise calculation of the three-dimensional radiation dose field in the spent fuel storage building. Through the spent fuel storage module and the storage building with shielding function, radiation shielding design is completed to meet China’s regulatory requirements, which ensures radiation safety for workers and the public during the transport and storage of spent fuel. It will provide a reference for construction of spent fuel dry storage facility of CPR1000 and HPR1000.


Author(s):  
R. Thomas Peake ◽  
Daniel Schultheisz ◽  
Loren W. Setlow ◽  
Brian Littleton ◽  
Reid Rosnick ◽  
...  

The United States Environmental Protection Agency’s (EPA) Radiation Protection Division is the portion of EPA (or the Agency) that develops environmental standards for radioactive waste disposal in the United States. One current issue of concern is the disposal of low activity radioactive waste (LAW), including wastes that would be produced by a radiological dispersal device (RDD), for which current disposal options may be either inconsistent with the hazard presented by the material or logistically problematic. Another major issue is related to the resurgence in uranium mining. Over the past several years, demand for uranium for nuclear power plant fuel has increased as has the price. The increase in price has made uranium mining potentially profitable in the US. EPA is reviewing its relevant regulations, developed primarily in the 1980s, for potential revisions. For example, in-situ leaching (also known as in-situ recovery) is now the technology of choice where applicable, yet our current environmental standards are focused on conventional uranium milling. EPA has two actions in process, one related to the Clean Air Act, the other related to revising the environmental standards that implement the Uranium Mill Tailings Radiation Control Act of 1978 (UMTRCA). Separately, but related, EPA has developed over the last several years uranium mining documents that address technologically enhanced natural occurring radioactive materials (TENORM) from abandoned uranium mines, and wastes generated by active uranium extraction facilities. Lastly, in 1977 EPA developed environmental standards that address nuclear energy, fuel fabrication, reprocessing, and other aspects of the uranium fuel cycle. In light of the increased interest in nuclear power and the potential implementation of advanced fuel cycle technologies, the Agency is now reviewing the standards to determine their continued applicability for the twenty-first century.


Author(s):  
William H. Miller ◽  
David Jonassen ◽  
Rose Marra ◽  
Matthew Schmidt ◽  
Matthew Easter ◽  
...  

The U.S. Department of Labor awarded a $2.3 million grant to the University of Missouri-Columbia (MU) in 2006 in response to the need for well-trained Radiation Protection Technicians (RPTs). The RPT curriculum initiative resulted from significant collaborations facilitated by MU with community colleges, nuclear power plants, professional organizations, and other nuclear industry stakeholders. The objective of the DOL project is to help increase the pool of well-qualified RPTs to enter the nuclear workforce. Our work is designed to address the nuclear industry’s well-documented, increasingly significant need for RPTs. In response to this need, MU and AmerenUE’s Callaway Nuclear Power Plant first partnered with Linn State Technical College’s Advanced Technology Center (LSTC/ATC) to initiate a two-year RPT degree program. The success of this program (enrollments have been increasing over the past four years to a Fall 2007 enrollment of 23) enabled the successful proposal to the DOL to expand this program nationwide. DOL participants include the following partners: Linn State Technical College with AmerenUE – Callaway; Central Virginia Community College with AREVA; Estrella Mountain Community College with Arizona Public Service – Palo Verde; MiraCosta Community College with Southern California Edison – San Onofre; and Hill College with Texas Utilities – Comanche Peak. The new DOL grant has allowed redevelopment of the LSTC/ATC curriculum using a web-based, scenario driven format, benchmarked against industry training standards. This curriculum will be disseminated to all partners. Integral in this curriculum is a paid, three to four month internship at a nuclear facility. Two of the six new RPT courses have been developed as of the end of 2007. Four of five partner schools are accepting students into this new program starting in the winter 2008 term. We expect that these institutions will graduate 100 new RPTs per year to help alleviate the personnel shortage in this critical area of need.


2006 ◽  
Vol 48 (4) ◽  
pp. 820-851 ◽  
Author(s):  
Joy Parr

Radiation is a workplace hazard that eludes the sensing body, or seems to. After Chernobyl and Three Mile Island, Kai Erickson described radiation as “an invisible threat,” “the very embodiment of stealth and treachery.” The first generation of Canadian nuclear power workers, from their four decades of experience around reactors has a different sense of the matter. They describe a physical awareness of the morphology and topography of radiation, a cultivated bodily knowledge that informed their actions as they produced power. They describe a “feel and a touch for the plant,” framed in theoretical studies, made through attentiveness and alert expectation, honed by being out and about in the station, being its intimate, “listening to its very cries.” By their telling, “doesn't feel right” ceased to be a metaphor about their workplace circumstance, and through study and practice, became a bodily effect, a report from the somatic. Key to work safety for Canadian nuclear workers were close study of the theory of ionizing radiation, adeptness with both the instruments which made radiation apparent and the calculations that made the readings on dials into qualitatively and spatially distinctive workplace presences, and skill in choosing, donning, building, and removing physical barriers between their bodies and radiation fields. Through this knowledge and practice, Canadian nuclear workers came to embody the hazards of the job. This working knowledge of the insensible enabled them to be responsible for their own radiation protection and for the safety of those with whom they worked.


2016 ◽  
Vol 45 (2_suppl) ◽  
pp. 23-32 ◽  
Author(s):  
M. Miyazaki

Many initiatives to measure the internal and external exposures of the residents of Fukushima have been undertaken since the accident at Fukushima Daiichi nuclear power plant. However, residents have had few, if any, opportunities for face-to-face explanations to understand the meaning of such measurements. Although the personal data of tens of thousands of residents were collected, these data were not analysed adequately, and were therefore not used to implement large-scale programmes to manage/reduce exposures. One of the lessons learned from the Fukushima accident is that it is imperative for the government to implement these measures for radiation protection, and to build an effective functioning service for the residents. The author, as a physician from the region, has worked as an explainer/interpreter of exposure dose measurements to individual residents. Another lesson learned from this experience is that local medical and health professionals can contribute to building a public system for radiation protection, by acting as ‘liaising officers’ to connect residents, the authorities, and experts from outside the region. This paper describes the author’s experience and lessons learned in the hope that this information will be useful in the event of a future accident.


Author(s):  
Claude Faidy

On December 2005, the French regulator issued a new regulation for French nuclear power plants, in particular for pressure equipment (PE). This regulation need first to agree with non-nuclear PE regulation and add to that some specific requirements, in particular radiation protection requirements. Different advantages are in these proposal, it’s more qualitative risk oriented and it’s an important link with non-nuclear industry. Only few components are nuclear specific. But, the general philosophy of the existing Codes (RCC-M, KTA or ASME) have to be improved. For foreign Codes, it’s plan to define the differences in the user specifications. In parallel to that, a new safety classification has been developed by French utility. The consequences is the need to cross all these specifications to define a minimum quality level for each components or systems. In the same time a new concept has been developed to replace the well known “Leak Before Break methodology” by the “Break Exclusion” methodology. This paper will summarize the key aspects of these different topics and regularly compare with ASME practices.


Atomic Energy ◽  
2008 ◽  
Vol 105 (2) ◽  
pp. 90-98
Author(s):  
A. P. Pyshko ◽  
A. Yu. Plotnikov ◽  
A. V. Son’ko

2021 ◽  
Vol 1 ◽  
pp. 31-31
Author(s):  
Roman Winter ◽  
Bernd Flemisch ◽  
Holger Class ◽  
Rainer Merk

Abstract. When nuclear power plants are dismantled, only a small portion is heavily contaminated with radioactivity and must be stored in a repository. The remaining material, mainly concrete rubble (construction waste), is decontaminated if necessary and can be stored in conventional surface landfills after clearance. The focus of this work is on the modelling of such landfills and the radioactive substances during raining events. The influence of the heterogeneous nature of the construction rubble should also be investigated. The simulation environment DuMux, mainly developed by our institute, is used to compare different modelling approaches. It follows a previous work by Merk (2012). The research work is supported and accompanied by the Federal Office for Radiation Protection (BfS). Parts of the research initiatives of the BfS in the area of clearance of materials with negligible radioactivity are also presented.


Sign in / Sign up

Export Citation Format

Share Document