Engineered Components for Spent Fuel Radioactive Waste Isolation Systems—are They Technically Justified?

1981 ◽  
Vol 11 ◽  
Author(s):  
H. C. Burkholder
Keyword(s):  
United States ◽  
Radioactive Waste ◽  
Release Rate ◽  
The United States ◽  
Radioactive Waste Disposal ◽  
Radionuclide Transport ◽  
Spent Fuel ◽  
Isolation System ◽  
Waste Forms ◽  
Isolation Systems

In response to draft radioactive waste disposal standards, R&D programs have been initiated in the United States which are aimed at developing and ultimately using radionuclide transport-delaying (e.g., long-lived waste containers) and radionuclide transport-controlling (e.g., very low release rate waste forms) engineered components as part of the isolation system. Before these programs proceed significantly, it seems prudent to evaluate the technical justification for development and use of sophisticated engineered components in radioactive waste isolation.

An Overview of US EPA’s Current Radioactive Waste Management and General Radiation Protection Efforts

2009 ◽  
Author(s):  
R. Thomas Peake ◽  
Daniel Schultheisz ◽  
Loren W. Setlow ◽  
Brian Littleton ◽  
Reid Rosnick ◽  
...  
Keyword(s):  
United States ◽  
Radioactive Waste ◽  
Radiation Protection ◽  
Nuclear Power ◽  
Fuel Cycle ◽  
The United States ◽  
Uranium Mining ◽  
Radioactive Waste Disposal ◽  
Environmental Standards

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.

Detecting Sources of Ionizing Radiation in the Waste Stream

2002 ◽  
Author(s):  
Michael Needham
Keyword(s):  
United States ◽  
Ionizing Radiation ◽  
Radioactive Waste ◽  
Solid Waste ◽  
Negative Impact ◽  
Industrial Process ◽  
Control Program ◽  
The United States ◽  
Radioactive Waste Disposal ◽  
Radioactive Material

Why is the detection of radioactive sources important to the solid waste industry?: Radioactive material is used extensively in the United States in research, medicine, education, and industry for the benefit of society (e.g. smoke detectors, industrial process gauges, medical diagnosis/treatment). Generally speaking, the Nuclear Regulatory Commission and state governments regulate the use and disposal of radioactive materials. Licensed radioactive waste disposal facilities receive the bulk of the waste generated in the United States with exceptions for low-level waste (e.g. medical patient waste) that may be disposed of as municipal waste. According to the Conference of Radiation Control Program Directors, Inc (CRCPD)., there has been an increasing number of incidence involving the detection of prohibited radioactive wastes at solid waste management facilities. While the CRCPD acknowledges that the increased incidence may be partially attributed to the growing number of solid waste facilities that have detection systems, undetected sources of ionizing radiation can harm the environment, have a negative impact on employee health and safety, and result in significant remedial actions. Implementing an effective detection/response plan can aid in the proper management of radioactive waste and serve to minimize the potential for negative outcomes.

Localized Corrosion and Stress Corrosion Cracking of Candidate Materials for High-Level Radioactive Waste Disposal Containers in U.S.: A Critical Literature Review

1988 ◽  
Vol 127 ◽  
Author(s):  
Joseph C. Farmer ◽  
R. Daniel McCright
Keyword(s):  
Radioactive Waste ◽  
The United States ◽  
Radioactive Waste Disposal ◽  
Localized Corrosion ◽  
Spent Fuel ◽  
High Level Radioactive Waste ◽  
Fuel Assemblies ◽  
Austenitic Alloys ◽  
High Level ◽  
Critical Literature

ABSTRACTThree iron-based to nickel-based austenitic alloys and three copper-based alloys are being considered in the United States of America as candidate materials for the fabrication of high-level radioactive waste containers. The austenitic alloys are Types 304L and 316L stainless steels as well as the high-nickel material Alloy 825. The copper-based alloys are CDA 102 (oxygen-free copper), CDA 613 (Cu-7A1), and CDA 715 (Cu-3ONi). Waste in the forms of spent fuel assemblies from reactors and borosilicate glass will be sent to a proposed repository at Yucca Mountain, Nevada. The decay of radionuclides will result in the generation of substantial heat and in gamma radiation.

The Influence of Isolator Hysteresis on Equipment Performance in Seismic Isolated Buildings

2010 ◽  
Vol 26 (1) ◽  
pp. 275-293 ◽  
Author(s):  
T. Y. Yang ◽  
Dimitrios Konstantinidis ◽  
James M. Kelly
Keyword(s):  
United States ◽  
Seismic Isolation ◽  
The United States ◽  
Large Displacements ◽  
Isolation System ◽  
Seismic Input ◽  
Alternative Approach ◽  
Moderate Earthquake ◽  
Time Histories ◽  
Isolation Systems

The seismic isolation code which must be used for all seismic isolated buildings in the United States is conservative in many of its provisions. While seismic isolation is flourishing in other countries, it is underused in the United States. For static analysis and for the selection of time histories, the spectrum is constant-velocity for periods of one second and longer, leading to large displacements for long period systems and forcing the designer to use added damping to reduce these displacements. The damping systems used are hysteretic with the characteristic that damping decreases with increasing displacement. To achieve the damping needed to reduce these large displacements, expected from very rare seismic input, means that at smaller displacements, caused by realistic levels of seismic input, the damping will be very much higher, and there may be stiffening of the isolation system, meaning that the building may not act as isolated and there may be an impact on sensitive internal equipment. This paper shows how highly damped isolation systems are counterproductive to isolation and suggests an alternative approach that will conform to code requirements but ensure that, at moderate earthquake inputs, the equipment remains protected, and the large code-mandated displacements are kept to acceptable levels.

Sign in / Sign up

Export Citation Format

Share Document