The Role of the Waste Isolation Pilot Plant in the Cleanup of the U.S. Nuclear Weapons Complex

2003 ◽  
Author(s):  
Lynne K. Smith ◽  
Mary L. Bisesi
Keyword(s):  
United States ◽  
Nuclear Weapons ◽  
Pilot Plant ◽  
The United States ◽  
Department Of Energy ◽  
United States Department ◽  
National Academy Of Sciences ◽  
Waste Isolation Pilot Plant ◽  
Term Operation ◽  
Transuranic Waste

As a result of nuclear weapons production, the United States of America produced significant quantities of transuranic waste, which consists of clothing, tools, rags, residues, debris and other items contaminated with small amounts of radioactive man-made elements — mostly plutonium — with an atomic number greater than that of uranium. Transuranic waste began accumulating in the 1940s and continued through the Cold War era. Today, most transuranic waste is stored at weapons production sites across the United States. In 1957, the National Academy of Sciences concluded that the most promising disposal option for radioactive wastes was disposal in deep geologic repositories situated in the salt formations. After nearly a decade of study, the United States Department of Energy decided in January 1981 to proceed with construction of the Waste Isolation Pilot Plant (WIPP) at a site 41.6 km (26 miles) southest of Carlsbad, New Mexico. After years of study, construction, and permitting, the WIPP facility became operational in early 1999. As the United States continues to clean up and close its former nuclear weapon facilities, the operation of WIPP will continue into the next several decades. This paper will provide on overview of the history, regulatory, and public process to permit a radioactive repository for disposal of transuranic wastes and the process to ensure its long-term operation in a safe and environmentally compliant manner.

Materials Interface Interactions Test (MIIT); in-Situ Testing of Simulated Hlw Forms in Salt- Performance of Srs Simulated Waste Glass After up to 5 Years of Burial at the Waste Isolation Pilot Plant (WIPP)

1991 ◽  
Vol 257 ◽  
Author(s):  
G.G. Wicks ◽  
A.R. Lodding ◽  
P.B. Macedo ◽  
D.E. Clark
Keyword(s):  
United States ◽  
Pilot Plant ◽  
Field Tests ◽  
Field Testing ◽  
The United States ◽  
Waste Glass ◽  
Department Of Energy ◽  
High Level Waste ◽  
Waste Isolation Pilot Plant ◽  
High Level

ABSTRACTThe first field tests conducted in the United States involving burial of simulated high-level waste [HLW] forms and package components, were started in July of 1986. The program, called the Materials Interface Interactions Test or MIIT, is the largest cooperative field-testing venture in the international waste management community. Included in the study are over 900 waste form samples comprising 15 different systems supplied by 7 countries. Also included are approximately 300 potential canister or overpack metal samples along with more than 500 geologic and backfill specimens. There are almost 2000 relevant interactions that characterize this effort which is being conducted in the bedded salt site at the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico. The MIIT program represents a joint endeavor managed by Sandia National Laboratories in Albuquerque, N.M., and Savannah River Laboratory in Aiken, S.C. and sponsored by the U.S. Department of Energy. Also involved in MIIT are participants from various laboratories and universities in France, Germany, Belgium, Canada, Japan, Sweden, the United Kingdom, and the United States. In July of 1991, the experimental portion of the 5-yr. MIIT program was completed. Although only about 5% of all MIIT samples have been assessed thus far, there are already interesting findings that have emerged. The present paper will discuss results obtained for SRS 165/TDS waste glass after burial of 6 mo., 1 yr. and 2 yrs., along with initial analyses of 5 yr. samples.

The Waste Isolation Pilot Plant: A Global Opportunity for Partnerships With a Purpose

2001 ◽  
Author(s):  
Inés R. Triay ◽  
Mark L. Matthews ◽  
Leif G. Eriksson ◽  
Frank D. Hansen
Keyword(s):  
United States ◽  
Pilot Plant ◽  
The United States ◽  
Department Of Energy ◽  
International Programs ◽  
Strategic Partnerships ◽  
Waste Isolation Pilot Plant ◽  
Deep Geological Disposal ◽  
Scientific Technical ◽  
Underground Research Laboratory

Abstract On March 26, 1999, the United States (U.S.) Department of Energy (DOE) Carlsbad Field Office (CBFO) opened the Waste Isolation Pilot Plant (WIPP) in New Mexico, United States of America (USA), for safe deep geological disposal of up to 175,584 cubic meters (m3) of long-lived radioactive wastes/materials (LLRMs). Twenty-four years of intensive, iterative interactions with scientific, environmental, public, institutional, political, and regulatory interest groups resolved all regulatory and legal challenges involved in bringing a deep geological repository for LLRMs to adequate scientific, technical, institutional, political, and public acceptance and fruition. International strategic partnerships and research and development (R&D) collaborations are cornerstones in both past and current strategies designed to timely, cost-effectively, and safely accomplish the CBFO mission. The primary objectives of the CBFO’s international programs are to: 1. Acquire information supporting the CBFO mission. 2. Present and share CBFO mission information, expertise, and facilities of potential interest and/or value to other radioactive waste management and disposal programs, including using the WIPP underground research laboratory (URL) for joint R&D and training.

Tracheobronchial Calcification in Members of a Fixed Population Sample

1989 ◽  
Vol 30 (3) ◽  
pp. 277-280 ◽  
Author(s):  
T. Fukuya ◽  
F. Mihara ◽  
S. Kudo ◽  
W. J. Russell ◽  
R. R. DeLongchamp ◽  
...  
Keyword(s):  
United States ◽  
Radiation Effects ◽  
Atomic Bomb ◽  
Population Sample ◽  
The United States ◽  
Department Of Energy ◽  
United States Department ◽  
National Academy Of Sciences ◽  
The Government ◽  
Fixed Population

The Radiation Effects Research Foundation (formerly, Atomic Bomb Casualty Commission; ABCC) was established in April 1975 as a private non-profit Japanese Foundation, supported equally by the Government of Japan through the Ministry of Health and Welfare, and the Government of the United States through the National Academy of Sciences under contract with the United States Department of Energy. Accepted 4 December 1988. In a review of the chest radiographs of 1 152 consecutively examined subjects, 10 cases (0.87%) of extensive tracheobronchial calcification were identified. In addition, 51 subjects having this coded diagnosis were identified among 11758 members of a fixed population sample. Sixty of these 61 subjects were women. Tracheobronchial calcification usually appeared after the age of 60. The subjects' clinical and other radiologic diagnoses were reviewed and tracheobronchial calcification appeared to have no clinical significance. Histologic findings in autopsied cases showed the calcifications and ossificiations to be in the cartilaginous rings themselves. However, the reason for the overwhelming prevalence of this entity in women remains to be resolved.

Cleaning Up the Legacy: Opening and Operating the Waste Isolation Pilot Plant

2001 ◽  
Author(s):  
Lynne K. Smith ◽  
Kathleen K. Clodfelter
Keyword(s):  
Pilot Plant ◽  
The United States ◽  
National Academy Of Sciences ◽  
Waste Isolation Pilot Plant ◽  
Term Operation ◽  
Disposal Option ◽  
Environmentally Sound ◽  
Academy Of Sciences ◽  
Transuranic Wastes

Abstract In 1957, the National Academy of Sciences concluded that the most promising disposal option for radioactive wastes was burial in deep geologic repositories situated in salt formations. In 1981, after decades of study, the United States initiated construction of the Waste Isolation Pilot Plant (WIPP) at a desert site 41.6 km (26 miles) southeast of Carlsbad, New Mexico. This paper provides an overview of the history and the regulatory and public process to permit a repository for disposal of transuranic wastes. In addition, the process to ensure its long-term operation in a safe and environmentally sound manner will also be discussed.

Lessons Learned at the Waste Isolation Pilot Plant: Share, Listen, and Learn to Earn Stakeholder Acceptance

2001 ◽  
Author(s):  
Leif G. Eriksson
Keyword(s):  
United States ◽  
Pilot Plant ◽  
Role Model ◽  
The United States ◽  
Lessons Learned ◽  
Department Of Energy ◽  
Host Community ◽  
Deep Geological Repository ◽  
Waste Isolation Pilot Plant ◽  
Geological Repository

Abstract On March 26, 1999, the United States (U.S.) Department of Energy (DOE) opened the nation’s first deep geological disposal system (repository) for long-lived radioactive wastes/materials (LLRMs) at the Waste Isolation Pilot Plant (WIPP) site, New Mexico, United States of America (USA). The opening of WIPP embodies gradually achieved acceptance, both local and global, on scientific, institutional, regulatory, political, and public levels. In the opinion of the author, five significant determinants for the successful siting, certification, and acceptance of WIPP, were the existence of: • A willing and supportive host community; • A strong, independent regulator; • A regulatory framework widely perceived to (over)protect public health and the environment; • A structurally simple, old, stable, host-rock with excellent radionuclide containment and isolation characteristics; and • An open siting, site characterization, repository development, certification and recertification process with regularly scheduled opportunities for information exchanges with affected and interested parties, including a) prompt responses to non-DOE concerns and b) transparency/traceability of external-input into, and the logic behind, the DOE’s decision-making process. The nation’s and the world’s next deep geological repository for LLRMs is currently scheduled to open in 2010. As follows, in addition to providing a national solution to safe disposal of LLRMs, the opening and continued safe operation of WIPP provides an international role model that effectively dispels the global myth that LLRMs cannot be safely disposed in a deep geological repository.

The AGT101 Advanced Automotive Gas Turbine

1982 ◽  
Author(s):  
R. A. Rackley ◽  
J. R. Kidwell
Keyword(s):  
United States ◽  
Gas Turbine ◽  
The United States ◽  
Gas Turbine Engine ◽  
Development Project ◽  
Single Stage ◽  
Department Of Energy ◽  
Inlet Temperature ◽  
United States Department ◽  
Turbine Engine

The Garrett/Ford Advanced Gas Turbine Powertrain System Development Project, authorized under NASA Contract DEN3-167, is sponsored by and is part of the United States Department of Energy Gas Turbine Highway Vehicle System Program. Program effort is oriented at providing the United States automotive industry the technology base necessary to produce gas turbine powertrains competitive for automotive applications having: (1) reduced fuel consumption, (2) multi-fuel capability, and (3) low emissions. The AGT101 powertrain is a 74.6 kW (100 hp), regenerated single-shaft gas turbine engine operating at a maximum turbine inlet temperature of 1644 K (2500 °F), coupled to a split differential gearbox and Ford automatic overdrive production transmission. The gas turbine engine has a single-stage centrifugal compressor and a single-stage radial inflow turbine mounted on a common shaft. Maximum rotor speed is 10,472 rad/sec (100,000 rpm). All high-temperature components, including the turbine rotor, are ceramic. AGT101 powertrain development has been initiated, with testing completed on many aerothermodynamic components in dedicated test rigs and start of Mod I, Build 1 engine testing.

Performance Goal-Based Seismic Design Standards for Critical Facilities in the United States

2003 ◽  
Author(s):  
Quazi A. Hossain
Keyword(s):  
United States ◽  
Seismic Design ◽  
Functional Performance ◽  
Design Method ◽  
The United States ◽  
Department Of Energy ◽  
Performance Goals ◽  
United States Department ◽  
Active Member ◽  
Performance Goal

For more than the last fifteen years, the United States Department of Energy (DOE) has been using a probabilistic performance goal-based seismic design method for structures, systems, and components (SSCs) in its nuclear and hazardous facilities. Using a graded approach, the method permits the selection of probabilistic performance goals or acceptable failure rates for SSCs based on the severity level of SSC failure consequences. The method uses a site-specific probabilistic seismic hazard curve as the basic seismic input motion definition, but utilizes the existing national industry consensus design codes for specifying load combination and design acceptance criteria in such a way that the target probabilistic performance goals are met. Recently, the American Nuclear Society (ANS) and the American Society of Civil Engineers (ASCE) have undertaken the development of a number of national consensus standards that will utilize the performance goal-based seismic design experience base in the DOE complex. These standards are presently in various stages of development, some nearing completion. Once completed, these standards are likely to be adopted by various agencies and organizations in the United States. In addition to the graded approach of DOE’s method, these standards incorporate design provisions that permit seismic design of SSCs to several levels of functional performance. This flexibility of choosing a functional performance level in the design process results in an optimum, but risk-consistent design. The paper will provide an outline of two of these standards-in-progress and will present the author’s understanding of their basic philosophies and technical bases. Even though the author is an active member of the development committees for these two standards, the technical opinions expressed in this paper are author’s own, and does not reflect the views of any of the committees or the views of the organizations with which any member of the committees are affiliated.

Sign in / Sign up

Export Citation Format

Share Document