Updated Strategic Assessment of the U.S. NRC Low-Level Radioactive Waste (LLW) Program and the new WCS Commercial Disposal Facility for LLW

Energy Technology Data Exchange (ETDEWEB)

Kessel, David S.; Kim, Chang-Lak [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2015-05-15

The purpose of this paper is to review the updated NRC low level radioactive waste regulatory strategy and also present an update on a significant change in the LLW disposal landscape in the U.S., the opening of a new commercial disposal facility, the Texas Compact Waste Facility (CWF) in Andrews, Texas. Operational since spring of 2012, the CWF is owned and licensed by the state of Texas and operated by Waste Control Specialists LLC (WCS). The WCS facility in western Andrews County is the only commercial facility in the United States licensed to dispose of Class A, B and C LLW in the U.S. in the past 40 years. Based on the observation that other suitable sites have been identified such as the Clive, Utah site that meet (almost) all of these criteria it would appear that the first and last factors in our list are the most problematic and it will require a change in the public acceptance and the political posture of states to help solve the national issue of safe and cost-effective LLW disposal.

The role of the national low level waste repository operator in delivering new solutions for the management of low level wastes in the UK - 16217

International Nuclear Information System (INIS)

Walkingshaw, Martin

2009-01-01

The UK National Low Level Waste Repository (LLWR) is located near to the village of Drigg in West Cumbria. It is the principal site for disposal of solid Low Level Radioactive Waste (LLW) in the United Kingdom. This paper describes the program of work currently being undertaken by the site's operators, (LLW Repository Ltd and its newly appointed Parent Body Organisation), to extend the life of the LLWR and reduce the overall cost of LLW management to the UK taxpayer. The current focus of this program is to prevent disposal capacity being taken up at LLWR by waste types which lend themselves to alternative treatment and/or disposition routes. The chosen approach enables consignors to segregate LLW at source into formats which allow further treatment for volume reduction or, (for wastes with lower levels of activity), consignment in the future to alternative disposal facilities. Segregated waste services are incorporated into LLW Disposal commercial agreements between the LLWR operator and waste consignors. (author)

Integration of U.S. Department of Energy (DOE) contractor installations for the purpose of optimizing treatment, storage, and disposal of low-level radioactive waste (LLW)

International Nuclear Information System (INIS)

Lucas, M.; Gnoose, J.; Coony, M.; Martin, E.; Piscitella, R.

1998-02-01

The US Department of Energy (DOE) manages a multibillion dollar environmental management (EM) program. In June 1996, the Assistant Secretary of Energy for EM issued a memorandum with guidance and a vision for a ten year planning process for the EM Program. The purpose of this process, which became known as the Accelerated Cleanup: Focus on 2006, is to make step changes within the DOE complex regarding the approach for making meaningful environmental cleanup progress. To augment the process, Assistant Secretary requested the site contractors to engage in an effort to identify and evaluate integration alternatives for EM waste stream treatment, storage, and disposal (TSD) that would parallel the 2006 Plan. In October 1996, ten DOE contractor installations began the task of identifying alternative opportunities for low level radioactive waste (LLW). Cost effective, efficient solutions were necessary to meet all requirements associated with storing, characterizing, treating, packaging, transporting, and disposing of LLW while protecting the workers' health and safety, and minimizing impacts to the environment. To develop these solutions, a systems engineering approach was used to establish the baseline requirements, to develop alternatives, and to evaluate the alternatives. Key assumptions were that unique disposal capabilities exist within the DOE that must be maintained; private sector disposal capability for some LLW may not continue to exist into the foreseeable future; and decisions made by the LLW Team must be made on a system or complex wide basis to fully realize the potential cost and schedule benefits. This integration effort promoted more accurate waste volume estimates and forecasts; enhanced recognition of existing treatment, storage, and disposal capabilities and capacities; and improved identification of cost savings across the complex

LLW notes. Vol. 11, No. 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-01

`LLW Notes` is distributed by Afton Associates, Inc. to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive `LLW Notes`. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

LLW notes. Volume 11, No.8

International Nuclear Information System (INIS)

1996-12-01

'LLW Notes' is distributed by Afton Associates, Inc. to Low-Level Radioactive Waste Forum Participants and other state, and compact officials identified by those Participants to receive 'LLW Notes'. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW notes. Vol. 11, No. 1

International Nuclear Information System (INIS)

1996-02-01

'LLW Notes' is distributed by Afton Associates, Inc. to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive 'LLW Notes'. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW notes, Vol. 11, No. 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

`LLW Notes` is distributed by Afton Associates, Inc. to Low-Level Radioactive Waste Forum Participants and other state, and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

LLW notes, Vol. 11, No. 2

International Nuclear Information System (INIS)

1996-03-01

'LLW Notes' is distributed by Afton Associates, Inc. to Low-Level Radioactive Waste Forum Participants and other state, and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

Life-Cycle Cost and Risk Analysis of Alternative Configurations for Shipping Low-Level Radioactive Waste to the Nevada Test Site

International Nuclear Information System (INIS)

PM Daling; SB Ross; BM Biwer

1999-01-01

The Nevada Test Site (NTS) is a major receiver of low-level radioactive waste (LLW) for disposal. Currently, all LLW received at NTS is shipped by truck. The trucks use highway routes to NTS that pass through the Las Vegas Valley and over Hoover Dam, which is a concern of local stakeholder groups in the State of Nevada. Rail service offers the opportunity to reduce transportation risks and costs, according to the Waste Management Programmatic Environmental Impact Statement (WM-PEIS). However, NTS and some DOE LLW generator sites are not served with direct rail service so intermodal transport is under consideration. Intermodal transport involves transport via two modes, in this case truck and rail, from the generator sites to NTS. LLW shipping containers would be transferred between trucks and railcars at intermodal transfer points near the LLW generator sites, NTS, or both. An Environmental Assessment (EA)for Intermodal Transportation of Low-Level Radioactive Waste to the Nevada Test Site (referred to as the NTSIntermodal -M) has been prepared to determine whether there are environmental impacts to alterations to the current truck routing or use of intermodal facilities within the State of Nevada. However, an analysis of the potential impacts outside the State of Nevada are not addressed in the NTS Intermodal EA. This study examines the rest of the transportation network between LLW generator sites and the NTS and evaluates the costs, risks, and feasibility of integrating intermodal shipments into the LLW transportation system. This study evaluates alternative transportation system configurations for NTS approved and potential generators based on complex-wide LLW load information. Technical judgments relative to the availability of DOE LLW generators to ship from their sites by rail were developed. Public and worker risk and life-cycle cost components are quantified. The study identifies and evaluates alternative scenarios that increase the use of rail (intermodal

Life-Cycle Cost and Risk Analysis of Alternative Configurations for Shipping Low-Level Radioactive Waste to the Nevada Test Site

Energy Technology Data Exchange (ETDEWEB)

PM Daling; SB Ross; BM Biwer

1999-12-17

The Nevada Test Site (NTS) is a major receiver of low-level radioactive waste (LLW) for disposal. Currently, all LLW received at NTS is shipped by truck. The trucks use highway routes to NTS that pass through the Las Vegas Valley and over Hoover Dam, which is a concern of local stakeholder groups in the State of Nevada. Rail service offers the opportunity to reduce transportation risks and costs, according to the Waste Management Programmatic Environmental Impact Statement (WM-PEIS). However, NTS and some DOE LLW generator sites are not served with direct rail service so intermodal transport is under consideration. Intermodal transport involves transport via two modes, in this case truck and rail, from the generator sites to NTS. LLW shipping containers would be transferred between trucks and railcars at intermodal transfer points near the LLW generator sites, NTS, or both. An Environmental Assessment (EA)for Intermodal Transportation of Low-Level Radioactive Waste to the Nevada Test Site (referred to as the NTSIntermodal -M) has been prepared to determine whether there are environmental impacts to alterations to the current truck routing or use of intermodal facilities within the State of Nevada. However, an analysis of the potential impacts outside the State of Nevada are not addressed in the NTS Intermodal EA. This study examines the rest of the transportation network between LLW generator sites and the NTS and evaluates the costs, risks, and feasibility of integrating intermodal shipments into the LLW transportation system. This study evaluates alternative transportation system configurations for NTS approved and potential generators based on complex-wide LLW load information. Technical judgments relative to the availability of DOE LLW generators to ship from their sites by rail were developed. Public and worker risk and life-cycle cost components are quantified. The study identifies and evaluates alternative scenarios that increase the use of rail (intermodal

Shipment of LLW by intercoastal maritime service

International Nuclear Information System (INIS)

Barbour, D.A.

1985-01-01

Transportation costs are a significant element of total waste disposal costs. In 1982, Nuclear Metals, Inc. (NMI) began a series of tests and investigations to examine the feasibility of using alternative modes for its low-level waste (LLW) shipments. NMI's investigations and experience have identified significant problems in transporting LLW by rail. Intercoastal maritime service, however, has been demonstrated as a safe and cost-effective way of transporting LLW from eastern seaboard generation sites to the repository at Beatty, Nevada. Intuition is an unreliable guide in this area. Waste managers need to periodically assess and compare combined transportation and burial costs for all site options to ensure that disposal operations are conducted in the most rational way

Alternative concepts for Low-Level Radioactive Waste Disposal: Conceptual design report

International Nuclear Information System (INIS)

1987-06-01

This conceptual design report is provided by the Department of Energy's Nuclear Energy Low-Level Waste Management Program to assist states and compact regions in developing new low-level radioactive waste (LLW) disposal facilities in accordance with the Low-Level Radioactive Waste Policy Amendment Act of 1985. The report provides conceptual designs and evaluations of six widely considered concepts for LLW disposal. These are shallow land disposal (SLD), intermediate depth disposal (IDD), below-ground vaults (BGV), above-ground vaults (AGV), modular concrete canister disposal (MCCD), earth-mounded concrete bunker (EMCB). 40 refs., 45 figs., 77 tabs

WRAP low level waste restricted waste management (LLW RWM) glovebox acceptance test report

International Nuclear Information System (INIS)

Leist, K.J.

1997-01-01

On April 22, 1997, the Low Level Waste Restricted Waste Management (LLW RWM) glovebox was tested using acceptance test procedure 13027A-87. Mr. Robert L. Warmenhoven served as test director, Mr. Kendrick Leist acted as test operator and test witness, and Michael Lane provided miscellaneous software support. The primary focus of the glovebox acceptance test was to examine glovebox control system interlocks, operator Interface Unit (OIU) menus, alarms, and messages. Basic drum port and lift table control sequences were demonstrated. OIU menus, messages, and alarm sequences were examined, with few exceptions noted. Barcode testing was bypassed, due to the lack of installed equipment as well as the switch from basic reliance on fixed bar code readers to the enhanced use of portable bar code readers. Bar code testing was completed during performance of the LLW RWM OTP. Mechanical and control deficiencies were documented as Test Exceptions during performance of this Acceptance Test. These items are attached as Appendix A to this report

LLW simmers as states scramble

International Nuclear Information System (INIS)

Malloy, M.

1994-01-01

Low-level radioactive waste disposal could be reaching a crisis point as states and private industry scramble to come up with permitted disposal facilities. Although not as notorious as high-level radioactive waste, the disposal of low-level radioactive wastes (LLW) is becoming more of concern -- some say nearing a crisis -- nationwide, because of the limited number of storage sites available. Most states have formed into groups called compacts, in which they jointly set up storage and disposal sites for their LLW. Most of the overall universe of LLW is generated and handled by the US Department of Energy. The remainder is produced and dealt with commercially. Commercial sources account for about one million cubic feet of LLW annually. LLW is defined as anything that is not the more potent, spent high-level nuclear fuel waste or radioactive waste from transuranic processes. Ninety to ninety-five percent of LLW is trash. The rest is either short-lived, or in a third category of both long- and short-lived LLW. That third category, while small, can still account for a high amount of curies of radioactivity

Low-level waste inventory, characteristics, generation, and facility assessment for treatment, storage, and disposal alternatives considered in the US Department of Energy waste management programmatic environmental impact statement

Energy Technology Data Exchange (ETDEWEB)

Goyette, M.L.; Dolak, D.A.

1996-12-01

This report provides technical support information for use in analyzing environmental impacts associated with U.S. Department of Energy (DOE) low-level radioactive waste (LLW) management alternatives in the Waste-Management (WM) Programmatic Environmental Impact Statement (PEIS). Waste loads treated and disposed of for each of the LLW alternatives considered in the DOE WM PEIS are presented. Waste loads are presented for DOE Waste Management (WM) wastes, which are generated from routine operations. Radioactivity concentrations and waste quantities for treatment and disposal under the different LLW alternatives are described for WM waste. 76 refs., 14 figs., 42 tabs.

Removal of radioactive caesium from low level radioactive waste (LLW) streams using cobalt ferrocyanide impregnated organic anion exchanger

Energy Technology Data Exchange (ETDEWEB)

Valsala, T.P., E-mail: tpvalsala@yahoo.co.in [Waste Management Division, Bhabha Atomic Research Centre, Trombay 400 085 (India); Roy, S.C. [PREFRE Division, Bhabha Atomic Research Centre, Tarapur 401 502 (India); Shah, J.G. [Back End Technology Division, Bhabha Atomic Research Centre, Trombay 400 085 (India); Gabriel, J.; Raj, Kanwar [Waste Management Division, Bhabha Atomic Research Centre, Trombay 400 085 (India); Venugopal, V. [Radiochemistry Division, Bhabha Atomic Research Centre, Trombay 400 085 (India)

2009-07-30

The volumes of low level waste (LLW) generated during the operation of nuclear reactor are very high and require a concentration step before suitable matrix fixation. The volume reduction (concentration) is achieved either by co-precipitating technique or by the use of highly selective sorbents and ion exchange materials. The present study details the preparation of cobalt ferrocyanide impregnated into anion exchange resin and its evaluation with respect to removal of Cs in LLW streams both in column mode and batch mode operations. The Kd values of the prepared exchanger materials were found to be very good in actual reactor LLW solutions also. It was observed that the exchanger performed very well in the pH range of 3-9. A batch size of 6 g l{sup -1} of the exchanger was enough to give satisfactory decontamination for Cs in actual reactor LLW streams. The lab scale and pilot plant scale performance of the exchanger material in both batch mode and column mode operations was very good.

Environmental assessment for the treatment of Class A low-level radioactive waste and mixed low-level waste generated by the West Valley Demonstration Project

International Nuclear Information System (INIS)

1995-11-01

The U.S. Department of Energy (DOE) is currently evaluating low-level radioactive waste management alternatives at the West Valley Demonstration Project (WVDP) located on the Western New York Nuclear Service Center (WNYNSC) near West Valley, New York. The WVDP's mission is to vitrify high-level radioactive waste resulting from commercial fuel reprocessing operations that took place at the WNYNSC from 1966 to 1972. During the process of high-level waste vitrification, low-level radioactive waste (LLW) and mixed low-level waste (MILLW) will result and must be properly managed. It is estimated that the WVDP's LLW storage facilities will be filled to capacity in 1996. In order to provide sufficient safe storage of LLW until disposal options become available and partially fulfill requirements under the Federal Facilities Compliance Act (FFCA), the DOE is proposing to use U.S. Nuclear Regulatory Commission-licensed and permitted commercial facilities in Oak Ridge, Tennessee; Clive, Utah; and Houston, Texas to treat (volume-reduce) a limited amount of Class A LLW and MLLW generated from the WVDP. Alternatives for ultimate disposal of the West Valley LLW are currently being evaluated in an environmental impact statement. This proposed action is for a limited quantity of waste, over a limited period of time, and for treatment only; this proposal does not include disposal. The proposed action consists of sorting, repacking, and loading waste at the WVDP; transporting the waste for commercial treatment; and returning the residual waste to the WVDP for interim storage. For the purposes of this assessment, environmental impacts were quantified for a five-year operating period (1996 - 2001). Alternatives to the proposed action include no action, construction of additional on-site storage facilities, construction of a treatment facility at the WVDP comparable to commercial treatment, and off-site disposal at a commercial or DOE facility

Materials and degradation modes in an alternative LLW [low-level waste] disposal facility

International Nuclear Information System (INIS)

Cowgill, M.G.; MacKenzie, D.R.

1989-01-01

The materials used in the construction of alternative low-level waste disposal facilities will be subject to interaction with both the internal and the external environments associated with the facilities and unless precautions are taken, may degrade, leading to structural failure. This paper reviews the characteristics of both environments with respect to three alternative disposal concepts, then assesses how reaction with them might affect the properties of the materials, which include concrete, steel-reinforced concrete, structural steel, and various protective coatings and membranes. It identifies and evaluates the probability of reactions occurring which might lead to degradation of the materials and so compromise the structure. The probability of failure (interpreted relative to the ability of the structure to restrict ingress and egress of water) is assessed for each material and precautionary measures, intended to maximize the durability of the facility, are reviewed. 19 refs., 2 tabs

Packaged low-level waste verification system

International Nuclear Information System (INIS)

Tuite, K.T.; Winberg, M.; Flores, A.Y.; Killian, E.W.; McIsaac, C.V.

1996-01-01

Currently, states and low-level radioactive waste (LLW) disposal site operators have no method of independently verifying the radionuclide content of packaged LLW that arrive at disposal sites for disposal. At this time, disposal sites rely on LLW generator shipping manifests and accompanying records to insure that LLW received meets the waste acceptance criteria. An independent verification system would provide a method of checking generator LLW characterization methods and help ensure that LLW disposed of at disposal facilities meets requirements. The Mobile Low-Level Waste Verification System (MLLWVS) provides the equipment, software, and methods to enable the independent verification of LLW shipping records to insure that disposal site waste acceptance criteria are being met. The MLLWVS system was developed under a cost share subcontract between WMG, Inc., and Lockheed Martin Idaho Technologies through the Department of Energy's National Low-Level Waste Management Program at the Idaho National Engineering Laboratory (INEL)

Packaging LLW and ILW

International Nuclear Information System (INIS)

Flowers, R.H.; Owen, R.G.

1991-01-01

Low level waste (LLW) accounts for 70-80% by volume of all radioactive wastes produced by the nuclear industry. It has low specific activity, negligible actinide content and requires little, if any, shielding to protect workers. Volume reduction for LLW of high volume but low density may be achieved by incineration and compaction as appropriate, before packaging for disposal by near surface burial. Intermediate level waste (ILW) is treated and packed to convert it into a stable form to minimize any release of activity and make handling easier. The matrix chosen for immobilization, usually cement, polymers or bitumen, depends on the nature of the waste and the acceptance criteria of the disposal facility. The special case of LLW and ILW which will arise from reactor decommissioning is discussed. Packaging methods adopted by individual countries are reviewed. The range of costs involved for packaging ILW is indicated. There is no international consensus on the performance required from packaged waste to ensure its suitability both for interim storage and final disposal. (UK)

The Evolution of Low-Level Radioactive Waste (LLW) Disposal Practices at the Savannah River Site Coupled with Vigorous Stakeholder Interaction

International Nuclear Information System (INIS)

Goldston, W. T.; Wilhite, E. L.; Cook, J. R.; Sauls, V. W.

2002-01-01

Low-level radioactive waste (LLW) disposal practices at SRS evolved from trench disposal with little long-term performance basis to disposal in robust concrete vaults, again without modeling long-term performance. Now, based on an assessment of long-term performance of various waste forms and methods of disposal, the LLW disposal program allows for a ''smorgasbord'' of various disposal techniques and waste forms, all modeled to ensure long-term performance is understood. New disposal techniques include components-in-grout, compaction/volume reduction prior to disposal, and trench disposal of extremely low activity waste. Additionally, factoring partition coefficient (Kd) measurements based on waste forms has been factored into performance models. This paper will trace the development of the different disposal methods, and the extensive public communications effort that resulted in endorsement of the changes by the SRS Citizens Advisory Board

Alternative techniques for low-level waste shallow land burial

International Nuclear Information System (INIS)

Levin, G.B.; Mezga, L.J.

1983-01-01

Experience to date relative to the shallow land burial of low-level radioactive waste (LLW) indicates that the physical stability of the disposal unit and the hydrologic isolation of the waste are the two most important factors in assuring disposal site performance. Disposal unit stability can be ensured by providing stable waste packages and waste forms, compacting backfill material, and filling the void spaces between the packages. Hydrologic isolation can be achieved though a combination of proper site selection, subsurface drainage controls, internal trench drainage systems, and immobilization of the waste. A generalized design of a LLW disposal site that would provide the desired long-term isolation of the waste is discussed. While this design will be more costly than current practices, it will provide additional confidence in predicted and reliability and actual site performance

LLW Forum meeting report, October 20--22, 1997

International Nuclear Information System (INIS)

Norris, C.; Brown, H.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-10-01

The Low-Level Radioactive Waste Forum met in Annapolis, Maryland, on October 20--22, 1997. Twenty-six Forum Participants, Alternate Forum Participants, and meeting designees representing 22 compacts and states participated. A report on the meeting is given under the following subtitles: New developments in states and compacts; Discussion with NRC Commissioner McGaffigan; Regulatory issues session; Executive session; LLW forum business session; DOE low-level waste management program; Transportation of radioactive waste; Environmental equity: Title VI; Congressional studies on Ward Valley Site; Implementation of DOE's strategy for waste management; Relicensing Envirocare; Draft agreement for uniform application of manifesting procedures; CRCPD report; Panel: Future of low-level radioactive waste management; Agenda planning: February 1998; Resolutions; and Attendance

ASSESSING EXPOSURE TO THE PUBLIC FROM LOW LEVEL RADIOACTIVE WASTE (LLW) TRANSPORTATION TO THE NEVADA TEST SITE

International Nuclear Information System (INIS)

Miller, J.J.; Campbell, S.; Church, B.W.; Shafer, D. S.; Gillespie, D.; Sedano, S.; Cebe, J.J.

2003-01-01

The United States (U.S.) Department of Energy (DOE) Nevada Test Site (NTS) is one of two regional sites where low-level radioactive waste (LLW) from approved DOE and U.S. DOD generators across the United States is disposed. In federal fiscal year (FY) 2002, over 57,000 cubic meters of waste was transported to and disposed at the NTS. DOE and U.S. Department of Transportation (DOT) regulations ensure that radiation exposure from truck shipments to members of the public is negligible. Nevertheless, particularly in rural communities along transportation routes in Utah and Nevada, there is perceived risk from members of the public about incremental exposure from LLW trucks, especially when ''Main Street'' and the LLW transportation route are the same. To better quantify the exposure to gamma radiation, a stationary monitoring array of four pressurized ion chambers (PICs) have been set up in a pullout just before LLW trucks reach the entrance to the NTS. The PICs are positioned at a distance of one meter from the sides of the truck trailer and at a height appropriate for the design of the trucks that will be used in FY2003 to haul LLW to the NTS. The use of four PICs (two on each side of the truck) is to minimize and to correct for non-uniformity where radiation levels from waste packages vary from side to side, and from front to back in the truck trailer. The PIC array is being calibrated by collecting readings from each PIC exposed to a known 137Cs source that was positioned at different locations on a flatbed stationed in the PIC array, along with taking secondary readings from other known sources. Continuous data collection using the PICs, with and without a truck in the array, is being used to develop background readings. In addition, acoustic sensors are positioned on each side of the PIC array to record when a large object (presumably a truck) enters the array. In FY2003, PIC surveys from as many incoming LLW trucks as possible will be made and survey data

Strategic environmental assessment for UK LLW management - 16392

International Nuclear Information System (INIS)

Craze, Andrew; Clark, Matthew; Davis, Pete

2009-01-01

NDA is delivering a Strategic Environmental Assessment (SEA) to underpin the UK Nuclear Industry Low Level Waste Strategy. The purpose of this assessment is embed sustainability issues into our decision making and to fulfill our requirements under the European Union's Strategic Environmental Assessment (SEA) Directive (2004/42/EU) and transposing UK Regulations, and to underpin the development of the strategy. The outputs of the SEA have provided input into particular aspects of the strategy, leading to a more robust and better informed result. Development of options to be assessed under the SEA has looked at a number of factors, including: - what the strategy is aiming to achieve - expectation from stakeholders as to what should be addressed - consideration of tactical approaches to implementation of the strategy in addition to high level strategic issues - links to other projects and programmes (for example the Environmental Safety Case for the Low Level Waste Repository. The SEA aims to provide a robust assessment of the environmental and sustainability impacts of alternative strategies for providing continued capability and capacity for the management and disposal of LLW in the UK. The assessment also considers other, more tactical, issues around implementation of the strategy, for example: issues around the location of LLW management facilities; the environmental impacts of alternative waste treatment options (metal recycling etc); considerations of alternative approaches to the classification of radioactive waste and opportunities that would result. Critical to the development of the SEA has been the involvement of statutory and non-statutory stakeholders, who have informed both the output and the approach taken. (authors)

Alternative methods for disposal of low-level radioactive wastes. Task 2c: technical requirements for earth mounded concrete bunker disposal of low-level radioactive waste. Volume 4

International Nuclear Information System (INIS)

Miller, W.O.; Bennett, R.D.

1985-10-01

The study reported herein contains the results of Task 2c (Technical Requirements for Earth Mounded Concrete Bunker Disposal of Low-Level Radioactive Waste) of a four-task study entitled ''Criteria for Evaluating Engineered Facilities''. The overall objective of this study is to ensure that the criteria needed to evaluate five alternative low-level radioactive waste (LLW) disposal methods are available to potential license applicants. The earth mounded concrete bunker disposal alternative is one of several methods that may be proposed for disposal of low-level radioactive waste. The name of this alternative is descriptive of the disposal method used in France at the Centre de la Manche. Experience gained with this method at the Centre is described, including unit operations and features and components. Some improvements to the French system are recommended herein, including the use of previous backfill around monoliths and extending the limits of a low permeability surface layer. The applicability of existing criteria developed for near-surface disposal (10 CFR Part 61 Subpart D) to the earth mounded concrete bunker disposal method, as assessed in Task 1, are reassessed herein. With minor qualifications, these criteria were found to be applicable in the reassessment. These conclusions differ slightly from the Task 1 findings

Preliminary low-level waste feed definition guidance - LLW pretreatment interface

International Nuclear Information System (INIS)

Shade, J.W.; Connor, J.M.; Hendrickson, D.W.; Powell, W.J.; Watrous, R.A.

1995-02-01

The document describes limits for key constituents in the LLW feed, and the bases for these limits. The potential variability in the stream is then estimated and compared to the limits. Approaches for accomodating uncertainty in feed inventory, processing strategies, and process design (melter and disposal system) are discussed. Finally, regulatory constraints are briefly addressed

Safety assessment of alternatives to shallow-land burial of low-level radioactive waste: Volume 2, Environmental conditions affecting reliability of engineered barriers

International Nuclear Information System (INIS)

Cerven, F.; Otis, M.D.

1987-09-01

The need for new disposal capacity for low-level radioactive waste (LLW) has led to a re-examination of disposal practices. A number of enhancements and alternatives to traditional shallow-land burial have been proposed to meet the need for new capacity and to address various concerns about the performance history of existing commercial LLW sites. Fifteen potentially important degradation mechanisms for a LLW facility are identified, categorized, and analyzed to determine their importance to the proper functioning of the disposal facility over its 500-year lifetime. Wind storms, biological intrusion, mechanical settling, freeze/thaw cycling, chemical degradation, wind erosion, and water erosion were considered the most important mechanisms. Data supporting concrete structure long-term performance in sulfate environments and long-term cover performance in erosive and biological intrusion environments were obtained. Research on the performance of covers and concrete structures in the presence of the other listed degradation mechanisms is recommended. 18 refs., 16 figs., 9 tabs

LLW Notes, Volume 9, Number 6. October 1994

International Nuclear Information System (INIS)

1994-10-01

LLW Notes is distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of state and compact representatives appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes, Volume 9, Number 6. October 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-10-01

LLW Notes is distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of state and compact representatives appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies and other interested parties.

LLW Forum meeting report, October 26--27, 1994

International Nuclear Information System (INIS)

1994-01-01

The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties. This report details activities of the meeting held October 26-27, 1994

LLW Forum meeting report, October 26--27, 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties. This report details activities of the meeting held October 26-27, 1994.

LLW Forum meeting report, February 13--16, 1996

International Nuclear Information System (INIS)

1996-01-01

The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties. This report details activities at the meeting held February 13-16, 1996

Siting Study for the Remote-Handled Low-Level Waste Disposal Project

Energy Technology Data Exchange (ETDEWEB)

Lisa Harvego; Joan Connolly; Lance Peterson; Brennon Orr; Bob Starr

2010-10-01

The U.S. Department of Energy has identified a mission need for continued disposal capacity for remote-handled low-level waste (LLW) generated at the Idaho National Laboratory (INL). An alternatives analysis that was conducted to evaluate strategies to achieve this mission need identified two broad options for disposal of INL generated remote-handled LLW: (1) offsite disposal and (2) onsite disposal. The purpose of this study is to identify candidate sites or locations within INL boundaries for the alternative of an onsite remote handled LLW disposal facility and recommend the highest-ranked locations for consideration in the National Environmental Policy Act process. The study implements an evaluation based on consideration of five key elements: (1) regulations, (2) key assumptions, (3) conceptual design, (4) facility performance, and (5) previous INL siting study criteria, and uses a five-step process to identify, screen, evaluate, score, and rank 34 separate sites located across INL. The result of the evaluation is identification of two recommended alternative locations for siting an onsite remote-handled LLW disposal facility. The two alternative locations that best meet the evaluation criteria are (1) near the Advanced Test Reactor Complex and (2) west of the Idaho Comprehensive Environmental Response, Compensation, and Liability Act Disposal Facility.

LLW Notes, vol. 9, no. 1. February/March 1994

International Nuclear Information System (INIS)

1994-03-01

LLW Notes is published ten times each year and is distributed to Low- Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of representatives of states and compacts established to facilitate state and compact commission implementation of the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies

The Department of Energy's National Disposition Strategy for the Treatment and Disposal of Low Level and Mixed Low Level Waste

International Nuclear Information System (INIS)

Peterson, G.R.; Tonkay, D.W.

2006-01-01

The U.S. Department of Energy's (DOE) Environmental Management (EM) program is committed to the environmental remediation of DOE sites. This cleanup mission will continue to produce large amounts of Low Level Waste (LLW) and Mixed Low-Level Waste (MLLW). This paper reports on the development of the DOE LLW/MLLW National Disposition Strategy that maps the Department's long-range strategy to manage LLW and MLLW. Existing corporate LLW and MLLW data proved insufficient to develop this strategy. Therefore, new data requirements were developed in conjunction with waste managers. The paper will report on the results of this data collection effort, which will result in development of DOE LLW/MLLW disposition maps. (authors)

Long-term storage of Greater-Than-Class C Low-Level Waste

International Nuclear Information System (INIS)

Magleby, M.T.

1990-01-01

Under Federal law, the Department of Energy (DOE) is responsible for safe disposal of Greater-Than-Class C Low-Level Waste (GTCC LLW) generated by licenses of the Nuclear Regulatory commission (NRC) or Agreement States. Such waste must be disposed of in a facility licensed by the NRC. It is unlikely that licensed disposal of GTCC LLW will be available prior to the year 2010. Pending availability of disposal capacity, DOE is assessing the need for collective, long-term storage of GTCC LLW. Potential risks to public health and safety caused by long-term storage of GTCC LLW at the place of generation will be evaluated to determine if alternative facilities are warranted. If warranted, several options will be investigated to determine the preferred alternative for long-term storage. These options include modification of an existing DOE facility, development of a new DOE facility, or development of a facility by the private sector with or without DOE support. Reasonable costs for long-term storage would be borne by the waste generators. 5 refs., 1 fig

Review of private sector and Department of Energy treatment, storage, and disposal capabilities for low-level and mixed low-level waste

Energy Technology Data Exchange (ETDEWEB)

Willson, R.A.; Ball, L.W.; Mousseau, J.D.; Piper, R.B.

1996-03-01

Private sector capacity for treatment, storage, and disposal (TSD) of various categories of radioactive waste has been researched and reviewed for the Idaho National Engineering Laboratory (INEL) by Lockheed Idaho Technologies Company, the primary contractor for the INEL. The purpose of this document is to provide assistance to the INEL and other US Department of Energy (DOE) sites in determining if private sector capabilities exist for those waste streams that currently cannot be handled either on site or within the DOE complex. The survey of private sector vendors was limited to vendors currently capable of, or expected within the next five years to be able to perform one or more of the following services: low-level waste (LLW) volume reduction, storage, or disposal; mixed LLW treatment, storage, or disposal; alpha-contaminated mixed LLW treatment; LLW decontamination for recycling, reclamation, or reuse; laundering of radioactively-contaminated laundry and/or respirators; mixed LLW treatability studies; mixed LLW treatment technology development. Section 2.0 of this report will identify the approach used to modify vendor information from previous revisions of this report. It will also illustrate the methodology used to identify any additional companies. Section 3.0 will identify, by service, specific vendor capabilities and capacities. Because this document will be used to identify private sector vendors that may be able to handle DOE LLW and mixed LLW streams, it was decided that current DOE capabilities should also be identified. This would encourage cooperation between DOE sites and the various states and, in some instances, may result in a more cost-effective alternative to privatization. The DOE complex has approximately 35 sites that generate the majority of both LLW and mixed LLW. Section 4.0 will identify these sites by Operations Office, and their associated LLW and mixed LLW TSD units.

Review of private sector and Department of Energy treatment, storage, and disposal capabilities for low-level and mixed low-level waste

International Nuclear Information System (INIS)

Willson, R.A.; Ball, L.W.; Mousseau, J.D.; Piper, R.B.

1996-03-01

Private sector capacity for treatment, storage, and disposal (TSD) of various categories of radioactive waste has been researched and reviewed for the Idaho National Engineering Laboratory (INEL) by Lockheed Idaho Technologies Company, the primary contractor for the INEL. The purpose of this document is to provide assistance to the INEL and other US Department of Energy (DOE) sites in determining if private sector capabilities exist for those waste streams that currently cannot be handled either on site or within the DOE complex. The survey of private sector vendors was limited to vendors currently capable of, or expected within the next five years to be able to perform one or more of the following services: low-level waste (LLW) volume reduction, storage, or disposal; mixed LLW treatment, storage, or disposal; alpha-contaminated mixed LLW treatment; LLW decontamination for recycling, reclamation, or reuse; laundering of radioactively-contaminated laundry and/or respirators; mixed LLW treatability studies; mixed LLW treatment technology development. Section 2.0 of this report will identify the approach used to modify vendor information from previous revisions of this report. It will also illustrate the methodology used to identify any additional companies. Section 3.0 will identify, by service, specific vendor capabilities and capacities. Because this document will be used to identify private sector vendors that may be able to handle DOE LLW and mixed LLW streams, it was decided that current DOE capabilities should also be identified. This would encourage cooperation between DOE sites and the various states and, in some instances, may result in a more cost-effective alternative to privatization. The DOE complex has approximately 35 sites that generate the majority of both LLW and mixed LLW. Section 4.0 will identify these sites by Operations Office, and their associated LLW and mixed LLW TSD units

A proposed alternative approach for protection of inadvertent human intruders from buried Department of Energy low level radioactive wastes

International Nuclear Information System (INIS)

Cochran, J.R.

1995-01-01

The burial of radioactive wastes creates a legacy. To limit the impact of this legacy on future generations, we establish and comply with performance objectives. This paper reviews performance objectives for the long-term isolation of buried radioactive wastes; identifies regulatorly-defined performance objectives for protecting the inadvertent human intruder (IHI) from buried low-level radioactive waste (LLW); (3) discusses a shortcoming of the current approach; and (4) offers an alternative approach for protecting the IHI. This alternative approach is written specifically for the burial of US Department of Energy (DOE) wastes at the Nevada Test Site (NTS), although the approach might be applied at other DOE burial sites

LLW Notes, vol.9, no. 5. August/September 1994

International Nuclear Information System (INIS)

1994-09-01

LLW Notes is distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of state and compact representatives appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes, vol.9, no. 5. August/September 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-09-01

LLW Notes is distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of state and compact representatives appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies and other interested parties.

Disposal of low-level and mixed low-level radioactive waste during 1990

International Nuclear Information System (INIS)

1993-08-01

Isotopic inventories and other data are presented for low-level radioactive waste (LLW) and mixed LLW disposed (and occasionally stored) during calendar year 1990 at commercial disposal facilities and Department of Energy (DOE) sites. Detailed isotopic information is presented for the three commercial disposal facilities located near Barnwell, SC, Richland, WA, and Beatty, NV. Less information is presented for the Envirocare disposal facility located near Clive, UT, and for LLW stored during 1990 at the West Valley site. DOE disposal information is included for the Savannah River Site (including the saltstone facility), Nevada Test Site, Los Alamos National Laboratory, Idaho National Engineering Laboratory, Hanford Site, Y-12 Site, and Oak Ridge National Laboratory. Summary information is presented about stored DOE LLW. Suggestions are made about improving LLW disposal data

LLW Forum meeting report, January 31--February 3, 1995

International Nuclear Information System (INIS)

1995-01-01

The Low-Level Radioactive Waste Forum (LLW) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties. This report details activities of the meeting held January 31-February 3, 1995

LLW Forum meeting report, January 31--February 3, 1995

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-31

The Low-Level Radioactive Waste Forum (LLW) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties. This report details activities of the meeting held January 31-February 3, 1995.

The cost of LLW disposal - Is it sound economics?

International Nuclear Information System (INIS)

Stelluto, Janis D.

1992-01-01

Low-level radioactive waste (LLW) management is a growth industry. Since 1980, when the LLW Policy Act was passed, regional and state LLW bureaucracies have grown, and LLW services and consulting businesses have prospered. Most states and federal agencies have LLW programs with increased regulation of LLW management. Costs of all these programs have soared as facilities for LLW disposal are proposed in sixteen, or more, locations in the country. LLW management costs have also increased as licensees implement comprehensive programs for volume reduction and waste form stabilization. Yet, the total cost of LLW management service is borne by nearly the same universe of payers as in 1980: taxpayers and radioactive materials licensees. Those costs are, in turn, passed on through taxes and consumer costs. Ultimately, everybody pays. Despite this investment, the LLW situation is adrift. New facilities have not been built, and existing facilities are closing or limiting access. LLW management has not advanced to a respected field of engineering and science. Nor does it include exceptional benefit and opportunity to host communities. A new focus is needed to allow an economically sound solution to emerge, one where the supply of LLW management and disposal fits the demand for service. (author)

Development of low-level radioactive waste disposal capacity in the United States - progress or stalemate?

International Nuclear Information System (INIS)

Devgun, J.S.; Larson, G.S.

1995-01-01

It has been fifteen years since responsibility for the disposal of commercially generated low-level radioactive waste (LLW) was shifted to the states by the United States Congress through the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA). In December 1985, Congress revisited the issue and enacted the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). No new disposal sites have opened yet, however, and it is now evident that disposal facility development is more complex, time-consuming, and controversial than originally anticipated. For a nation with a large nuclear power industry, the lack of availability of LLW disposal capacity coupled with a similar lack of high-level radioactive waste disposal capacity could adversely affect the future viability of the nuclear energy option. The U.S. nuclear power industry, with 109 operating reactors, generates about half of the LLW shipped to commercial disposal sites and faces dwindling access to waste disposal sites and escalating waste management costs. The other producers of LLW - industries, government (except the defense related research and production waste), academic institutions, and medical institutions that account for the remaining half of the commercial LLW - face the same storage and cost uncertainties. This paper will summarize the current status of U.S. low-level radioactive waste generation and the status of new disposal facility development efforts by the states. The paper will also examine the factors that have contributed to delays, the most frequently suggested alternatives, and the likelihood of change

Development of low-level radioactive waste disposal capacity in the United States -- Progress or stalemate?

International Nuclear Information System (INIS)

Devgun, J.S.

1995-01-01

It has been fifteen years since responsibility for the disposal of commercially generated low-level radioactive waste (LLW) was shifted to the states by the United States Congress through the Low-Level Radioactive Waste Policy Act of 1980 (LLRWPA). In December 1985, Congress revisited the issue and enacted the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA). No new disposal sites have opened yet, however, and it is now evident that disposal facility development is more complex, time-consuming, and controversial than originally anticipated. For a nation with a large nuclear power industry, the lack of availability of LLW disposal capacity coupled with a similar lack of high-level radioactive waste disposal capacity could adversely affect the future viability of the nuclear energy option. The US nuclear power industry, with 109 operating reactors, generates about half of the LLW shipped to commercial disposal sites and faces dwindling access to waste disposal sites and escalating waste management costs. The other producers of LLW -- industries, government (except the defense related research and production waste), academic institutions, and medical institutions that account for the remaining half of the commercial LLW -- face the same storage and cost uncertainties. This paper will summarize the current status of US low-level radioactive waste generation and the status of new disposal facility development efforts by the states. The paper will also examine the factors that have contributed to delays, the most frequently suggested alternatives, and the likelihood of change

Greater-than-Class-C low-level radioactive waste management concepts

International Nuclear Information System (INIS)

Knecht, M.A.

1988-01-01

In 1986, Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985 assigned to the Federal Government responsibility for the disposal of commercial greater-than-Class-C (GTCC) low-level radioactive waste (LLW). In 1987, DOE committed to Congress to accept GTCC LLW and provide storage and other waste management as necessary until disposal capacity is available. Current estimates are that about 6,000 m 3 of unpackaged GTCC LLW will be generated to the year 2020. Generators estimate that 100 m 3 of raw GTCC LLW might exceed planned storage capacity to the year 2020. This paper reports the activities of the National Low-Level Waste Program to manage GTCC low-level radioactive waste

New trends in the low-level waste management in Italy

International Nuclear Information System (INIS)

Costa, A.; Donato, A.

1987-01-01

The low level radioactive waste production per year in Italy is evaluated to be at the origin of the order of about 2500 cu.m.. The LLW management scheme in the past was based on a double approach, depending on the waste origin. The LLW from nuclear activities were stored on site under the responsibility of the producers, which had no real possibility to dispose off the LLW in the lack of authorized disposal sites. The management of the LLW coming from other activities (hospitals, university etc.) was left mainly to the sense of responsibility of the same producers which, under the local authorities authorization released case by case, were permitted by the existing regulations to store and sometimes to discharge the wastes, after a suitable decay period. In this context, the government charged the ENEA (Italian Committee for Nuclear and Alternative Energies Development), in the frame of the national energy plan, to overview and organize the whole matter. This paper describes the new trends adopted by ENEA for the LLW management

Social and institutional evaluation report for Greater-Than-Class C Low-Level Radioactive Waste Disposal

International Nuclear Information System (INIS)

Anderson, T.L.; Lewis, B.E.; Turner, K.H.; Rozelle, M.A.

1993-10-01

This report identifies and characterizes social and institutional issues that would be relevant to the siting, licensing, construction, closure, and postclosure of a Greater-Than-Class-C low-level radioactive waste (GTCC LLW) disposal facility. A historical perspective of high-level radioactive waste (HLW) and LLW disposal programs is provided as an overview of radioactive waste disposal and to support the recommendations and conclusions in the report. A characterization of each issue is provided to establish the basis for further evaluations. Where applicable, the regulatory requirements of 10 CFR 60 and 61 are incorporated in the issue characterizations. The issues are used to compare surface, intermediate depth, and deep geologic disposal alternatives. The evaluation establishes that social and institutional issues do not significantly discriminate among the disposal alternatives. Recommendations are provided for methods by which the issues could be considered throughout the lifecycle of a GTCC LLW disposal program

Social and institutional evaluation report for Greater-Than-Class C Low-Level Radioactive Waste Disposal

Energy Technology Data Exchange (ETDEWEB)

Anderson, T.L.; Lewis, B.E.; Turner, K.H.; Rozelle, M.A. [Dames and Moore, Denver, CO (United States)

1993-10-01

This report identifies and characterizes social and institutional issues that would be relevant to the siting, licensing, construction, closure, and postclosure of a Greater-Than-Class-C low-level radioactive waste (GTCC LLW) disposal facility. A historical perspective of high-level radioactive waste (HLW) and LLW disposal programs is provided as an overview of radioactive waste disposal and to support the recommendations and conclusions in the report. A characterization of each issue is provided to establish the basis for further evaluations. Where applicable, the regulatory requirements of 10 CFR 60 and 61 are incorporated in the issue characterizations. The issues are used to compare surface, intermediate depth, and deep geologic disposal alternatives. The evaluation establishes that social and institutional issues do not significantly discriminate among the disposal alternatives. Recommendations are provided for methods by which the issues could be considered throughout the lifecycle of a GTCC LLW disposal program.

LLW Notes, volume 9, No. 7. November and December 1994

International Nuclear Information System (INIS)

1994-12-01

LLW Notes is distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of state and compact representatives appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes, volume 9, No. 7. November and December 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-01

LLW Notes is distributed to Low-Level Radioactive Waste Forum Participants and other state and compact officials identified by those Participants to receive LLW Notes. The Low-Level Radioactive Waste Forum is an association of state and compact representatives appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies and other interested parties.

Long-range low-level waste management needs

International Nuclear Information System (INIS)

Gloyna, E.F.

1980-01-01

In all waste management considerations, it is necessary to establish the waste source; characterize the waste components; determine treatability; evaluate specific details that comprise a systems approach to overall waste management; and implement practical collection, packaging, storage disposal and monitoring technology. This paper evaluates management considerations by defining the source and magnitude of low-level wastes (LLW), relating LLW disposal, defining principles of LLW burial, and listing LLW burial considerations. 17 refs

DOE LLW classification rationale

International Nuclear Information System (INIS)

Flores, A.Y.

1991-01-01

This report was about the rationale which the US Department of Energy had with low-level radioactive waste (LLW) classification. It is based on the Nuclear Regulatory Commission's classification system. DOE site operators met to review the qualifications and characteristics of the classification systems. They evaluated performance objectives, developed waste classification tables, and compiled dose limits on the waste. A goal of the LLW classification system was to allow each disposal site the freedom to develop limits to radionuclide inventories and concentrations according to its own site-specific characteristics. This goal was achieved with the adoption of a performance objectives system based on a performance assessment, with site-specific environmental conditions and engineered disposal systems

Greater-than-Class-C Low-Level Waste Data Base user's manual

International Nuclear Information System (INIS)

1992-07-01

The Greater-than-Class-C Low-level Waste (GTCC LLW) Data Base characterizes GTCC LLW using low, base, and high cases for three different scenarios: unpackaged, packaged, and concentration averages. The GTCC LLW Data Base can be used to project future volumes and radionuclide activities. This manual provides instructions for users of the GTCC LLW Data Base

Secondary Low-Level Waste Treatment Strategy Analysis

International Nuclear Information System (INIS)

D.M. LaRue

1999-01-01

The objective of this analysis is to identify and review potential options for processing and disposing of the secondary low-level waste (LLW) that will be generated through operation of the Monitored Geologic Repository (MGR). An estimate of annual secondary LLW is generated utilizing the mechanism established in ''Secondary Waste Treatment Analysis'' (Reference 8.1) and ''Secondary Low-Level Waste Generation Rate Analysis'' (Reference 8.5). The secondary LLW quantities are based on the spent fuel and high-level waste (HLW) arrival schedule as defined in the ''Controlled Design Assumptions Document'' (CDA) (Reference 8.6). This analysis presents estimates of the quantities of LLW in its various forms. A review of applicable laws, codes, and standards is discussed, and a synopsis of those applicable laws, codes, and standards and their impacts on potential processing and disposal options is presented. The analysis identifies viable processing/disposal options in light of the existing laws, codes, and standards, and then evaluates these options in regard to: (1) Process and equipment requirements; (2) LLW disposal volumes; and (3) Facility requirements

Greater-than-Class C low-level waste characterization technical review process

Energy Technology Data Exchange (ETDEWEB)

Hutchison, D.; Magleby, M.

1990-01-01

Existing volume projections of greater-than-Class C low-level waste (GTCC LLW) vary significantly. The Department of Energy (DOE) National Low-Level Waste Management Program (NLLWMP) has undertaken activities to develop a best estimate of GTCC LLW volumes and activities for use as the planning basis. Initial information about the generation of GTCC LLW was obtained through a DOE Energy Information Administration survey. That information, combined with information from other related literature, formed the basis of a computer model, which projects potential GTCC LLW. This paper describes uncertainties in existing GTCC LLW characterization and volume projections data and describes the technical review process that is being used to assist in projections of GTCC LLW expected for storage and disposal. 8 refs., 2 tabs.

Greater-than-Class C low-level waste characterization technical review process

International Nuclear Information System (INIS)

Hutchison, D.; Magleby, M.

1990-01-01

Existing volume projections of greater-than-Class C low-level waste (GTCC LLW) vary significantly. The Department of Energy (DOE) National Low-Level Waste Management Program (NLLWMP) has undertaken activities to develop a best estimate of GTCC LLW volumes and activities for use as the planning basis. Initial information about the generation of GTCC LLW was obtained through a DOE Energy Information Administration survey. That information, combined with information from other related literature, formed the basis of a computer model, which projects potential GTCC LLW. This paper describes uncertainties in existing GTCC LLW characterization and volume projections data and describes the technical review process that is being used to assist in projections of GTCC LLW expected for storage and disposal. 8 refs., 2 tabs

Review of available options for low level radioactive waste disposal

International Nuclear Information System (INIS)

1992-07-01

The scope of this report includes: descriptions of the options available; identification of important elements in the selection process; discussion and assessment of the relevance of the various elements for the different options; cost data indicating the relative financial importance of different parts of the systems and the general cost level of a disposal facility. An overview of the types of wastes included in low level waste categories and an approach to the LLW management system is presented. A generic description of the disposal options available and the main activities involved in implementing the different options are described. Detailed descriptions and cost information on low level waste disposal facility concepts in a number of Member States are given. Conclusions from the report are summarized. In addition, this report provides a commentary on various aspects of land disposal, based on experience gained by IAEA Member States. The document is intended to complement other related IAEA publications on LLW management and disposal. It also demonstrates that alternatives solutions for the final disposal of LLW are available and can be safely operated but the choice of an appropriate solution must be a matter for national strategy taking into account local conditions. 18 refs, 16 figs, 1 tab

Oak Ridge Low Level Waste Management Task Force summary

International Nuclear Information System (INIS)

Van Hoesen, S.D.

1985-01-01

New facilities are required in the next five years to manage low level radioactive wastes (LLW) produced on the Oak Ridge Reservation (ORR). The Central Waste Disposal Facility (CWDF) was planned to provide the needed additional facilities beginning in late 1985. The CWDF was planned as a shallow land burial facility to dispose of non-stabilized LLW. However, comments on the CWDF Draft Environmental Impact Statement (DEIS) received from the State of Tennessee, the Environmental Protection Agency, and the Nuclear Regulatory Commission identified major issues related to the treatment of alternatives as required by the National Environmental Policy Act, and the potential for unacceptable groundwater contamination resulting from shallow land burial of non-stabilized waste. A series of initial and detailed evaluations are being conducted to develop the basic environmental performance and cost information needed to compare several LLW management approaches and arrive at a proposed system for development. The evaluations are targeted for completion by October

Low-level radioactive waste disposal technologies used outside the United States

International Nuclear Information System (INIS)

Templeton, K.J.; Mitchell, S.J.; Molton, P.M.; Leigh, I.W.

1994-01-01

Low-level radioactive waste (LLW) disposal technologies are an integral part of the waste management process. In the United States, commercial LLW disposal is the responsibility of the State or groups of States (compact regions). The United States defines LLW as all radioactive waste that is not classified as spent nuclear fuel, high- level radioactive waste, transuranic waste, or by-product material as defined in Section II(e)(2) of the Atomic Energy Act. LLW may contain some long-lived components in very low concentrations. Countries outside the United States, however, may define LLW differently and may use different disposal technologies. This paper outlines the LLW disposal technologies that are planned or being used in Canada, China, Finland, France, Germany, Japan, Sweden, Taiwan, and the United Kingdom (UK)

Proceedings of the sixth annual Participants' Information Meeting DOE Low-Level Waste Management Program

International Nuclear Information System (INIS)

1984-12-01

Sessions were held on disposal technology, characteristics and treatment of low-level waste, environmental aspects and performance prediction, predicting source terms for low-level wastes (LLW), performance assessment for LLW disposal facilities, and approaches to LLW facility siting and characteristics. Fifty-six papers were indexed separately

LLW disposal, 1996 and beyond, an industry perspective

International Nuclear Information System (INIS)

Genoa, P.H.

1996-01-01

In this article the author reviews what has been done in the past 15 years in terms of opening sites for disposal of low-level radioactive wastes, and what seems to be on the horizon. He reviews process timelines, timelines from regional efforts, and timelines for LLW facilities. The author also looks at what types of changes have been made in the generation, control, and volume of LLW. He examines the pressures which have driven these changes, both from society and from cost control economics. The author tries to look at what government, waste generators, and the waste management industry should do to make progress toward adequate solutions to address the LLW disposal problems

Low level waste repositories

International Nuclear Information System (INIS)

Hill, P.R.H.; Wilson, M.A.

1983-11-01

Factors in selecting a site for low-level radioactive waste disposal are discussed. South Australia has used a former tailings dam in a remote, arid location as a llw repository. There are also low-level waste disposal procedures at the Olympic Dam copper/uranium project

LLW Notes: Volume 10, Number 7

International Nuclear Information System (INIS)

Norris, C.

1995-10-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW notes: Volume 10, Number 5

International Nuclear Information System (INIS)

1995-07-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes: Volume 10, Number 3

International Nuclear Information System (INIS)

1995-04-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes: Volume 10, Number 4

International Nuclear Information System (INIS)

1995-06-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes: Volume 10, Number 8

International Nuclear Information System (INIS)

Norris, C.

1995-01-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW notes: Volume 10, Number 6

International Nuclear Information System (INIS)

Norris, C.

1995-09-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

LLW Notes: Volume 10, Number 7

Energy Technology Data Exchange (ETDEWEB)

Norris, C. [ed.] [Afton Associates, Inc., Washington, DC (United States)

1995-10-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

LLW notes: Volume 10, Number 5

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

LLW Notes: Volume 10, Number 4

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

LLW notes: Volume 10, Number 6

Energy Technology Data Exchange (ETDEWEB)

Norris, C. [ed.] [Afton Associates, Inc., Washington, DC (United States)

1995-09-01

The Low-Level Radioactive Waste Forum is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties.

DBMS: a tool for managing LLW data

International Nuclear Information System (INIS)

Vlajcic, P.

1984-01-01

As part of the DOE's National Low-Level Radioactive Waste Management Program, a Data Base Management System (DBMS) has been developed by EG and G Idaho, lead contractor for the national LLW management program, in cooperation with the DOE and the Southern States Energy Board, a regional research group sponsored by 17 states. Basically, DBMS offers states free use of a powerful central computer (located in Idaho) for the storage, processing, and retrieval of LLW data, and the capability to forecast their handling, treatment, transport, and disposal needs

Project Execution Plan for the Remote Handled Low-Level Waste Disposal Project

Energy Technology Data Exchange (ETDEWEB)

Danny Anderson

2014-07-01

As part of ongoing cleanup activities at the Idaho National Laboratory (INL), closure of the Radioactive Waste Management Complex (RWMC) is proceeding under the Comprehensive Environmental Response, Compensation, and Liability Act (42 USC 9601 et seq. 1980). INL-generated radioactive waste has been disposed of at RWMC since 1952. The Subsurface Disposal Area (SDA) at RWMC accepted the bulk of INL’s contact and remote-handled low-level waste (LLW) for disposal. Disposal of contact-handled LLW and remote-handled LLW ion-exchange resins from the Advanced Test Reactor in the open pit of the SDA ceased September 30, 2008. Disposal of remote-handled LLW in concrete disposal vaults at RWMC will continue until the facility is full or until it must be closed in preparation for final remediation of the SDA (approximately at the end of fiscal year FY 2017). The continuing nuclear mission of INL, associated ongoing and planned operations, and Naval spent fuel activities at the Naval Reactors Facility (NRF) require continued capability to appropriately dispose of contact and remote handled LLW. A programmatic analysis of disposal alternatives for contact and remote-handled LLW generated at INL was conducted by the INL contractor in Fiscal Year 2006; subsequent evaluations were completed in Fiscal Year 2007. The result of these analyses was a recommendation to the Department of Energy (DOE) that all contact-handled LLW generated after September 30, 2008, be disposed offsite, and that DOE proceed with a capital project to establish replacement remote-handled LLW disposal capability. An analysis of the alternatives for providing replacement remote-handled LLW disposal capability has been performed to support Critical Decision-1. The highest ranked alternative to provide this required capability has been determined to be the development of a new onsite remote-handled LLW disposal facility to replace the existing remote-handled LLW disposal vaults at the SDA. Several offsite DOE

Low-level radioactive waste research program plan

International Nuclear Information System (INIS)

O'Donnell, E.; Lambert, J.

1989-11-01

The Waste Management Branch, Division of Engineering, Office of Nuclear Regulatory Research, has developed a strategy for conducting research on issues of concern to the US Nuclear Regulatory Commission (NRC) in its efforts to ensure safe disposal of low-level radioactive waste (LLW). The resulting LLW research program plan provides an integrated framework for planning the LLW research program to ensure that the program and its products are responsive and timely for use in NRC's LLW regulatory program. The plan discusses technical and scientific issues and uncertainties associated with the disposal of LLW, presents programmatic goals and objectives for resolving them, establishes a long-term strategy for conducting the confirmatory and investigative research needed to meet these goals and objectives, and includes schedules and milestones for completing the research. Areas identified for investigation include waste form and other material concerns, failure mechanisms and radionuclide releases, engineered barrier performance, site characterization and monitoring, and performance assessment. The plan proposes projects that (1) analyze and test actual LLW and solidified LLW under laboratory and field conditions to determine leach rates and radionuclide releases, (2) examine the short- and long-term performance of concrete-enhanced LLW burial structures and high-integrity containers, and (3) attempt to predict water movement and contaminant transport through low permeability saturated media and unsaturated porous media. 4 figs., 3 tabs

Progress on management business system of LLW generated from research and industrial nuclear facilities

International Nuclear Information System (INIS)

Izumida, Tatsuo

2014-01-01

RANDEC has been studying a management business system of LLW (Low Level Waste) generated from research and industrial facilities since 2008. To examine economical problems, the income and expenditure of LLW treatment business was simulated. As a result, raising method of the funds which is required in preparatory stage of LLW treatment business is an obvious issue to carry out as public utility works. (author)

Siting simulation for low-level waste disposal facilities

International Nuclear Information System (INIS)

Roop, R.D.; Rope, R.C.

1985-01-01

The Mock Site Licensing Demonstration Project has developed the Low-Level Radioactive Waste Siting Simulation, a role-playing exercise designed to facilitate the process of siting and licensing disposal facilities for low-level waste (LLW). This paper describes the development, content, and usefulness of the siting simulation. The simulation can be conducted at a workshop or conference, involves 14 or more participants, and requires about eight hours to complete. The simulation consists of two sessions; in the first, participants negotiate the selection of siting criteria, and in the second, a preferred disposal site is chosen from three candidate sites. The project has sponsored two workshops (in Boston, Massachusetts and Richmond, Virginia) in which the simulation has been conducted for persons concerned with LLW management issues. It is concluded that the simulation can be valuable as a tool for disseminating information about LLW management; a vehicle that can foster communication; and a step toward consensus building and conflict resolution. The DOE National Low-Level Waste Management Program is now making the siting simulation available for use by states, regional compacts, and other organizations involved in development of LLW disposal facilities

Low-level radioactive waste treatment systems in northern Europe

International Nuclear Information System (INIS)

Sjoeblom, R.

1987-08-01

In the United States, the use of low-level waste (LLW) treatment systems by low level waste generators can be expected to expand with increasing costs for disposal and continuing uncertainty over the availability of disposal space. This development increases the need for performance information and operational data and has prompted the US Department of Energy to commission several compilations of LLW systems experience. The present paper summarizes some of the know-how from Northern Europe where the incentive for LLW treatment and volume reduction is very high since deposition space has not been available for many years. 65 refs., 10 figs., 4 tabs

State compacts and low-level waste

International Nuclear Information System (INIS)

Brown, H.

1984-01-01

In 1979, for the first time, low-level waste (LLW) was brought to the attention of policy makers in most states. For several decades, technical personnel had regulated and managed LLW, but elected officials and their staff had been largely ignorant of the origins and destination of low-level radioactive materials. Events in the fall of 1979 set in motion a sequence of events that has compelled the continuing attention of policy makers in every state in the nation. In December 1979, the Executive Committee of the National Governors' Association appointed an eight-member task force, chaired by Governor Bruce Babbitt of Arizona, to review low-level waste management and to formulate state policy by July 1980. The principal findings were as follows: 1. LLW could be managed most efficiently, both technically and politically, at the state level. 2. Each state should take responsibility for its own waste. 3. The creation of a regional waste management system by means of interstate compacts offered the best promise of creating new disposal capacity. 4. Regions should be allowed to exclude waste generated outside their borders after a specified date

Low-level waste certification plan

International Nuclear Information System (INIS)

Greenhalph, W.O.

1995-01-01

This plan describes the organization and methodology for the certification of solid low-level waste (LLW) and mixed-waste (MW) generated at any of the facilities or major work activities of the Engineered Process Application (EPA) organization. The primary LLW and MW waste generating facility operated by EPA is the 377 Building. This plan does not cover the handling of hazardous or non-regulated waste, though they are mentioned at times for completeness

Low-level radioactive waste vitrification: effect of Cs partitioning

International Nuclear Information System (INIS)

Horton, W.S.; Ougouag, A.M.

1986-01-01

The traditional Low-Level Radioactive Waste (LLW) immobilization options are cementation or bituminization. Either of these options could be followed by shallow-land burial (SLB) or above-ground disposal. These rather simple LLW procedures appeared to be readily available, to meet regulatory requirements, and to satisfy cost constraints. The authorization of State Compacts, the forced closure of half of the six SLB disposal facilities of the nation, and the escalation of transportation/disposal fees diminish the viability of these options. The synergetic combination of these factors led to a reassessment of traditional methods and to an investigation of other techniques. This paper analyzes the traditional LLW immobilization options, reviews the impact of the LLW stream composition on Low-Level Waste Vitrification (LLWV), then proposes and briefly discusses several techniques to control the volatile radionuclides in a Process Improved LLWV system (PILLWV)

Ensuring robust decisions and deployable solutions in UK LLW management

International Nuclear Information System (INIS)

Clark, Matthew

2014-01-01

The Nuclear Decommissioning Authority (NDA) is responsible for the decommissioning and site restoration of civil nuclear liabilities in the UK. Our decommissioning programme will last over 100 years and generate approximately 3.8 million m3 of LLW, three quarters of which will be VLLW. As well as decommissioning sites, our estate includes operations, such as power generation at Wylfa and reprocessing and waste management at Sellafield. As a result we have a clear interest in effective and affordable management of low level waste. This is further enhanced by two important aspects: our role in developing and implementing strategy for the management of nuclear industry LLW in the UK and our ownership of the Low Level Waste Repository, a critical part of the UK's radioactive waste management infrastructure. Disposal capacity at LLWR is a precious resource; recognition of this fact has provided effective leverage to changing the way LLW is managed in the UK. In 2010 we published the UK Nuclear Industry LLW Strategy which comprised three main themes: the waste hierarchy; making the best use of existing LLW management assets; and, the need for new fit-for-purpose waste management routes. In order to preserve disposal capacity at LLWR we wanted to increase choice for organisations that manage LLW. Regulation of the LLW management has also had to keep pace with and enable this change. Increasing choice requires an increased focus on making robust, and not always easy, decisions. In the past, 'LLW' was simply consigned for disposal at LLWR, now LLW managers have to make decisions between clearance, exemption, reuse, recycling, incineration and disposal. Arguably, these decisions become more finely balanced at the lower end of the LLW spectrum. In the UK, a number of tools and sources of support are in place to help with this process, including: the National LLW Programme; good practice guidance (industry led) on assessing Best Available Techniques; and a

Collective bads: The case of low-level radioactive waste compacts

International Nuclear Information System (INIS)

McGinnis, M.V.

1994-01-01

In low-level radioactive waste (LLW) compact development, policy gridlock and intergovernmental conflict between states has been the norm. In addition to the not-in-my-backyard (NIMBY) phenomenon, LLW compacts must content with myriad political and ethical dilemmas endemic to a particular collective bad. This paper characterizes the epistemology of collective bads, and reviews how LLW compacts deal with such bads. In addition, using data from survey questionnaires and interviews, this paper assesses the cooperative nature of LLW compacts in terms of their levels of regional autonomy, regional efficacy, allocation of costs and benefits, and their technocentric orientation

Development of the advanced package system for miscellaneous LLW

International Nuclear Information System (INIS)

Miyamoto, K.

1991-01-01

Miscellaneous LLW (low-level radioactive miscellaneous solid wastes) such as parts of machines, pieces of piping, HEPA filter, incineration ashes from nuclear power plants will be disposed in shallow land after stuffing into 200 liter steel drums. The package system of these miscellaneous LLW is required to contain such radionuclides as 14 C, 137 Cs and etc. for a few hundred years. The advanced package system for miscellaneous LLW has been developed. This package system is composed of steel drums with resin mortar inner liner and non shrinkage fills with high flowability. Resin mortar liners have stronger water permeability resistance and higher compressive strength than other cement mortars. Strong water permeability resistance of resin mortar liners prevent underground water from infiltration into fills and solid wastes. On the other hand, as the high flowabilities and non shrinkage of this fills give very low gross void fraction of the package system and have strong adsorption ability of radionuclides. In addition, steel drums with resin mortar inner liners have merits in their high density, uniformity and simplicity in manufacturing. Consequently, this package system is promising candidate barrier for the containment of radionuclides from miscellaneous LLW. (J.P.N.)

Issue briefs on low-level radioactive wastes

International Nuclear Information System (INIS)

1981-01-01

This report contains 4 Issue Briefs on low-level radioactive wastes. They are entitled: Handling, Packaging, and Transportation, Economics of LLW Management, Public Participation and Siting, and Low Level Waste Management

Performance assessment strategy for low-level waste disposal sites

International Nuclear Information System (INIS)

Starmer, R.J.; Deering, L.G.; Weber, M.F.

1988-01-01

This paper describes US Nuclear Regulatory Commission (NRC) staff views on predicting the performance of low-level radioactive waste disposal facilities. Under the Atomic Energy Act, as amended, and the Low Level Radioactive Waste Policy Act, as amended, the NRC and Agreement States license land disposal of low-level radioactive waste (LLW) using the requirements in 10 CFR Part 61 or comparable state requirements. The purpose of this paper is to briefly describe regulatory requirements for performance assessment in low-level waste licensing, a strategy for performance assessments to support license applications, and NRC staff licensing evaluation of performance assessments. NRC's current activities in developing a performance assessment methodology will provide an overall systems modeling approach for assessing the performance of LLW disposal facilities. NRC staff will use the methodology to evaluate performance assessments conducted by applicants for LLW disposal facilities. The methodology will be made available to states and other interested parties

How a developing country is facing LLW disposal problem

International Nuclear Information System (INIS)

Huang, C.C.; Shao, Y.T.; Tsai, C.M.

1993-01-01

Taiwan is a small island which measures about 36,000 square kilometers with over 70% mountainous area. Today over 90% of low-level radioactive waste (LLW) is produced from six nuclear power units operated by the Taiwan Power Company (Taipower or TPC). The rest of the country's LLW is produced from medical, agricultural, industrial, educational and research programs. Due to the fact that over 90% of Taiwan's LLW is produced by Taipower, Taipower was designated by the Government to dispose of LLW for entire country. This paper will focus on the planning and implementation of the first phase. Through area screening and potential site evaluation, candidate sites will be selected based on currently available information and sites investigation. At the same time, the disposal methods will be evaluated in terms of safety, cost, and Taiwan's generic conditions of climate, geology, and topography. The conceptual design of the disposal method(s) will then be developed. Also, during site investigation, preliminary designs will be made

Economy may be harmed by lack of LLW disposal

International Nuclear Information System (INIS)

Anon.

1994-01-01

A study released by Organizations United for Responsible Low-Level Radioactive Waste Solutions warns that the substantial benefits of using radioactive materials are threatened by the lack of a low-level waste (LLW) disposal facility. The main point of the study is the threat to the American economy posed by insufficient facilities for disposal of the 1.7 billion ft 3 of LLW produced by the use of radioactive materials every year only 34.8 percent of which comes from nuclear power plants. open-quotes Thirty years of experience have provided the technical knowledge to design waste disposal facilities that protect the public and environment. But an impending lack of adequate disposal facilities jeopardizes our continued use of radioactive materials,close quotes according to the study

Mechanisms of long-term concrete degradation in LLW disposal facilities

International Nuclear Information System (INIS)

Rogers, V.C.

1987-01-01

Most low-level waste (LLW) disposal alternatives, except shallow land burial and improved shallow land burial, involve the use of concrete as an extra barrier for containment. Because concrete is a porous-type material, its moisture retention and transport properties can be characterized with parameters that are also used to characterize the geohydrologic properties of soils. Several processes can occur with the concrete to degrade it and to increase both the movement of water and contaminants through the disposal facility. The effect of these processes must be quantified in designing and estimating the long-term performance of disposal facilities. Modeling the long-term performance of LLW disposal technologies involves, first, estimating the degradation rate of the concrete in a particular facility configuration and environmental setting; second, calculating the water flow through the facility as a function of time; third, calculating the contaminant leaching usually by diffusion or dissolution mechanisms, and then coupling the facility water and contaminant outflow to a hydrogeological and environmental uptake model for environmental releases or doses

Strategy and plan for siting and licensing a Rocky Mountain low-level radioactive waste facility

International Nuclear Information System (INIS)

Whitman, M.

1983-09-01

In 1979, the States of Nevada and Washington temporarily closed their commercial low-level radioactive waste (LLW) disposal facilities and South Carolina, the only other state hosting such a facility, restricted the amount of waste it would accept. All three states then announced that they did not intend to continue the status quo of accepting all of the country's commercial low-level radioactive waste. Faced with this situation, other states began considering alternative LLW management and disposal options. In the Rocky Mountain region, this evolved into discussions for the development of an interstate compact to manage low-level waste. Inherent in this management plan was a strategy to site and license a new LLW disposal facility for the Rocky Mountain region. The Rocky Mountain Low-Level Radioactive Waste Compact was negotiated over the course of a year, with final agreement on the language of the compact agreed to in early 1982. States eligible to join the compact are Arizona, Colorado, Nevada, New Mexico, Utah, and Wyoming. Colorado adopted the compact into law in 1982, and Nevada, New Mexico and Wyoming adopted it in 1983. Utah has joined the Northwest Compact, although it may decide to join the Rocky Mountain Compact after a new disposal facility is developed for the region. Arizona has taken no action on the Rocky Mountain Compact

Information systems to support low-level waste management: perspective from the State of Illinois

International Nuclear Information System (INIS)

Willaford, D.M.

1987-01-01

The Illinois Department of Nuclear Safety (IDNS) is required by state law to develop a comprehensive regulatory system for low-level radioactive waste (LLW) management. Reliable, extensive information about LLW in Illinois is needed to plan and implement such a regulatory program. IDNS annually surveys, by mail and follow-up phone calls, approximately 260 LLW generators in Illinois. This information is being supplemented by a more detailed characterization of waste streams. Additional information needed for IDNS's regulatory program includes data on components of a waste disposal facility (e.g., concrete performance), site and performance computer models for various kinds of sites and for alternative waste disposal facility designs. In the future, all states will need more information than has been historically the case, given the changes in management and disposal systems and the increased role of the states

Intermodal transportation of low-level radioactive waste to the Nevada Test Site

International Nuclear Information System (INIS)

1998-09-01

The Nevada Test Site (NTS) presently serves as a disposal site for low-level radioactive waste (LLW) generated by DOE-approved generators. The environmental impacts resulting from the disposal of LLW at the NTS are discussed in the Final Environmental Impact Statement (EIS) for the Nevada Test Site Off-Site Locations in the State of Nevada (NTS EIS). During the formal NTS EIS scoping period, it became clear that transportation of LLW was an issue that required attention. Therefore, the Nevada Transportation Protocol Working Group (TPWG) was formed in 1995 to identify, prioritize, and understand local issues and concerns associated with the transportation of LLW to the NTS. Currently, generators of LLW ship their waste to the NTS by legal-weight truck. In 1995, the TPWG suggested the DOE could reduce transportation costs and enhance public safety by using rail transportation. The DOE announced, in October 1996, that they would study the potential for intermodal transportation of LLW to the NTS, by transferring the LLW containers from rail cars to trucks for movements to the NTS. The TPWG and DOE/NV prepared the NTS Intermodal Transportation Facility Site and Routing Evaluation Study to present basic data and analyses on alternative rail-to-truck transfer sites and related truck routes for LLW shipments to the NTS. This Environmental Assessment (EA) identifies the potential environmental impacts and transportation risks of using new intermodal transfer sites and truck routes or continuing current operations to accomplish the objectives of minimizing radiological risk, enhancing safety, and reducing cost. DOE/NV will use the results of the assessment to decide whether or not to encourage the LLW generators and their transportation contractors to change their current operations to accomplish these objectives

Summary report, low-level radioactive waste management activities in the states and compacts. Vol. 4. No. 1

International Nuclear Information System (INIS)

1996-01-01

'Low-Level Radioactive Waste Management Activities in the States and Compacts' is a supplement to 'LLW Notes' and is distributed periodically by Afton Associates, Inc. to state, compact and federal officials that receive 'LLW Notes'. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

Summary report. Low-level radioactive waste management activities in the states and compacts. Volume 4, No. 2

International Nuclear Information System (INIS)

1996-08-01

'Low-Level Radioactive Waste Management Activities in the States and Compacts' is a supplement to 'LLW Notes' and is distributed periodically by Afton Associates, Inc. to state, compact and federal officials that receive 'LLW Notes'. The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representatives, appointed by governors and compact commissions, established to facilitate state and compact implementation of the Low- Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The LLW Forum provides an opportunity for state and compact officials to share information with one another and to exchange views with officials of federal agencies and other interested parties

An overview of commercial low-level radioactive waste disposal technology

International Nuclear Information System (INIS)

Plummer, T.L.; Morreale, B.J.

1991-01-01

The primary objective of low-level radioactive (LLW) waste management is to safely dispose of LLW while protecting the health of the public and the quality of the environment. LLW in the United States is generated through both Department of Energy (DOE) and commercial activities. In this paper, waste from commercial activities will be referred to as ''commercial LLW.'' The DOE waste will not be discussed in this paper. Commercial LLW is waste that is generated by Nuclear Regulatory Commission (NRC) designated licensees or Agreement States. Commercial LLW is generated by nuclear power reactors, hospitals, universities, and manufacturers. This paper will give an overview of the current disposal technologies planned by selected States' for disposing of their LLW and the processes by which those selections were made. 3 refs

Solid low level waste management guidelines: Final report

International Nuclear Information System (INIS)

Castagnacci, A.; Dalton, D.; Genoa, P.

1994-11-01

Since 1989, the nuclear industry has been moving in the direction of greater minimization of low level radioactive waste (LLW). This has been driven in part by increasing regulatory attention, but it also is in response to the desire on the part of nuclear utilities to be more cost efficient and to be environmentally responsive. Over the past half-dozen years, LLW disposal costs have increased dramatically. In addition, improvements in LLW volume reduction technologies have substantially reduced the volume of LLW that is disposed. At the same time, utilities are implementing aggressive source reduction programs and programs to reuse materials so as to extend the useful life of many materials. Thus, there has been a dramatic change in LLW economics and LLW management practices in just the past few years. This report was developed by utility nuclear experts to provide guidance to all utilities on mechanisms for integrating the program economics, advanced volume reduction techniques, and approaches to source reduction. Thus, utilizes will be able to use this report as a guide to optimizing their LLW program economics and minimizing LLW disposal volumes to the smallest reasonable fraction. This report discusses the implementation of these guidelines, management support, waste materials and waste inventory, radioactive tool and equipment management, protective clothing management, processing and volume reduction, solid LLW tracking, outage LLW management, and interim storage of LLW

Waste management system functional requirements for Interim Waste Management Facilities (IWMFs) and technology demonstrations, LLWDDD [Low-Level Disposal Development and Demonstration] Program

International Nuclear Information System (INIS)

1988-03-01

The purpose of this report is to build upon the preceding decisions and body of information to prepare draft system functional requirements for each classification of waste disposal currently proposed for Low-Level Waste Disposal Development Demonstration (LLWDDD) projects. Functional requirements identify specific information and data needs necessary to satisfy engineering design criteria/objectives for Interim Waste Management Facilities. This draft will suppor the alternatives evaluation process and will continue to evolve as strategy is implemented, regulatory limits are established, technical and economic uncertainties are resolved, and waste management plans are being implemented. This document will become the planning basis for the new generation of solid LLW management facilities on new sites on the Reservation. Eighteen (18) general system requirements are identified which are applicable to all four Low-Level Waste (LLW) disposal classifications. Each classification of LLW disposal is individually addressed with respect ot waste characteristics, site considerations, facility operations, facility closure/post-closure, intruder barriers, institutional control, and performance monitoring requirements. Three initial LLW disposal sites have been proposed as locations on the ORR for the first demonstrations

LLW Dumpster study: Task 009

International Nuclear Information System (INIS)

Frye, J.A.

1989-08-01

Over a span of several years, the public has reported visible leakage emanating from ten cubic yard Dumpsters used to transport Low Level Radioactive Wastes (LLW) from LANL generation sites to the disposal site at TA-54, Area G. The purpose of this study was to: Investigate probable causes of leakages, Inspect existing Dumpsters in the fields Propose immediate short-range solutions to the problem, and Propose long-range solutions based on predicted future requirements. Field investigations indicated that LLW is handled carefully and professional at the individual generation sites and again during pick-up delivery, and disposal at TA-54. It was also apparent, however, that Dumpsters not designed for LLW service are used to store this radioactive material for extended time periods while being subjected to the full range of Northern New Mexico weather conditions. All Dumpsters inspected had 1/8 in to 2 in gaps in their closures (loading doors and discharge ramps) through which driving rain or melting snow could easily enter. Seven Dumpsters were located outside secure areas. No cases of actual contamination were discovered, only the appearance of contamination i.e. the dripping of collected rainwater or melting ice and snow from Dumpsters being transported over public roads

Draft low level waste technical summary

International Nuclear Information System (INIS)

Powell, W.J.; Benar, C.J.; Certa, P.J.; Eiholzer, C.R.; Kruger, A.A.; Norman, E.C.; Mitchell, D.E.; Penwell, D.E.; Reidel, S.P.; Shade, J.W.

1995-09-01

The purpose of this document is to present an outline of the Hanford Site Low-Level Waste (LLW) disposal program, what it has accomplished, what is being done, and where the program is headed. This document may be used to provide background information to personnel new to the LLW management/disposal field and to those individuals needing more information or background on an area in LLW for which they are not familiar. This document should be appropriate for outside groups that may want to learn about the program without immediately becoming immersed in the details. This document is not a program or systems engineering baseline report, and personnel should refer to more current baseline documentation for critical information

Low-level-waste-treatment handbook

International Nuclear Information System (INIS)

Clinton, S.D.; Goeller, H.E.; Holladay, D.W.; Donaldson, T.L.

1982-01-01

The initial draft of the Low-Level Waste Treatment Handbook has been prepared and submitted to the DOE Low-Level Waste Management Program for review and comment. A revised draft is scheduled to be delivered to DOE Headquarters in December 1982. The Handbook is designed to be useful to all individuals and groups concerned with low-level wastes. It is one of several volumes that will ultimately comprise a Low-Level Waste Technology Handbook. The objective of the Low-Level Waste Treatment Handbook is to present an overview of current practices related to the segregation, classification, volume reduction, solidification, handling, packaging, and transportation of LLW for disposal in a shallow land burial facility. The Handbook is intended to serve as a guide to individuals interested in the treatment and handling of low-level radioactive waste. The Handbook will not explicitly tell the user how to design and operate LLW treatment facilities, but rather will identify (1) kinds of information required to evaluate the options, (2) methods that may be used to evaluate these options, and (3) limitations associated with the selection of the treatment options. The focus of the Handbook is providing guidance on how to do waste treatment for disposal by shallow land burial

LLW Forum meeting report, July 20--22, 1994

International Nuclear Information System (INIS)

1994-01-01

The Low-Level Radioactive Waste Forum (LLW Forum) is an association of state and compact representative, appointed by governors and compact commissions, established to facilitate state and compact commission implementation of the Low-Level radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies. This report details activities of the meeting held July 20-22, 1994

Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Task 2b: Earth-mounded concrete bunkers

International Nuclear Information System (INIS)

Denson, R.H.; Bennett, R.D.; Wamsley, R.M.; Bean, D.L.; Ainsworth, D.L.

1988-01-01

The US Army Engineers Waterways Experiment Station (WES) and US Army Engineer Division, Huntsville (HNDED) have developed general design criteria and specific design review criteria for the earth-mounded concrete bunker (EMCB) alternative method of low-level radioactive waste (LLW) disposal. An EMCB is generally described as a reinforced concrete vault placed below grade, underneath a tumulus, surrounded by filter-blanket and drainage zones. The tumulus is covered over with a low permeability cover layer and top soil with vegetation. Eight major review criteria categories have been developed ranging from the loads imposed on the EMCB structure through material quality and durability considerations. Specific design review criteria have been developed in detail for each of the eight major categories. 63 refs., 13 figs., 2 tabs

LLW Notes, Volume 12, Number 3

International Nuclear Information System (INIS)

Norris, C.; Brown, H.; Colsant, J.; Lovinger, T.; Scheele, L.; Shaker, M.A.

1997-03-01

Contents include articles entitled: California DHS sues US Interior Department to compel land transfer; LLW Forum holds winter meeting; LLW Forum waste information working group meets; LLW Forum regulatory issues discussion group meets; Envirocare investigation transferred to feds; Host state TCC meets in Laughlin, Nevada; BLM to require new permit for California site testing; Federal agencies and committees; Pena sworn in as Energy Secretary, Grumbly departs DOE; U.S. Supreme Court tackles property rights issues; GAO to study DOI's actions; Congress scrutinizes FY '98 budget requests; and Senate committee passes high-level waste bill: Clinton threatens to veto

Oak Ridge low-level waste disposal facility designs

International Nuclear Information System (INIS)

Van Hoesen, S.D.; Jones, L.S.

1991-01-01

The strategic planning process that culuminates in the identification, selection, construction, and ultimate operation of treatment, storage, and disposal facilities for all types of low-level waste (LLW) generated on the Oak Ridge Reservation (ORR) was conducted under the Low-Level Waste Disposal Development and Demonstration (LLWDDD) Program. This program considered management of various concentrations of short half-life radionuclides generated principally at Oak Ridge National Laboratory (ORNL) and long half-life radionuclides (principally uranium) generated at the Oak Ridge Y-12 Plant and the Oak Ridge K-25 Plant. The LLWDDD Program is still ongoing and involves four phases: (1) alternative identification and evaluation, (2) technology demonstration, (3) limited operational implementation, and (4) full operational implementation. This document provides a discussion of these phases

Development of threshold guidance: National Low-Level Radioactive Waste Management Program

International Nuclear Information System (INIS)

1986-09-01

The current study has been conducted to provide DOE with a technical basis for the development of threshold guidance. The objective of the study was to develop the necessary background information and recommendations to assist the DOE in implementing the threshold limit concept for the disposal of DOE wastes at DOE facilities. The nature of low-level radioactive waste (LLW) varies greatly in both form and radionuclide content. While some low-level waste streams can contain substantial quantities of radioactive constituents, a potentially significant fraction of low-level waste is contaminated either very slightly or not at all. There is a strong likelihood that managing wastes with extremely low levels of radioactivity as nonradioactive waste would pose no significant safety problems and could result in substantial cost savings relative to its handling as LLW. Since all materials, including waste products, contain some radioactivity, it is necessary to distinguish between those wastes that would require disposal as LLW and those that have sufficiently low levels of radiological content to be managed according to their nonradiological properties. 131 refs., 9 figs., 24 tabs

Comments on EPA's LLW preproposal

International Nuclear Information System (INIS)

Littleton, B.K.; Weinstock, L.

1995-01-01

The Environmental Protection Agency (EPA) is currently developing standards for the management, storage, and disposal of Low-Level Radioactive Waste (LLW). The Atomic Energy Act delegated EPA, among other provisions, the authority to establish generally applicable standards for the disposal of radioactive waste to ensure that the public and the environment are adequately protected from potential radiation impacts. As an initial effort to open communications on a standard for LLW, the Agency developed a preproposal draft (Preproposal Draft of 40 CFR Part 193 - 30 Nov 94) and circulated it to interested parties for review and comment. The extended comment period ended April 12, 1995. A summary of the comments received and analyzed to date follows. After all comments have been analyzed, the rule will undergo an Agency clearance process and be sent to the Office of Management and Budget for review. After that review, the formal process of publication of the proposed rule in the Federal Register and the formal public comment period will begin

Remote-Handled Low-Level Waste Disposal Project Code of Record

Energy Technology Data Exchange (ETDEWEB)

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2012-06-01

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

Remote-Handled Low-Level Waste Disposal Project Code of Record

Energy Technology Data Exchange (ETDEWEB)

S.L. Austad, P.E.; L.E. Guillen, P.E.; C. W. McKnight, P.E.; D. S. Ferguson, P.E.

2014-06-01

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

Remote-Handled Low-Level Waste Disposal Project Code of Record

Energy Technology Data Exchange (ETDEWEB)

Austad, S. L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Guillen, L. E. [Idaho National Lab. (INL), Idaho Falls, ID (United States); McKnight, C. W. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Ferguson, D. S. [Idaho National Lab. (INL), Idaho Falls, ID (United States)

2015-04-01

The Remote-Handled Low-Level Waste (LLW) Disposal Project addresses an anticipated shortfall in remote-handled LLW disposal capability following cessation of operations at the existing facility, which will continue until it is full or until it must be closed in preparation for final remediation of the Subsurface Disposal Area (approximately at the end of Fiscal Year 2017). Development of a new onsite disposal facility will provide necessary remote-handled LLW disposal capability and will ensure continuity of operations that generate remote-handled LLW. This report documents the Code of Record for design of a new LLW disposal capability. The report is owned by the Design Authority, who can authorize revisions and exceptions. This report will be retained for the lifetime of the facility.

Recommendations to the NRC for review criteria for alternative methods of low-level radioactive waste disposal: Task 2a, Below-ground vaults

International Nuclear Information System (INIS)

Denson, R.H.; Bennett, R.D.; Wamsley, R.M.; Bean, D.L.; Ainsworth, D.L.

1987-12-01

The US Army Engineer Waterways Experiment Station (WES) and the US Army Engineer Division, Huntsville (HNDED) have developed general design criteria and specific design review criteria for the below-ground vault (BGV) alternative method of low-level radioactive waste (LLW) disposal. A BGV is a reinforced concrete vault (floor, walls, and roof) placed underground below the frost line, and above the water table, surrounded by filter blanket and drainage zones and covered with a low permeability earth layer and top soil with vegetation. Eight major review criteria categories have been developed ranging from the loads imposed on the BGV structure through material quality and durability considerations. Specific design review criteria have been developed in detail for seven of the eight major categories. 59 refs., 14 figs., 2 tabs

Demonstration tests for low level radioactive waste packaging safety

International Nuclear Information System (INIS)

Nagano, I.; Shimura, S.; Miki, T.; Tamamura, T.; Kunitomi, K.

1993-01-01

The transport packaging for low level radioactive waste (so-called the LLW packaging) has been developed to be utilized for transportation of LLW in 200 liter-drums from Japanese nuclear power stations to the LLW Disposal Center at Rokkashomura in Aomori Prefecture. Transportation is expected to start from December in 1992. We will explain the brief history of the development, technical features and specifications as well as two kinds of safety demonstration tests, namely one is '1.2 meter free drop test' and the other is 'ISO container standard test'. (J.P.N.)

State implementation of the Low-Level Radioactive Waste Policy Amendments Act of 1985: Progress and issues

International Nuclear Information System (INIS)

Tait, T.D.

1987-03-01

The 1980 Low-Level Radioactive Waste Policy Act (Public Law 96-573) assigned each state the responsibility for providing disposal capacity for the low-level radioactive waste (LLW) generated within its borders, except for certain LLW generated by the activities of the federal government. The law also authorized and encouraged states to enter into interstate compacts to provide for the establishment and operation of regional LLW disposal facilities. The January 1986 enactment of Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA), resolved an impasse that had delayed congressional consent to seven interstate compacts formed for the regional disposal of LLW. The Act ensures that LLW generators will have continued access to the three existing commercial LLW disposal sites through 1992 as long as their states or regions are in compliance with milestones prescribed in the Act for development of new disposal facilities. Furthermore, the LLRWPAA assigned several responsibilities to the Department of Energy. The objective of the Low-Level Radioactive Waste Policy Amendments Act of 1985 is to ensure the development of an effective, safe, and environmentally acceptable nationwide system for the disposal of LLW by 1993. The Department of Energy is assisting the states and regions to achieve that objective and ensure that the system that is developed provides for the safe management and disposal of LLW at reasonable costs. Furthermore, the Department is working with the states and regions to ensure that while the new system is being developed, there are not disruptions in the current LLW management and disposal practices and that the public continues to receive the benefits of the industries that rely on nuclear materials to deliver their services

Hanford low-level vitrification melter testing -- Master list of data submittals

International Nuclear Information System (INIS)

Hendrickson, D.W.

1995-01-01

The Westinghouse Hanford Company (WHC) is conducting a two-phased effort to evaluate melter system technologies for vitrification of liquid low-level radioactive waste (LLW) streams. The evaluation effort includes demonstration testing of selected glass melter technologies and technical reports regarding the applicability of the glass melter technologies to the vitrification of Hanford LLW tank waste. The scope of this document is to identify and list vendor document submittals in technology demonstration support of the Hanford Low-Level Waste Vitrification melter testing program. The scope of this document is limited to those documents responsive to the Statement of Work, accepted and issued by the LLW Vitrification Program. The purpose of such a list is to maintain configuration control of vendor supplied data and to enable ready access to, and application of, vendor supplied data in the evaluation of melter technologies for the vitrification of Hanford low-level tank wastes

LLW Forum meeting report, April 18--19, 1991

International Nuclear Information System (INIS)

1991-01-01

The Low-Level Radioactive Waste Forum is an association of representatives of states and compacts established to facilitate state and compact commission implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies. LLW Forum participants include representatives from regional compacts, designated host states, unaffiliated states, and states with currently- operating low-level radioactive waste facilities. This quarterly meeting was held on April 18-19, 1991

Guidance for closure of existing DOE LLW disposal sites

International Nuclear Information System (INIS)

Blanchfield, L.

1987-01-01

During FY 1986, a closure guidance document was developed. The purpose of this document is to provide guidance in support of DOE Order 5820.2 to site operating contractors for the stabilization and closure of existing low-level waste (LLW) shallow land disposal sites at US Department of Energy (DOE) facilities. Guidance is provided to aid operators in placing existing LLW sites in a closed conditions, i.e., a condition in which a nonoperational site meets postclosure performance requirements and can be shown, within a high degree of confidence, to perform as anticipated in the future, under the most cost-effective maintenance approach. Guidance is based on the philosophy that closure should be planned and performed using a systems approach. Plans for FY 1987 call for revision of the document to incorporate more information on closure of LLW sites also containing radioactive mixed waste and/or transuranic waste. 4 references, 3 figures, 2 tables

The Yami's opposition to the Lanyu LLW storage installation

International Nuclear Information System (INIS)

Li, K.K.; Chang, S.Y.

1993-01-01

Since 1982, the solidified low-level radioactive wastes (LLW) in Taiwan, regardless of the origins, have been sent to Lanyu for interim storage. Lanyu is a small island located 80 kilometers southeast of Taiwan. Its unique Polynesian cultural characteristics make it an attractive tourist spot. Dissatisfaction of being the commonly neglected powerless minority, in addition to the political claims from the outside environmental activists made the majority of the Lanyu residents oppose the operation of the storage facility. Approximately 80,000 drums of these wastes have been sent to Lanyu. Although the radiological monitoring results demonstrated that the current operation causes negligible impact on the environment. Accounting for the fast changing social and political situations in Taiwan today, without a good public acceptance program for both sides, the continuous operation of the Lanyu LLW storage facility until the year 2002, at which time the LLW disposal facility will be commissioned, could be in limbo

Greater-than-Class C low-level radioactive waste characterization. Appendix E-4: Packaging factors for greater-than-Class C low-level radioactive waste

International Nuclear Information System (INIS)

Quinn, G.; Grant, P.; Winberg, M.; Williams, K.

1994-09-01

This report estimates packaging factors for several waste types that are potential greater-than-Class C (GTCC) low-level radioactive waste (LLW). The packaging factor is defined as the volume of a GTCC LLW disposal container divided by the as-generated or ''unpackaged'' volume of the waste loaded into the disposal container. Packaging factors reflect any processes that reduce or increase an original unpackaged volume of GTCC LLW, the volume inside a waste container not occupied by the waste, and the volume of the waste container itself. Three values are developed that represent (a) the base case or most likely value for a packaging factor, (b) a high case packaging factor that corresponds to the largest anticipated disposal volume of waste, and (c) a low case packaging factor for the smallest volume expected. GTCC LLW is placed in three categories for evaluation in this report: activated metals, sealed sources, and all other waste

Models and criteria for LLW disposal performance

International Nuclear Information System (INIS)

Smith, C.F.; Cohen, J.J.

1980-12-01

A primary objective of the Low Level Waste (LLW) Management Program is to assure that public health is protected. Predictive modeling, to some extent, will play a role in meeting this objective. This paper considers the requirements and limitations of predictive modeling in providing useful inputs to waste mangement decision making. In addition, criteria development needs and the relation between criteria and models are discussed

Models and criteria for LLW disposal performance

International Nuclear Information System (INIS)

Smith, C.F.; Cohen, J.J.

1980-01-01

A primary objective of the Low Level Waste (LLW) Management Program is to assure that public health is protected. Predictive modeling, to some extent, will play a role in meeting this objective. This paper considers the requirements and limitations of predictive modeling in providing useful inputs to waste management decision making. In addition, criteria development needs and the relation between criteria and models are discussed

Legislator's guide to low-level radioactive waste management

International Nuclear Information System (INIS)

Jordan, J.M.; Melson, L.G.

1981-05-01

The purpose of the guide is to provide state legislators and their staff with information on low-level radioactive waste management, issues of special concern to the states, and policy options. During 1979, producers of low-level radioactive wastes (LLW) faced a crisis. Two of the three commercial disposal sites were temporarily closed and some LLW producers were running short on storage space. For hospitals, clinics, research organizations, and some industries, this meant potential curtailment of activities that produced these materials. Commercial nuclear reactors were not as hard hit during the crisis because they have larger storage areas. The two sites at Beatty, Nevada, and Hanford, Washington, reopened and the immediate crisis was averted. However, the longer term problem of shortage of disposal capacity was just beginning to be recognized. States should be concerned with this problem for several reasons. First, all states produce LLW although the volumes differ among states. Second, states have the responsibility to protect the public health and welfare of their citizens. Third, states may be given the authority to regulate LLW disposal if they enter into agreements with the federal government (Agreement States Program), and 26 states have that authority. Fourth, because of the long-term monitoring and surveillance necessary at a disposal site, states rather than private industry will be held responsible for ensuring that the disposal site is performing safely. Finally, Congress established a policy in 1980 that each state is responsible for the safe disposal of LLW generated within its borders. This policy also includes provisions that could lead to excluding states from using disposal facilities unless they have entered into regional agreements with other states. Two primary options exist for a state: developing its own disposal facility for LLW generated within its borders or joining with other states to develop a regional disposal facility

LLW Forum meeting report, April 25--27, 1994

International Nuclear Information System (INIS)

1994-01-01

The Low-Level radioactive Waste Forum is an association of representatives of states and compacts established to facilitate state and compact commission implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies. LLW Forum participants include representatives from regional compacts, designated host states, unaffiliated states, and states with currently-operating low-level radioactive waste facilities. This quarterly meeting was held April 25-27, 1994 and activities during the first quarter of 1994 are detailed

LLW Forum meeting report, April 25--27, 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-31

The Low-Level radioactive Waste Forum is an association of representatives of states and compacts established to facilitate state and compact commission implementation of the Low-Level Radioactive Waste Policy Act of 1980 and the Low-Level Radioactive Waste Policy Amendments Act of 1985 and to promote the objectives of low-level radioactive waste regional compacts. The Forum provides an opportunity for states and compacts to share information with one another and to exchange views with officials of federal agencies. LLW Forum participants include representatives from regional compacts, designated host states, unaffiliated states, and states with currently-operating low-level radioactive waste facilities. This quarterly meeting was held April 25-27, 1994 and activities during the first quarter of 1994 are detailed..

Low-level radioactive waste facility siting in the Rocky Mountain compact region

International Nuclear Information System (INIS)

Whitman, M.

1983-09-01

The puprose of the Rocky Mountain Low-Level Radioactive Waste Compact is to develop a regional management system for low-level waste (LLW) generated in the six states eligible for membership: Arizona, Colorado, Nevada, New Mexico, Utah and Wyoming. Under the terms of the compact, any party state generating at least 20% of the region's waste becomes responsible for hosting a regional LLW management facility. However, the compact prescribes no system which the host state must follow to develop a facility, but rather calls on the state to fulfill its responsibility through reliance on its own laws and regulations. Few of the Rocky Mountain compact states have legislation dealing specifically with LLW facility siting. Authority for LLW facility siting is usually obtained from radiation control statutes and solid or hazardous waste statutes. A state-by-state analysis of the siting authorities of each of the Rock Mountain compact states as they pertain to LLW disposal facility siting is presented. Siting authority for LLW disposal facilities in the Rocky Mountain compact region runs from no authority, as in Wyoming, to general statutory authority for which regulations would have to be promulgated, as in Arizona and Nevada, to more detailed siting laws, as in Colorado and New Mexico. Barring an amendment to, or different interpretation of, the Utah Hazardous Waste Facility Siting Act, none of the Rocky Mountain States' LLW facility siting authorities preempt local veto authorities

Low-level waste program technical strategy

International Nuclear Information System (INIS)

Bledsoe, K.W.

1994-01-01

The Low-Level Waste Technical Strategy document describes the mechanisms which the Low-Level Waste Program Office plans to implement to achieve its mission. The mission is to manage the receipt, immobilization, packaging, storage/disposal and RCRA closure (of the site) of the low-level Hanford waste (pretreated tank wastes) in an environmentally sound, safe and cost-effective manner. The primary objective of the TWRS Low-level waste Program office is to vitrify the LLW fraction of the tank waste and dispose of it onsite

Managing Greater-Than-Class C low-level radioactive waste: A strategic plan

International Nuclear Information System (INIS)

1990-04-01

This strategic plan describes the DOE goals, objectives, and strategy for fulfilling its responsibility to dispose of Greater-Than-Class C low-level radioactive waste (GTCC LLW), in accordance with the requirements of Section 3(b) of the Low-Level Radioactive Waste Policy Amendments Act of 1985, Public Law 99-240. The strategy for fulfilling this responsibility consists of three sequential tasks: interim storage of limited quantities of GTCC LLW at currently operating DOE facilities on an as-needed basis; general acceptance of GTCC LLW for storage in a DOE dedicated facility pending disposal; and disposal in a facility licensed by the Nuclear Regulatory Commission (NRC). The objectives, assumptions, and strategies for each of these tasks are presented in this plan

FUNDING ALTERNATIVES FOR LOW-LEVEL WASTE DISPOSAL

International Nuclear Information System (INIS)

Becker, Bruce D.; Carilli, Jhon

2003-01-01

For 13 years, low-level waste (LLW) generator fees and disposal volumes for the U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Operations Office (NNSA/NV) Radioactive Waste Management Sites (RWMSs) had been on a veritable roller coaster ride. As forecast volumes and disposal volumes fluctuated wildly, generator fees were difficult to determine and implement. Fiscal Year (FY) 2000 forecast projections were so low, the very existence of disposal operations at the Nevada Test Site (NTS) were threatened. Providing the DOE Complex with a viable, cost-effective disposal option, while assuring the disposal site a stable source of funding, became the driving force behind the development of the Waste Generator Access Fee at the NTS. On September 26, 2000, NNSA/NV (after seeking input from DOE/Headquarters [HQ]), granted permission to Bechtel Nevada (BN) to implement the Access Fee for FY 2001 as a two-year Pilot Program. In FY 2001 (the first year the Access Fee was implemented), the NTS Disposal Operations experienced a 90 percent increase in waste receipts from the previous year and a 33 percent reduction in disposal fee charged to the waste generators. Waste receipts for FY 2002 were projected to be 63 percent higher than FY 2001 and 15 percent lower in cost. Forecast data for the outyears are just as promising. This paper describes the development, implementation, and ultimate success of this fee strategy

Design and operational considerations of United States commercial near-surface low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Birk, S.M.

1997-10-01

In accordance with the Low-Level Radioactive Waste Policy Amendments Act of 1985, states are responsible for providing for disposal of commercially generated low-level radioactive waste (LLW) within their borders. LLW in the US is defined as all radioactive waste that is not classified as spent nuclear fuel, high-level radioactive waste, transuranic waste, or by-product material resulting from the extraction of uranium from ore. Commercial waste includes LLW generated by hospitals, universities, industry, pharmaceutical companies, and power utilities. LLW generated by the country''s defense operations is the responsibility of the Federal government and its agency, the Department of Energy. The commercial LLRW disposal sites discussed in this report are located near: Sheffield, Illinois (closed); Maxey Flats, Kentucky (closed); Beatty, Nevada (closed); West Valley, New York (closed); Barnwell, South Carolina (operating); Richland, Washington (operating); Ward Valley, California, (proposed); Sierra Blanca, Texas (proposed); Wake County, North Carolina (proposed); and Boyd County, Nebraska (proposed). While some comparisons between the sites described in this report are appropriate, this must be done with caution. In addition to differences in climate and geology between sites, LLW facilities in the past were not designed and operated to today''s standards. This report summarizes each site''s design and operational considerations for near-surface disposal of low-level radioactive waste. The report includes: a description of waste characteristics; design and operational features; post closure measures and plans; cost and duration of site characterization, construction, and operation; recent related R and D activities for LLW treatment and disposal; and the status of the LLW system in the US

Plans for managing greater-than-glass C low-level waste

International Nuclear Information System (INIS)

Newberry, W.F.; Coleman, J.A.

1990-01-01

Low-level waste is defined in the Low-Level Radioactive Waste Policy Amendments Act of 1985 (Title I, Public Law 99-240) as radioactive waste that is neither high-level radioactive waste, spent nuclear fuel, nor by-product material (mill tailings). This paper presents proposed plans for the Department of Energy to fulfill its responsibility to dispose of GTCC LLW under the 1985 law, and to ensure that safe options are available for long-term management of such, pending the availability of disposal capacity. In the absence of a concentration-based definition for high-level waste, there currently is no upper bound for the concentration of radionuclides in low-level waste. DOE's plans for managing and disposing of GTCC LLW are generally consistent with a report issued by the Congressional Office of Technology Assessment in October 1988, An Evaluation of Options for Managing Greater-than-Class C Low-Level Radioactive Waste

Department of Energy low-level radioactive waste disposal concepts

International Nuclear Information System (INIS)

Ozaki, C.; Page, L.; Morreale, B.; Owens, C.

1990-01-01

The Department of Energy manages its low-level waste (LLW), regulated by DOE Order 5820.2A by using an overall systems approach. This systems approach provides an improved and consistent management system for all DOE LLW waste, from generation to disposal. This paper outlines six basic disposal concepts used in the systems approach, discusses issues associated with each of the concepts, and outlines both present and future disposal concepts used at six DOE sites

Safety analysis and inventory control of transuranic and low-level waste in common storage

International Nuclear Information System (INIS)

Porten, D.R.; Bonner, A.L.; Joyce, J.P.

1993-01-01

This paper describes a methodology developed For the inventory control of low-level waste (LLW) and transuranic (TRU) waste, when both are stored in the same location, and both contribute to an inventory constrained by safety considerations. Development of the method arose from the necessity to make safety analysis calculations for the addition of LLW, in quantities greater than existing inventory limits would allow when stored with TRU waste, in the Hanford Central Waste Complex (CWC)-Ensuring that the dose consequences of credible releases are maintained at low-hazard limits or less, was used to allow greater than Type A quantities of LLW into the CWC. Basically, what happens is the original limited amount of TRU allowed is reduced by some equivalent amount of LLW introduced. The total quantity of TRU, and LLW in excess of Type A quantities, must be administratively maintained via curie equivalency Factors to ensure operation as a low-hazard Facility. The ''equivalency'' between TRU and LLW proposed here is specific only to the CWC, but the methodology can be used for other specific applications, such as TRU and LLW storage or handling facilities where inventory limits must be enforced or where a simplified inventory system is required

Greater-than-Class C low-level radioactive waste characterization. Appendix D-3: Characterization of greater-than-Class C low-level radioactive waste from other generators

International Nuclear Information System (INIS)

Fish, L.W.

1994-09-01

The Other Generators category includes all greater-than-Class C low-level radioactive waste (GTCC LLW) that is not generated or held by nuclear utilities or sealed sources licensees or that is not stored at Department of Energy facilities. To determine the amount of waste within this category, 90 LLW generators were contacted; 13 fit the Other Generators category. Based on information received from the 13 identified Other Generators, the GTCC LLW Management Program was able to (a) characterize the nature of industries in this category, (b) estimate the 1993 inventory of Other Generator waste for high, base, and low cases, and (c) project inventories to the year 2035 for high, base, and low cases. Assumptions were applied to each of the case estimates to account for generators who may not have been identified in this study

Microbial degradation of low-level radioactive waste

International Nuclear Information System (INIS)

Rogers, R.D.; Hamilton, M.A.; Veeh, R.H.; McConnell, J.W. Jr.

1994-04-01

The Nuclear Regulatory Commission stipulates that disposed low-level radioactive waste (LLW) be stabilized. Because of apparent ease of use and normal structural integrity, cement has been widely used as a binder to solidify LLW. However, the resulting waste forms are sometimes susceptible to failure due to the actions of waste constituents, stress, and environment. This report reviews laboratory efforts that are being developed to address the effects of microbiologically influenced chemical attack on cement-solidified LLW. Groups of microorganisms are being employed that are capable of metabolically converting organic and inorganic substrates into organic and mineral acids. Such acids aggressively react with cement and can ultimately lead to structural failure. Results on the application of mechanisms inherent in microbially influenced degradation of cement-based material are the focus of this report. Sufficient data-validated evidence of the potential for microbially influenced deterioration of cement-solidified LLW has been developed during the course of this study. These data support the continued development of appropriate tests necessary to determine the resistance of cement-solidified LLW to microbially induced degradation that could impact the stability of the waste form. They also justify the continued effort of enumeration of the conditions necessary to support the microbiological growth and population expansion

Development of a computerized data base for low-level waste leaching data

International Nuclear Information System (INIS)

Dougherty, D.R.; Colombo, P.

1987-01-01

A computerized data base (db) of low-level waste (LLW) leaching data is being compiled by Brookhaven National Laboratory under contract to the DOE Low-Level Waste Management Program. Although this db is being compiled as part of an effort to develop accelerated leach test procedures for LLW forms, other involved in LLW management may find it useful. The db is implemented on an IBM PC XT and is self-contained in that its data manipulation and analysis programs are not proprietary (i.e., need not be purchased). The db includes data from the Accelerated Leach Test(s) Program plus selected literature data, which have been selected based on criteria that include completeness of the experimental description and elucidation of leaching mechanisms. 6 references, 5 figures, 3 tables

Commercial disposal options for Idaho National Engineering Laboratory low-level radioactive waste

International Nuclear Information System (INIS)

Porter, C.L.; Widmayer, D.A.

1995-09-01

The Idaho National Engineering Laboratory (INEL) is a Department of Energy (DOE)-owned, contractor-operated site. Significant quantities of low-level radioactive waste (LLW) have been generated and disposed of onsite at the Radioactive Waste Management Complex (RWMC). The INEL expects to continue generating LLW while performing its mission and as aging facilities are decommissioned. An on-going Performance Assessment process for the RWMC underscores the potential for reduced or limited LLW disposal capacity at the existing onsite facility. In order to properly manage the anticipated amount of LLW, the INEL is investigating various disposal options. These options include building a new facility, disposing the LLW at other DOE sites, using commercial disposal facilities, or seeking a combination of options. This evaluation reports on the feasibility of using commercial disposal facilities

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis

Energy Technology Data Exchange (ETDEWEB)

David Duncan

2011-04-01

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

Remote-Handled Low Level Waste Disposal Project Alternatives Analysis

Energy Technology Data Exchange (ETDEWEB)

David Duncan

2010-10-01

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis

Energy Technology Data Exchange (ETDEWEB)

David Duncan

2011-03-01

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

Remote-Handled Low-Level Waste Disposal Project Alternatives Analysis

Energy Technology Data Exchange (ETDEWEB)

David Duncan

2010-06-01

This report identifies, evaluates, and compares alternatives for meeting the U.S. Department of Energy’s mission need for management of remote-handled low-level waste generated by the Idaho National Laboratory and its tenants. Each alternative identified in the Mission Need Statement for the Remote-Handled Low-Level Waste Treatment Project is described and evaluated for capability to fulfill the mission need. Alternatives that could meet the mission need are further evaluated and compared using criteria of cost, risk, complexity, stakeholder values, and regulatory compliance. The alternative for disposal of remote-handled low-level waste that has the highest confidence of meeting the mission need and represents best value to the government is to build a new disposal facility at the Idaho National Laboratory Site.

A preliminary evaluation of alternatives for disposal of INEL low-level waste and low-level mixed waste

International Nuclear Information System (INIS)

Smith, T.H.; Roesener, W.S.; Jorgenson-Waters, M.J.

1993-07-01

The Mixed and Low-Level Waste Disposal Facility (MLLWDF) project was established in 1992 by the US Department of Energy Idaho Operations Office to provide enhanced disposal capabilities for Idaho National Engineering Laboratory (INEL) low-level mixed waste and low-level waste. This Preliminary Evaluation of Alternatives for Disposal of INEL Low-Level Waste and Low-Level Mixed Waste identifies and evaluates-on a preliminary, overview basis-the alternatives for disposal of that waste. Five disposal alternatives, ranging from of no-action'' to constructing and operating the MLLWDF, are identified and evaluated. Several subalternatives are formulated within the MLLWDF alternative. The subalternatives involve various disposal technologies as well as various scenarios related to the waste volumes and waste forms to be received for disposal. The evaluations include qualitative comparisons of the projected isolation performance for each alternative, and facility, health and safety, environmental, institutional, schedule, and rough order-of-magnitude life-cycle cost comparisons. The performance of each alternative is evaluated against lists of ''musts'' and ''wants.'' Also included is a discussion of other key considerations for decisionmaking. The analysis of results indicated further study is necessary to obtain the best estimate of long-term future waste volume and characteristics from the INEL Environmental Restoration activities and the expanded INEL Decontamination and Decommissioning Program

'Strategy is a commodity, implementation is an art' - 2 years of implementation of the UK national LLW strategy

International Nuclear Information System (INIS)

Cassidy, Helen; Rossiter, David

2013-01-01

The Low Level Waste Repository (LLWR) is the primary facility for disposal of Low Level Waste (LLW) in the United Kingdom (UK), serving the UK nuclear industry and a diverse range of other sectors. Management of LLW in the UK historically was dominated by disposal to the LLWR. The value of the LLWR as a national asset was recognised by the 2007 UK Governmental Policy on management of solid LLW. At this time, analysis of the projected future demand for disposal at LLWR against facility capacity was undertaken identifying a credible risk that the capacity of LLWR would be insufficient to meet future demand if existing waste management practices were perpetuated. To mitigate this risk a National Strategy for the management of LLW in the UK was developed by the Nuclear Decommissioning Authority (NDA), partnered with LLW Repository Ltd. (the organisation established in 2008 to manage the LLWR on behalf of NDA). This strategy was published in 2010 and identified three mechanisms for protection of the capacity of LLWR - application of the Waste Hierarchy by waste producers; optimised use of existing assets for LLW management; and opening of new waste treatment and disposal routes to enable diversion of waste away from the LLWR. (authors)

Comparison of low-level waste disposal programs of DOE and selected international countries

International Nuclear Information System (INIS)

Meagher, B.G.; Cole, L.T.

1996-06-01

The purpose of this report is to examine and compare the approaches and practices of selected countries for disposal of low-level radioactive waste (LLW) with those of the US Department of Energy (DOE). The report addresses the programs for disposing of wastes into engineered LLW disposal facilities and is not intended to address in-situ options and practices associated with environmental restoration activities or the management of mill tailings and mixed LLW. The countries chosen for comparison are France, Sweden, Canada, and the United Kingdom. The countries were selected as typical examples of the LLW programs which have evolved under differing technical constraints, regulatory requirements, and political/social systems. France was the first country to demonstrate use of engineered structure-type disposal facilities. The UK has been actively disposing of LLW since 1959. Sweden has been disposing of LLW since 1983 in an intermediate-depth disposal facility rather than a near-surface disposal facility. To date, Canada has been storing its LLW but will soon begin operation of Canada's first demonstration LLW disposal facility

A review of low-level radioactive waste compacts on a national level

International Nuclear Information System (INIS)

Brenneman, F.N.

1985-01-01

Since the 1950s, increased quantities of low-level radioactive waste (LLW) have been produced in the United States as a result of the use of radioactive materials in medical diagnoses and treatment, research, industrial processes, and electrical power generation by nuclear plants. With increasing volumes of commercially generated waste, the private sector was encouraged to develop LLW disposal facilities, to be licensed by the AEC or by AEC Agreement states. In 1962, the commercially operated Beaty, Nevada low-level waste facility was opened. During the ensuing nine years, five additional low-level waste disposal facilities opened, resulting, although not planned, in a regional distribution of such facilities. A number of technical and regulatory issues were raised over a period of two years by states and federal agencies, and, for the most part, were resolved. The NRC, DOE, and DOT reviewed and commented on the compacts throughout the drafting of compact language. Comments addressed the scope of the compacts (''management'' vs. ''disposal''), inspection of NRC licensees, regulatory roles of compact commissions, and regulatory requirements inconsistent with federal regulations, to name a few. Among those unresolved issues in some compacts is the definition of LLW, which varies among the compacts. Those in PL96-573 and the Nuclear Waste Policy Act of 1982 were both used, with and without variations. The definition of transuranic waste and those concentrations allowable at the disposal facilities are not uniform in the compacts

Basic approach to the disposal of low level radioactive waste generated from nuclear reactors containing comparatively high radioactivity

International Nuclear Information System (INIS)

Moriyama, Yoshinori

1998-01-01

Low level radioactive wastes (LLW) generated from nuclear reactors are classified into three categories: LLW containing comparatively high radioactivity; low level radioactive waste; very low level radioactive waste. Spent control rods, part of ion exchange resin and parts of core internals are examples of LLW containing comparatively high radioactivity. The Advisory Committee of Atomic Energy Commission published the report 'Basic Approach to the Disposal of LLW from Nuclear Reactors Containing Comparatively High Radioactivity' in October 1998. The main points of the proposed concept of disposal are as follows: dispose of underground deep enough not be disturb common land use (e.g. 50 to 100 m deep); dispose of underground where radionuclides migrate very slowly; dispose of with artificial engineered barrier which has the same function as the concrete pit; control human activities such as land use of disposal site for a few hundreds years. (author)

Differential diagnosis of pulmonary emphysema using the CT index: LL%w

Energy Technology Data Exchange (ETDEWEB)

Kitahara, Yoshinari; Takamoto, Masahiro; Maruyama, Masao; Tanaka, Yasushi; Ishibashi, Tuneo; Shinoda, Atsushi [Ohmuta National Hospital, Fukuoka (Japan)

1989-06-01

We measured the computed tomography (CT) index, LL%w, in 81 patients of chronic obstructive pulmonary disease (COPD) and asthma. In this study we defined LL%w as the mean value of the proportion of the low density area under -950 Hounsfield units in the six lung fields: upper, middle and lower lung fields bilaterally, at deep expiration. To examine the usefulness of LL%w in differentiating pulmomary emphysema (PE) from bronchial asthma (BA) and chronic bronchitis (CB), we excluded the overlapped cases of each disease. Mean value (+- standard deviation) of LL%w in PE was 24.6+-20.2% (n=40), whereas it was 0.5+-0.8% (n=27) in BA and 0.2+-0.3% (n=14) in CB respectively. There were clear statistically differences in the values of LL%w between clinically diagnosed emphysema and others. We considered that the value of LL%w within 1% would be observed nonspecifically, because the frequent existence of low density areas originated in bronchial tangents and/or motion artifacts mainly in the left lower lung field. Thus we judged that cases with over 1% of LL%w had abnormal CT findings. The relationship between clinically diagnosed emphysema and CT abnormality (LL%w > 1%) was significant in the analysis of the four-fold table. The CT sensitivity for diagnosing PE was 100%, the CT specificity was 87.8%, and CT accuracy was 93.8%. When cases of LL%w > 1% were shown in BA or CB, it would be better to consider the existence of complicated emphysema or the presence of air trapping or air spaces of any origin. We compared three groups (A', E', C') selected from groups BA, PE and CB, respectively. The groups consisted of patients showing almost the same mean values of FEV{sub 1.0}/VC(%). The value of the LL%w of E', selected from PE, also showed a significantly higher value than those from BA or CB. (J.P.N).

Differential diagnosis of pulmonary emphysema using the CT index: LL%w

International Nuclear Information System (INIS)

Kitahara, Yoshinari; Takamoto, Masahiro; Maruyama, Masao; Tanaka, Yasushi; Ishibashi, Tuneo; Shinoda, Atsushi

1989-01-01

We measured the computed tomography (CT) index, LL%w, in 81 patients of chronic obstructive pulmonary disease (COPD) and asthma. In this study we defined LL%w as the mean value of the proportion of the low density area under -950 Hounsfield units in the six lung fields: upper, middle and lower lung fields bilaterally, at deep expiration. To examine the usefulness of LL%w in differentiating pulmomary emphysema (PE) from bronchial asthma (BA) and chronic bronchitis (CB), we excluded the overlapped cases of each disease. Mean value (± standard deviation) of LL%w in PE was 24.6±20.2% (n=40), whereas it was 0.5±0.8% (n=27) in BA and 0.2±0.3% (n=14) in CB respectively. There were clear statistically differences in the values of LL%w between clinically diagnosed emphysema and others. We considered that the value of LL%w within 1% would be observed nonspecifically, because the frequent existence of low density areas originated in bronchial tangents and/or motion artifacts mainly in the left lower lung field. Thus we judged that cases with over 1% of LL%w had abnormal CT findings. The relationship between clinically diagnosed emphysema and CT abnormality (LL%w > 1%) was significant in the analysis of the four-fold table. The CT sensitivity for diagnosing PE was 100%, the CT specificity was 87.8%, and CT accuracy was 93.8%. When cases of LL%w > 1% were shown in BA or CB, it would be better to consider the existence of complicated emphysema or the presence of air trapping or air spaces of any origin. We compared three groups (A', E', C') selected from groups BA, PE and CB, respectively. The groups consisted of patients showing almost the same mean values of FEV 1.0 /VC(%). The value of the LL%w of E', selected from PE, also showed a significantly higher value than those from BA or CB. (J.P.N)

Current status of sea transport of nuclear fuel materials and LLW in Japan

International Nuclear Information System (INIS)

Kitagawa, Hiroshi; Akiyama, Hideo

2000-01-01

Along with the basic policy of the nuclear fuel cycle of Japan, many fuel cycle facilities have been already constructed in Rokkasho-Mura, Aomori prefecture, such as the uranium enrichment plant, the low level waste disposal center and the receiving pool of the spent nuclear fuels for reprocessing. These facilities belong to the Japan Nuclear Fuel Limited. (JNFL). Domestic sea transport of the spent nuclear fuels (SF) has been carried out since 1977 to the Tokai Reprocessing Plant, and the first sea transport of the SF to the fuel cycle facility in Rokkasho-Mura was done in Oct, 1998 using a new exclusive ship 'Rokuei-Maru'. Sea transport of the low level radioactive wastes (LLW) has been carried out since 1992 to the Rokkasho LLW Disposal Center, and about 130,000 LLW drams were transported from the nuclear power plant sites. These sea transport have demonstrated the safety of the transport of the nuclear fuel cycle materials. It is hoped that the safe sea transport of the nuclear fuel materials will contribute to the more progress of the nuclear fuel cycle activities of Japan. (author)

Test Plan: Phase 1, Hanford LLW melter tests, GTS Duratek, Inc

International Nuclear Information System (INIS)

Eaton, W.C.

1995-01-01

This document provides a test plan for the conduct of vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384215] is GTS Duratek, Inc., Columbia, Maryland. The GTS Duratek project manager for this work is J. Ruller. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes melting of glass with Hanford LLW Double-Shell Slurry Feed waste simulant in a DuraMelter trademark vitrification system

Melter system technology testing for Hanford Site low-level tank waste vitrification

International Nuclear Information System (INIS)

Wilson, C.N.

1996-01-01

Following revisions to the Tri-Party Agreement for Hanford Site cleanup, which specified vitrification for Complete melter feasibility and system operability immobilization of the low-level waste (LLW) tests, select reference melter(s), and establish reference derived from retrieval and pretreatment of the radioactive LLW glass formulation that meets complete systems defense wastes stored in 177 underground tanks, commercial requirements (June 1996). Available melter technologies were tested during 1994 to 1995 as part of a multiphase program to select reference Submit conceptual design and initiate definitive design technologies for the new LLW vitrification mission

U.S. policy and current practices for blending low-level radioactive waste for disposal

Energy Technology Data Exchange (ETDEWEB)

Kessel, David S.; Kim, Chang Lak [KEPCO International Nuclear Graduate School, Ulsan (Korea, Republic of)

2016-09-15

In the near future, many countries, including the Republic of Korea, will face a significant increase in low level radioactive waste (LLW) from nuclear power plant decommissioning. The purpose of this paper is to look at blending as a method for enhancing disposal options for low-level radioactive waste from the decommissioning of nuclear reactors. The 2007 U.S. Nuclear Regulatory Commission strategic assessment of the status of the U.S. LLW program identified the need to move to a risk-informed and performance-based regulatory approach for managing LLW. The strategic assessment identified blending waste of varying radionuclide concentrations as a potential means of enhancing options for LLW disposal. The NRC's position is that concentration averaging or blending can be performed in a way that does not diminish the overall safety of LLW disposal. The revised regulatory requirements for blending LLW are presented in the revised NRC Branch Technical Position for Concentration Averaging and Encapsulation (CA BTP 2015). The changes to the CA BTP that are the most significant for NPP operation, maintenance and decommissioning are reviewed in this paper and a potential application is identified for decommissioning waste in Korea. By far the largest volume of LLW from NPPs will come from decommissioning rather than operation. The large volumes in decommissioning present an opportunity for significant gains in disposal efficiency from blending and concentration averaging. The application of concentration averaging waste from a reactor bio-shield is also presented.

U.S. policy and current practices for blending low-level radioactive waste for disposal

International Nuclear Information System (INIS)

Kessel, David S.; Kim, Chang Lak

2016-01-01

In the near future, many countries, including the Republic of Korea, will face a significant increase in low level radioactive waste (LLW) from nuclear power plant decommissioning. The purpose of this paper is to look at blending as a method for enhancing disposal options for low-level radioactive waste from the decommissioning of nuclear reactors. The 2007 U.S. Nuclear Regulatory Commission strategic assessment of the status of the U.S. LLW program identified the need to move to a risk-informed and performance-based regulatory approach for managing LLW. The strategic assessment identified blending waste of varying radionuclide concentrations as a potential means of enhancing options for LLW disposal. The NRC's position is that concentration averaging or blending can be performed in a way that does not diminish the overall safety of LLW disposal. The revised regulatory requirements for blending LLW are presented in the revised NRC Branch Technical Position for Concentration Averaging and Encapsulation (CA BTP 2015). The changes to the CA BTP that are the most significant for NPP operation, maintenance and decommissioning are reviewed in this paper and a potential application is identified for decommissioning waste in Korea. By far the largest volume of LLW from NPPs will come from decommissioning rather than operation. The large volumes in decommissioning present an opportunity for significant gains in disposal efficiency from blending and concentration averaging. The application of concentration averaging waste from a reactor bio-shield is also presented

Gas generation from low-level radioactive waste: Concerns for disposal

International Nuclear Information System (INIS)

Siskind, B.

1992-01-01

The Advisory Committee on Nuclear Waste (ACNW) has urged the Nuclear Regulatory Commission (NRC) to reexamine the topic of hydrogen gas generation from low-level radioactive waste (LLW) in closed spaces to ensure that the slow buildup of hydrogen from water-bearing wastes in sealed containers does not become a problem for long-term safe disposal. Brookhaven National Laboratory (BNL) has prepared a report, summarized in this paper, for the NRC to respond to these concerns. The paper discusses the range of values for G(H 2 ) reported for materials of relevance to LLW disposal; most of these values are in the range of 0.1 to 0.6. Most studies of radiolytic hydrogen generation indicate a leveling off of pressurization, probably because of chemical kinetics involving, in many cases, the radiolysis of water within the waste. Even if no leveling off occurs, realistic gas leakage rates (indicating poor closure by gaskets on drums and liners) will result in adequate relief of pressure for radiolytic gas generation from the majority of commercial sector LLW packages. Biodegradative gas generation, however, could pose a pressurization hazard even at realistic gas leakage rates. Recommendations include passive vents on LLW containers (as already specified for high integrity containers) and upper limits to the G values and/or the specific activity of the LLW

Complex-wide review of DOE's Low-Level Waste Management ES ampersand H vulnerabilities. Volume I. Final report

International Nuclear Information System (INIS)

1996-05-01

The Department of Energy (DOE) conducted a comprehensive complex-wide review of its management of low-level waste (LLW) and the radioactive component of mixed low-level waste (MLLW). This review was conducted in response to a recommendation from the Defense Nuclear Facilities Safety Board (DNFSB) which was established and authorized by Congress to oversee DOE. The DNFSB's recommendation concerning conformance with safety standards at DOE LLW sites was issued on September 8, 1994 and is referred to as Recommendation 94-2. DOE's Implementation Plan for its response to Recommendation 94-2 was submitted to the DNFSB on March 31, 1995. The DNFSB recommended that a complex-wide review of DOE's LLW management be initiated. The goal of the complex-wide review of DOE's LLW management system was to identify both programmatic and physical vulnerabilities that could lead to unnecessary radiation exposure of workers or the public or unnecessary releases of radioactive materials to the environment. Additionally, the DNFSB stated that an objective of the complex-wide review should be to establish the dimensions of the DOE LLW problem and support the identification of corrective actions to address safe disposition of past, present, and future volumes of LLW. The complex-wide review involved an evaluation of LLW management activities at 38 DOE facilities at 36 sites that actively manage LLW and MLLW

Current status of low-level-waste-segregation technology

International Nuclear Information System (INIS)

Clark, D.E.; Colombo, P.; Sailor, V.L.

1982-01-01

The adoption of improved waste segregation practices by waste generators and burial sites will result in the improved disposal of low-level wastes (LLW) in the future. Many of the problems connected with this disposal mode are directly attributable to or aggravated by the indiscriminate mixing of various waste types in burial trenches. Thus, subsidence effects, contact with ground fluids, movement of radioactivity in the vapor phase, migration of radionuclides due to the presence of chelating agents or products of biological degradation, deleterious chemical reactions, and other problems have occurred. Regulations are currently being promulgated which will require waste segregation to a high degree at LLW burial sites. The state-of-the-art of LLW segregation technology and current practices in the USA have been surveyed at representative facilities. Favorable experience has been reported at various sites following the application of segregation controls. This paper reports on the state-of-the-art survey and addresses current and projected LLW segregation practices and their relationship to other waste management activities

Lessons learned from international siting experiences of LLW Disposal facilities

International Nuclear Information System (INIS)

McCabe, G.H.

1990-01-01

This paper reports that the United States can gain insight into successfully siting low-level radioactive waste (LLW) disposal facilities by studying the process in other nations. Siting experiences in France and Sweden are compared to experiences in the United States. Three factors appear to making siting of LLW disposal facilities easier in France and Sweden than in the United States. First, the level of public trust in the government and the entities responsible for siting, developing, and operating a LLW disposal facility is much greater in France and Sweden than in the United States. Second, France and Sweden are much more dependent on nuclear power than is the United States. Third, French and Swedish citizens do not have the same access to the siting process (i.e., legal means to intervene) as do U.S. citizens. To compensate for these three factors, public officials responsible for siting a facility may need to better listen to the concerns of public interest groups and citizen advisory committees and amend their siting process accordingly and better share power and control with the public. If these two techniques are implemented earnestly by the states, siting efforts may be increasingly more successful in the United States

LLW (Low-Level Waste) Forum meeting report, February 10-13, 1998, San Diego, CA

International Nuclear Information System (INIS)

1998-01-01

The Low-Level Radioactive Waste Forum met in San Diego, California, on February 10--13, 1998. Twenty-four Forum Participants, Alternate Forum Participants, and meeting designees representing 19 compacts, host states, and unaffiliated states participated. Additional information was provided by 19 resource people from, variously, the States of California, Colorado, and Utah; the National Governors' Association; the Department of the Army; EPA; DOE and DOE's National Low-Level Waste Management Program; NRC; the Electric Power Research Institute and the Nuclear Energy Institute; US Ecology, Chem-Nuclear Systems, Envirocare of Utah, and Waste Control Specialists (represented by Egan and Associates); and Rocketdyne Propulsion and Power. Also in attendance, as observers, were six other state and compact officials; a staff person from DOE's National Low-Level Waste Management Program; one NRC headquarters staff person; and seven representatives of other interested parties, including a regional generators' organization, two generators, one California anti-nuclear group, and two private companies

Alternative waste management concept for medium and low level wastes by in-situ solidification

International Nuclear Information System (INIS)

Kraemer, R.

1982-01-01

Since 1976, a German R and D project has been carried out to find an alternative concept for the treatment and disposal of MLW and LLW arising mainly in the planned German reprocessing plant and other nuclear facilities (LWR, fuel fabrication, R and D establishments). The main feature of this concept is an in-situ solidification of preconditioned waste granules in large salt caverns located in the deep geological underground, thus avoiding such non-radioactive ballast as lost concrete shielding and container material. (orig./RW)

Sources, amounts, and characteristics of low-level radioactive solid wastes

International Nuclear Information System (INIS)

Kibbey, A.H.; Godbee, H.W.

1979-01-01

Low-level radioactive solid wastes (LLW) are generated in the nuclear fuel cycle, national defense programs, institutional (especially medical/biological) applications, and other research and development activities. The estimated total accumulation of defense LLW, approx. 50.8 x 10 6 ft 3 (approx. 1.4 x 10 6 m 3 ), is roughly three times that estimated for commercial LLW, mill tailings excepted. All nuclear fuel cycle steps generate some LLW, but power plants are the chief source. From 1975 through 1977, reactor process stream cleanup generated approx. 1 x 10 6 (approx. 2.8 x 10 4 m 3 ) annually. Spent fuel storage (or reprocessing) and facility decontamination and decommissioning will become important LLW generators as the nuclear power industry matures. The LLW contains dry contaminated trash, much of which is combustible and/or compactible; discarded tools and equipment; wet filter sludges and ion-exchange resins; disposable filter cartridges; and solidified or sorbed liquids, including some organics. A distinguishing characteristic of LLW is a long-lived alpha-emitting transuranic content of 5 ft 3 (approx. 2.1 x 10 4 m 3 )/y. The majority of these wastes, > 6 x 10 5 ft 3 (> 1.7 x 10 4 m 3 ), was medical and academic wastes which usually contained isotopes with induced activities of less than or equal to 60-day half-life, neglecting 3 H and 14 C

Greater-than-Class C Low-Level Radioactive Waste Program 1992 baseline strategy

International Nuclear Information System (INIS)

1993-02-01

This baseline strategy document describes Department of Energy (DOE) goals, objectives, and strategy for fulfilling its responsibility to dispose of greater-than-Class C low-level radioactive waste (GTCC LLW) according to the requirements of Section 3(b) of the Low-Level Radioactive Waste Policy Amendments Act of 1985, Public Law 99-240. This document describes the baseline strategy being employed at the end of FY 1992. The strategy for fulfilling the above responsibility consists of three tasks: interim storage of limited quantities of GTCC LLW at a currently operating DOE facility to eliminate a potential public health and safety threcceptance of GTCC LLW for storage in a DOE dedicated facility on an as-needed basis pending disposal; and disposal in a facility licensed by the Nuclear Regulatory Commission. The objectives, assumptions, and strategies for each of these tasks are presented in this plan

Development of a multimedia radionuclide exposure model for low-level waste management

International Nuclear Information System (INIS)

Onishi, Y.; Whelan, G.; Skaggs, R.L.

1982-03-01

A method is being developed for assessing exposures of the air, water, and plants to low-level waste (LLW) as a part of an overall development effort of a LLW site evaluation methodology. The assessment methodology will predict LLW exposure levels in the environment by simulating dominant mechanisms of LLW migration and fate. The methodology consists of a series of physics-based models with proven histories of success; the models interact with each other to simulate LLW transport in the ecosystem. A scaled-down version of the methodology was developed first by combining the terrestrial ecological model, BIOTRAN; the overland transport model, ARM; the instream hydrodynamic model, DKWAV; and the instream sediment-contaminant transport model, TODAM (a one-dimensional version of SERATRA). The methodology was used to simulate the migration of 239 Pu from a shallow-land disposal site (known as Area C) located near the head of South Mortandad Canyon on the LANL site in New Mexico. The scenario assumed that 239 Pu would be deposited on the land surface through the natural processes of plant growth, LLW uptake, dryfall, and litter decomposition. Runoff events would then transport 239 Pu to and in the canyon. The model provided sets of simulated LLW levels in soil, water and terrestrial plants in the region surrounding the site under a specified land-use and a waste management option. Over a 100-yr simulation period, only an extremely small quantity (6 x 10 -9 times the original concentration) of buried 239 Pu was taken up by plants and deposited on the land surface. Only a small fraction (approximately 1%) of that contamination was further removed by soil erosion from the site and carried to the canyon, where it remained. Hence, the study reveals that the environment around Area C has integrity high enough to curtail LLW migration under recreational land use

Low-level radioactive waste (LLW) management at the Nevada Test Site (NTS)

International Nuclear Information System (INIS)

Becker, B.D.; Gertz, C.P.; Clayton, W.A.; Crowe, B.M.

1998-01-01

In 1978, the Department of Energy, Nevada Operations Office (DOE/NV), established a managed LLW disposal project at the Nevada Test Site (NTS). Two, sites which were already accepting limited amounts of on-site generated waste for disposal and off-site generated Transuranic Waste for interim storage, were selected to house the disposal facilities. In those early days, these sites, located about 15 miles apart, afforded the DOE/NV the opportunity to use at least two technologies to manage its waste cost effectively. The Area 5 Radioactive Waste Management Site (RWMS) uses engineered shallow-land burial cells to dispose packaged waste while the Area 3 RWMS uses subsidence craters formed from underground testing of nuclear weapons for the disposal of packaged and unpackaged bulk waste. The paper describes the technical attributes of both Area 5 and Area 3 facilities, the acceptance process, the disposal processes, and present and future capacities of both sites

Delivering step change improvements to UK low level waste strategy - 16188

International Nuclear Information System (INIS)

Dean, Jason; Rossiter, David

2009-01-01

The UK Nuclear Industry continues to produce significant quantities of Low Level Waste (LLW) as decommissioning projects generating waste become more prevalent. Current infrastructure and projected increasing waste volumes will deliver a volumetric shortfall of storage capacity in the near future. Recently established as a standalone site licence company, the Low Level Waste Repository (LLWR) near Drigg, in West Cumbria (formerly operated and owned by British Nuclear Group) is tasked with managing the safe treatment and disposal of LLW in the UK, on behalf of the Nuclear Decommissioning Authority (NDA). The problem is complex involving many stakeholders with potentially different priorities. Previously, most nuclear waste generators operated independently with limited integration with other similar organisations. However, the current financial, programme and technical pressures require collaborative working to facilitate a step-change improvement in LLW management. Achieving this quickly is as much of a challenge as delivering robust cost effective technical solutions. NDA is working in partnership with LLWR to develop a LLW Strategy for the Nuclear Industry and has in parallel commissioned a number of studies by the National Nuclear Laboratory (NNL), looking at opportunities to share best practice. A National Strategy Group has been established to develop a working partnership between the Nuclear Decommissioning Authority, LLW Repository Ltd, Regulators, Stakeholders and LLW Consignors, promoting innovation, value for money, and robust implementation of the waste hierarchy (avoid-reduce-re-use-recycle). Additionally the LLWR supported by the NNL have undertaken a comprehensive strategic review of the UK's LLW management activities. Initial collaborative work has provided for the first time a detailed picture of the existing strategic baseline and identified significant national benefits from improving the way LLW is forecasted, characterised, segregated, and

Low-level waste drum staging building at Weapons Engineering Tritium Facility, TA-16, Los Alamos National Laboratory, Los Alamos, New Mexico. Environmental Assessment

International Nuclear Information System (INIS)

1994-08-01

The proposed action is to place a 3 meter (m) by 4.5 m (10 ft x 15 ft) prefabricated storage building (transportainer) adjacent to the existing Weapons Engineering Tritium Facility (WETF) at Technical Area (TA-) 16, Los Alamos National Laboratory (LANL), and to use the building as a staging site for sealed 55 galllon drums of noncompactible waste contaminated with low levels of tritium (LLW). Up to eight drums of waste would be accumulated before the waste is moved by LANL Waste Management personnel to the existing on-site LLW disposal area at TA-54. The drum staging building would be placed on a bermed asphalt pad, near other existing accumulation structures for office trash and compactible LLW. The no-action alternative is to continue storing drums of LLW in the WETF laboratories where they occupy valuable work space, hamper movement of personnel and equipment, and require waste management personnel to enter those laboratories in order to remove filled drums. No new waste would be generated by implementing the proposed action; no changes or increases in WETF operations or waste production rate are anticipated as a result of staging drums of LLW outside the main laboratory building. The site for the LLW drum staging building would not impact any sensitive areas. Tritium emissions from the drums of LLW were included within the source term for normal operations at the WETF; the cumulative impacts would not be increased

Evaluating Options for Disposal of Low-Level Waste at LANL

International Nuclear Information System (INIS)

Hargis, K.M.; French, S.B.; Boyance, J.A.

2009-01-01

Los Alamos National Laboratory (LANL) generates a wide range of waste types, including solid low-level radioactive waste (LLW), in conducting its national security mission and other science and technology activities. Although most of LANL's LLW has been disposed on-site, limitations on expansion, stakeholder concerns, and the potential for significant volumes from environmental remediation and decontamination and demolition (D and D) have led LANL to evaluate the feasibility of increasing off-site disposal. It appears that most of the LLW generated at LANL would meet the Waste Acceptance Criteria at the Nevada Test Site or available commercial LLW disposal sites. Some waste is considered to be problematic to transport to off-site disposal even though it could meet the off-site Waste Acceptance Criteria. Cost estimates for off-site disposal are being evaluated for comparison to estimated costs under the current plans for continued on-site disposal. An evaluation of risks associated with both on-site and off-site disposal will also be conducted. (authors)

Overview of commercial low-level radioactive waste disposal in the United States

International Nuclear Information System (INIS)

Smith, P.

1994-01-01

Disposal of commercial low-level radioactive waste (LLW) is a critical part of the national infrastructure needed to maintain the health of American businesses, universities, and hospitals. Currently only 19 States (located in the Northwest and Southeast) have access to operating disposal facilities; all other States are storing their LLW until they open new disposal facilities on their own or in concert with other States through regional compact agreements. In response to recommendations from the National Governors Association, Congress assigned the burden for LLW disposal to all States, first in 1980 through Public Law 96-573, the open-quotes Low-level Radioactive Waste Policy Actclose quotes, and again in 1986 through Public Law 99-240, the open-quotes Low-Level Radioactive Waste Policy Amendments Act of 1985close quotes. As directed by Congress, the Department of Energy provides technical assistance to States and compact regions with this task. After almost 14 years, nine compact regions have been ratified by Congress; California, Texas, North Carolina, and Nebraska have submitted license applications; California has issued an operating license; and the number of operating disposal facilities has decreased from three to two

Defining mixed low-level radioactive and hazardous waste

International Nuclear Information System (INIS)

Weber, M.F.

1987-01-01

During the last several months, staffs of the US Nuclear Regulatory Commission (NRC) and the US Environmental Protection Agency (EPA) have been developing a working definition of Mixed Low-Level Radioactive and Hazardous Waste (Mixed LLW). Such wastes are currently being regulated by NRC under authority of the Atomic Energy Act (AEA), as amended, and by EPA under the Resource Conservation and Recovery Act (RCRA), as amended. Development of the definition is one component of a comprehensive program to resolve differences between the regulatory programs of the two agencies pertaining to the regulation of the management and disposal of Mixed LLW. Although the definition is still undergoing legal and policy reviews in both agencies, this paper presents the current working definition, discusses a methodology that may be used by NRC licensees to identify Mixed LLW, and provides responses to anticipated questions from licensees about the definition. 3 references, 1 figure

Greater-than-Class C low-level radioactive waste characterization. Appendix A-2: Timing of greater-than-Class C low-level radioactive waste from nuclear power plants

International Nuclear Information System (INIS)

Steinke, W.F.

1994-09-01

Planning for the storage or disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of that waste. Timing, or the date the waste will require storage or disposal, is an integral aspect of that planning. The majority of GTCC LLW is generated by nuclear power plants, and the length of time a reactor remains operational directly affects the amount of GTCC waste expected from that reactor. This report uses data from existing literature to develop high, base, and low case estimates for the number of plants expected to experience (a) early shutdown, (b) 40-year operation, or (c) life extension to 60-year operation. The discussion includes possible effects of advanced light water reactor technology on future GTCC LLW generation. However, the main focus of this study is timing for shutdown of current technology reactors that are under construction or operating

Low-level radioactive waste disposal operations at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Stanford, A.R.

1997-01-01

Los Alamos National Laboratory (LANL) generates Low-Level Radioactive Waste (LLW) from various activities: research and development, sampling and storage of TRU wastes, decommissioning and decontamination of facilities, and from LANL's major role in stockpile stewardship. The Laboratory has its own active LLW disposal facility located at Technical Area 54, Area G. This paper will identify the current operations of the facility and the issues pertaining to operating a disposal facility in today's compliance and cost-effective environment

Evaluating biological transport of radionuclides at low-level waste burial sites

International Nuclear Information System (INIS)

Cadwell, L.L.; Kennedy, W.E.; McKenzie, D.H.

1983-08-01

The purpose of the work reported here is to develop and demonstrate methods for evaluating the long-term impact of biological processes at low-level waste (LLW) disposal sites. As part of this effort, we developed order-of-magnitude estimates of dose-to-man resulting from animal burrowing activity and plant translocation of radionuclides. Reference low-level waste sites in both arid and humid areas of the United States were examined. The results of our evaluation for generalized arid LLW burial site are presented here. Dose-to-man estimates resulting from biotic transport are compared with doses calculated from human intrusion exposure scenarios. Dose-to-man estimates, as a result of biotic transport, are of the same order of magnitude as those resulting from a more commonly evaluated human intrusion scenario. The reported lack of potential importance of biotic transport at LLW sites in earlier assessment studies is not confirmed by our findings. These results indicate that biotic transport has the long-term potential to mobilize radionuclides. Therefore, biotic transport should be carefully evaluated during burial site assessment

Treatment of low level radioactive liquid waste containing appreciable concentration of TBP degraded products.

Science.gov (United States)

Valsala, T P; Sonavane, M S; Kore, S G; Sonar, N L; De, Vaishali; Raghavendra, Y; Chattopadyaya, S; Dani, U; Kulkarni, Y; Changrani, R D

2011-11-30

The acidic and alkaline low level radioactive liquid waste (LLW) generated during the concentration of high level radioactive liquid waste (HLW) prior to vitrification and ion exchange treatment of intermediate level radioactive liquid waste (ILW), respectively are decontaminated by chemical co-precipitation before discharge to the environment. LLW stream generated from the ion exchange treatment of ILW contained high concentrations of carbonates, tributyl phosphate (TBP) degraded products and problematic radio nuclides like (106)Ru and (99)Tc. Presence of TBP degraded products was interfering with the co-precipitation process. In view of this a modified chemical treatment scheme was formulated for the treatment of this waste stream. By mixing the acidic LLW and alkaline LLW, the carbonates in the alkaline LLW were destroyed and the TBP degraded products got separated as a layer at the top of the vessel. By making use of the modified co-precipitation process the effluent stream (1-2 μCi/L) became dischargeable to the environment after appropriate dilution. Based on the lab scale studies about 250 m(3) of LLW was treated in the plant. The higher activity of the TBP degraded products separated was due to short lived (90)Y isotope. The cement waste product prepared using the TBP degraded product was having good chemical durability and compressive strength. Copyright © 2011 Elsevier B.V. All rights reserved.

Department of Energy treatment capabilities for greater-than-Class C low-level radioactive waste

International Nuclear Information System (INIS)

Morrell, D.K.; Fischer, D.K.

1995-01-01

This report provides brief profiles for 26 low-level and high-level waste treatment capabilities available at the Idaho National Engineering Laboratory (INEL), Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL), Pacific Northwest Laboratory (PNL), Rocky Flats Plant (RFP), Savannah River Site (SRS), and West Valley Demonstration Plant (WVDP). Six of the treatments have potential use for greater-than-Class C low-level waste (GTCC LLW). They include: (a) the glass ceramic process and (b) the Waste Experimental Reduction Facility incinerator at INEL; (c) the Super Compaction and Repackaging Facility and (d) microwave melting solidification at RFP; (e) the vitrification plant at SRS; and (f) the vitrification plant at WVDP. No individual treatment has the capability to treat all GTCC LLW streams. It is recommended that complete physical and chemical characterizations be performed for each GTCC waste stream, to permit using multiple treatments for GTCC LLW

Nonradiological groundwater quality at low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Goode, D.J.

1986-04-01

The NRC is investigating appropriate regulatory options for disposal of low-level radioactive waste containing nonradiological hazardous constituents, as defined by EPA regulations. Standard EPA/RCRA procedures to determine hazardous organics, metals, indicator parameters, and general water quality are applied to samples from groundwater monitoring wells at two commercial low-level radioactive waste disposal sites. At the Sheffield, IL site (nonoperating), several typical organic solvents are identified in elevated concentrations in onsite wells and in an offsite area exhibiting elevated tritium concentrations. At the Barnwell, SC site (operating), only very low concentrations of three organics are found in wells adjacent to disposal units. Hydrocarbons associated with petroleum products are detected at both sites. Hazardous constituents associated with previosuly identified major LLW mixed waste streams, toluene, xylene, chromium, and lead, are at or below detection limits or at background levels in all samples. Review of previously collected data also supports the conclusion that organic solvents are the primary nonradiological contaminants associated with LLW disposal

Studies on disposal of low-level radioactive wastes in Turkey

International Nuclear Information System (INIS)

Uslu, I.; Fields, D.E.; Yalcintas, M.G.

1989-08-01

The Turkish Government is in the process of planning two nuclear reactors in Turkey. Studies have begun for improved control of low level wastes (LLW) in Turkey before establishment of these reactors. In this study, the PRESTO-II (Prediction of Radiation Exposures form Shallow Trench Operations) computer code is used to assess the risk associated with the shallow land disposal of low level waste (LLW) in various sites in Turkey. PRESTO-II is a computer code developed under the United States Environmental Protection Agency, Department of Energy and Nuclear Regulatory Commission funding to evaluate possible health effects from radioactive releases from shallow, radioactive waste disposal trenches and from areas contaminated with operational spillage. A preliminary simulation using the PRESTO-II computer code has been run for the site in Koteyli, Balikesir, Turkey. This example simulation was performed using the same radionuclide data set believed representative of the LLW disposal facility in Barnwell, South Carolina. Site environmental variables were selected to typify credible worst case exposure scenarios. Radionuclide inventories are primarily based on estimated waste composition rather than measured values. 9 refs., 4 figs., 1 tab

Managing California's low-level waste: state policy and waste generators

International Nuclear Information System (INIS)

Pasternak, A.D.; Cramer, E.N.

1985-01-01

Since 1982, public and private organizations in California that use radioactive materials and generate low-level radioactive waste have worked together through the California Radioactive Materials Management Forum (CRMMF) to assure the continued safe disposal of low-level waste (LLW). The forum's corporate and institutional members include electric utilities, universities, hospitals, industries, professional societies, and firms engaged in biological research and the manufacture of radiopharmaceuticals. In addition, over 200 individuals are members. The objectives of CRMMF are: (a) establishing a disposal facility for LLW in California and (b) maintaining access to the existing disposal sites in Washington, Nevada, and South Carolina until a California site is licensed and operating. This paper describes the forum's programs in the areas of legislation, litigation, and public information that contribute to the achievement of these objectives

Analysis of the low-level waste radionuclide inventory for the Radioactive Waste Management Complex performance assessment

Energy Technology Data Exchange (ETDEWEB)

Plansky, L.E.; Hoiland, S.A.

1992-02-01

This report summarizes the results of a study to improve the estimates of the radionuclides in the low-level radioactive waste (LLW) inventory which is buried in the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA). The work is done to support the RWMC draft performance assessment (PA). Improved radionuclide inventory estimates are provided for the INEL LLW generators. Engineering, environmental assessment or other research areas may find use for the information in this report. It may also serve as a LLW inventory baseline for data quality assurance. The individual INEL LLW generators, their history and their activities are also described in detail.

Analysis of the low-level waste radionuclide inventory for the Radioactive Waste Management Complex performance assessment

International Nuclear Information System (INIS)

Plansky, L.E.; Hoiland, S.A.

1992-02-01

This report summarizes the results of a study to improve the estimates of the radionuclides in the low-level radioactive waste (LLW) inventory which is buried in the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC) Subsurface Disposal Area (SDA). The work is done to support the RWMC draft performance assessment (PA). Improved radionuclide inventory estimates are provided for the INEL LLW generators. Engineering, environmental assessment or other research areas may find use for the information in this report. It may also serve as a LLW inventory baseline for data quality assurance. The individual INEL LLW generators, their history and their activities are also described in detail

Potential co-disposal of greater-than-class C low-level radioactive waste with Department of Energy special case waste - greater-than-class C low-level waste management program

International Nuclear Information System (INIS)

Allred, W.E.

1994-09-01

This document evaluates the feasibility of co-disposing of greater-than-Class C low-level radioactive waste (GTCC LLW) with U.S. Department of Energy (DOE) special case waste (SCW). This document: (1) Discusses and evaluates key issues concerning co-disposal of GTCC LLW with SCW. This includes examining these issues in terms of regulatory concerns, technical feasibility, and economics; (2) Examines advantages and disadvantages of such co-disposal; and (3) Makes recommendations. Research and analysis of the issues presented in this report indicate that it would be technically and economically feasible to co-dispose of GTCC LLW with DOE SCW. However, a dilemma will likely arise in the current division of regulatory responsibilities between the U.S. Nuclear Regulatory Commission and DOE (i.e., current requirement for disposal of GTCC LLW in a facility licensed by the Nuclear Regulatory Commission). DOE SCW is currently not subject to this licensing requirement

Design and construction of low level radioactive waste disposal facility at Rokkasho storage center

International Nuclear Information System (INIS)

Takahashi, K.; Itoh, H.; Iimura, H.; Shimoda, H.

1992-01-01

Japan Nuclear Fuel Industries Co., Inc. (JNFI) which has been established to dispose through burial the low-level radioactive waste (LLW) produced by nuclear power stations over the country is now constructing Rokkasho LLW Storage Center at Rokkasho Village,Aomori Prefecture. At this storage center JNFI plans to bury about 200,000m 3 , of LLW (equivalent to about one million drums each with a 200 liter capacity), and ultimately plans to bury about 600,000m 3 about 3 million drums of LLW. About the construction of the burial facilities for the first-stage LLW equivalent to 200,000 drums (each with a 200-liter capacity) we obtained the government's permit in November, 1990 and set out the construction work from the same month, which has since been promoted favorably. The facilities are scheduled to start operation from December, 1992. This paper gives an overview of at these facilities

Development of a plan for a national LLW information management system based on data acquired from a uniform manifest

International Nuclear Information System (INIS)

Gingerich, R.; Shimer, R.P.

1986-01-01

The Western Governors' Association (WGA), with funding from the Department of Energy's (DOE) National Low-Level Radioactive Waste Management Program, has completed an 18-month national project to develop a plan for a national low-level waste (LLW) information management system based on data from a uniform manifest for shipments of LLW. Under the plan, waste generators would fill out a manifest for a shipment just as they do currently, but they would use a nationally standard form. Shortly after a shipment arrives at a disposal facility or a processor, data from the manifest would be entered into the Program's Low-Level Waste Information Management System (LLWIMS). The data would be available via computer to state, compact and federal officials. This paper provides an overview of the plan for implementing and operating a national information management system linked to manifest data. It reports on the progress that has been made toward implementing the system and outlines the work that remains to be done. Finally, the paper examines the crucial role the system will play in the development of an acceptable system for managing the nation's LLW, particularly in the post-1986 transition period

Low-level wastes pathways at EDF

International Nuclear Information System (INIS)

Hilmoine, R.; Casseau, L.Ph.

1999-01-01

First, what are, for EDF, the main issues dealing with the future management of low level wastes (LLW) will be recalled; and followed by a description of what are the implications of implementing these management principles: areas zoning, set up of pathways, traceability of the wastes and associated controls. The origin of the wastes will then be described using both qualitative and quantitative approaches; the description will specifically address the spreading of wastes production in time. LLW management at EDF will then be envisaged: storage in a specific discharge, pathways for treatment and elimination of wastes with acceptable radiological impact and costs. The example of LLW oils will be developed: particularly as far as hypothesis and results concerning the radiological impacts are concerned. The choice of incineration will then be justified, however expected difficulties to implement it industrially will be pointed out. Other on going studies and their main results will be mentioned: the present time is a turning point on that issue between thought and action; to be on going dismantling must take into account the emerging principles and give rise to good communication. (author)

Methods for verifying compliance with low-level radioactive waste acceptance criteria

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-09-01

This report summarizes the methods that are currently employed and those that can be used to verify compliance with low-level radioactive waste (LLW) disposal facility waste acceptance criteria (WAC). This report presents the applicable regulations representing the Federal, State, and site-specific criteria for accepting LLW. Typical LLW generators are summarized, along with descriptions of their waste streams and final waste forms. General procedures and methods used by the LLW generators to verify compliance with the disposal facility WAC are presented. The report was written to provide an understanding of how a regulator could verify compliance with a LLW disposal facility`s WAC. A comprehensive study of the methodology used to verify waste generator compliance with the disposal facility WAC is presented in this report. The study involved compiling the relevant regulations to define the WAC, reviewing regulatory agency inspection programs, and summarizing waste verification technology and equipment. The results of the study indicate that waste generators conduct verification programs that include packaging, classification, characterization, and stabilization elements. The current LLW disposal facilities perform waste verification steps on incoming shipments. A model inspection and verification program, which includes an emphasis on the generator`s waste application documentation of their waste verification program, is recommended. The disposal facility verification procedures primarily involve the use of portable radiological survey instrumentation. The actual verification of generator compliance to the LLW disposal facility WAC is performed through a combination of incoming shipment checks and generator site audits.

Methods for verifying compliance with low-level radioactive waste acceptance criteria

International Nuclear Information System (INIS)

1993-09-01

This report summarizes the methods that are currently employed and those that can be used to verify compliance with low-level radioactive waste (LLW) disposal facility waste acceptance criteria (WAC). This report presents the applicable regulations representing the Federal, State, and site-specific criteria for accepting LLW. Typical LLW generators are summarized, along with descriptions of their waste streams and final waste forms. General procedures and methods used by the LLW generators to verify compliance with the disposal facility WAC are presented. The report was written to provide an understanding of how a regulator could verify compliance with a LLW disposal facility's WAC. A comprehensive study of the methodology used to verify waste generator compliance with the disposal facility WAC is presented in this report. The study involved compiling the relevant regulations to define the WAC, reviewing regulatory agency inspection programs, and summarizing waste verification technology and equipment. The results of the study indicate that waste generators conduct verification programs that include packaging, classification, characterization, and stabilization elements. The current LLW disposal facilities perform waste verification steps on incoming shipments. A model inspection and verification program, which includes an emphasis on the generator's waste application documentation of their waste verification program, is recommended. The disposal facility verification procedures primarily involve the use of portable radiological survey instrumentation. The actual verification of generator compliance to the LLW disposal facility WAC is performed through a combination of incoming shipment checks and generator site audits

Low-level radioactive waste minimization for health care institutions

International Nuclear Information System (INIS)

Williams, G.

1990-01-01

In recent years medical waste has been the subject of considerable public and governmental attention. This has been, in part, due to the media's attraction to unfortunate instances of environmental pollution caused by hazardous and medical wastes. While a considerable amount of information is currently available on the treatment and disposal practices for hazardous wastes, a shortfall of information exists on the subject of medical wastes. Such wastes are generated by various health care institutions. Medical waste is a wide and all encompassing term which refers to a variety of wastes. This presentation addresses medical low-level (LLW) radioactive waste; its generation, recovery and handling. The development of generic waste minimization models and greater use of alternative technologies are part of the discussion

Conceptual designs for waste quality checking facilities for low level and intermediate level radioactive wastes and hazardous waste

International Nuclear Information System (INIS)

Driver, S.; Griffiths, M.; Leonard, C.D.; Smith, D.L.G.

1992-01-01

This report summarises work carried out on the design of facilities for the quality checking of Intermediate and Low Level Radioactive Waste and Hazardous Waste. The procedures used for the quality checking of these categories of waste are summarised. Three building options are considered: a separate LLW facility, a combined facility for LLW and HW and a Waste Quality Checking Facility for the three categories of waste. Budget Cost Estimates for the three facilities are given based on 1991 prices. (author)

Inventory and characteristics of current and projected low-level radioactive materials and waste in the United States

International Nuclear Information System (INIS)

Bisaria, A.; Bugos, R.G.; Pope, R.B.; Salmon, R.; Storch, S.N.; Lester, P.B.

1994-01-01

The Integrated Data Base (IDB), under US Department of Energy (DOE) funding and guidance, provides an annual update of compiled data on current and projected inventories and characteristics of DOE and commercially owned radioactive wastes. The data base addresses also the inventories of DOE and commercial spent fuel. These data are derived from reliable information from government sources, open literature, technical reports, and direct contacts. The radioactive materials considered are spent nuclear fuel, high-level waste (HLW), transuranic (TRU) waste, low-level waste (LLW), commercial uranium mill tailings, environmental restoration wastes, and mixed-LLW. This paper primarily focuses on LLW inventory and characterization

Microbial degradation of low-level radioactive waste. Final report

International Nuclear Information System (INIS)

Rogers, R.D.; Hamilton, M.A.; Veeh, R.H.; McConnell, J.W. Jr.

1996-06-01

The Nuclear Regulatory Commission stipulates in 10 CFR 61 that disposed low-level radioactive waste (LLW) be stabilized. To provide guidance to disposal vendors and nuclear station waste generators for implementing those requirements, the NRC developed the Technical Position on Waste Form, Revision 1. That document details a specified set of recommended testing procedures and criteria, including several tests for determining the biodegradation properties of waste forms. Information has been presented by a number of researchers, which indicated that those tests may be inappropriate for examining microbial degradation of cement-solidified LLW. Cement has been widely used to solidify LLW; however, the resulting waste forms are sometimes susceptible to failure due to the actions of waste constituents, stress, and environment. The purpose of this research program was to develop modified microbial degradation test procedures that would be more appropriate than the existing procedures for evaluation of the effects of microbiologically influenced chemical attack on cement-solidified LLW. The procedures that have been developed in this work are presented and discussed. Groups of microorganisms indigenous to LLW disposal sites were employed that can metabolically convert organic and inorganic substrates into organic and mineral acids. Such acids aggressively react with cement and can ultimately lead to structural failure. Results on the application of mechanisms inherent in microbially influenced degradation of cement-based material are the focus of this final report. Data-validated evidence of the potential for microbially influenced deterioration of cement-solidified LLW and subsequent release of radionuclides developed during this study are presented

Design and operational considerations of United States commercial nea-surface low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Birk, Sandra M.

1997-01-01

Low-level radioactive waste disposal standards and techniques in the United States have evolved significantly since the early 1960's. Six commercial LLW disposal facilities(Barnwell, Richland, Ward Valley, Sierra Blanca, Wake County and Boyd County) operated and proposed between 1962 and 1997. This report summarizes each site's design and operational considerations for near-surface disposal of low-level radioactive waste. These new standards and mitigating efforts at closed facilities (Sheffield, Maxey Flats, Beatty and West Valley) have helped to ensure that the public has been safely protected from LLW. 15 refs

Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics

International Nuclear Information System (INIS)

Hulse, R.A.

1991-08-01

Planning for storage or disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of that waste to estimate volumes, radionuclide activities, and waste forms. Data from existing literature, disposal records, and original research were used to estimate the characteristics and project volumes and radionuclide activities to the year 2035. GTCC LLW is categorized as: nuclear utilities waste, sealed sources waste, DOE-held potential GTCC LLW; and, other generator waste. It has been determined that the largest volume of those wastes, approximately 57%, is generated by nuclear power plants. The Other Generator waste category contributes approximately 10% of the total GTCC LLW volume projected to the year 2035. Waste held by the Department of Energy, which is potential GTCC LLW, accounts for nearly 33% of all waste projected to the year 2035; however, no disposal determination has been made for that waste. Sealed sources are less than 0.2% of the total projected volume of GTCC LLW

Some considerations in the evaluation of concrete as a structural material for alternative LLW disposal technologies

International Nuclear Information System (INIS)

MacKenzie, D.R.; Siskind, B.; Bowerman, B.S.; Piciulo, P.L.

1987-01-01

The objective of this study was to develop information needed to evaluate the long-term performance of concrete and reinforced concrete as a structural material for alternative LLW disposal methods. The capability to carry out such an evaluation is required for licensing a site which employs one of these alternative methods. The basis for achieving the study objective was the review and analysis of the literature on concrete and its properties, particularly its durability. In carrying out this program characteristics of concrete useful in evaluating its performance and factors that can affect its performance were identified. The factors are both intrinsic, i.e., associated with composition of the concrete (and thus controllable), and extrinsic, i.e., due to external environmental forces such as climatic conditions and aggressive chemicals in the soil. The testing of concrete, using both accelerated tests and long-term non-accelerated tests, is discussed with special reference to its application to modeling of long-term performance prediction. On the basis of the study's results, conditions for acceptance are recommended as an aid in the licensing of disposal sites which make use of alternative methods

Solid low-level radioactive waste volume projections at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Art, K.; Minton-Hughes, J.; Peper, C.

1995-01-01

In response to regulatory requirements, the current economic environment, and diminishing on-site low-level radioactive waste (LLW) disposal capacity, LANL needed to develop a system to collect data on future LLW generation that would comply with DOE Order 5820. 2A and be an effective facility planning tool. The LANL Volume Projections Project (VPP) was created to meet these needs. This paper describes objectives, scope, and components of the VPP that will provide information essential to future facility planning and development

Impacts of hazardous waste regulation on low-level waste management

International Nuclear Information System (INIS)

Sharples, F.E.; Eyman, L.D.

1987-01-01

Since passage of the 1984 amendments to the Resource Conservation and Recovery Act (RCRA), major changes have occurred in the regulation of hazardous waste. The US Environmental Protection Agency (EPA) has also greatly modified its interpretation of how these regulations apply to wastes from federal facilities, including defense wastes from US Department of Energy (DOE) sites. As a result, the regulatory distinctions between low-level radioactive waste (LLW) and hazardous waste are becoming blurred. This paper discusses recent statutory and regulatory changes and how they might affect the management of LLW at DOE facilities. 6 references

A sensitivity study of an evaluation of alternatives for disposal of INEL low-level waste and low-level mixed waste

International Nuclear Information System (INIS)

Roesener, W.S.; Smith, T.H.; Jorgenson-Waters, M.J.; Sherick, M.J.

1995-01-01

This paper presents insights gained from an informal sensitivity study of an evaluation of disposal alternatives for Idaho National Engineering Laboratory low-level waste and low-level mixed waste. The insights relate to the sensitivity of the alternative rankings to changes in assumptions identified as open-quotes key uncertaintiesclose quotes. The result of the sensitivity study is that significant changes occur in the rankings when selected open-quotes key uncertaintiesclose quotes are varied over reasonable ranges. Three alternatives involving the use of (a) shallow land burial and boreholes or (b) greater-depth burial and boreholes rank high for all cases investigated. The other alternatives rank low in some or all cases

DOE systems approach to a low-level waste management information system: summary paper

International Nuclear Information System (INIS)

Esparza, V.

1987-01-01

The LLWMP is performing an assessment of waste information systems currently in use at each DOE site for recording LLW data. The assessment is being conducted to determine what changes to the waste information systems, if any, are desirable to support implementation of this systems approach to LLW management. Recommendations will be made to DOE from this assessment and what would be involved to modify current DOE waste generator information practices to support an appropriately structured overall DOE LLW data systems. In support of reducing the uncertainty of decision-making, DOE has selected a systems approach to keep pace with an evolving regulatory climate to low-level waste. This approach considers the effects of each stage of the entire low-level waste management process. The proposed systems approach starts with the disposal side of the waste management system and progresses towards the waste generation side of the waste management system. Using this approach provides quantitative performance to be achieved. In addition, a systems approach also provides a method for selecting appropriate technology based on engineering models

The planning and management system of the low level radioactive waste transportation

International Nuclear Information System (INIS)

Tanaka, K.; Yoshida, K.; Miyamoto, J.; Sanui, T.; Noura, T.; Kitanishi, K.; Nara, S.

1993-01-01

Nuclear Fuel Transport Co, Ltd. (hereafter called NFT) was the first in Japan to transport low-level radioactive waste (LLW). It is now engaged in preparatory operations with the slogan 'Improved Safety and Reliability' and is introducing advanced mechanization systems to provide safety and reliability in software management such as transportation planning and transportation information management. The following is an introduction of these systems, which provide overall support in transportation planning determination and transportation management operations related to the LLW transportation cycle. (J.P.N.)

Characteristics of low-level radioactive waste disposed during 1987--1989

International Nuclear Information System (INIS)

Roles, G.W.

1990-12-01

This report presents the volume, activity, and radionuclide distributions in low-level radioactive waste (LLW) disposed during 1987 through 1989 at the commercial disposal facilities located near Barnwell, SC, Richland, WA, and Beatty, NV. The report has been entirely assembled from descriptions of waste provided in LLW shipment manifests. Individual radionuclide distributions are listed as a function of waste class, of general industry, and of waste stream. In addition, information is presented about disposal of wastes containing chelating agents, about use of solidification media, about the distribution of radiation levels at the surfaces of waste containers, and about the distribution of waste container sizes. Considerably more information is presented about waste disposed at the Richland and Beatty disposal facilities than at the Barnwell disposal facility

Developing a low-level radioactive waste disposal facility in Connecticut: Update on progress and new directions

Energy Technology Data Exchange (ETDEWEB)

Gingerich, R.E. [Connecticut Hazardous Waste Management Service, Hartford, CT (United States)

1993-03-01

Connecticut is a member of the Northeast Interstate Low-Level Radioactive Waste Management Compact (Northeast LLRW Compact). The other member of the Northeast LLRW Compact is New Jersey. The Northeast Interstate Low-Level Radioactive Waste Commission (Northeast Compact Commission), the Northeast LLRW Compact`s governing body, has designated both Connecticut and New Jersey as host states for disposal facilities. The Northeast Compact Commission has recommended that, for purposes of planning for each state`s facility, the siting agency for the state should use projected volumes and characteristics of the LLW generated in its own state. In 1987 Connecticut enacted legislation that assigns major responsibilities for developing a LLW disposal facility in Connecticut to the Connecticut Hazardous Waste Management Service (CHWMS). The CHWMS is required to: prepare and revise, as necessary, a LLW Management Plan for the state; select a site for a LLW disposal facility; select a disposal technology to be used at the site; select a firm to obtain the necessary approvals for the facility and to develop and operate it; and serve as the custodial agency for the facility. This paper discusses progress in developing a facility.

Operation and management plan of Rokkasho Low Level Radioactive Waste Disposal Center

International Nuclear Information System (INIS)

Nakanishi, Z.; Tomozawa, T.; Mahara, Y.; Iimura, H.

1993-01-01

Japan Nuclear Fuel Limited (JNFL) started the operation of the Rokkasho Low-Level Radioactive Waste Disposal Center in December, 1992. This center is located at Rokkasho Village in Aomori Prefecture. The facility in this center will provide for the disposal of 40,000 m 3 of the low-level radioactive waste (LLW) produced from domestic nuclear power stations. The facility will receive between 5,000 m 3 and 10,000 m 3 of waste every year. Strict and efficient institutional controls, such as the monitoring of the environment and management of the site, is required for about 300 years. This paper provides an outline of the LLW burial operation and management program at the disposal facility. The facility is located 14--19 meters below the ground surface in the hollowed out Takahoko Formation

76 FR 10810 - Public Workshop to Discuss Low-Level Radioactive Waste Management

Science.gov (United States)

2011-02-28

... Radioactive Waste Management AGENCY: Nuclear Regulatory Commission. ACTION: Public Workshop and Request for... regulatory framework for the management of commercial low-level radioactive waste (LLW). The purpose of this...-level radioactive wastes that did not exist at the time part 61 was promulgated. The developments...

Low-level radioactive waste source terms for the 1992 integrated data base

International Nuclear Information System (INIS)

Loghry, S.L.; Kibbey, A.H.; Godbee, H.W.; Icenhour, A.S.; DePaoli, S.M.

1995-01-01

This technical manual presents updated generic source terms (i.e., unitized amounts and radionuclide compositions) which have been developed for use in the Integrated Data Base (IDB) Program of the U.S. Department of Energy (DOE). These source terms were used in the IDB annual report, Integrated Data Base for 1992: Spent Fuel and Radioactive Waste Inventories, Projections, and Characteristics, DOE/RW-0006, Rev. 8, October 1992. They are useful as a basis for projecting future amounts (volume and radioactivity) of low-level radioactive waste (LLW) shipped for disposal at commercial burial grounds or sent for storage at DOE solid-waste sites. Commercial fuel cycle LLW categories include boiling-water reactor, pressurized-water reactor, fuel fabrication, and uranium hexafluoride (UF 6 ) conversion. Commercial nonfuel cycle LLW includes institutional/industrial (I/I) waste. The LLW from DOE operations is category as uranium/thorium fission product, induced activity, tritium, alpha, and open-quotes otherclose quotes. Fuel cycle commercial LLW source terms are normalized on the basis of net electrical output [MW(e)-year], except for UF 6 conversion, which is normalized on the basis of heavy metal requirement [metric tons of initial heavy metal ]. The nonfuel cycle commercial LLW source term is normalized on the basis of volume (cubic meters) and radioactivity (curies) for each subclass within the I/I category. The DOE LLW is normalized in a manner similar to that for commercial I/I waste. The revised source terms are based on the best available historical data through 1992

Public Acceptance of Low-Level Waste Disposal Critical to the Nuclear Renaissance

International Nuclear Information System (INIS)

Sonny Goldston, W.T.

2009-01-01

The disposal of various Low-Level Waste (LLW) forms projected to result from the operation of a pilot or large scale Advanced Fuel Cycle Initiative Programs' (formally known as Global Nuclear Energy Partnership (GNEP)) reprocessing and vitrification plants requires the DOE LLW program and regulatory structure to be utilized in its present form due to the limited availability of Nuclear Regulatory Commission licensed commercial LLW disposal facilities to handle wastes with radionuclide concentrations that are greater than Nuclear Regulatory Commission (NRC) Class A limits. This paper will describe the LLW forms and the regulatory structures and facilities available to dispose of this waste. Then the paper discusses the necessity of an excellent public involvement program to ensure the success of an effective technical solution. All of the decisions associated with the management of these wastes are of interest to the public and successful program implementation would be impossible without including the public up-front in the program formulation. Serious problems can result if program decisions are made without public involvement, and if the public is informed after key decisions are made. This paper will describe the regulatory and public involvement program and their effects on the decisions concerning the disposal of Low-Level Radioactive Waste (LLW) at the Savannah River Site (SRS). An extensive public communications effort resulted in endorsement of changes in disposal practices by the SRS Citizens Advisory Board that was critical to the success of the program. A recommendation will be made to install a public involvement program that is similar to the SRS Citizens Advisory Board in order to ensure the success of the AFCI programs in view of the limited availability to handle the wastes from the program and the public acceptance of change that will be required. (authors)

Current practices for maintaining occupational exposures ALARA at low-level waste disposal sites

International Nuclear Information System (INIS)

Hadlock, D.E.; Herrington, W.N.; Hooker, C.D.; Murphy, D.W.; Gilchrist, R.L.

1983-12-01

The United States Nuclear Regulatory Commission contracted with Pacific Northwest Laboratory (PNL) to provide technical assistance in establishing operational guidelines, with respect to radiation control programs and methods of minimizing occupational radiation exposure, at Low-Level Waste (LLW) disposal sites. The PNL, through site visits, evaluated operations at LLW disposal sites to determine the adequacy of current practices in maintaining occupational exposures as low as is reasonably achievable (ALARA). The data sought included the specifics of: ALARA programs, training programs, external exposure control, internal exposure control, respiratory protection, surveillance, radioactive waste management, facilities and equipment, and external dose analysis. The results of the study indicated the following: The Radiation Protection and ALARA programs at the three commercial LLW disposal sites were observed to be adequate in scope and content compared to similar programs at other types of nuclear facilities. However, it should be noted that there were many areas that could be improved upon to help ensure the health and safety of occupationally exposed individuals

Current practices for maintaining occupational exposures ALARA at low-level waste disposal sites

Energy Technology Data Exchange (ETDEWEB)

Hadlock, D.E.; Herrington, W.N.; Hooker, C.D.; Murphy, D.W.; Gilchrist, R.L.

1983-12-01

The United States Nuclear Regulatory Commission contracted with Pacific Northwest Laboratory (PNL) to provide technical assistance in establishing operational guidelines, with respect to radiation control programs and methods of minimizing occupational radiation exposure, at Low-Level Waste (LLW) disposal sites. The PNL, through site visits, evaluated operations at LLW disposal sites to determine the adequacy of current practices in maintaining occupational exposures as low as is reasonably achievable (ALARA). The data sought included the specifics of: ALARA programs, training programs, external exposure control, internal exposure control, respiratory protection, surveillance, radioactive waste management, facilities and equipment, and external dose analysis. The results of the study indicated the following: The Radiation Protection and ALARA programs at the three commercial LLW disposal sites were observed to be adequate in scope and content compared to similar programs at other types of nuclear facilities. However, it should be noted that there were many areas that could be improved upon to help ensure the health and safety of occupationally exposed individuals.

1980 state-by-state assessment of low-level radioactive wastes shipped to commercial disposal sites

International Nuclear Information System (INIS)

1982-06-01

Information is presented on the volumes, curie values, sources, and disposal of low-level radioactive wastes (LLW) in each state. The wastes are segmented into 2 broad categories - institutional/industrial and commercial power reactor wastes. The volumes and curie values were obtained from the commercial site operators. The percentage of LLW disposed of at each of the 3 operating disposal sites located at Barnwell, SC, Beatty, NV, and Richland, WA are included

Operation and management plan of Rokkasho Low Level Radioactive Waste Disposal Center

Energy Technology Data Exchange (ETDEWEB)

Nakanishi, Z.; Tomozawa, T.; Mahara, Y.; Iimura, H. [Japan Nuclear Fuel Ltd., Tokyo (Japan). Radioactive Waste Management Dept.

1993-12-31

Japan Nuclear Fuel Limited (JNFL) started the operation of the Rokkasho Low-Level Radioactive Waste Disposal Center in December, 1992. This center is located at Rokkasho Village in Aomori Prefecture. The facility in this center will provide for the disposal of 40,000 m{sup 3} of the low-level radioactive waste (LLW) produced from domestic nuclear power stations. The facility will receive between 5,000 m{sup 3} and 10,000 m{sup 3} of waste every year. Strict and efficient institutional controls, such as the monitoring of the environment and management of the site, is required for about 300 years. This paper provides an outline of the LLW burial operation and management program at the disposal facility. The facility is located 14--19 meters below the ground surface in the hollowed out Takahoko Formation.

Investigations with respect to pressure build-up in 200 l drums with supercompacted low level waste (LLW)

International Nuclear Information System (INIS)

Kroth, K.; Lammertz, H.

1988-04-01

In the drum storage facilities of various nuclear power stations, ballooning effects have recently been observed on a limited number of 200 l drums filled with hypercompacted mixed LLW. The ballooning of the drums lid and bottom is due to internal overpressure caused by gas formation in the waste. The internal drum pressures and the composition of the drum gases were measured on a considerable number of 200 l drums. Hydrogen, formed by chemical reactions between the waste components, was identified as the pressure generating gas. The reasons for the hydrogen formation were investigated on both real and simulated wastes. (orig.) [de

Concept development for saltstone and low level waste disposal

International Nuclear Information System (INIS)

Wilhite, E.L.

1987-03-01

A low-level alkaline salt solution will be a byproduct in the processing of high-level waste at the Savannah River Plant (SRP). This solution will be incorporated into a cement wasteform, saltstone, and placed in surface vaults. Laboratory and field testing and mathematical modeling have demonstrated the predictability of contaminant release from cement wasteforms. Saltstone disposal in surface vaults will meet drinking water standards in shallow groundwater at the disposal area boundary. Planning for new Low-Level Waste (LLW) disposal could incorporate concepts developed for saltstone disposal

Low level radioactive waste disposal

International Nuclear Information System (INIS)

Balaz, J.; Chren, O.

2015-01-01

The Mochovce National Radwaste Repository is a near surface multi-barrier disposal facility for disposal of processed low and very low level radioactive wastes (radwastes) resulting from the operation and decommissioning of nuclear facilities situated in the territory of the Slovak Republic and from research institutes, laboratories, hospitals and other institutions (institutional RAW) which are in compliance with the acceptance criteria. The basic safety requirement of the Repository is to avoid a radioactive release to the environment during its operation and institutional inspection. This commitment is covered by the protection barrier system. The method of solution designed and implemented at the Repository construction complies with the latest knowledge and practice of the repository developments all over the world and meets requirements for the safe radwaste disposal with minimum environmental consequences. All wastes are solidified and have to meet the acceptance criteria before disposal into the Repository. They are processed and treated at the Bohunice RAW Treatment Centre and Liquid RAW Final Treatment Facility at Mochovce. The disposal facility for low level radwastes consists of two double-rows of reinforced concrete vaults with total capacity 7 200 fibre reinforced concrete containers (FCCs) with RAW. One double-row contains 40 The operation of the Repository was started in year 2001 and after ten years, in 2011 was conducted the periodic assessment of nuclear safety with positive results. Till the end of year 2014 was disposed to the Repository 11 514 m 3 RAW. The analysis of total RAW production from operation and decommissioning of all nuclear installation in SR, which has been carried out in frame of the BIDSF project C9.1, has showed that the total volume estimation of conditioned waste is 108 thousand m 3 of which 45.5 % are low level waste (LLW) and 54,5 % very low level waste (VLLW). On the base of this fact there is the need to build 7

Low-level waste management alternatives and analysis in DOE`s programmatic environmental impact statement

Energy Technology Data Exchange (ETDEWEB)

Gerstein, J.S. [Dept. of Energy, Washington, DC (United States). Office of Environmental Restoration and Waste Management

1993-03-01

The Department of Energy is preparing a Programmatic Environmental Impact Statement (PEIS) for the Environmental Restoration and Waste Management Program. The PEIS has been divided into an Environmental Restoration section and a Waste Management section. Each section has a unique set of alternatives. This paper will focus on the waste management alternatives and analysis. The set of alternatives for waste management has been divided into waste categories. These categories are: high-level waste, transuranic waste, low-level waste, low-level mixed waste, greater-than-class C and low-level waste from commercial sources, hazardous waste, and spent nuclear fuel. This paper will discuss the alternatives and analytical approach that will be used to evaluate these alternatives for the low-level waste section. Although the same alternatives will be considered for all waste types, the analysis will be performed separately for each waste type. In the sections that follow, information will be provided on waste management configurations, the analysis of waste management alternatives, waste types and locations, facility and transportation activities, the facility and transportation impacts assessment, and the compilation of impacts.

Vectra GSI, Inc. low-level waste melter testing Phase 1 test report

Energy Technology Data Exchange (ETDEWEB)

Stegen, G.E.; Wilson, C.N.

1996-02-21

A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense wastes stored in underground tanks at the Hanford Site in southeastern Washington State. Vectra GSI, Inc. was one of seven vendors selected for Phase 1 of the melter demonstration tests using simulated LLW that were completed during fiscal year 1995. The attached report prepared by Vectra GSI, Inc. describes results of melter testing using slurry feed and dried feeds. Results of feed drying and prereaction tests using a fluid bed calciner and rotary dryer also are described.

Vectra GSI, Inc. low-level waste melter testing Phase 1 test report

International Nuclear Information System (INIS)

Stegen, G.E.; Wilson, C.N.

1996-01-01

A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense wastes stored in underground tanks at the Hanford Site in southeastern Washington State. Vectra GSI, Inc. was one of seven vendors selected for Phase 1 of the melter demonstration tests using simulated LLW that were completed during fiscal year 1995. The attached report prepared by Vectra GSI, Inc. describes results of melter testing using slurry feed and dried feeds. Results of feed drying and prereaction tests using a fluid bed calciner and rotary dryer also are described

Licensing procedures for Low-Level Waste disposal facilities

International Nuclear Information System (INIS)

Roop, R.D.; Van Dyke, J.W.

1985-09-01

This report describes the procedures applicable to siting and licensing of disposal facilities for low-level radioactive wastes. Primary emphasis is placed on those procedures which are required by regulations, but to the extent possible, non-mandatory activities which will facilitate siting and licensing are also considered. The report provides an overview of how the procedural and technical requirements for a low-level waste (LLW) disposal facility (as defined by the Nuclear Regulatory Commission's Rules 10 CFR Parts 2, 51, and 61) may be integrated with activities to reduce and resolve conflict generated by the proposed siting of a facility. General procedures are described for site screening and selection, site characterization, site evaluation, and preparation of the license application; specific procedures for several individual states are discussed. The report also examines the steps involved in the formal licensing process, including docketing and initial processing, preparation of an environmental impact statement, technical review, hearings, and decisions. It is concluded that development of effective communication between parties in conflict and the utilization of techniques to manage and resolve conflicts represent perhaps the most significant challenge for the people involved in LLW disposal in the next decade. 18 refs., 6 figs

Low level waste management at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Rodgers, A.D.; Truitt, D.J.; Logan, J.A.; Brown, R.M.

1986-02-01

EG and G Idaho, Inc. is the lead contractor for the Department of Energy (DOE) National Low Level Waste Management Program, established in 1979. In this role, the company uses its waste management expertise to provide management and technical direction to support the disposal of low-level waste (LLW) in a manner that protects the environment and the public health and safety while improving efficiency and cost-effectiveness. Program activities are divided into two areas: defense-related and commercial nuclear reactor programs. The defense program was established to develop technology improvements, provide technology transfer, and to ensure a more efficient and uniform system for low level waste disposal. To achieve the program's goals, it is necessary to improve, document, and, where necessary, develop new methods for waste generation reduction, waste treatment, shallow-land burial, greater confinement disposal, and measures to correct existing site deficiencies. The commercial low level waste management program provides support to assist the states in developing an effective national low level waste management system and provides technical assistance for siting of regional commercial LLW disposal sites. The program provides technical and informational support to state officials, low level waste generators, managers, and facility operators to resolve low level waste problems and to improve the systems' overall effectiveness. Procedures are developed and documented and made available to commercial users through this program. Additional work is being conducted to demonstrate the stabilization and closure of low level radioactive waste disposal sites and develop the criteria and procedures for acceptance of such sites by the Department of Energy after closure has been completed. 7 refs., 6 figs., 1 tab

Low level waste management: a compilation of models and monitoring techniques. Volume 1

Energy Technology Data Exchange (ETDEWEB)

Mosier, J.E.; Fowler, J.R.; Barton, C.J. (comps.)

1980-04-01

In support of the National Low-Level Waste (LLW) Management Research and Development Program being carried out at Oak Ridge National Laboratory, Science Applications, Inc., conducted a survey of models and monitoring techniques associated with the transport of radionuclides and other chemical species from LLW burial sites. As a result of this survey, approximately 350 models were identified. For each model the purpose and a brief description are presented. To the extent possible, a point of contact and reference material are identified. The models are organized into six technical categories: atmospheric transport, dosimetry, food chain, groundwater transport, soil transport, and surface water transport. About 4% of the models identified covered other aspects of LLW management and are placed in a miscellaneous category. A preliminary assessment of all these models was performed to determine their ability to analyze the transport of other chemical species. The models that appeared to be applicable are identified. A brief survey of the state-of-the-art techniques employed to monitor LLW burial sites is also presented, along with a very brief discussion of up-to-date burial techniques.

Low level waste management: a compilation of models and monitoring techniques. Volume 1

International Nuclear Information System (INIS)

Mosier, J.E.; Fowler, J.R.; Barton, C.J.

1980-04-01

In support of the National Low-Level Waste (LLW) Management Research and Development Program being carried out at Oak Ridge National Laboratory, Science Applications, Inc., conducted a survey of models and monitoring techniques associated with the transport of radionuclides and other chemical species from LLW burial sites. As a result of this survey, approximately 350 models were identified. For each model the purpose and a brief description are presented. To the extent possible, a point of contact and reference material are identified. The models are organized into six technical categories: atmospheric transport, dosimetry, food chain, groundwater transport, soil transport, and surface water transport. About 4% of the models identified covered other aspects of LLW management and are placed in a miscellaneous category. A preliminary assessment of all these models was performed to determine their ability to analyze the transport of other chemical species. The models that appeared to be applicable are identified. A brief survey of the state-of-the-art techniques employed to monitor LLW burial sites is also presented, along with a very brief discussion of up-to-date burial techniques

Guidelines for radiological performance assessment of DOE low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Case, M.J.; Otis, M.D.

1988-07-01

This document provides guidance for conducting radiological performance assessments of Department of Energy (DOE) low-level radioactive waste (LLW) disposal facilities. The guidance is specifically intended to provide the fundamental approach necessary to meet the performance assessment requirements. The document is written for LLW facility operators or other personnel who will manage the performance assessment task. The document is meant to provide guidance for conducting performance assessments in a generally consistent manner at all DOE LLW disposal facilities. The guidance includes a summary of performance objectives to be met by LLW disposal facilities (these objectives are derived from current DOE and other applicable federal regulatory guidelines); specific criteria for an adequate performance assessment and from which a minimum set of required calculations may be determined; recommendations of methods for screening critical components of the analysis system so that these components can be addressed in detail; recommendations for the selection of existing models and the development of site-specific models; recommendations of techniques for comparison of assessment results with performance objectives; and a summary of reporting requirements

Highly durable and low permeable concrete for LLW facilities

International Nuclear Information System (INIS)

Yanagibashi, Kunio; Saito, Toshio; Odagawa, Masaro.

1997-01-01

Concrete used for LLW facilities is required to be highly durable. The authors evaluated concrete containing glycol ether derivatives and silica fume as admixtures. Compressive strength, diffusion coefficient of water, depth of accelerated carbonation, drying shrinkage, depth of chlorides penetration and resistance to freezing and thawing were investigated using concrete specimens. Compressive strength, depth of accelerated carbonation, diffusion coefficient of 137 Cs were investigated using mortar specimens before and after irradiation of gamma rays. Results showed that using glycol ether derivatives and silica fume was effective in improving the durability. (author)

Greater-Than-Class C low-level radioactive waste treatment technology evaluation

International Nuclear Information System (INIS)

Garrison, T.W.; Fischer, D.K.

1993-01-01

This report was developed to provide the Greater-Than-Class C Low-Level Radioactive Waste Management Program with criteria and a methodology to select candidate treatment technologies for Greater-Than-Class C low-level radioactive waste (GTCC LLW) destined for dedicated storage and ultimately disposal. The technology selection criteria are provided in a Lotus spreadsheet format to allow the methodology to evolve as the GTCC LLW Program evolves. It is recognized that the final disposal facility is not yet defined; thus, the waste acceptance criteria and other facility-specific features are subject to change. The spreadsheet format will allow for these changes a they occur. As additional treatment information becomes available, it can be factored into the analysis. The technology selection criteria were established from program goals, draft waste acceptance criteria for dedicated storage (including applicable regulations), and accepted remedial investigation methods utilized under the Comprehensive Environmental Response, Compensation, and Liability Act. Kepner-Tregoe decisionmaking techniques are used to compare and rank technologies against the criteria

Radioactive waste management complex low-level waste radiological composite analysis

Energy Technology Data Exchange (ETDEWEB)

McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.; Keck, K.N.; Honeycutt, T.K.

1998-05-01

The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consists of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective.

Radioactive waste management complex low-level waste radiological composite analysis

International Nuclear Information System (INIS)

McCarthy, J.M.; Becker, B.H.; Magnuson, S.O.; Keck, K.N.; Honeycutt, T.K.

1998-05-01

The composite analysis estimates the projected cumulative impacts to future members of the public from the disposal of low-level radioactive waste (LLW) at the Idaho National Engineering and Environmental Laboratory (INEEL) Radioactive Waste Management Complex (RWMC) and all other sources of radioactive contamination at the INEEL that could interact with the LLW disposal facility to affect the radiological dose. Based upon the composite analysis evaluation, waste buried in the Subsurface Disposal Area (SDA) at the RWMC is the only source at the INEEL that will significantly interact with the LLW facility. The source term used in the composite analysis consists of all historical SDA subsurface disposals of radionuclides as well as the authorized LLW subsurface disposal inventory and projected LLW subsurface disposal inventory. Exposure scenarios evaluated in the composite analysis include all the all-pathways and groundwater protection scenarios. The projected dose of 58 mrem/yr exceeds the composite analysis guidance dose constraint of 30 mrem/yr; therefore, an options analysis was conducted to determine the feasibility of reducing the projected annual dose. Three options for creating such a reduction were considered: (1) lowering infiltration of precipitation through the waste by providing a better cover, (2) maintaining control over the RWMC and portions of the INEEL indefinitely, and (3) extending the period of institutional control beyond the 100 years assumed in the composite analysis. Of the three options investigated, maintaining control over the RWMC and a small part of the present INEEL appears to be feasible and cost effective

Lawrence Livermore National Laboratory low-level waste systems performance assessment

International Nuclear Information System (INIS)

1990-11-01

This Low-Level Radioactive Waste (LLW) Systems Performance Assessment (PA) presents a systematic analysis of the potential risks posed by the Lawrence Livermore National Laboratory (LLNL) waste management system. Potential risks to the public and environment are compared to established performance objectives as required by DOE Order 5820.2A. The report determines the associated maximum individual committed effective dose equivalent (CEDE) to a member of the public from LLW and mixed waste. A maximum annual CEDE of 0.01 mrem could result from routine radioactive liquid effluents. A maximum annual CEDE of 0.003 mrem could result from routine radioactive gaseous effluents. No other pathways for radiation exposure of the public indicated detectable levels of exposure. The dose rate, monitoring, and waste acceptance performance objectives were found to be adequately addressed by the LLNL Program. 88 refs., 3 figs., 17 tabs

Greater-than-Class C low-level radioactive waste characterization. Appendix E-5: Impact of the 1993 NRC draft Branch Technical Position on concentration averaging of greater-than-Class C low-level radioactive waste

International Nuclear Information System (INIS)

Tuite, P.; Tuite, K.; Harris, G.

1994-09-01

This report evaluates the effects of concentration averaging practices on the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) generated by the nuclear utility industry and sealed sources. Using estimates of the number of waste components that individually exceed Class C limits, this report calculates the proportion that would be classified as GTCC LLW after applying concentration averaging; this proportion is called the concentration averaging factor. The report uses the guidance outlined in the 1993 Nuclear Regulatory Commission (NRC) draft Branch Technical Position on concentration averaging, as well as waste disposal experience at nuclear utilities, to calculate the concentration averaging factors for nuclear utility wastes. The report uses the 1993 NRC draft Branch Technical Position and the criteria from the Barnwell, South Carolina, LLW disposal site to calculate concentration averaging factors for sealed sources. The report addresses three waste groups: activated metals from light water reactors, process wastes from light-water reactors, and sealed sources. For each waste group, three concentration averaging cases are considered: high, base, and low. The base case, which is the most likely case to occur, assumes using the specific guidance given in the 1993 NRC draft Branch Technical Position on concentration averaging. To project future GTCC LLW generation, each waste category is assigned a concentration averaging factor for the high, base, and low cases

Low-level radioactive waste management: transitioning to off-site disposal at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Dorries, Alison M.

2010-01-01

Facing the closure of nearly all on-site management and disposal capability for low-level radioactive waste (LLW), Los Alamos National Laboratory (LANL) is making ready to ship the majority of LLW off-site. In order to ship off-site, waste must meet the Treatment, Storage, and Disposal Facility's (TSDF) Waste Acceptance Criteria (WAC). In preparation, LANL's waste management organization must ensure LANL waste generators characterize and package waste compliantly and waste characterization documentation is complete and accurate. Key challenges that must be addressed to successfully make the shift to off-site disposal of LLW include improving the detail, accuracy, and quality of process knowledge (PK) and acceptable knowledge (AK) documentation, training waste generators and waste management staff on the higher standard of data quality and expectations, improved WAC compliance for off-site facilities, and enhanced quality assurance throughout the process. Certification of LANL generators will allow direct off-site shipping of LLW from their facilities.

Plans for managing greater-than-class C low-level waste

International Nuclear Information System (INIS)

Newberry, W.F.; Coleman, J.A.

1990-01-01

Low-level waste is defined in the Low-Level Radioactive Waste Policy Amendments Act of 1985 (Title I, Public Law 99-240) as radioactive waste that is neither high-level radioactive waste, spent nuclear fuel, nor by-product material (mill tailings). This paper presents proposed plans for the Department of Energy to fulfill its responsibility to dispose of GTCC LLW under the 1985 law, and to ensure that safe options are available for long-term management of such, pending the availability of disposal capacity. In the absence of a concentration-based definition for high-level waste, there currently is no upper bound for the concentration of radionuclides in low-level waste

Environmental monitoring of subsurface low-level waste disposal facilities at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Ashwood, T.L.; Hicks, D.S.

1992-01-01

Oak Ridge National Laboratory (ORNL) generates low-level waste (LLW) as part of its research and isotope production activities. This waste is managed in accordance with US Department of Energy (DOE) Order 5820.2A. Solid LLW management includes disposal in above-ground, tumulus-type facilities as well as in various types of subsurface facilities. Since 1986, subsurface disposal has been conducted using various designs employing greater-confinement-disposal (GCD) techniques. The purpose of this paper is to present monitoring results that document the short-term performance of these GCD facilities

Immobilization and Waste Form Product Acceptance for Low Level and TRU Waste Forms

International Nuclear Information System (INIS)

Holtzscheiter, E.W.; Harbour, J.R.

1998-05-01

The Tanks Focus Area is supporting technology development in immobilization of both High Level (HLW) and Low Level (LLW) radioactive wastes. The HLW process development at Hanford and Idaho is patterned closely after that of the Savannah River (Defense Waste Processing Facility) and West Valley Sites (West Valley Demonstration Project). However, the development and options open to addressing Low Level Waste are diverse and often site specific. To start, it is important to understand the breadth of Low Level Wastes categories

Hanford low-level waste process chemistry testing data package

International Nuclear Information System (INIS)

Smith, H.D.; Tracey, E.M.; Darab, J.G.; Smith, P.A.

1996-03-01

Recently, the Tri-Party Agreement (TPA) among the State of Washington Department of Ecology, U.S. Department of Energy (DOE) and the US Environmental Protection Agency (EPA) for the cleanup of the Hanford Site was renegotiated. The revised agreement specifies vitrification as the encapsulation technology for low level waste (LLW). A demonstration, testing, and evaluation program underway at Westinghouse Hanford Company to identify the best overall melter-system technology available for vitrification of Hanford Site LLW to meet the TPA milestones. Phase I is a open-quotes proof of principleclose quotes test to demonstrate that a melter system can process a simulated highly alkaline, high nitrate/nitrite content aqueous LLW feed into a glass product of consistent quality. Seven melter vendors were selected for the Phase I evaluation: joule-heated melters from GTS Duratek, Incorporated (GDI); Envitco, Incorporated (EVI); Penberthy Electomelt, Incorporated (PEI); and Vectra Technologies, Incorporated (VTI); a gas-fired cyclone burner from Babcock ampersand Wilcox (BCW); a plasma torch-fired, cupola furnace from Westinghouse Science and Technology Center (WSTC); and an electric arc furnace with top-entering vertical carbon electrodes from the U.S. Bureau of Mines (USBM)

Selected radionuclides important to low-level radioactive waste management

International Nuclear Information System (INIS)

1996-11-01

The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). This report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237

Selected radionuclides important to low-level radioactive waste management

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-11-01

The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). This report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237.

Rooting depths of plants on low-level waste disposal sites

International Nuclear Information System (INIS)

Foxx, T.S.; Tierney, G.D.; Williams, J.M.

1984-11-01

In 1981-1982 an extensive bibliographic study was done to reference rooting depths of native plants in the United States. The data base presently contains 1034 different rooting citations with approximately 12,000 data elements. For this report, data were analyzed for rooting depths related to species found on low-level waste (LLW) sites at Los Alamos National Laboratory. Average rooting depth and rooting frequencies were determined and related to present LLW maintenance. The data base was searched for information on rooting depths of 53 species found on LLW sites at Los Alamos National Laboratory. The study indicates 12 out of 13 grasses found on LLW sites root below 91 cm. June grass [Koeleria cristata (L.) Pers.] (76 cm) was the shallowest rooting grass and side-oats grama [Bouteloua curtipendula (Michx.) Torr.] was the deepest rooting grass (396 cm). Forbs were more variable in rooting depths. Indian paintbrush (Castelleja spp.) (30 cm) was the shallowest rooting forb and alfalfa (Medicago sativa L.) was the deepest (>3900 cm). Trees and shrubs commonly rooted below 457 cm. The shallowest rooting tree was elm (Ulmus pumila L.) (127 cm) and the deepest was one-seed juniper [Juniperus monosperma (Engelm) Sarg.] (>6000 cm). Apache plume [Fallugia paradoxa (D. Don) Endl.] rooted to 140 cm, whereas fourwing saltbush [Atriplex canecens (Pursh) Nutt.] rooted to 762 cm

Equity of commercial low-level radioactive waste disposal fees. Report to Congress

International Nuclear Information System (INIS)

1998-02-01

In the Report accompanying the Fiscal Year 1997 Senate Energy and Water Development Appropriations Bill, the Senate Appropriations Committee directed the Department of Energy (DOE) to prepare a study of the costs of operating a low-level radioactive waste (LLW) disposal facility such as the one at Barnwell, South Carolina, and to determine whether LLW generators are paying equitable disposal fees. The disposal costs of four facilities are reviewed in this report, two operating facilities and two planned facilities. The operating facilities are located at Barnwell, South Carolina, and Richland, Washington. They are operated by Chem-Nuclear, LLC, (Chem-Nuclear), and US Ecology, Inc., (US Ecology), respectively. The planned facilities are expected to be built at Ward Valley, California, and Sierra Blanca, Texas. They will be operated by US Ecology and the State of Texas, respectively. This report found that disposal fees vary significantly among facilities for a variety of reasons. However, the information suggests that at each disposal facility, LLW generators pay equitable disposal fees

GTS Duratek, phase I Hanford low-level waste melter tests: Final report

International Nuclear Information System (INIS)

Eaton, W.C.

1995-01-01

A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense waste stored in underground tanks at the Hanford Site in southeastern Washington State. Phase 1 of the melter demonstration tests using simulated LLW was completed during fiscal year 1995. This document is the final report on testing performed by GTS Duratek Inc. in Columbia, Maryland. GTS Duratek (one of the seven vendors selected) was chosen to demonstrate Joule heated melter technology under WHC subcontract number MMI-SVV-384215. The report contains description of the tests, observations, test data and some analysis of the data as it pertains to application of this technology for LLW vitrification. The document also contains summaries of the melter offgas reports issued as separate documents for the 100 kg melter (WHC-SD-WM-VI-028) and for the 1000 kg melter (WHC-SD-WM-VI-029)

Development of an accelerated leach test(s) for low-level waste forms

International Nuclear Information System (INIS)

Dougherty, D.R.; Fuhrmann, M.; Colombo, P.

1986-01-01

An accelerated leach test(s) is being developed to predict long-term leaching behavior of low-level radioactive waste (LLW) forms in their disposal environments. As necessary background, a literature survey of reported leaching mechanisms, available mathematical models and factors that affect leaching of LLW forms has been compiled. Mechanisms which have been identified include diffusion, dissolution, ion exchange, corrosion and surface effects. A computerized data base of LLW leaching data and mathematical models is being developed. The data is being used for model evaluation by curve fitting and statistical analysis according to standard procedures of statistical quality control. Long-term leach tests on portland cement, bitumen and vinyl ester-styrene (VES) polymer waste forms are underway which are designed to identify and evaluate factors that accelerate leaching without changing the mechanisms. Initial results on the effect of temperature on leachability indicate that the leach rates of cement and VES waste forms increase with increasing temperature, whereas, the leach rate of bitumen is little affected

Facility status and progress of the INEL's WERF MLLW and LLW incinerator

International Nuclear Information System (INIS)

Conley, D.; Corrigan, S.

1996-01-01

The Idaho National Engineering Laboratory's (INEL) Waste Experimental Reduction Facility (WERF) incinerator began processing beta/gamma- emitting low-level waste (LLW) in September 1984. A Resource Conservation and Recovery Act (RCRA) trial burn for the WERF incinerator was conducted in 1986, and in 1989 WERF began processing (hazardous and low-level radioactive) waste known as mixed low-level waste (MLLW). On February 14, 1991 WERF operations were suspended to improve operating procedures and configuration management. On July 12, 1995, WERF initiated incineration of LLW; and on September 20, 1995 WERF resumed its primary mission of incinerating MLLW. MLLW incineration is proceeding under RCRA interim status. State of Idaho issuance of the Part B permit is one of the State's highest permitting priorities. The State of Idaho's Division of Environmental Quality is reviewing the permit application along with a revised trial burn plan that was also submitted with the application. The trial burn has been proposed to be performed in 1996 to demonstrate compliance with the current incinerator guidance. This paper describes the experiences and problems associated with WERF's operations, incineration of MLLW, and the RCRA Part B Permit Application. Some of the challenges that have been overcome include waste characterization, waste repackaging, repackaged waste storage, and implementation of RCRA interim status requirements. A number of challenges remain. They include revision of the RCRA Part B Permit Application and the Trial Burn Plan in response to comments from the state permit application reviewers as well as facility and equipment upgrades required to meet RCRA Permitted Status

Low-level radioactive waste management at the Nevada Test Site - Current status

International Nuclear Information System (INIS)

Becker, B.D.; Crowe, B.M.; Gertz, C.P.; Clayton, W.A.

1999-01-01

The performance objectives of the Department of Energy's Low-Level Radioactive Waste (LLW) disposal facilities located at the Nevada Test Site transcend those of any other radioactive waste disposal site in the US. Situated at the southern end of the Great Basin, 800 feet above the water table, the Area 5 Radioactive Waste Management Site (RWMS) has utilized a combination of engineered shallow land disposal cells and deep augured shafts to dispose a variety of waste streams. These include high volume low-activity wastes, classified materials, and high-specific-activity special case wastes. Twenty miles north of Area 5 is the Area 3 RWMS. Here bulk LLW disposal takes place in subsidence craters formed from underground testing of nuclear weapons. Earliest records indicate that documented LLW disposal activities have occurred at the Area 5 and Area 3 RWMS's since 1961 and 1968, respectively. However, these activities have only been managed under a formal program since 1978. This paper describes the technical attributes of the facilities, present and future capacities and capabilities, and provides a description of the process from waste approval to final disposition. The paper also summarizes the current status of the waste disposal operations

Low-level radioactive waste disposal in the USA - Use of mill tailings impoundments as a new policy option

International Nuclear Information System (INIS)

Farrell, C.W.

2006-01-01

Disposal of low-level radioactive waste (LLW) in the United States is facing severe and immediate capacity limitations. Seemingly intractable regulatory and jurisdictional conflicts make establishment of new LLW disposal sites effectively impossible. Uranium mill tailings impoundments constructed at conventional uranium open-cast and underground mines could offer approximately 40 to 80+ million tons of disposal capacity for low activity radioactive waste. Such impoundments would provide an enhanced, high level of environmental and health and safety protection for the direct disposal of depleted uranium, special nuclear material, technologically-enhanced, naturally-occurring radioactive material (TENORM) and mixed waste. Many waste streams, such as TENORM and decommissioning rubble, will be high-volume, low activity materials and ideally suited for disposal in such structures. Materials in a given decay chain with a total activity from all radionuclides present of ∼820 Bq/g (2.22 x 10 -08 Ci/g) with no single radionuclide present in an activity greater than ∼104 Bq/g (2,800 pCi/g) should be acceptable for disposal. Materials of this type could be accepted without any site-specific dose modelling, so long as the total activity of the tailings impoundment not exceed its design capacity (generally 82 x 10 07 Bq/metric tonne) (0.020 Ci/short ton) and the cover design requirements to limit radon releases are satisfied. This paper provides background on US LLW disposal regulations, examines LLW disposal options under active consideration by the US Environmental Protection Agency and Department of Energy, develops generic waste acceptance criteria and identifies policy needs for federal and state governments to facilitate use of uranium mill tailings impoundments for LLW disposal. (author)

Development of new low level radioactive waste disposal sites: A progress report

International Nuclear Information System (INIS)

Anderson, Robert T.; Antonucci, George J.; Ryan, Michael T.

1992-01-01

The status of the development of three new low level radioactive waste disposal facilities for the Central Midwest (Illinois), Southeastern (North Carolina) and Appalachian (Pennsylvania) compacts is presented. These three sites will dispose of about 50-65 percent of the commercial low-level waste (LLW) generated in the U.S. annually. Chem-Nuclear, as developer and proposed operator of all three sites has used a common approach to site development. This approach has been based on their twenty-plus years of operating experience and a standard technical approach. The technology employed is an above-grade, multiple engineered barrier design. The paper also contrasts actual progress at each site with a generalized project schedule. Areas of schedule delays are noted along with the steps being taken to accelerate schedule. Finally, we note that continued progress and timely start-up of operations of these new sites is critical on a national basis. This is due to the possibility of near-term closure of the existing LLW disposal sites. (author)

Commercial low-level radioactive waste management

International Nuclear Information System (INIS)

Coleman, J.A.

1982-01-01

The goals, objectives and activities of the Department of Energy's Low-Level Radioactive Waste Management program are reviewed. The goal of the overall Program is to support development of an acceptable, nationwide, near surface waste disposal system by 1986. The commercial LLW program has two major functions: (1) application of the technology improvements for waste handling, treatment and disposal, and (2) assistance to states as they carry out their responsibilities under the Low-Level Radioactive Waste Policy Act of 1980. The priorities for the commercial side of the Low-Level Waste Management Program have been established to meet one goal: to support development of an effective commercial management system by 1986. The first priority is being given to supporting state efforts in forming the institutional structures needed to manage the system. The second priority is the state and industry role in transferring and demonstrating treatment and disposal technologies

Licensing procedures for Low-Level Waste disposal facilities

Energy Technology Data Exchange (ETDEWEB)

Roop, R.D.; Van Dyke, J.W.

1985-09-01

This report describes the procedures applicable to siting and licensing of disposal facilities for low-level radioactive wastes. Primary emphasis is placed on those procedures which are required by regulations, but to the extent possible, non-mandatory activities which will facilitate siting and licensing are also considered. The report provides an overview of how the procedural and technical requirements for a low-level waste (LLW) disposal facility (as defined by the Nuclear Regulatory Commission's Rules 10 CFR Parts 2, 51, and 61) may be integrated with activities to reduce and resolve conflict generated by the proposed siting of a facility. General procedures are described for site screening and selection, site characterization, site evaluation, and preparation of the license application; specific procedures for several individual states are discussed. The report also examines the steps involved in the formal licensing process, including docketing and initial processing, preparation of an environmental impact statement, technical review, hearings, and decisions. It is concluded that development of effective communication between parties in conflict and the utilization of techniques to manage and resolve conflicts represent perhaps the most significant challenge for the people involved in LLW disposal in the next decade. 18 refs., 6 figs.

Overview of EPA's environmental standards for the land disposal of LLW and NARM waste - 1988

International Nuclear Information System (INIS)

Gruhlke, J.M.; Galpin, F.L.; Holcomb, W.F.

1988-01-01

The Environmental Protection Agency program to develop proposed generally applicable environmental standards for land disposal of low-level radioactive waste (LLW) and certain naturally occurring and accelerator-produced radioactive wastes has been completed. The elements of the proposed standards include the following: (a) exposure limits for predisposal management and storage operations, (b) criteria for other regulatory agencies to follow in specifying wastes that are below regulatory concern; (c) postdisposal exposure limits, (d) groundwater protection requirements, and (e) qualitative implementation requirements. In addition to covering those radioactive wastes subject to the Atomic Energy Act, the Agency also intends to propose a standard to require the disposal of high concentration, naturally occurring and accelerator-produced radioactive materials wastes exceeding 2 nCi/g, excluding a few consumer items, in regulated LLW disposal facilities

Model for analyzing demand for low-level waste transport containers - regionalized and non-regionalized scenarios

International Nuclear Information System (INIS)

Nelson, A.J.; Rose, K.

1982-01-01

Certain types of low-level radioactive waste (LLW) must be shipped in expensive special containers. It is therefore desirable to keep container utilization high. There must be a stock of containers sufficient to ship waste in a timely fashion, but one does not want to have containers sitting idle a significant fraction of the time. A computerized discrete event network model has been developed and is described in this report. The model allows an analyst to determine the effects of varying the increase in LLW, establishment of regional disposal, etc. on requirements for shipping containers

Experience and improved techniques in radiological environmental monitoring at major DOE low-level waste disposal sites

International Nuclear Information System (INIS)

1986-09-01

A summary of routine radiological environmental surveillance programs conducted at major active US Department of Energy (DOE) solid low-level waste (LLW) disposal sites is provided. The DOE disposal sites at which monitoring programs were reviewed include those located at Hanford, Idaho National Engineering Laboratory (INEL), Nevada Test Site (NTS), Los Alamos National Laboratory (LANL), Oak Ridge National Laboratory (ORNL) and Savannah River Plant (SRP). The review is limited to activities conducted for the purpose of monitoring disposal site performance. Areas of environmental monitoring reviewed include air monitoring for particulates and gases, monitoring of surface water runoff, surface water bodies, ground water, monitoring of surface soils and the vadose zone, and monitoring of ambient penetrating radiation. Routine environmental surveillance is conducted at major LLW disposal sites at various levels of effort for specific environmental media. In summary, all sites implement a routine monitoring program for penetrating radiation. Four sites (INEL, NTS, LANL, and SRP) monitor particulates in air specifically at LLW disposal sites. Hanford monitors particulates at LLW sites in conjunction with monitoring of other site operations. Particulates are monitored on a reservationwide network at ORNL. Gases are monitored specifically at active LLW sites operated at NTS, LANL, and SRP. Ground water is monitored specifically at LLW sites at INEL, LANL, and SRP, in conjunction with other operations at Hanford, and as part of a reservationwide program at NTS and ORNL. Surface water is monitored at INEL, LANL, and SRP LLW sites. Surface soil is sampled and analyzed on a routine basis at INEL and LANL. Routine monitoring of the vadose zone is conducted at the INEL and SRP. Techniques and equipment in use are described and other aspects of environmental monitoring programs, such as quality assurance and data base management, are reviewed

Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics. Revision 1

Energy Technology Data Exchange (ETDEWEB)

1994-09-01

The Department of Energy`s (DOE`s) planning for the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of the waste. This report estimates volumes, radionuclide activities, and waste forms of GTCC LLW to the year 2035. It groups the waste into four categories, representative of the type of generator or holder of the waste: Nuclear Utilities, Sealed Sources, DOE-Held, and Other Generator. GTCC LLW includes activated metals (activation hardware from reactor operation and decommissioning), process wastes (i.e., resins, filters, etc.), sealed sources, and other wastes routinely generated by users of radioactive material. Estimates reflect the possible effect that packaging and concentration averaging may have on the total volume of GTCC LLW. Possible GTCC mixed LLW is also addressed. Nuclear utilities will probably generate the largest future volume of GTCC LLW with 65--83% of the total volume. The other generators will generate 17--23% of the waste volume, while GTCC sealed sources are expected to contribute 1--12%. A legal review of DOE`s obligations indicates that the current DOE-Held wastes described in this report will not require management as GTCC LLW because of the contractual circumstances under which they were accepted for storage. This report concludes that the volume of GTCC LLW should not pose a significant management problem from a scientific or technical standpoint. The projected volume is small enough to indicate that a dedicated GTCC LLW disposal facility may not be justified. Instead, co-disposal with other waste types is being considered as an option.

Greater-than-Class C low-level radioactive waste characterization: Estimated volumes, radionuclide activities, and other characteristics. Revision 1

International Nuclear Information System (INIS)

1994-09-01

The Department of Energy's (DOE's) planning for the disposal of greater-than-Class C low-level radioactive waste (GTCC LLW) requires characterization of the waste. This report estimates volumes, radionuclide activities, and waste forms of GTCC LLW to the year 2035. It groups the waste into four categories, representative of the type of generator or holder of the waste: Nuclear Utilities, Sealed Sources, DOE-Held, and Other Generator. GTCC LLW includes activated metals (activation hardware from reactor operation and decommissioning), process wastes (i.e., resins, filters, etc.), sealed sources, and other wastes routinely generated by users of radioactive material. Estimates reflect the possible effect that packaging and concentration averaging may have on the total volume of GTCC LLW. Possible GTCC mixed LLW is also addressed. Nuclear utilities will probably generate the largest future volume of GTCC LLW with 65--83% of the total volume. The other generators will generate 17--23% of the waste volume, while GTCC sealed sources are expected to contribute 1--12%. A legal review of DOE's obligations indicates that the current DOE-Held wastes described in this report will not require management as GTCC LLW because of the contractual circumstances under which they were accepted for storage. This report concludes that the volume of GTCC LLW should not pose a significant management problem from a scientific or technical standpoint. The projected volume is small enough to indicate that a dedicated GTCC LLW disposal facility may not be justified. Instead, co-disposal with other waste types is being considered as an option

Solid low-level waste forecasting guide

International Nuclear Information System (INIS)

Templeton, K.J.; Dirks, L.L.

1995-03-01

Guidance for forecasting solid low-level waste (LLW) on a site-wide basis is described in this document. Forecasting is defined as an approach for collecting information about future waste receipts. The forecasting approach discussed in this document is based solely on hanford's experience within the last six years. Hanford's forecasting technique is not a statistical forecast based upon past receipts. Due to waste generator mission changes, startup of new facilities, and waste generator uncertainties, statistical methods have proven to be inadequate for the site. It is recommended that an approach similar to Hanford's annual forecasting strategy be implemented at each US Department of Energy (DOE) installation to ensure that forecast data are collected in a consistent manner across the DOE complex. Hanford's forecasting strategy consists of a forecast cycle that can take 12 to 30 months to complete. The duration of the cycle depends on the number of LLW generators and staff experience; however, the duration has been reduced with each new cycle. Several uncertainties are associated with collecting data about future waste receipts. Volume, shipping schedule, and characterization data are often reported as estimates with some level of uncertainty. At Hanford, several methods have been implemented to capture the level of uncertainty. Collection of a maximum and minimum volume range has been implemented as well as questionnaires to assess the relative certainty in the requested data

Alternatives generation and analysis report for immobilized low-level waste interim storage architecture

Energy Technology Data Exchange (ETDEWEB)

Burbank, D.A., Westinghouse Hanford

1996-09-01

The Immobilized Low-Level Waste Interim Storage subproject will provide storage capacity for immobilized low-level waste product sold to the U.S. Department of Energy by the privatization contractor. This report describes alternative Immobilized Low-Level Waste storage system architectures, evaluation criteria, and evaluation results to support the Immobilized Low-Level Waste storage system architecture selection decision process.

Preliminary fee methodology for recovering GTCC-LLW management costs

International Nuclear Information System (INIS)

Clark, L.L.

1990-06-01

The US Department of Energy (DOE) is currently planning a fee to recover costs of managing Greater-Than-Class-C Low-Level Waste (GTCC-LLW). A cash flow basis will be used for fee calculations to ensure recovery of all applicable program costs. Positive cash flows are revenues received from waste generators. Negative cash flows are program expenses for storage, transportation, treatment, and disposal of the wastes and for program development, evaluation, and administration. Program balances are the net result of positive and negative cash flows each year. The methodology calculates fees that will recovery all program expenses taking into account cost inflation. 3 refs., 1 tab

Use of a Shielded High Resolution Gamma Spectrometry System to Segregate LLW from Contact Handleable ILW Containing Plutonium - 13046

Energy Technology Data Exchange (ETDEWEB)

Lester, Rosemary; Wilkins, Colin [Canberra UK Ltd, Unit 1 B528.1, Harwell Science Campus, Oxfordshire OX11 0DF (United Kingdom); Chard, Patrick [Canberra UK Ltd, Forss Business and Technology park, Thurso, Caithness KW14 7UZ (United Kingdom); Jaederstroem, Henrik; LeBlanc, Paul; Mowry, Rick [Canberra Industries, Inc., 800 Research Parkway, Meriden, Connecticut, 06450 (United States); MacDonald, Sanders; Gunn, William [Dounreay Site Restoration Limited, Dounreay, Thurso, Caithness, KW14 7TZ (United Kingdom)

2013-07-01

Dounreay Site Restoration Limited (DSRL) have a number of drums of solid waste that may contain Plutonium Contaminated Material. These are currently categorised as Contact Handleable Intermediate Level Waste (CHILW). A significant fraction of these drums potentially contain waste that is in the Low Level Waste (LLW) category. A Canberra Q2 shielded high resolution gamma spectrometry system is being used to quantify the total activity of drums that are potentially in the LLW category in order to segregate those that do contain LLW from CHILW drums and thus to minimise the total volume of waste in the higher category. Am-241 is being used as an indicator of the presence of plutonium in the waste from its strong 59.54 keV gamma-ray; a knowledge of the different waste streams from which the material originates allows a pessimistic waste 'fingerprint' to be used in order to determine an upper limit to the activities of the weak and non-gamma-emitting plutonium and associated radionuclides. This paper describes the main features of the high resolution gamma spectrometry system being used by DSRL to perform the segregation of CHILW and LLW and how it was configured and calibrated using the Canberra In-Situ Object Counting System (ISOCS). It also describes how potential LLW drums are selected for assay and how the system uses the existing waste stream fingerprint information to determine a reliable upper limit for the total activity present in each measured drum. Results from the initial on-site commissioning trials and the first measurements of waste drums using the new monitor are presented. (authors)

Taiwan industrial cooperation program technology transfer for low-level radioactive waste final disposal - phase I.

Energy Technology Data Exchange (ETDEWEB)

Knowlton, Robert G.; Cochran, John Russell; Arnold, Bill Walter; Jow, Hong-Nian; Mattie, Patrick D.; Schelling, Frank Joseph Jr. (; .)

2007-01-01

Sandia National Laboratories and the Institute of Nuclear Energy Research, Taiwan have collaborated in a technology transfer program related to low-level radioactive waste (LLW) disposal in Taiwan. Phase I of this program included regulatory analysis of LLW final disposal, development of LLW disposal performance assessment capabilities, and preliminary performance assessments of two potential disposal sites. Performance objectives were based on regulations in Taiwan and comparisons to those in the United States. Probabilistic performance assessment models were constructed based on limited site data using software including GoldSim, BLT-MS, FEHM, and HELP. These software codes provided the probabilistic framework, container degradation, waste-form leaching, groundwater flow, radionuclide transport, and cover infiltration simulation capabilities in the performance assessment. Preliminary performance assessment analyses were conducted for a near-surface disposal system and a mined cavern disposal system at two representative sites in Taiwan. Results of example calculations indicate peak simulated concentrations to a receptor within a few hundred years of LLW disposal, primarily from highly soluble, non-sorbing radionuclides.

Review of hydrodynamic and transport models and data collected near the mid-Atlantic low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Onishi, Y.; Hibler, L.F.; Sherwood, C.R.

1987-08-01

The objectives of this study were to (1) briefly review and evaluate available simulation models that may be used to predict the distribution of low-level radioactive waste (LLW) from the 2800-m and 3800-m Low Level Radioactive Disposal Sites in the Mid-Atlantic Continental Slope and Rise on a regional (a few hundred kilometers square) scale, (2) identify pertinent physical, biological, and geological oceanographic data in or near those LLW disposal sites, and (3) determine minimum data requirements for regional modeling. With suitable model modifications such as turbulence closure, enhanced sediment transport, radionuclide transport, and/or curvilinear coordinate system setup, the FLESCOT model, the FLOWER model, and Blumberg's model would be appropriate candidates for regional radionuclide modeling to predict the transport and dispersion of LLW disposed in the 2800-m and 3800-m sites. Although the RMA10 model does not incorporate a turbulence closure scheme, this model, with some modifications, is also an appropriate candidate for regional radionuclide modeling. FLESCOT is currently the only one that solves distributions of flow, turbulence, salinity, water temperature, sediments, dissolved contaminants, and sediment-sorbed contaminants. Thus, the FLESCOT model is recommended to be applied to the 2800-m and 3800-m sites to predict the transport and accumulation of LLW on a regional scale

Idaho Chemical Processing Plant low-level waste grout stabilization development program FY-96 status report

International Nuclear Information System (INIS)

Herbst, A.K.

1996-09-01

The general purpose of the Grout Stabilization Development Program is to solidify and stabilize the liquid low-level wastes (LLW) generated at the Idaho Chemical Processing Plant (ICPP). It is anticipated that LLW will be produced from the following: (1) chemical separation of the tank farm high-activity sodium-bearing waste; (2) retrieval, dissolution, and chemical separation of the aluminum, zirconium, and sodium calcines; (3) facility decontamination processes; and (4) process equipment waste. The main tasks completed this fiscal year as part of the program were chromium stabilization study for sodium-bearing waste and stabilization and solidification of LLW from aluminum and zirconium calcines. The projected LLW will be highly acidic and contain high amounts of nitrates. Both of these are detrimental to Portland cement chemistry; thus, methods to precondition the LLW and to cure the grout were explored. A thermal calcination process, called denitration, was developed to solidify the waste and destroy the nitrates. A three-way blend of Portland cement, blast furnace slag, and fly ash was successfully tested. Grout cubes were prepared at various waste loadings to maximize loading while meeting compressive strength and leach resistance requirements. For the sodium LLW, a 25% waste loading achieves a volume reduction of 3.5 and a compressive strength of 2,500 pounds per square inch while meeting leach, mix, and flow requirements. It was found that the sulfur in the slag reduces the chromium leach rate below regulatory limits. For the aluminum LLW, a 15% waste loading achieves a volume reduction of 8.5 and a compressive strength of 4,350 pounds per square inch while meeting leach requirements. Likewise for zirconium LLW, a 30% waste loading achieves a volume reduction of 8.3 and a compressive strength of 3,570 pounds per square inch

Planning and consultation procedures for low-level radioactive waste disposal

International Nuclear Information System (INIS)

Kemp, R.

1989-03-01

This Report is the result of a year-long study funded by UK Nirex Ltd. between 1986 and 1987. The central purpose was to learn from overseas experience of planning and public consultation procedures associated with the establishment of low-level radioactive waste (LLW) disposal sites. The most recent information on LLW developments in the United States, Canada, France, Holland, Switzerland, Sweden, and West Germany was sought, particularly in regard to: (1) the efficacy of public consultation and negotiation procedures, focusing in particular on the perceived problems, successes and areas for improvement; (2) the key aspects bearing on the public acceptability of LLW proposals; and (3) the form and effect of any compensation mechanisms in operation. The greatest success overseas appears to be linked to some combination of the following elements: authority and clarity in the exposition of the direction of radioactive waste management policy, backed up by authoritative and independent analysis; the early involvement of local authority (county council/regional authority) organisations in the site selection process; careful attention to the potential contribution of authoritative independent advisory groups on both technical and procedural/site selection matters; the development and nurturing of local liaison committees to establish good communications at the local level; careful consideration of means of devolving some power to local authority level for safety reassurance, for example, in relation to site inspections and safety monitoring; the development of an incremental, openly negotiated approach to compensation. (author)

Identifying industrial best practices for the waste minimization of low-level radioactive materials

Energy Technology Data Exchange (ETDEWEB)

Levin, V.

1996-04-01

In US DOE, changing circumstances are affecting the management and disposal of solid, low-level radioactive waste (LLW). From 1977 to 1991, the nuclear power industry achieved major reductions in solid waste disposal, and DOE is interested in applying those practices to reduce solid waste at DOE facilities. Project focus was to identify and document commercial nuclear industry best practices for radiological control programs supporting routine operations, outages, and decontamination and decommissioning activities. The project team (DOE facility and nuclear power industry representatives) defined a Work Control Process Model, collected nuclear power industry Best Practices, and made recommendations to minimize LLW at DOE facilities.

Segregation practices in the management of low-level radioactive wastes

International Nuclear Information System (INIS)

Clark, D.E.; Colombo, P.

1981-10-01

A scoping study has been undertaken to determine the state-of-the-art of waste segregation technology as applied to the management of low-level waste (LLW). Present-day waste segregation practices were surveyed through a review of the recent literature and by means of personal interviews with personnel at selected facilities. Among the nuclear establishments surveyed were Department of Energy (DOE) laboratories and plants, nuclear fuel cycle plants, public and private laboratories, institutions, industrial plants, and DOE and commercially operated shallow land burial sites. These survey data were used to analyze the relationship between waste segregation practices and waste treatment/disposal processes, to assess the developmental needs for improved segregation technology, and to evaluate the costs and benefits associated with the implementation of waste segregation controls. For improved processing and disposal of LLW, it is recommended that waste segregation be practiced wherever it is technically feasible and cost-effective to do so. It is noted that LLW management practices are now undergoing rapid change such that the technology and requirements for waste segregation in the near future may differ significantly from those of the present day

Microbial degradation of low-level radioactive waste. Volume 2, Annual report for FY 1994

International Nuclear Information System (INIS)

Rogers, R.D.; Hamilton, M.A.; Veeh, R.H.; McConnell, J.W. Jr.

1995-08-01

The Nuclear Regulatory Commission stipulates in 10 CFR 61 that disposed low-level radioactive waste (LLW) be stabilized. To provide guidance to disposal vendors and nuclear station waste generators for implementing those requirements, the NRC developed the Technical Position on Waste Form, Revision 1. That document details a specified set of recommended testing procedures and criteria, including several tests for determining the biodegradation properties of waste forms. Cement has been widely used to solidify LLW; however, the resulting waste forms are sometimes susceptible to failure due to the actions of waste constituents, stress, and environment. The purpose of this research program is to develop modified microbial degradation test procedures that will be more appropriate than the existing procedures for evaluating the effects of microbiologically influenced chemical attack on cement-solidified LLW. Groups of microorganisms indigenous to LLW disposal sites are being employed that can metabolically convert organic and inorganic substrates into organic and mineral acids. Such acids aggressively react with cement and can ultimately lead to structural failure. Results over the past year on the application of mechanisms inherent in microbially influenced degradation of cement-based material are the focus of the annual report. Data-validated evidence of the potential for microbially influenced deterioration of cement-solidified LLW and subsequent release of radionuclides has been developed during this study

Certification Plan, low-level waste Hazardous Waste Handling Facility

International Nuclear Information System (INIS)

Albert, R.

1992-01-01

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan also incorporates the applicable elements of waste reduction, which include both up-front minimization and end-product treatment to reduce the volume and toxicity of the waste; segregation of the waste as it applies to certification; an executive summary of the Waste Management Quality Assurance Implementing Management Plan (QAIMP) for the HWHF and a list of the current and planned implementing procedures used in waste certification. This plan provides guidance from the HWHF to waste generators, waste handlers, and the Waste Certification Specialist to enable them to conduct their activities and carry out their responsibilities in a manner that complies with the requirements of WHC-WAC. Waste generators have the primary responsibility for the proper characterization of LLW. The Waste Certification Specialist verifies and certifies that LBL LLW is characterized, handled, and shipped in accordance with the requirements of WHC-WAC. Certification is the governing process in which LBL personnel conduct their waste generating and waste handling activities in such a manner that the Waste Certification Specialist can verify that the requirements of WHC-WAC are met

GTS Duratek, Phase I Hanford low-level waste melter tests: 100-kg melter offgas report

International Nuclear Information System (INIS)

Eaton, W.C.

1995-11-01

A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense wastes stored in underground tanks at the Hanford Site in southeastern Washington State. Phase 1 of the melter demonstration tests using simulated LLW was completed during fiscal year 1995. This document is the 100-kg melter offgas report on testing performed by GTS Duratek, Inc., in Columbia, Maryland. GTS Duratek (one of the seven vendors selected) was chosen to demonstrate Joule heated melter technology under WHC subcontract number MMI-SVV-384215. The document contains the complete offgas report on the 100-kg melter as prepared by Parsons Engineering Science, Inc. A summary of this report is also contained in the GTS Duratek, Phase I Hanford Low-Level Waste Melter Tests: Final Report (WHC-SD-WM-VI-027)

Final environmental assessment for off-site transportation of low-level waste from four California sites under the management of the U.S. Department of Energy Oakland Operations Office

International Nuclear Information System (INIS)

1997-10-01

The Department of Energy Oakland Operations Office (DOE/OAK) manages sites within California that generate Low Level Waste (LLW) in the course or routine site operations. It is the preference of the DOE to dispose of LLW at federally owned and DOE-operated disposal facilities; however, in some circumstances DOE Headquarters has determined that disposal at commercial facilities is appropriate, as long as the facility meets all regulatory requirements for the acceptance and disposal of LLW, including the passage of a DOE audit to determine the adequacy of the disposal site. The DOE would like to ship LLW from four DOE/OAK sites in California which generate LLW, to NRC-licensed commercial nuclear waste disposal facilities such as Envirocare in Clive, Utah and Chem Nuclear in Barnwell, South Carolina. Transportation impacts for shipment of LLW and MLLW from DOE Oakland sites to other DOE sites was included in the impacts identified in the Department's Waste Management Programmatic Environmental Impact Statement (WM-PEIS), published in May, 1997, and determined to be low. The low impacts for shipment to commercial sites identified herein is consistent with the WM-PEIS results

Feasibility study on equipment of LLW management business system

International Nuclear Information System (INIS)

Shimizu, Takafumi

2010-01-01

LLW from university and private company has been kept in their own nuclear facilities in Japan. RANDEC has been studying business system for the treatment and conditioning of LLW before disposal. Reference to proven waste treatment process used in Nuclear Power Plant, it was studied that the appropriate treatment process for the LLW from university and private company. The waste will be collected from the university and private company to a central treatment facility. After operations such as unpacking, classification, compression, incineration and others, the waste will be treated to waste form. Most equipment are adopted by the process technology used in Nuclear Power Plant. But some equipment such as measurement of radio activity and solidification of powder need to be studied for the treatment of LLW from university and private company. (author)

Evaluation of Department of Energy-held potential Greater-Than-Class C Low-Level Radioactive Waste

International Nuclear Information System (INIS)

1992-03-01

A number of commercial facilities have generated potential Greater-Than-Class C Low-Level Radioactive Waste (GTCC LLW), and through contractual arrangements with the US Department of Energy (DOE) and/or for health and safety reasons, the waste is being stored by DOE. A determination is required, considering specific circumstances under which DOE accepted the waste, whether disposal is a US Nuclear Regulatory Commission-licensed facility or by DOE in a nonlicensed facility is appropriate. This report presents the preliminary results of an assessment conducted by EG ampersand G Idaho, Inc. legal counsel and GTCC LLW Program staff

Development of an accelerated leach test(s) for low-level waste forms

International Nuclear Information System (INIS)

Dougherty, D.R.; Fuhrmann, M.; Colombo, P.

1985-01-01

An accelerated leach test(s) is being developed to predict long-term leaching behavior of low-level radioactive waste (LLW) forms in their disposal environments. As necessary background, a literature survey of reported leaching mechanisms, available mathematical models and factors that affect leaching of LLW forms has been compiled. Mechanisms which have been identified include diffusion, dissolution, ion exchange, corrosion and surface effects. A computerized data base of LLW leaching data and mathematical models is being developed. The data is being used for model evaluation by curve fitting and statistical analysis according to standard procedures of statistical quality control. Long-term leach tests on portland cement, bitumen and vinyl ester-styrene (VES) polymer waste forms are underway which are designed to identify and evaluate factors that accelerate leaching without changing the mechanisms. Initial results on the effect of temperature on leachability indicate that the leach rates of cement and VES waste forms increase with increasing temperature, whereas, the leach rate of bitumen is little affected. 10 refs., 5 figs

LLW disposal wasteform preparation in the UK: the role of high force compaction

Energy Technology Data Exchange (ETDEWEB)

Johnson, L. F.; Fearnley, I. G. [British Nuclear Fuels Ltd., Sellafield (United Kingdom)

1991-07-01

British Nuclear Fuels plc (BNFL) owns and operates the principal UK solid low level radioactive waste (LLW) disposal site. The site is located at Drigg in West Cumbria some 6 km to the south east of BNFL's Sellafield reprocessing complex. Sellafield is the major UK generator of LLW, accounting for about 85% of estimated future arisings of raw (untreated, unpackaged) waste. Non-Sellafield consignors to the Drigg site include other BNFL production establishments, nuclear power stations, sites of UKAEA, Ministry of Defence facilities, hospitals, universities, radioisotope production sites and various other industrial organisations. In September 1987, BNFL announced a major upgrade of operations at the Drigg site aimed at improving management practices, the efficiency of space utilisation and enhancing the visual impact of disposal operations. During 1989 a review of plans for compaction and containerisation of Sellafield waste identified that residual voidage in ISO freight containers could be significant even after the introduction of compaction. Subsequent studies which examined a range of compaction and packaging options concluded that the preferred scheme centred on the use of high force compaction (HFC) of compactable waste, and grouting to take up readily accessible voidage in the wasteform. The paper describes the emergence of high force compaction as the preferred scheme for wasteform preparation and subsequent benefits against the background of the overall development of Low Level Waste disposal operations at Drigg.

LLW disposal wasteform preparation in the UK: the role of high force compaction

International Nuclear Information System (INIS)

Johnson, L. F.; Fearnley, I. G.

1991-01-01

British Nuclear Fuels plc (BNFL) owns and operates the principal UK solid low level radioactive waste (LLW) disposal site. The site is located at Drigg in West Cumbria some 6 km to the south east of BNFL's Sellafield reprocessing complex. Sellafield is the major UK generator of LLW, accounting for about 85% of estimated future arisings of raw (untreated, unpackaged) waste. Non-Sellafield consignors to the Drigg site include other BNFL production establishments, nuclear power stations, sites of UKAEA, Ministry of Defence facilities, hospitals, universities, radioisotope production sites and various other industrial organisations. In September 1987, BNFL announced a major upgrade of operations at the Drigg site aimed at improving management practices, the efficiency of space utilisation and enhancing the visual impact of disposal operations. During 1989 a review of plans for compaction and containerisation of Sellafield waste identified that residual voidage in ISO freight containers could be significant even after the introduction of compaction. Subsequent studies which examined a range of compaction and packaging options concluded that the preferred scheme centred on the use of high force compaction (HFC) of compactable waste, and grouting to take up readily accessible voidage in the wasteform. The paper describes the emergence of high force compaction as the preferred scheme for wasteform preparation and subsequent benefits against the background of the overall development of Low Level Waste disposal operations at Drigg

The solidification of low level radioactive organic fluids with Envirostone Gypsum Cement

International Nuclear Information System (INIS)

Rosenstiel, T.L.; Lange, R.G.

1984-01-01

The primary method for the management of low level radioactive waste (LLW) has been and continues to be the isolation of the waste in a solid mass. Of the four typical LLW streams, organic fluids pose the most significant waste isolation problem. The organic fluids comprised of lubrication oils, hydraulic fluids, sludges, scintillation fluids, etc., result from the operation and maintenance of nuclear power generating stations, research activities, tooling operations, and diagnostic analyses. The United States Gypsum Company developed the patented Envirostone Gypsum Cement system for the solidification of all types of low level radioactive wastes to facilitate handling and transportation to regulated LLW disposal sites. For the solidification of organic fluids, Envirostone Gypsum Cement is used in conjunction with Envirostone Emulsifier, selected for its ability to emulsify a broad range of organic fluids in aqueous solutions. In the solidification process it is theorized that as the crystalline matrix of the gypsum forms, the micelles of the emulsifier behave as a chemical bridge which draws the organic fluid into the crystalline structure via the hydration water. Initial testing of physical properties of solidified waste forms, including leachability, per the requirements and the procedures specified for 10 CFR Part 61 as outlined in the Branch Technical Position Report from the United States Nuclear Regulatory Commission were in progress as of the writing of this paper. Upon completion of this testing a Topical Report will be submitted to the USNRC for review and approval. The presentation reviews field experience in the use of Envirostone Gypsum Cement for the solidification of low level radioactive organic fluids from nuclear power generating stations and makes an economic comparison between Envirostone Gypsum Cement and portland cement systems

Rokkasho low-level radioactive waste disposal in Japan

International Nuclear Information System (INIS)

Takahashi, Y.

1994-01-01

Japan Nuclear Fuel Limited commenced the operation of the shallow land disposal of low-level radioactive waste from reactor operation, in 1992 at Rokkasho site in Aomori Prefecture. JNFL is private company whose main activities within the responsibility of JNFL are: 1) Disposal of low-level radioactive waste, 2) Uranium enrichment, 3) Reprocessing of spent nuclear fuels, 4) Temporary storage of returned wastes from COGEMA and BNFL by reprocessing contracts, prior to disposal. JNFL selected the site for the disposal of LLW at Rokkasho in Aomori Prefecture, then bought land of 3.4 million m 2 . Among waste spectrum, LLWs from nuclear power plants, from uranium enrichment and from reprocessing are to be managed by JNFL, including dismantling of these facilities, and JNFL has plan to dispose about 600 thousand m 3 of wastes ultimately. On the middle of November 1990 JNFL got the permission of the application for 40 thousand m 3 (equivalent to 200,000 drums each with a 200-liter capacity) of reactor operating wastes which is solidified with cement, bitumen or plastics as a first stage. And after the construction work for about 2 years, the operations started at Dec. 8th, 1992. The Disposal center has already accepted about 24,000 LLW drums as of the end of February, 1994. (author)

Analysis of low-level wastes. Review of hazardous waste regulations and identification of radioactive mixed wastes. Final report

International Nuclear Information System (INIS)

Bowerman, B.S.; Kempf, C.R.; MacKenzie, D.R.; Siskind, B.; Piciulo, P.L.

1985-12-01

Regulations governing the management and disposal of hazardous wastes have been promulgated by the US Environmental Protection Agency under authority of the Resource Conservation and Recovery Act. These were reviewed and compared with the available information on the properties and characteristics of low-level radioactive wastes (LLW). In addition, a survey was carried out to establish a data base on the nature and composition of LLW in order to determine whether some LLW streams could also be considered hazardous as defined in 40 CFR Part 261. For the survey, an attempt was made to obtain data on the greatest volume of LLW; hence, as many large LLW generators as possible were contacted. The list of 238 generators contacted was based on information obtained from NRC and other sources. The data base was compiled from completed questionnaires which were returned by 97 reactor and non-reactor facilities. The waste volumes reported by these respondents corresponded to approximately 29% of all LLW disposed of in 1984. The analysis of the survey results indicated that three broad categories of LLW may be radioactive mixed wastes. They include: waste containing organic liquids, disposed of by all types of generators; wastes containing lead metal, i.e., discarded shielding or lead containers; wastes containing chromates, i.e., nuclear power plant process wastes where chromates are used as corrosion inhibitors. Certain wastes, specific to particular generators, were identified as potential mixed wastes as well. 8 figs., 48 tabs

Health physics challenges during decontamination for safe disposal of low level liquid effluent tank as inactive scrap

International Nuclear Information System (INIS)

Akila, R.; Sultan, Bajeer; Sarangapani, R.; Jose, M.T.

2018-01-01

The Low-level Liquid waste (LLW) generated during the regeneration of mixed bed column of KAMINI reactor is collected in the SS Delay Tanks located on the western side of RML building. It was proposed to dismantle and dispose the tank as solid waste. The tank weighs about 2 ton. An attempt was made to decontaminate the tank to levels below the exempt quantity so as to qualify it as scrap of unrestricted release. This is first time in IGCAR wherein a material used in a radioactive facility for storing LLW is being released as scrap of unrestricted release and this paper discusses about the same

Innovative Disposal Practices at the Nevada Test Site to Meet Its Low-Level Waste Generators' Future Disposal Needs

International Nuclear Information System (INIS)

Di Sanza, E.F.; Carilli, J.T.

2006-01-01

Low-level radioactive waste (LLW) streams which have a clear, defined pathway to disposal are becoming less common as U.S. Department of Energy accelerated cleanup sites enters their closure phase. These commonly disposed LLW waste streams are rapidly being disposed and the LLW inventory awaiting disposal is dwindling. However, more complex waste streams that have no path for disposal are now requiring attention. The U.S. Department of Energy (DOE) National Nuclear Security Administration Nevada Site Office (NSO) Environmental Management Program is charged with the responsibility of carrying out the disposal of onsite and off-site defense-generated and research-related LLW at the Nevada. Test Site (NTS). The NSO and its generator community are constantly pursuing new LLW disposal techniques while meeting the core mission of safe and cost-effective disposal that protects the worker, the public and the environment. From trenches to present-day super-cells, the NTS disposal techniques must change to meet the LLW generator's disposal needs. One of the many ways the NTS is addressing complex waste streams is by designing waste specific pits and trenches. This ensures unusual waste streams with high-activity or large packaging have a disposal path. Another option the NTS offers is disposal of classified low-level radioactive-contaminated material. In order to perform this function, the NTS has a safety plan in place as well as a secure facility. By doing this, the NTS can accept DOE generated classified low-level radioactive-contaminated material that would be equivalent to U.S. Nuclear Regulatory Commission Class B, C, and Greater than Class C waste. In fiscal year 2006, the NTS will be the only federal disposal facility that will be able to dispose mixed low-level radioactive waste (MLLW) streams. This is an activity that is highly anticipated by waste generators. In order for the NTS to accept MLLW, generators will have to meet the stringent requirements of the NTS

T-Rex system for operation in TRU, LLW, and hazardous zones

International Nuclear Information System (INIS)

Kline, H.M.; Andreychek, T.P.; Beeson, B.K.

1993-01-01

There are a large number of sites around the world containing TRU (transuranic) waste, low level waste (LLW), and hazardous areas that require teleoperated, heavy lift manipulators with long reach and high precision to handle the materials stored there. Teleoperation of the equipment is required to reduce the risk to operating personnel to as-low-as-reasonably-achievable (ALARA) levels. The Transuranic Storage Area Remote Excavator system (T-Rex) is designed to fill this requirement at low cost through the integration of a production front shovel excavator with a control system, local and remote operator control stations, a closed-circuit television system (CCTV), multiple end effectors and a quick-change system. This paper describes the conversion of an off-the-shelf excavator with a hydraulic control system, the integration of an onboard remote control system, vision system, and the design of a remote control station

Low-level radioactive waste performance assessments: Source term modeling

International Nuclear Information System (INIS)

Icenhour, A.S.; Godbee, H.W.; Miller, L.F.

1995-01-01

Low-level radioactive wastes (LLW) generated by government and commercial operations need to be isolated from the environment for at least 300 to 500 yr. Most existing sites for the storage or disposal of LLW employ the shallow-land burial approach. However, the U.S. Department of Energy currently emphasizes the use of engineered systems (e.g., packaging, concrete and metal barriers, and water collection systems). Future commercial LLW disposal sites may include such systems to mitigate radionuclide transport through the biosphere. Performance assessments must be conducted for LUW disposal facilities. These studies include comprehensive evaluations of radionuclide migration from the waste package, through the vadose zone, and within the water table. Atmospheric transport mechanisms are also studied. Figure I illustrates the performance assessment process. Estimates of the release of radionuclides from the waste packages (i.e., source terms) are used for subsequent hydrogeologic calculations required by a performance assessment. Computer models are typically used to describe the complex interactions of water with LLW and to determine the transport of radionuclides. Several commonly used computer programs for evaluating source terms include GWSCREEN, BLT (Breach-Leach-Transport), DUST (Disposal Unit Source Term), BARRIER (Ref. 5), as well as SOURCE1 and SOURCE2 (which are used in this study). The SOURCE1 and SOURCE2 codes were prepared by Rogers and Associates Engineering Corporation for the Oak Ridge National Laboratory (ORNL). SOURCE1 is designed for tumulus-type facilities, and SOURCE2 is tailored for silo, well-in-silo, and trench-type disposal facilities. This paper focuses on the source term for ORNL disposal facilities, and it describes improved computational methods for determining radionuclide transport from waste packages

Evaluation of low-level radioactive waste characterization and classification programs of the West Valley Demonstration Project

International Nuclear Information System (INIS)

Taie, K.R.

1994-01-01

The West Valley Demonstration Project (WVDP) is preparing to upgrade their low-level radioactive waste (LLW) characterization and classification program. This thesis describes a survey study of three other DOE sites conducted in support of this effort. The LLW characterization/classification programs of Oak Ridge National Laboratory, Savannah River Site, and Idaho National Engineering Laboratory were critically evaluated. The evaluation was accomplished through tours of each site facility and personnel interviews. Comparative evaluation of the individual characterization/classification programs suggests the WVDP should purchase a real-time radiography unit and a passive/active neutron detection system, make additional mechanical modifications to the segmented gamma spectroscopy assay system, provide a separate building to house characterization equipment and perform assays away from waste storage, develop and document a new LLW characterization/classification methodology, and make use of the supercompactor owned by WVDP

Modeling the economics of LLW volume reduction

International Nuclear Information System (INIS)

Voth, M.H.; Witzig, W.F.

1986-01-01

Generators of low-level (radioactive) waste (LLW) are under pressure to implement volume reduction (VR) programs for political and economic reasons. Political reasons include the appearance of generating less waste or meeting quotas. Economic reasons include avoiding high disposal costs and associated surcharges. Volume reduction results in less total volume over which fixed disposal costs are allocated and therefore higher unit costs for disposal. As numerous small compacts are developed, this often overlooked effect becomes more pronounced. The described model presents two unique significant features. First, a feedback loop considers the impact of VR on disposal rates, and second, it appeals to logic without extensive knowledge of VR technology or computer modeling. The latter feature is especially useful in conveying information to students and nontechnical decision makers, demonstrating the impact of each of a complicated set of variables with reproducible results

Low-level waste certification plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility. Revision 1

International Nuclear Information System (INIS)

1995-01-01

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan is composed to meet the requirements found in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and follows the suggested outline provided by WHC in the letter of April 26, 1990, to Dr. R.H. Thomas, Occupational Health Division, LBL. LLW is to be transferred to the WHC Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington

Low-level waste certification plan for the Lawrence Berkeley Laboratory Hazardous Waste Handling Facility. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-10

The purpose of this plan is to describe the organization and methodology for the certification of low-level radioactive waste (LLW) handled in the Hazardous Waste Handling Facility (HWHF) at Lawrence Berkeley Laboratory (LBL). This plan is composed to meet the requirements found in the Westinghouse Hanford Company (WHC) Solid Waste Acceptance Criteria (WAC) and follows the suggested outline provided by WHC in the letter of April 26, 1990, to Dr. R.H. Thomas, Occupational Health Division, LBL. LLW is to be transferred to the WHC Hanford Site Central Waste Complex and Burial Grounds in Hanford, Washington.

The development of gate monitor for low level radioactive waste

International Nuclear Information System (INIS)

Fujisawa, Morio; Watanabe, Michito; Kato, Tatsuo

1994-01-01

Low-level radioactive waste (LLW) generated from nuclear power plants in Japan, have been deposited in the yard of each power plant. At present, it is stored in about 500,000 drum cans (200l each). These drum cans are carried to Mutsu-ogawara Port by special transport ships and then transferred to Rokkasho LLW transport trucks (special vehicles) for storage. The gate monitor is used to automatically measure the dose rate on the vehicles loaded with transport vessels from a remote location, to ensure the safe transportation from Mutsu-ogawara Port the Burying Center. It is a new system which has been developed for effective measurement of dose rate on a number of transport vessels in a short time. This system is the first in the world for measuring dose rate on vehicles. Such a system cannot be found in any country of the world. (author)

Performance assessment for the disposal of low-level waste in the 200 West Area Burial Grounds

Energy Technology Data Exchange (ETDEWEB)

Wood, M.I.; Khaleel, R.; Rittmann, P.D.; Lu, A.H.; Finfrock, S.H.; DeLorenzo, T.H. [Westinghouse Hanford Co., Richland, WA (United States); Serne, R.J.; Cantrell, K.J. [Pacific Northwest Lab., Richland, WA (United States)

1995-06-01

This document reports the findings of a performance assessment (PA) analysis for the disposal of solid low-level radioactive waste (LLW) in the 200 West Area Low-Level Waste Burial Grounds (LLBG) in the northwest corner of the 200 West Area of the Hanford Site. This PA analysis is required by US Department of Energy (DOE) Order 5820.2A (DOE 1988a) to demonstrate that a given disposal practice is in compliance with a set of performance objectives quantified in the order. These performance objectives are applicable to the disposal of DOE-generated LLW at any DOE-operated site after the finalization of the order in September 1988. At the Hanford Site, DOE, Richland Operations Office (RL) has issued a site-specific supplement to DOE Order 5820.2A, DOE-RL 5820.2A (DOE 1993), which provides additiona I ce objectives that must be satisfied.

Performance assessment for the disposal of low-level waste in the 200 West Area Burial Grounds

International Nuclear Information System (INIS)

Wood, M.I.; Khaleel, R.; Rittmann, P.D.; Lu, A.H.; Finfrock, S.H.; DeLorenzo, T.H.; Serne, R.J.; Cantrell, K.J.

1995-06-01

This document reports the findings of a performance assessment (PA) analysis for the disposal of solid low-level radioactive waste (LLW) in the 200 West Area Low-Level Waste Burial Grounds (LLBG) in the northwest corner of the 200 West Area of the Hanford Site. This PA analysis is required by US Department of Energy (DOE) Order 5820.2A (DOE 1988a) to demonstrate that a given disposal practice is in compliance with a set of performance objectives quantified in the order. These performance objectives are applicable to the disposal of DOE-generated LLW at any DOE-operated site after the finalization of the order in September 1988. At the Hanford Site, DOE, Richland Operations Office (RL) has issued a site-specific supplement to DOE Order 5820.2A, DOE-RL 5820.2A (DOE 1993), which provides additiona I ce objectives that must be satisfied

U.S. Bureau of Mines, Phase 1 Hanford low-level waste melter tests. Final report

International Nuclear Information System (INIS)

Eaton, W.C.; Oden, L.L.; O'Connor, W.K.

1995-11-01

A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense wastes stored in underground tanks at the Hanford Site in southeastern Washington State. Phase 1 of the melter demonstration tests using simulated LLW was completed during fiscal year 1995. This document is the melter offgas report on testing performed by the U.S. Department of the Interior, Bureau of Mines, Albany Research Center in Albany, Oregon. The Bureau of Mines (one of the seven vendors selected) was chosen to demonstrate carbon electrode melter technology (also called carbon arc or electric arc) under WHC Subcontract number MMI-SVV-384216. The report contains description of the tests, observation, test data and some analysis of the data as it pertains to application of this technology for LLW vitrification. Testing consisted of melter feed preparation and three melter tests, the first of which was to fulfill the requirements of the statement of work (WHC-SD-EM-RD-044), and the second and third were to address issues identified during the first test. The document also contains summaries of the melter offgas report issued as a separate document U.S. Bureau of Mines, Phase 1 Hanford Low-Level Waste Melter Tests: Melter Offgas Report (WHC-SD-WM-VI-032)

U.S. Bureau of Mines, Phase 1 Hanford low-level waste melter tests. Final report

Energy Technology Data Exchange (ETDEWEB)

Eaton, W.C. [Westinghouse Hanford Co., Richland, WA (United States); Oden, L.L.; O`Connor, W.K. [Bureau of Mines, Albany, OR (United States). Albany Research Center

1995-11-01

A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense wastes stored in underground tanks at the Hanford Site in southeastern Washington State. Phase 1 of the melter demonstration tests using simulated LLW was completed during fiscal year 1995. This document is the melter offgas report on testing performed by the U.S. Department of the Interior, Bureau of Mines, Albany Research Center in Albany, Oregon. The Bureau of Mines (one of the seven vendors selected) was chosen to demonstrate carbon electrode melter technology (also called carbon arc or electric arc) under WHC Subcontract number MMI-SVV-384216. The report contains description of the tests, observation, test data and some analysis of the data as it pertains to application of this technology for LLW vitrification. Testing consisted of melter feed preparation and three melter tests, the first of which was to fulfill the requirements of the statement of work (WHC-SD-EM-RD-044), and the second and third were to address issues identified during the first test. The document also contains summaries of the melter offgas report issued as a separate document U.S. Bureau of Mines, Phase 1 Hanford Low-Level Waste Melter Tests: Melter Offgas Report (WHC-SD-WM-VI-032).

Control and tracking arrangements for solid low-level waste disposals to the UK Drigg disposal site

International Nuclear Information System (INIS)

Elgie, K.G.; Grimwood, P.D.

1993-01-01

The Drigg disposal site has been the principal disposal site for solid low-level radioactive wastes (LLW) in the United Kingdom since 1959. It is situated on the Cumbrian coast, some six kilometers to the south of the Sellafield nuclear reprocessing site. The Drigg site receives LLW from a wide range of sources including nuclear power generation, nuclear fuel cycle activities, defense activities, isotope manufacture, universities, hospitals, general industry and clean-up of contaminated sites. This LLW has been disposed of in a series of trenches cut into the underlying clay layer of the site, and, since 1988, also into concrete lined vault. The total volume of LLW disposed of at Drigg is at present in the order of 800,000m 3 , with disposals currently approximately 25,000m 3 per year. British Nuclear Fuels plc (BNFL) owns and operates the Drigg disposal site. To meet operational and regulatory requirements, BNFL needs to ensure the acceptability of the disposed waste and be able to track it from its arising point to its specific disposal location. This paper describes the system that has been developed to meet these requirements

An innovative approach to solid Low Level Radioactive Waste processing and disposal

International Nuclear Information System (INIS)

Pancake, D.C. Jr.; Sodaro, M.A.

1994-01-01

This paper will focus on a new system of Low Level Radioactive Waste (LLW) accumulation, processing and packaging, as-well as the implementation of a Laboratory-wide training program used to introduce new waste accumulation containers to all of the on-site radioactive waste generators, and to train them on the requirements of this innovative waste characterization and documentation program

Design/installation and structural integrity assessment under the Federal Facility Agreement for Bethel Valley Low-Level Waste Collection and Transfer System upgrade for Building 2026 (High Radiation Level Analytical Laboratory) and Building 2099 (Monitoring and Control Station) at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

1994-10-01

This document presents a Design/Installation and Structural Integrity Assessment for a replacement tank system for portions of the Bethel Valley Low Level Waste (LLW) System, located at the Oak Ridge Reservation, Oak Ridge, Tennessee. This issue of the assessment covers the design aspects of the replacement tank system, and certifies that the design has sufficient structural integrity and is acceptable for the storing or treating of hazardous and/or radioactive substances. The present issue identifies specific activities that must be completed during the fabrication, installation, and testing of the replacement tank system in order to provide assurance that the final installation complies with governing requirements. Portions of the LLW system are several decades old, or older, and do not comply with current environmental protection regulations. Several subsystems of the LLW system have been designated to receive a state-of-the-art replacement and refurbishment. One such subsystem serves Building 2026, the High Radiation Level Analytical Laboratory. This assessment focuses on the scope of work for the Building 2026 replacement LLW Collection and Transfer System, including the provision of a new Monitoring and Control Station (Building 2099) to receive, store, and treat (adjust pH) low level radioactive waste

Low-level radioactive waste management handbook series: Low-level radioactive waste management in medical and biomedical research institutions

International Nuclear Information System (INIS)

1987-03-01

Development of this handbook began in 1982 at the request of the Radhealth Branch of the California Department of Health Services. California Assembly Bill 1513 directed the DHS to ''evaluate the technical and economic feasibility of (1) reducing the volume, reactivity, and chemical and radioactive hazard of (low-level radioactive) waste and (2) substituting nonradioactive or short-lived radioactive materials for those radionuclides which require long-term isolation from the environment. A contract awarded to the University of California at Irvine-UCI (California Std. Agreement 79902), to develop a document focusing on methods for decreasing low-level radioactive waste (LLW) generation in institutions was a result of that directive. In early 1985, the US Department of Energy, through EG and G Idaho, Inc., contracted with UCI to expand, update, and revise the California text for national release

Waste minimization for commercial radioactive materials users generating low-level radioactive waste

International Nuclear Information System (INIS)

Fischer, D.K.; Gitt, M.; Williams, G.A.; Branch, S.; Otis, M.D.; McKenzie-Carter, M.A.; Schurman, D.L.

1991-07-01

The objective of this document is to provide a resource for all states and compact regions interested in promoting the minimization of low-level radioactive waste (LLW). This project was initiated by the Commonwealth of Massachusetts, and Massachusetts waste streams have been used as examples; however, the methods of analysis presented here are applicable to similar waste streams generated elsewhere. This document is a guide for states/compact regions to use in developing a system to evaluate and prioritize various waste minimization techniques in order to encourage individual radioactive materials users (LLW generators) to consider these techniques in their own independent evaluations. This review discusses the application of specific waste minimization techniques to waste streams characteristic of three categories of radioactive materials users: (1) industrial operations using radioactive materials in the manufacture of commercial products, (2) health care institutions, including hospitals and clinics, and (3) educational and research institutions. Massachusetts waste stream characterization data from key radioactive materials users in each category are used to illustrate the applicability of various minimization techniques. The utility group is not included because extensive information specific to this category of LLW generators is available in the literature

A process for establishing a financial assurance plan for LLW disposal facilities

International Nuclear Information System (INIS)

Smith, P.

1993-04-01

This document describes a process by which an effective financial assurance program can be developed for new low-level radioactive waste (LLW) disposal facilities. The report identifies examples of activities that might cause financial losses and the types of losses they might create, discusses mechanisms that could be used to quantify and ensure against the various types of potential losses identified and describes a decision process to formulate a financial assurance program that takes into account the characteristics of both the potential losses and available mechanisms. A sample application of the concepts described in the report is provided

A process for establishing a financial assurance plan for LLW disposal facilities

Energy Technology Data Exchange (ETDEWEB)

Smith, P. [EG and G Idaho, Inc., Idaho Falls, ID (United States). National Low-Level Waste Management Program

1993-04-01

This document describes a process by which an effective financial assurance program can be developed for new low-level radioactive waste (LLW) disposal facilities. The report identifies examples of activities that might cause financial losses and the types of losses they might create, discusses mechanisms that could be used to quantify and ensure against the various types of potential losses identified and describes a decision process to formulate a financial assurance program that takes into account the characteristics of both the potential losses and available mechanisms. A sample application of the concepts described in the report is provided.

Evaluation of melter technologies for vitrification of Hanford site low-level tank waste - phase 1 testing summary report

Energy Technology Data Exchange (ETDEWEB)

Wilson, C.N., Westinghouse Hanford

1996-06-27

Following negotiation of the fourth amendment to the Tri- Party Agreement for Hanford Site cleanup, commercially available melter technologies were tested during 1994 and 1995 for vitrification of the low-level waste (LLW) stream to be derived from retrieval and pretreatment of the radioactive defense wastes stored in 177 underground tanks. Seven vendors were selected for Phase 1 testing to demonstrate vitrification of a high-sodium content liquid LLW simulant. The tested melter technologies included four Joule-heated melters, a carbon electrode melter, a combustion melter, and a plasma melter. Various dry and slurry melter feed preparation processes also were tested. The technologies and Phase 1 testing results were evaluated and a preliminary technology down-selection completed. This report describes the Phase 1 LLW melter vendor testing and the tested technologies, and summarizes the testing results and the preliminary technology recommendations.

Greater-than-Class C low-level radioactive waste shipping package/container identification and requirements study. National Low-Level Waste Management Program

Energy Technology Data Exchange (ETDEWEB)

Tyacke, M.

1993-08-01

This report identifies a variety of shipping packages (also referred to as casks) and waste containers currently available or being developed that could be used for greater-than-Class C (GTCC) low-level waste (LLW). Since GTCC LLW varies greatly in size, shape, and activity levels, the casks and waste containers that could be used range in size from small, to accommodate a single sealed radiation source, to very large-capacity casks/canisters used to transport or dry-store highly radioactive spent fuel. In some cases, the waste containers may serve directly as shipping packages, while in other cases, the containers would need to be placed in a transport cask. For the purpose of this report, it is assumed that the generator is responsible for transporting the waste to a Department of Energy (DOE) storage, treatment, or disposal facility. Unless DOE establishes specific acceptance criteria, the receiving facility would need the capability to accept any of the casks and waste containers identified in this report. In identifying potential casks and waste containers, no consideration was given to their adequacy relative to handling, storage, treatment, and disposal. Those considerations must be addressed separately as the capabilities of the receiving facility and the handling requirements and operations are better understood.

Operation for Rokkasho Low Level Radioactive Waste Disposal Center

International Nuclear Information System (INIS)

Kamizono, Hideki

2008-01-01

The Rokkasho Low Level Radioactive Waste (LLW) Disposal Center is located in Oishitai, Rokkasho-mura, Kamikitagun, of Aomori Prefecture. This district is situated in the southern part of Shimohita Peninsula in the northeastern corner of the prefecture, which lies at the northern tip of Honshu, Japan's main island. The Rokkasho LLW Disposal Center deals with only LLW generated by operating of nuclear power plants. The No.1 and No.2 disposal facility are now in operation. The disposal facilities in operation have a total dispose capacity of 80,000m 3 (equivalent to 400,000 drums). Our final business scope is to dispose of radioactive waste corresponding to 600,000 m 3 (equivalent to 3000,000 drums). For No.1 disposal facility, we have been disposing of homogeneous waste, including condensed liquid waste, spent resin, solidified with cement and asphalt, etc. For No.2 disposal facility, we can bury a solid waste solidified with mortar, such as activated metals and plastics, etc. Using an improved construction technology for an artificial barrier, the concrete pits in No.2 disposal facility could be constructed more economical and spacious than that of No.1. Both No.1 and No.2 facility will be able to bury about 200,000 waste packages (drums) each corresponding to 40,000 m 3 . As of March 17, 2008, Approximately 200,00 waste drums summing up No.1 and No.2 disposal facility have been received from Nuclear power plants and buried. (author)

The application of probabilistic risk assessment to a LLW incinerator

International Nuclear Information System (INIS)

Li, K.K.; Huang, F.T.

1993-01-01

The 100 Kg/hr low-level radioactive waste (LLW) incinerator and the 1,500 ton supercompactor are two main vehicles in the Taiwan Power Company's Volume Reduction Center. Since the hot test of the incinerator in mid 1990, various problems associated with the original design and operating procedures were encountered. During the early stages of putting an incinerator in service, the modification and fine-tuning of the system would help future reliable operations. The probabilistic risk assessment (PRA) method was introduced to evaluate the interaction between potential system failure and its environmental impact and further help diagnose the system defects initially. The draft Level 1 system analysis was completed and the event and fault trees were constructed. Qualitatively, this approach is useful for preventing the system failure from occurring. However, Levels 2 and 3 analysis can only be done when sufficient data become available in the future

U.S. Bureau of Mines, phase I Hanford low-level waste melter tests: Melter offgas report

International Nuclear Information System (INIS)

Eaton, W.C.

1995-01-01

A multiphase program was initiated in 1994 to test commercially available melter technologies for the vitrification of the low-level waste (LLW) stream from defense wastes stored in underground tanks at the Hanford Site in southeastern Washington State. Phase 1 of the melter demonstration tests using simulated LLW was completed during fiscal year 1995. This document is the melter offgas report on testing performed by the U.S. Department of the Interior, Bureau of Mines, Albany Research Center in Albany, Oregon. The Bureau of Mines (one of the seven vendors selected) was chosen to demonstrate carbon electrode melter technology (also called carbon arc or electric arc) under WHC subcontract number MMI-SVV-384216. The document contains the complete offgas report for the first 24-hour melter test (WHC-1) as prepared by Entropy Inc. A summary of this report is also contained in the''U.S. Bureau of Mines, Phase 1 Hanford Low-Level Waste Melter Tests: Final Report'' (WHC-SD-WM-VI-030)

77 FR 58416 - Comparative Environmental Evaluation of Alternatives for Handling Low-Level Radioactive Waste...

Science.gov (United States)

2012-09-20

... for Handling Low-Level Radioactive Waste Spent Ion Exchange Resins From Commercial Nuclear Power... Radioactive Waste Spent Ion Exchange Resins from Commercial Nuclear Power Reactors. DATES: Please submit... Evaluation of Alternatives for Handling Low-Level Radioactive Waste Spent Ion Exchange Resins from Commercial...

A comparison of solidification media for the stabilization of low- level radioactive wastes

International Nuclear Information System (INIS)

Cowgill, M.G.

1991-10-01

When requirements exist to stabilize low-level radioactive waste (LLW) prior to disposal, efforts to achieve this stability often center on the mixing of the waste with a solidification medium. Although historically the medium of choice has been based on the use of portland cement as the binder material, several other options have been developed and subsequently implemented. These include thermoplastic polymers, thermosetting polymers and gypsum. No one medium has thus far been successful in providing stability to all forms of LLW. The characteristics and attributes of these different binder materials are reviewed and compared. The aspects examined include availability of information, limitations to use, sensitivity to process or waste chemistry changes, radionuclide retention ability, modeling of radionuclide release processes, ease and safety of use, and relative costs

Greater-than-Class C low-level radioactive waste transportation regulations and requirements study

International Nuclear Information System (INIS)

Tyacke, M.; Schmitt, R.

1993-07-01

The purpose of this report is to identify the regulations and requirements for transporting greater-than-Class C (GTCC) low-level radioactive waste (LLW) and to identify planning activities that need to be accomplished in preparation for transporting GTCC LLW. The regulations and requirements for transporting hazardous materials, of which GTCC LLW is included, are complex and include several Federal agencies, state and local governments, and Indian tribes. This report is divided into five sections and three appendices. Section 1 introduces the report. Section 2 identifies and discusses the transportation regulations and requirements. The regulations and requirements are divided into Federal, state, local government, and Indian tribes subsections. This report does not identify the regulations or requirements of specific state, local government, and Indian tribes, since the storage, treatment, and disposal facility locations and transportation routes have not been specifically identified. Section 3 identifies the planning needed to ensure that all transportation activities are in compliance with the regulations and requirements. It is divided into (a) transportation packaging; (b) transportation operations; (c) system safety and risk analysis, (d) route selection; (e) emergency preparedness and response; and (f) safeguards and security. This section does not provide actual planning since the details of the Department of Energy (DOE) GTCC LLW Program have not been finalized, e.g., waste characterization and quantity, storage, treatment and disposal facility locations, and acceptance criteria. Sections 4 and 5 provide conclusions and referenced documents, respectively

Planning and consultation procedures for low-level radioactive waste disposal: a comparative analysis of overseas experience

International Nuclear Information System (INIS)

Kemp, R.

1989-03-01

The results are presented of a study the purpose of which was to learn from experience in countries other than the UK, of planning and public consultation procedures associated with the establishment of low-level radioactive waste (LLW) disposal sites. Information on LLW developments in the United States, Canada, France, Holland, Switzerland, Sweden, and West Germany was sought. Particular regard was given to the efficacy of public consultation and negotiation procedures; the key aspects bearing on the public acceptability of LLW proposals; and the form and effect of any compensation mechanisms in operation. The main findings include: (i) Public acceptability of radioactive waste proposals depends upon a combination of basic understanding, trust, consultation and negotiation. (ii) There is no overall correct approach. (iii) The greatest success overseas appears to be linked to some combination of the following elements: authority and clarity in the exposition of radioactive waste management policy; the early involvement of local authority organisations in site selection; careful attention to the potential contribution of authoritative independent advisory groups; the development and nurturing of local liaison committees to establish good communications at the local level; careful consideration of means of devolving some power to local authority level for safety reassurance; and the development of an incremental, openly negotiated approach to compensation. (author)

Management of low- and intermediate level waste in Sweden

International Nuclear Information System (INIS)

Carlsson, Jan

1999-01-01

This presentation describes how the management of radioactive waste is organised in Sweden, where Swedish law places the responsibility for such management with the waste generators. The four nuclear utilities have formed a joint company, the Swedish Nuclear Fuel and Waste Management Co., SKB, to handle the nuclear waste. The Swedish waste management system includes a final repository for short-lived low level waste (LLW) and intermediate level waste (ILW) and an interim storage facility for spent nuclear fuel and long-lived waste. Some very low-level, short-lived waste is disposed of in shallow-land repositories at the nuclear power stations. The final repository is situated in underground rock caverns close to the Forsmark nuclear power plant. The rock caverns have been excavated to a depth of more than 50 m beneath the Baltic Sea floor. LLW is compacted into bales or packaged in metal drums or cases that can be transported in standard freight containers. Radioactive materials used in other sectors such as hospitals are collected and packaged at Studsvik and later deposited in the deep repository. ILW is mixed with cement or bitumen and cast in cement or steel boxes or metal drums. The final repository has different chambers for different kinds of waste. The environmental impact of the repository is negligible. Because Sweden's nuclear power plants and the SKB facilities all are located on the coast, all the waste transport can be conducted by sea. The costs of managing and disposing of Sweden's nuclear waste are small compared to the price of electricity

Performance evaluation and operational experience with a semi-automatic monitor for the radiological characterization of low-level wastes

International Nuclear Information System (INIS)

Davey, E.C.; Csullog, G.W.

1987-03-01

Chalk River Nuclear Laboratories (CRNL) have undertaken a Waste Disposal Project to co-ordinate the transition from the current practice of interim storage to permanent disposal for low-level radioactive wastes (LLW). The strategy of the project is to classify and segregate waste segments according to their hazardous radioactive lifetimes and to emplace them in disposal facilities engineered to isolate and contain them. To support this strategy, a waste characterization program was set up to estimate the volume and radioisotope inventories of the wastes managed by CRNL. A key element of the program is the demonstration of a non-invasive measurement technique for the isotope-specific characterization of solid LLW. This paper describes the approach taken at CRNL for the non-invasive assay of LLW and the field performance and early operational experience with a waste characterization monitor to be used in a waste processing facility

Performance evaluation and operational experience with a semi-automatic monitor for the radiological characterization of low-level wastes

International Nuclear Information System (INIS)

Davey, E.C.; Csullog, G.W.

1987-01-01

Chalk River Nuclear Laboratories (CRNL) have undertaken a Waste Disposal Project to co-ordinate the transition from the current practice of interim storage to permanent disposal for low-level radioactive wastes (LLW). The strategy of the project is to classify and segregate waste segments according to their hazardous radioactive lifetimes and to emplace them in disposal facilities engineered to isolate and contain them. To support this strategy, a waste characterization program was set up to estimate the volume and radioisotope inventories of the wastes managed by CRNL. A key element of the program is the demonstration of a non-invasive measurement technique for the isotope-specific characterization of solid LLW. This paper describes the approach taken at CRNL for the non-invasive assay of LLW and the field performance and early operational experience with a waste characterization monitor to be used in a waste processing facility

Letter report: Pre-conceptual design study for a pilot-scale Non-Radioactive Low-Level Waste Vitrification Facility

International Nuclear Information System (INIS)

Thompson, R.A.; Morrissey, M.F.

1996-03-01

This report presents a pre-conceptual design study for a Non-Radioactive Low-Level Waste, Pilot-Scale Vitrification System. This pilot plant would support the development of a full-scale LLW Vitrification Facility and would ensure that the full-scale facility can meet its programmatic objectives. Use of the pilot facility will allow verification of process flowsheets, provide data for ensuring product quality, assist in scaling to full scale, and support full-scale start-up. The facility will vitrify simulated non-radioactive LLW in a manner functionally prototypic to the full-scale facility. This pre-conceptual design study does not fully define the LLW Pilot-Scale Vitrification System; rather, it estimates the funding required to build such a facility. This study includes identifying all equipment necessary. to prepare feed, deliver it into the melter, convert the feed to glass, prepare emissions for atmospheric release, and discharge and handle the glass. The conceived pilot facility includes support services and a structure to contain process equipment

T-Rex system for operation in TRU, LLW, and hazardous zones

International Nuclear Information System (INIS)

Kline, H.M.; Andreycheck, T.P.; Beeson, B.K.

1995-01-01

T-Rex stands for Transuranic Storage Area Remote Excavator that is dedicated to the retrieval of above ground waste containers and overburden at the Radioactive Waste Management Complex (RWMC) located at the Idaho National Engineering Laboratory. There are a number of sites around the world containing (transuranic) (TRU), low level (LLW), and hazardous wastes that requires teleoperated, heavy lift manipulators with long reach and high precision to handle the materials stored there. Remote operation of equipment will reduce the risk to personnel to as-low-as-reasonably-achievable (ALARA) levels. The T-Rex is designed to fulfill this requirement at relatively low cost through the integration of a production front shovel excavator with a control system, local and remote operator control stations, a closed-circuit television system (CCTV), and multiple end effectors with quick changeout capability. This paper describes the conversion of an off-the-shelf excavator to a machine utilizing a modified hydraulic system, an integrated onboard remote control system, CCTV system, collision avoidance system, and a remote control station

Review of science and technology for disposal of low-level waste on the seabed and high-level waste in the subseabed

International Nuclear Information System (INIS)

Anderson, D.R.; Boyer, D.G.; Hollister, C.D.

1983-01-01

In 1980 it was recommended that an effort be made to increase the scientific data base relating to the oceanographic and biological characteristic of the Northeast Atlantic dumping area. The overall safety of sea dumping operations depends on a number of factors such as the characteristics of the dumping site, the amount, composition, conditioning, and packaging of waste, and the way in which operations are organized and controlled. An NEA research and environmental surveillance program related to sea disposal of low-level radioactive waste (LLW) is proceeding. Information from these studies will apply to disposal of LLW such as reactors from nuclear submarines and contaminated soil, as well as to packaged LLW. In Sweden, construction has begun on a repository located in the granitic rock beneath the seabed. The feasibility of a concept of burying high-level radioactive waste within the geologically stable formations of the deep ocean floor is being assessed. These subseabed options for a waste repository are being considered for several reasons. The granitic rock selected for the Swedish repository has a low hydraulic gradient, thereby reducing the amount of radioactivity tht will diffuse out of the repository. The sea water that covers the repository will dilute and disperse any radioisotopes that do escape from the repository. The other nations studying the feasibility of a subseabed repository are examining the fine-grained clay formations within the stable, predictable deep-sea regions, away from the boundaries of the lithospheric plates and productive surface waters. This clay has properties that may serve to permanently isolate radioactive waste. The most important characteristics of such clays are their vertical and lateral uniformity, low permeability, very high cation retention capacity, and potential for self-healing when disturbed

Predisposal management of low and intermediate level radioactive waste. Safety guide

International Nuclear Information System (INIS)

2003-01-01

considered in this publication begins with the refining and conversion of uranium concentrates. Recommendations on the management of radioactive waste from the mining and milling of uranium and thorium ores are provided. Some parts of the nuclear fuel cycle generate both high level waste and LLW. The management of high level waste itself generates LLW. The predisposal management of this LLW is included in the scope of this Safety Guide. Recommendations on the predisposal management of high level waste are provided. The recommendations in this Safety Guide primarily concern complex management activities for LLW. The regulatory body should decide which parts of this Safety Guide are relevant and appropriate for particular circumstances, and the extent to which the recommendations and guidance apply. This Safety Guide provides only introductory material on the transport and storage of LLW. Requirements and recommendations are provided in Refs. There may be non-radiological hazards associated with the predisposal management of LLW. Some guidance is given on the safety measures to be taken against non-radiological hazards if they have potential consequences for radiation safety. However, detailed recommendations are beyond the scope of this Safety Guide. The user should seek guidance from the regulatory body in the areas of health and safety and environmental protection

Scenario sensitivity analyses performed on the PRESTO-EPA LLW risk assessment models

International Nuclear Information System (INIS)

Bandrowski, M.S.

1988-01-01

The US Environmental Protection Agency (EPA) is currently developing standards for the land disposal of low-level radioactive waste. As part of the standard development, EPA has performed risk assessments using the PRESTO-EPA codes. A program of sensitivity analysis was conducted on the PRESTO-EPA codes, consisting of single parameter sensitivity analysis and scenario sensitivity analysis. The results of the single parameter sensitivity analysis were discussed at the 1987 DOE LLW Management Conference. Specific scenario sensitivity analyses have been completed and evaluated. Scenario assumptions that were analyzed include: site location, disposal method, form of waste, waste volume, analysis time horizon, critical radionuclides, use of buffer zones, and global health effects

Alpha low-level stored waste systems design study

Energy Technology Data Exchange (ETDEWEB)

Feizollahi, F.; Teheranian, B. (Morrison Knudson Corp., San Francisco, CA (United States). Environmental Services Div.); Quapp, W.J. (EG and G Idaho, Inc., Idaho Falls, ID (United States))

1992-08-01

The Stored Waste System Design Study (SWSDS), commissioned by the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examines relative life-cycle costs associated with three system concepts for processing the alpha low-level waste (alpha-LLW) stored at the Radioactive Waste Management Complex's Transuranic Storage Area at the INEL. The three system concepts are incineration/melting; thermal treatment/solidification; and sort, treat, and repackage. The SWSDS identifies system functional and operational requirements and assesses implementability; effectiveness; cost; and demonstration, testing, and evaluation (DT E) requirements for each of the three concepts.

Alpha low-level stored waste systems design study

Energy Technology Data Exchange (ETDEWEB)

Feizollahi, F.; Teheranian, B. [Morrison Knudson Corp., San Francisco, CA (United States). Environmental Services Div.; Quapp, W.J. [EG and G Idaho, Inc., Idaho Falls, ID (United States)

1992-08-01

The Stored Waste System Design Study (SWSDS), commissioned by the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examines relative life-cycle costs associated with three system concepts for processing the alpha low-level waste (alpha-LLW) stored at the Radioactive Waste Management Complex`s Transuranic Storage Area at the INEL. The three system concepts are incineration/melting; thermal treatment/solidification; and sort, treat, and repackage. The SWSDS identifies system functional and operational requirements and assesses implementability; effectiveness; cost; and demonstration, testing, and evaluation (DT&E) requirements for each of the three concepts.

Alpha low-level stored waste systems design study

International Nuclear Information System (INIS)

Feizollahi, F.; Teheranian, B.

1992-08-01

The Stored Waste System Design Study (SWSDS), commissioned by the Waste Technology Development Department at the Idaho National Engineering Laboratory (INEL), examines relative life-cycle costs associated with three system concepts for processing the alpha low-level waste (alpha-LLW) stored at the Radioactive Waste Management Complex's Transuranic Storage Area at the INEL. The three system concepts are incineration/melting; thermal treatment/solidification; and sort, treat, and repackage. The SWSDS identifies system functional and operational requirements and assesses implementability; effectiveness; cost; and demonstration, testing, and evaluation (DT ampersand E) requirements for each of the three concepts

Geochemical effects on the behavior of LLW radionuclides in soil/groundwater environments

Energy Technology Data Exchange (ETDEWEB)

Krupka, K.M.; Sterne, R.J. [Pacific Northwest Lab., Richland, WA (United States)

1995-12-31

Assessing the migration potential of radionuclides leached from low-level radioactive waste (LLW) and decommissioning sites necessitates information on the effects of sorption and precipitation on the concentrations of dissolved radionuclides. Such an assessment requires that the geochemical processes of aqueous speciation, complexation, oxidation/reduction, and ion exchange be taken into account. The Pacific Northwest National Laboratory (PNNL) is providing technical support to the U.S. Nuclear Regulatory Commission (NRC) for defining the solubility and sorption behavior of radionuclides in soil/ground-water environments associated with engineered cementitious LLW disposal systems and decommissioning sites. Geochemical modeling is being used to predict solubility limits for radionuclides under geochemical conditions associated with these environments. The solubility limits are being used as maximum concentration limits in performance assessment calculations describing the release of contaminants from waste sources. Available data were compiled regarding the sorption potential of radionuclides onto {open_quotes}fresh{close_quotes} cement/concrete where the expected pH of the cement pore waters will equal to or exceed 10. Based on information gleaned from the literature, a list of preferred minimum distribution coefficients (Kd`s) was developed for these radionuclides. The K{sub d} values are specific to the chemical environments associated with the evolution of the compositions of cement/concrete pore waters.

Detailed description of a new management system for solid, short-lived low and intermediate level radioactive waste at Ignalina NPP

International Nuclear Information System (INIS)

2002-01-01

The objective is to modify and extend the existing system at the Ignalina Nuclear Power Plant (INPP) for handling of Very Low Level Waste (VLLW), short lived Low and Intermediate Level Waste (LLW-SL and ILW-SL). The ultimate aim is to reduce the risks and the influence on the personnel and the environment. According to the request from INPP, the modified system is based on the existence of an incineration plant. This system description describes treatment of non-combustible VLLW, LLW-SL and ILW-SL at a new waste handling facility (WHF) located in the future buildings 159/2 and 159/3 at the INPP. The new WHF is also handling Exempt Waste (EW), Reusable Material (RM) and Free Release Goods (FRG). The buildings 159/2 and 159/3 are future extensions of the existing building 159. (author)

Research and development on the melting test of low-level radioactive miscellaneous solid waste

International Nuclear Information System (INIS)

Nakashio, Nobuyuki; Hoshi, Akiko; Kameo, Yutaka; Nakashima, Mikio

2007-02-01

The Nuclear Science Research Institute of the Japan Atomic Energy Agency constructed the Advanced Volume Reduction Facilities (AVRF) in February 2003 for treatment of low-level radioactive miscellaneous solid waste (LLW). The waste volume reduction is carried out by a high-compaction process or melting processes in the AVRF. In advance of operating the melting process in the AVRF, melting tests of simulated LLW with RI tracers ( 60 Co, 137 Cs and 152 Eu) have been conducted by using the plasma melter in pilot scale. Viscosity of molten waste, chemical composition and physical properties of solidified products and distribution of the tracers in each product were investigated in various melting conditions. It was confirmed that the viscosity of molten waste was able to be controlled by adjusting chemical composition of molten waste. The RI tracer were almost uniformly distributed in the solidified products. The retention of 137 Cs depended on the basicity (CaO/SiO 2 ) of the solidified products. The solidified product possessed satisfactory compressive strength. In the case of basicity less than 0.8, the leachability of RI tracers from the solidified products was less than or equal to that of a high-level vitrified waste. In this review, experimental results of the melting tests were discussed in order to contribute to actual treatment of LLW in the AVRF. (author)

Preliminary post-closure safety assessment of repository concepts for low level radioactive waste at the Bruce Site, Ontario

International Nuclear Information System (INIS)

Little, R.H.; Penfold, J.S.S.; Egan, M.J.; Leung, H.

2005-01-01

The preliminary post-closure safety assessment of permanent repository concepts for low-level radioactive waste (LLW) at the Ontario Power Generation (OPG) Bruce Site is described. The study considered the disposal of both short and long-lived LLW. Four geotechnically feasible repository concepts were considered (two near-surface and two deep repositories). An approach consistent with best international practice was used to provide a reasoned and comprehensive analysis of post-closure impacts of the repository concepts. The results demonstrated that the deep repository concepts in shale and in limestone, and the surface repository concept on sand should meet radiological protection criteria. For the surface repository concept on glacial till, it appears that increased engineering such as grouting of waste and voids should be considered to meet the relevant dose constraint. Should the project to develop a permanent repository for LLW proceed, it is expected that this preliminary safety assessment would need to be updated to take account of future site-specific investigations and design updates. (author)

Alternatives to control subsidence at low-level radioactive waste burial sites

International Nuclear Information System (INIS)

Phillips, S.J.; Carlson, R.A.

1981-09-01

A substantial quantity of low-level radioactive and hazardous wastes has been interred in shallow land burial structures throughout the United States. Many of these structures (trenches, pits, and landfills) have experienced geotechnical subsidence problems and may require stabilization. Ground surface manifestations of subsidence include: large cracks, basins, and cave-ins. Subsidence is primarily caused by void filling, and physicochemical degradation and solubilization of buried wastes. These surface features represent a potential for increased contamination transport to the biosphere via water, air, biologic, and direct pathways. Engineering alternatives for the reduction of buried waste and matrix materials voids are identified and discussed. The advantages, disadvantages, and costs of each alternative are evaluated. Falling mass, pile driving and in situ incineration engineering alternatives were selected for further development

The establishment of computer codes for radiological assessment on LLW final disposal in Taiwan

International Nuclear Information System (INIS)

Yang, C.C.; Chen, H.T.; Shih, C.L.; Yeh, C.S.; Tsai, C.M.

1988-01-01

For final shallow land disposal of Low Level Waste (LLW) in Taiwan, an effort was initiated to establish the evaluation codes for the needs of environmental impact analysis. The objective of the computer code is to set up generic radiological standards for future evaluation on 10 CFR Part 61 Licensing Requirements for Land Disposal of Radioactive Wastes. In determining long-term influences resulting from radiological impacts of LLW at disposal sites there are at least three quantifiable impact measures selected for calculation: dose to members of the public (individual and population), occupational exposures and costs. The computer codes are from INTRUDE, INVERSI and INVERSW of NUREG-0782, OPTIONR and GRWATRR of NUREG-0945. They are both installed in FACOM-M200 and IBM PC/AT systems of Institute of Nuclear Energy Research (INER). The systematic analysis of the computer codes depends not only on the data bases supported by NUREG/CR-1759 - Data Base for Radioactive Waste Management, Volume 3, Impact Analysis Methodology Report but also the information collected from the different exposure scenarios and pathways. The sensitivity study is also performed to assure the long-term stability and security for needs of determining performance objectives

Considerations for alternative low-level radioactive disposal sites

International Nuclear Information System (INIS)

Beck, J.M.

1986-01-01

In the immediate future, there is a need for low-level radioactive disposal sites to accommodate wastes that would otherwise be placed at a later date in permanent, government sanctioned ''compact'' sites. Until these ''compact'' sites become operational, a potential, relatively low-cost alternative exists in the numerous inactive uranium processing sites that are likewise proposed for remedial action removal or stabilization operations. This paper addressed disposal from the aspects of engineering design, economics and liability of participating parties. Many uranium (and by-product) processing facilities in the western states now stand idle due to current economic conditions within the industry. Many more were previously deactivated for various reasons. All must be dealt with under the UMTRA Program Guidelines with regard to removal, reclamation or other remedial action activities. With cooperative efforts, some of these sites would appear to be suitable for disposal of small volume, low-level radioactive wastes that presently render urban properties valueless in terms of real estate and aesthetic values. Likely sites would appear to be those slated for in-place stabilization and reclamation, particularly where the urban property material has a lower level of radioactivity than the disposal site material. The resultant impacts for site stabilization and reclamation would be solely in the areas of increased material volumes (generally requiring a minimal increase in engineering design complexity) and liability. Clearly, liability will be the overriding factor in such an approach. With the complex hierarchy of regulatory agencies involved and the private sector, what appears to be a relative simple and economic approach may have extreme difficulty in achieving reality

Vitrification treatment options for disposal of greater-than-Class-C low-level waste in a deep geologic repository

International Nuclear Information System (INIS)

Fullmer, K.S.; Fish, L.W.; Fischer, D.K.

1994-11-01

The Department of Energy (DOE), in keeping with their responsibility under Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985, is investigating several disposal options for greater-than-Class C low-level waste (GTCC LLW), including emplacement in a deep geologic repository. At the present time vitrification, namely borosilicate glass, is the standard waste form assumed for high-level waste accepted into the Civilian Radioactive Waste Management System. This report supports DOE's investigation of the deep geologic disposal option by comparing the vitrification treatments that are able to convert those GTCC LLWs that are inherently migratory into stable waste forms acceptable for disposal in a deep geologic repository. Eight vitrification treatments that utilize glass, glass ceramic, or basalt waste form matrices are identified. Six of these are discussed in detail, stating the advantages and limitations of each relative to their ability to immobilize GTCC LLW. The report concludes that the waste form most likely to provide the best composite of performance characteristics for GTCC process waste is Iron Enriched Basalt 4 (IEB4)

Soil characterization methods for unsaturated low-level waste sites

International Nuclear Information System (INIS)

Wierenga, P.J.; Young, M.H.; Hills, R.G.

1993-01-01

To support a license application for the disposal of low-level radioactive waste (LLW), applicants must characterize the unsaturated zone and demonstrate that waste will not migrate from the facility boundary. This document provides a strategy for developing this characterization plan. It describes principles of contaminant flow and transport, site characterization and monitoring strategies, and data management. It also discusses methods and practices that are currently used to monitor properties and conditions in the soil profile, how these properties influence water and waste migration, and why they are important to the license application. The methods part of the document is divided into sections on laboratory and field-based properties, then further subdivided into the description of methods for determining 18 physical, flow, and transport properties. Because of the availability of detailed procedures in many texts and journal articles, the reader is often directed for details to the available literature. References are made to experiments performed at the Las Cruces Trench site, New Mexico, that support LLW site characterization activities. A major contribution from the Las Cruces study is the experience gained in handling data sets for site characterization and the subsequent use of these data sets in modeling studies

Low level tank waste disposal study

Energy Technology Data Exchange (ETDEWEB)

Mullally, J.A.

1994-09-29

Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site.

Low level tank waste disposal study

International Nuclear Information System (INIS)

Mullally, J.A.

1994-01-01

Westinghouse Hanford Company (WHC) contracted a team consisting of Los Alamos Technical Associates (LATA), British Nuclear Fuel Laboratories (BNFL), Southwest Research Institute (SwRI), and TRW through the Tank Waste Remediation System (TWRS) Technical Support Contract to conduct a study on several areas concerning vitrification and disposal of low-level-waste (LLW). The purpose of the study was to investigate how several parameters could be specified to achieve full compliance with regulations. The most restrictive regulation governing this disposal activity is the National Primary Drinking Water Act which sets the limits of exposure to 4 mrem per year for a person drinking two liters of ground water daily. To fully comply, this constraint would be met independently of the passage of time. In addition, another key factor in the investigation was the capability to retrieve the disposed waste during the first 50 years as specified in Department of Energy (DOE) Order 5820.2A. The objective of the project was to develop a strategy for effective long-term disposal of the low-level waste at the Hanford site

Selection of a computer code for Hanford low-level waste engineered-system performance assessment

International Nuclear Information System (INIS)

McGrail, B.P.; Mahoney, L.A.

1995-10-01

Planned performance assessments for the proposed disposal of low-level waste (LLW) glass produced from remediation of wastes stored in underground tanks at Hanford, Washington will require calculations of radionuclide release rates from the subsurface disposal facility. These calculations will be done with the aid of computer codes. Currently available computer codes were ranked in terms of the feature sets implemented in the code that match a set of physical, chemical, numerical, and functional capabilities needed to assess release rates from the engineered system. The needed capabilities were identified from an analysis of the important physical and chemical process expected to affect LLW glass corrosion and the mobility of radionuclides. The highest ranked computer code was found to be the ARES-CT code developed at PNL for the US Department of Energy for evaluation of and land disposal sites

Application of an infiltration evaluation methodology to a hypothetical low-level waste disposal facility

International Nuclear Information System (INIS)

Meyer, P.D.

1993-12-01

This report provides an analysis of infiltration and percolation at a hypothetical low-level waste (LLW) disposal facility was carried out. The analysis was intended to illustrate general issues of concern in assessing the performance of LLW disposal facilities. Among the processes considered in the analysis were precipitation, runoff, information, evaporation, transpiration, and redistribution. The hypothetical facility was located in a humid environment characterized by frequent and often intense precipitation events. The facility consisted of a series of concrete vaults topped by a multilayer cover. Cover features included a sloping soil surface to promote runoff, plant growth to minimize erosion and promote transportation, a sloping clay layer, and a sloping capillary barrier. The analysis within the root zone was carried out using a one-dimensional, transient simulation of water flow. Below the root zone, the analysis was primarily two-dimensional and steady-state

Achieving local support for a low-level radioactive waste disposal facility in Illinois

International Nuclear Information System (INIS)

Kerr, T.A.; Seidler, P.E.

1989-01-01

This paper discusses how Illinois is progressing toward the goal of having a new low-level radioactive waste (LLW) disposal facility in operation by the federally mandated milestone of January 1, 1993. To accomplish this task, Illinois has adopted a voluntary siting process. The voluntary siting process will be successful by definition only if a high level of local support can be achieved and sustained. A strong public participation program in conjunction with a comprehensive information and education program is essential to fostering the necessary local support. Many other elements are also needed throughout this process. The Illinois Department of Nuclear Safety (IDNS) has found that making grants to local governments, awarding scholarships for area students, enacting a comprehensive system of legislation and regulations, explaining the site identification and characterization program, describing facility design features, practicing a strong policy of buying and hiring locally, maintaining good relationships with local news media and building trust through personal relationships have all greatly contributed to support for the LLW program in the potential host communities

Low-level radioactive-waste compacts. Status report as of July 1982

International Nuclear Information System (INIS)

1982-07-01

The Low-Level Radioactive Waste Policy Act (P.L. 96-573), enacted in December 1980, established as federal policy that states take responsibility for providing disposal capacity for low-level radioactive waste (LLW) generated within their borders, except for defense waste and Federal R and D. At the request of Senator James A. McClure, Chairman of the Senate Committee on Energy and Natural Resources, DOE has documented the progress of states individually and collectively in fulfilling their responsibilities under the Public Law. Regionalization through formation of low-level waste compacts has been the primary vehicle by which many states are assuming this responsibility. To date seven low-level waste compacts have been drafted and six have been enacted by state legislatures or ratified by a governor. As indicated by national progress to date, DOE considers the task of compacting achievable by the January 1, 1986, exclusionary date set in law, although several states and NRC questioned this

Low-level radioactive-waste compacts. Status report as of July 1982

Energy Technology Data Exchange (ETDEWEB)

1982-07-01

The Low-Level Radioactive Waste Policy Act (P.L. 96-573), enacted in December 1980, established as federal policy that states take responsibility for providing disposal capacity for low-level radioactive waste (LLW) generated within their borders, except for defense waste and Federal R and D. At the request of Senator James A. McClure, Chairman of the Senate Committee on Energy and Natural Resources, DOE has documented the progress of states individually and collectively in fulfilling their responsibilities under the Public Law. Regionalization through formation of low-level waste compacts has been the primary vehicle by which many states are assuming this responsibility. To date seven low-level waste compacts have been drafted and six have been enacted by state legislatures or ratified by a governor. As indicated by national progress to date, DOE considers the task of compacting achievable by the January 1, 1986, exclusionary date set in law, although several states and NRC questioned this.

Taking the UK's national LLW programme from strategy development to implementation - 59059

International Nuclear Information System (INIS)

Rossiter, David; O'Donnell, Rachel

2012-01-01

In 2008 UK Nuclear Waste Management Ltd (UKNWM) became the Parent Body Organisation (PBO) at the Low Level Waste Repository (LLWR) in the UK. LLWR is the primary disposal facility for the UK's LLW, supporting a wide range of industries across the nuclear power generation, reprocessing, defence, health care, education, and oil and gas sectors. One of the key tasks following the appointment of the new PBO was to work with the Nuclear Decommissioning Authority (NDA) to develop a national strategy for LLW generated in the UK, predominantly in the NDA estate. The new National Strategy for LLW was required to address the gap between the forecast waste arisings and predicted capacity at LLWR. The National Strategy for LLW Management was published in August 2010 following an 18 month development period. The main focus of the strategy is on three areas: - Application of the waste management hierarchy to extend the life of LLWR and ensure waste is managed in a risk-based, fit-for-purpose manner - Making best use of existing assets such as transport, packaging, treatment and disposal facilities - Opening up new fit-for-purpose waste management routes to divert waste away from LLWR Developing a robust strategy is vital to provide strategic direction to Government, waste producers, regulators, and stakeholders. Once the strategy is developed and approved, the key challenge is then to implement the strategy on a national scale in an efficient and cost-effective manner that delivers maximum value for money to the UK taxpayer. As well as developing the strategy, LLWR has been actively working to develop the enablers to implement the strategy. Since the publication of the strategy in August 2010 LLWR has been re-organised to reflect the shift in focus, from strategy development to implementation and delivery of the strategy. New resources have been brought in with international waste management experience to help integrate delivery with waste producers. This paper covers the

Low-level radioactive waste transportation safety history

International Nuclear Information System (INIS)

McClure, J.D.

1997-01-01

The Radioactive Materials Incident Report (RMIR) database was developed fin 1981 at the Transportation Technology Center of Sandia National Laboratories to support its research and development activities for the US department of Energy (DOE). This database contains information about radioactive material (RAM) transportation incidents that have occurred in the US since 1971. These data were drawn from the US Department of Transportation's (DOT) Hazardous Materials Incident Report system, from Nuclear Regulatory Commission (NRC) files, and from various agencies including state radiological control offices. Support for the RMIR data base is funded by the US DOE National Transportation Program (NTP). Transportation events in RMIR are classified in one of the following ways: as a transportation accident, as a handling accident, or as a reported incident. This presentation will provide definitions for these classifications and give examples of each. The primary objective of this presentation is to provide information on nuclear materials transportation accident/incident events involving low-level waste (LLW) that have occurred in the US for the period 1971 through 1996. Among the areas to be examined are: transportation accidents by mode, package response during accidents, and an examination of accidents where release of contents has occurred. Where information is available, accident and incident history and package response for LLW packages in transportation accidents will be described

Development of a computerized data base for low-level radioactive waste leaching data: Topical report

International Nuclear Information System (INIS)

Dougherty, D.R.; Colombo, P.

1986-09-01

This report documents the development of a computerized data base (db) of leaching data for solidified low-level radioactive waste (LLW) forms. Brookhaven National Lab performed this work under contract with the US Department of Energy's Low-Level Waste Management Program as part of an effort to develop an accelerated leach test(s) that can be used to predict leachabilities of LLW forms over long time periods, i.e., hundreds of years. The accelerated leach test(s) is (are) to be developed based on knowledge of leaching mechanisms and factors that affect leaching. Although developed specifically for the Accelerated Leach Test(s) Program, this db may be useful to others concerned with the management of low-level waste. The db is being developed to provide efficient data compilation and analysis capabilities. The data compiled in the db, which include data from the Accelerated Leach Test(s) Program and selected data from the literature, have been selected to elucidate leaching mechanisms and factors that affect leaching and are not meant to be a comprehensive compilation of leaching data. This report presents the data compilation aspect of the db. It does not present the programmatic results obtained from analysis of the data regarding leaching mechanisms and factors that affect leaching, which will be presented in reports from the Accelerated Leach Test(s) Program. 6 refs

Advanced technology for disposal of low-level radioactive/waste

International Nuclear Information System (INIS)

Anderson, R.T.

1990-01-01

New Low-Level Radioactive Waste (LLW) sites will be opened in this decade. These sites will replace the existing sites, and will be developed for waste generated at both commercial and governmental facilities. The design and operation of these facilities will include additional engineered provisions to further minimize the probability for any radioactive material release for upwards of 500 years following site closure. Chem-Nuclear Systems, Inc. (CNSI) has been selected by several state waste compacts to design, construct and operate new LLW disposal sites. These new sites will be located in Illinois, North Carolina and Pennsylvania. They will receive waste generated at commercial sites (power utilities, commercial processors, hospitals, etc.), with volumes ranging from 200,000 to 550,000 cubic feet per year. As currently planned, these facilities will be operational for from 20 to 50 years. The basis of the new designs is multiple engineered barriers which augments the natural features of the site and the solid form of the waste as shipped by the generator. The design concept is referred to as the Triple Safe concept, since it is composed of three distinct engineered barriers. This design has been adapted from disposal technology developed in France. This paper discusses aspects of the Triple Safe technology which CNSI is now developing for the new LLW sites. The designs, while not absolutely identical at each site, do have many common features. The author believes that these are representative of disposal technology to be used in the US in the 1990's and beyond. The current projection is that these sites will become operational in the 1993-97 time period

Using Geographic Information Systems to Determine Site Suitability for a Low-Level Radioactive Waste Storage Facility.

Science.gov (United States)

Wilson, Charles A; Matthews, Kennith; Pulsipher, Allan; Wang, Wei-Hsung

2016-02-01

Radioactive waste is an inevitable product of using radioactive material in education and research activities, medical applications, energy generation, and weapons production. Low-level radioactive waste (LLW) makes up a majority of the radioactive waste produced in the United States. In 2010, over two million cubic feet of LLW were shipped to disposal sites. Despite efforts from several states and compacts as well as from private industry, the options for proper disposal of LLW remain limited. New methods for quickly identifying potential storage locations could alleviate current challenges and eventually provide additional sites and allow for adequate regional disposal of LLW. Furthermore, these methods need to be designed so that they are easily communicated to the public. A Geographic Information Systems (GIS) based method was developed to determine suitability of potential LLW disposal (or storage) sites. Criteria and other parameters of suitability were based on the Code of Federal Regulation (CFR) requirements as well as supporting literature and reports. The resultant method was used to assess areas suitable for further evaluation as prospective disposal sites in Louisiana. Criteria were derived from the 10 minimum requirements in 10 CFR Part 61.50, the Nuclear Regulatory Commission's Regulatory Guide 0902, and studies at existing disposal sites. A suitability formula was developed permitting the use of weighting factors and normalization of all criteria. Data were compiled into GIS data sets and analyzed on a cell grid of approximately 14,000 cells (covering 181,300 square kilometers) using the suitability formula. Requirements were analyzed for each cell using multiple criteria/sub-criteria as well as surrogates for unavailable datasets. Additional criteria were also added when appropriate. The method designed in this project proved to be sufficient for initial screening tests in determining the most suitable areas for prospective disposal (or storage

Branch technical position for performance assessment of low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

Campbell, A.C.; Abramson, L.; Byrne, R.M.

1994-01-01

The U.S. Nuclear Regulatory Commission has developed a Draft Branch Technical Position on Performance Assessment of Low-Level Radioactive Waste Disposal Facilities. The draft technical position addresses important issues in performance assessment modeling and provides a framework and technical basis for conducting and evaluating performance assessments in a disposal facility license application. The technical position also addresses specific technical policy issues and augments existing NRC guidance pertaining to LLW performance assessment

Evaluation of Department of Energy-Held Potential Greater-Than-Class C Low-Level Radioactive Waste. Revision 1

International Nuclear Information System (INIS)

1994-09-01

A number of commercial facilities have generated potential greater-than-Class C low-level radioactive waste (GTCC LLW), and, through contractual arrangements with the US Department of Energy (DOE) or for health and safety reasons, DOE is storing the waste. This report presents the results of an assessment conducted by the GTCC LLW Management Program to consider specific circumstances under which DOE accepted the waste, and to determine whether disposal in a facility licensed by the US Nuclear Regulatory Commission, or by DOE in a nonlicensed facility, is appropriate. Input from EG ampersand G Idaho, Inc., and DOE Idaho Operations Office legal departments concerning the disposal requirements of this waste were the basis for the decision process used in this report

Evaluation of Department of Energy-Held Potential Greater-Than-Class C Low-Level Radioactive Waste. Revision 1

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-09-01

A number of commercial facilities have generated potential greater-than-Class C low-level radioactive waste (GTCC LLW), and, through contractual arrangements with the US Department of Energy (DOE) or for health and safety reasons, DOE is storing the waste. This report presents the results of an assessment conducted by the GTCC LLW Management Program to consider specific circumstances under which DOE accepted the waste, and to determine whether disposal in a facility licensed by the US Nuclear Regulatory Commission, or by DOE in a nonlicensed facility, is appropriate. Input from EG&G Idaho, Inc., and DOE Idaho Operations Office legal departments concerning the disposal requirements of this waste were the basis for the decision process used in this report.

Assessment of Reusing 14-Ton, Thin-Wall, Depleted UF6 Cylinders as LLW Disposal Containers

International Nuclear Information System (INIS)

O'Connor, D.G.; Poole, A.B.; Shelton, J.H.

2000-01-01

Approximately 700,000 MT of DUF 6 is stored, or will be produced under a current agreement with the USEC, at the Paducah site in Kentucky, Portsmouth site in Ohio, and ETTP site in Tennessee. On July 21, 1998, the 105th Congress approved Public Law 105-204, which directed that facilities be built at the Kentucky and Ohio sites to convert DUF 6 to a stable form for disposition. On July 6, 1999, the Department of Energy (DOE) issued the ''Final Plan for the Conversion of Depleted Uranium Hexafluoride as Required by Public Law 105-204'', in which DOE committed to develop a ''Depleted Uranium Hexafluoride Materials Use Roadmap''. On September 1,2000, DOE issued the ''Draft Depleted Uranium Hexafluoride Materials Use Roadmap'' (Roadmap), which provides alternate paths for the long-term storage, beneficial use, and eventual disposition of each product form and material that will result from the DUF 6 conversion activity. One of the paths being considered for DUF 6 cylinders is to reuse the empty cylinders as containers to transport and dispose of LLW, including the converted DU. The Roadmap provides results of the many alternate uses and disposal paths for conversion products and the empty DUF 6 storage cylinders. As a part of the Roadmap, evaluations were conducted of cost savings, technical maturity, barriers to implementation, and other impacts. Results of these evaluations indicate that using the DUF 6 j storage cylinders as LLW disposal containers could provide moderate cost savings due to the avoided cost of purchasing LLW packages and the avoided cost of disposing of the cylinders. No significant technical or institutional .issues were identified that.would make using cylinders as LLW packages less effective than other disposition paths. Over 58,000 cylinders have been used, or will be used, to store DUF 6 . Over 5 1,000 of those cylinders are 14TTW cylinders with a nominal wall thickness of 5/16-m (0.79 cm). These- 14TTW cylinders, which have a nominal diameter

Solid low level waste management guidelines

International Nuclear Information System (INIS)

Saunders, P.

1995-01-01

In the 1980's the nuclear industry began focusing a great deal of attention on minimizing the volume of low level radioactive waste (LLW) that required disposal. This was driven by several factors including rising disposal costs, increased regulatory pressures, and increased pressure from other organizations such as INPO. In the 1990's most utilities are faced with intense competition in the electrical generation market. The survival of a utility is based on their ability to produce electricity by the most efficient and economical means available. Waste management related costs are a substantial portion of most utilities O ampersand M budgets. Disposal site access denial continues to be a major factor in waste management program decision, and the pressures to minimize waste volumes from outside organizations is greater than ever

Practical Model of Cement Based Grout Mix Design, for Use into Low Level Radiation Waste Management

Directory of Open Access Journals (Sweden)

Radu Lidia

2015-12-01

Full Text Available The cement based grouts, as functional performance composite materials, are widely used for both immobilisation and encapsulation as well as for stabilization in the field of inorganic waste management. Also, to ensure that low level radioactive waste (LLW are contained for storage and ultimate disposal, they are encapsulated or immobilized in monolithic waste forms, with cement –based grouts.

Spatial and temporal distribution of risks associated with low-level radioactive waste disposal

International Nuclear Information System (INIS)

Thompson, P.B.

1988-01-01

The major purposes of this dissertation are to examine the economic tradeoffs which arise in the process of LLW disposal and to derive a framework within which the impact of these tradeoffs on LLW disposal policy can be analyzed. There are two distinct stages in the disposal of LLW - the transportation of the waste from sources to disposal sites and the disposal of the waste. The levels of costs and risks associated with these two stages depend on the number and location of disposal sites. Having more disposal sites results in lower transportation costs and risks but also in greater disposal costs and risks. The tradeoff between transportation costs and risks can also be viewed as a tradeoff between present and future risks. Therefore, an alteration in the spatial distribution of LLW disposal sites necessarily implies a change in the temporal distribution of risks. These tradeoffs are examined in this work through the use of a transportation model to which probabilistic radiation exposure constraints are added. Future (disposal) risks are discounted. The number and capacities of LLW disposal sites are varied in order to derive a series of system costs and corresponding expected cancers. This provides policy makers with a cost vs. cancers possibility function

Preliminary assessment of the performance of concrete as a structural material for alternative low-level radioactive waste disposal technologies

International Nuclear Information System (INIS)

MacKenzie, D.R.; Siskind, B.; Bowerman, B.S.; Piciulo, P.L.

1986-12-01

The objective of this study was to develop information needed to evaluate the long-term performance of concrete and reinforced concrete as a structural material for alternative LLW disposal methods. The capability to carry out such an evaluation is required for licensing a site which employs one of these alternative methods. The basis for achieving the study objective was the review and analysis of the literature on concrete and its properties, particularly its durability. In carrying out this program, criteria for evaluating performance of concrete and factors that can effect its performance were identified. The factors are both intrinsic, i.e., associated with composition of the concrete (and thus controllable), and extrinsic, i.e., due to external environmental forces such as climatic conditions and aggressive chemicals in the soil. A section of the report is devoted to the properties of coatings and their possible use in protecting concrete from chemical attack and enhancing its useful properties. The testing of concrete, using both accelerated tests and long-term non-accelerated tests, is discussed with special reference to its application to modeling of long-term performance prediction. On the basis of the study's results, minimum acceptance criteria are recommended as an aid in the licensing of disposal sites which make sure use of alternative methods

Treatment methods for radioactive mixed wastes in commercial low-level wastes: technical considerations

International Nuclear Information System (INIS)

MacKenzie, D.R.; Kempf, C.R.

1986-01-01

Treatment options for the management of three generic categories of radioactive mixed waste in commercial low-level wastes (LLW) have been identified and evaluated. These wastes were characterized as part of a BNL study in which LLW generators were surveyed for information on potential chemical hazards in their wastes. The general treatment options available for mixed wastes are destruction, immobilization, and reclamation. Solidification, absorption, incineration, acid digestion, wet-air oxidation, distillation, liquid-liquid wastes. Containment, segregation, decontamination, and solidification or containment of residues, have been considered for lead metal wastes which have themselves been contaminated and are not used for purposes of waste disposal shielding, packaging, or containment. For chromium-containing wastes, solidification, incineration, wet-air oxidation, acid digestion, and containment have been considered. For each of these wastes, the management option evaluation has included an assessment of testing appropriate to determine the effect of the option on both the radiological and potential chemical hazards present

Treatment methods for radioactive mixed wastes in commercial low-level wastes: technical considerations

Energy Technology Data Exchange (ETDEWEB)

MacKenzie, D.R.; Kempf, C.R.

1986-01-01

Treatment options for the management of three generic categories of radioactive mixed waste in commercial low-level wastes (LLW) have been identified and evaluated. These wastes were characterized as part of a BNL study in which LLW generators were surveyed for information on potential chemical hazards in their wastes. The general treatment options available for mixed wastes are destruction, immobilization, and reclamation. Solidification, absorption, incineration, acid digestion, wet-air oxidation, distillation, liquid-liquid wastes. Containment, segregation, decontamination, and solidification or containment of residues, have been considered for lead metal wastes which have themselves been contaminated and are not used for purposes of waste disposal shielding, packaging, or containment. For chromium-containing wastes, solidification, incineration, wet-air oxidation, acid digestion, and containment have been considered. For each of these wastes, the management option evaluation has included an assessment of testing appropriate to determine the effect of the option on both the radiological and potential chemical hazards present.

Research and development of treatment techniques for LLW from decommissioning: Decontamination and volume reduction techniques

International Nuclear Information System (INIS)

Hirabayashi, T.; Kameo, Y.; Nakashio, N.

2001-01-01

For the purpose of reducing the amount and/or volume of low-level radioactive waste (LLW) arising from decommissioning of nuclear reactor, the Japan Atomic Energy Research Institute (JAERI) has been developing four decontamination techniques. They are: (a) Gas-carrying abrasive method, (b) In-situ remote electropolishing method for pipe system before dismantling, (c) Bead reaction - thermal shock method, and (d) Laser induced chemical method for components after dismantling. JAERI in developing techniques are also carrying out melting tests of metal and non-metal. Melting was confirmed to be effective in reducing the volume, homogenizing, and furthermore stabilizing non-metallic wastes. (author)

Canadian experiences in characterizing two low-level and intermediate-level radioactive waste management sites

International Nuclear Information System (INIS)

Heystee, R.J.; Rao, P.K.M.

1984-02-01

Low-level waste (LLW) and intermediate-level reactor waste (ILW) arise in Canada from the operation of nuclear power reactors for the generation of electricity and from the operation of reactors for nuclear research and development as well as for the production of separated radioisotopes. The majority of this waste is currently being safely managed at two sites in the Province of Ontario: (1) Chalk River Nuclear Laboratories, and (2) Ontario Hydro's Bruce Nuclear Power Development Radioactive Waste Operations Site 2. Although these storage facilities can safely manage the waste for a long period of time, there are advantages in disposal of the LLW and ILW. The design of the disposal facilities and the assessment of long-term performance will require that the hydrologic and geologic data be gathered for a potential disposal site. Past site characterization programs at the two aforementioned waste storage sites have produced information which will be useful to future disposal studies in similar geologic materials. The assessment of long-term performance will require that predictions be made regarding the potential subsurface migration of radionuclides. However there still remain many uncertainties regarding the chemical and physical processes which affect radionuclide mobility and concentrations, in particular hydrodynamic dispersion, geochemical reactions, and transport through fractured media. These uncertainties have to be borne in mind when conducting the performance assessments and adequate conservatism must be included to account for the uncertainties. (author)

Environmental assessment for Sandia National Laboratories/New Mexico offsite transportation of low-level radioactive waste

International Nuclear Information System (INIS)

1996-09-01

Sandia National Laboratories, New Mexico (SNL/NM) is managed and operated by Sandia Corporation, a Lockheed Martin Company. SNL/NM is located on land owned by the U.S. Department of Energy (DOE) within the boundaries of the Kirtland Air Force Base (KAFB) in Albuquerque, New Mexico. The major responsibilities of SNL/NM are the support of national security and energy projects. Low-level radioactive waste (LLW) is generated by some of the activities performed at SNL/NM in support of the DOE. This report describes potential environmental effects of the shipments of low-level radioactive wastes to other sites

Alternative disposal options for alpha-mixed low-level waste

International Nuclear Information System (INIS)

Loomis, G.G.; Sherick, M.J.

1995-01-01

This paper presents several disposal options for the Department of Energy alpha-mixed low-level waste. The mixed nature of the waste favors thermally treating the waste to either an iron-enriched basalt or glass waste form, at which point a multitude of reasonable disposal options, including in-state disposal, are a possibility. Most notably, these waste forms will meet the land-ban restrictions. However, the thermal treatment of this waste involves considerable waste handling and complicated/expensive offgas systems with secondary waste management problems. In the United States, public perception of offgas systems in the radioactive incinerator area is unfavorable. The alternatives presented here are nonthermal in nature and involve homogenizing the waste with cryogenic techniques followed by complete encapsulation with a variety of chemical/grouting agents into retrievable waste forms. Once encapsulated, the waste forms are suitable for transport out of the state or for actual in-state disposal. This paper investigates variances that would have to be obtained and contrasts the alternative encapsulation idea with the thermal treatment option

Alternative disposal options for alpha-mixed low-level waste

Energy Technology Data Exchange (ETDEWEB)

Loomis, G.G.; Sherick, M.J. [Idaho National Engineering Lab., Idaho Falls, ID (United States)

1995-12-31

This paper presents several disposal options for the Department of Energy alpha-mixed low-level waste. The mixed nature of the waste favors thermally treating the waste to either an iron-enriched basalt or glass waste form, at which point a multitude of reasonable disposal options, including in-state disposal, are a possibility. Most notably, these waste forms will meet the land-ban restrictions. However, the thermal treatment of this waste involves considerable waste handling and complicated/expensive offgas, systems with secondary waste management problems. In the United States, public perception of off gas systems in the radioactive incinerator area is unfavorable. The alternatives presented here are nonthermal in nature and involve homogenizing the waste with cryogenic techniques followed by complete encapsulation with a variety of chemical/grouting agents into retrievable waste forms. Once encapsulated, the waste forms are suitable for transport out of the state or for actual in-state disposal. This paper investigates variances that would have to be obtained and contrasts the alternative encapsulation idea with the thermal treatment option.

Low-level waste institutional waste incinerator program

International Nuclear Information System (INIS)

Thompson, J.D.

1980-04-01

Literature surveyed indicated that institutional LLW is composed of organic solids and liquids, laboratory equipment and trash, and some pathological waste. Some toxic and hazardous chemicals are included in the variety of LLW generated in the nation's hospitals, universities, and research laboratories. Thus, the incinerator to be demonstrated in this program should be able to accept each of these types of materials as feedstock. Effluents from the DOE institutional incinerator demonstration should be such that all existing and proposed environmental standards be met. A design requirement was established to meet the most stringent flue gas standards. LLW incineration practice was reviewed in a survey of institutional LLW generators. Incinerator manufacturers were identified by the survey, and operational experience in incineration was noted for institutional users. Manufacturers identified in the survey were contacted and queried with regard to their ability to supply an incinerator with the desired capability. Special requirements for ash removal characteristics and hearth type were imposed on the selection. At the present time, an incinerator type, manufacturer, and model have been chosen for demonstration

The Legal and Policy Framework for Waste Disposition - Legal and policy framework for low level waste treatment and disposal

International Nuclear Information System (INIS)

Leech, Jonathan

2014-01-01

UK policy and strategy for the management of LLW has changed significantly in recent years, not least through development and implementation of the 'UK Strategy for the Management of Solid Low Level Radioactive Waste from the Nuclear Industry' as part of the UK Nuclear Decommissioning Authority's mission. This has influenced all aspects of LLW management in the UK, including metals recycling and VLLW disposal. The paper will outline the legal context for these changes in the UK and highlight how international conventions and legal frameworks have influenced these developments. In particular, the paper will look at the following important influences on choices for recycling and disposal of LLW and VLLW. - The Paris and Brussels Conventions on third party liabilities for nuclear damage; - on-going work to implement the 2004 Protocols to those conventions, including the impact on disposal sites and proposals to exclude VLLW disposal sites from liabilities regimes; - The Revised Waste Framework Directive and Waste Hierarchy; - Relevant European pollution prevention and control legislation and Best Available Techniques. (author)

Evaluation of alternatives to shallow land burial at the radioactive waste management complex

International Nuclear Information System (INIS)

Cerven, F.

1988-01-01

Alternative waste disposal technologies were reviewed relative to Nuclear Regulatory Commission (NRC) 10 CFR 61 low-level waste (LLW) disposal criteria and the emerging DOE 5820.2 Chapter 3 criteria. The intent of the review was to select a technology which would meet or improve upon the disposal practices set forth in these regulations and orders. The evaluation of the disposal technologies yielded a disposal design which incorporates three elements: an all earth cover, earth vaults for the Class A (1) bottom discharge cask inserts, and a concrete vault for the Class B and C (2 and 3) bulk waste

Screening of alternative methods for the disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

Macbeth, P.J.; Thamer, B.J.; Christensen, D.E.; Wehmann, G.

1978-10-01

A systematic method for categorizing these disposal alternatives which provides assurance that no viable alternatives are overlooked is reported. Alternatives are categorized by (1) the general media in which disposal occurs, (2) by whether the disposal method can be considered as dispersal, containment or elimination of the wastes, and (3) by the applicability of the disposal method to the possible physical waste forms. A literature survey was performed and pertinent references listed for the various alternatives discussed. A bibliography is given which provides coverage of published information on low-level radioactive waste management options. The extensive list of disposal alternatives identified was screened and the most viable choices were selected for further evaluation. A Technical Advisory Panel met and reviewed the results. Suggestions from that meeting and other comments are discussed. The most viable options selected for further evaluation are: (1) improving present shallow land burial practices; (2) deeper depth burial; (3) disposal in cavities; (4) disposal in exposed or buried structures; and (5) ocean disposal. 42 references

Development of DUST: A computer code that calculates release rates from a LLW disposal unit

International Nuclear Information System (INIS)

Sullivan, T.M.

1992-01-01

Performance assessment of a Low-Level Waste (LLW) disposal facility begins with an estimation of the rate at which radionuclides migrate out of the facility (i.e., the disposal unit source term). The major physical processes that influence the source term are water flow, container degradation, waste form leaching, and radionuclide transport. A computer code, DUST (Disposal Unit Source Term) has been developed which incorporates these processes in a unified manner. The DUST code improves upon existing codes as it has the capability to model multiple container failure times, multiple waste form release properties, and radionuclide specific transport properties. Verification studies performed on the code are discussed

Evaluation of alternative methods for the disposal of low-level radioactive wastes

International Nuclear Information System (INIS)

Macbeth, P.; Wehmann, G.; Thamer, B.J.; Card, D.H.

1979-07-01

A comparative analysis of the most viable alternatives for disposal of solid low-level radioactive wastes is presented to aid in evaluating national waste management options. Four basic alternative methods are analyzed and compared to the present practice of shallow land burial. These include deeper burial, disposal in mined cavities, disposal in engineered structures, and disposal in the oceans. Some variations in the basic methods are also presented. Technical, socio-political, and economic factors are assigened relative importances (weights) and evaluated for the various alternatives. Based on disposal of a constant volume of waste with given nuclear characteristics, the most desirable alternatives to shallow land burial in descending order of desirability appear to be: improving present practices, deeper burial, use of acceptable abandoned mines, new mines, ocean dumping, and structural disposal concepts. It must be emphasized that the evaluations reported here are generic, and use of other weights or different values for specific sites could change the conclusions and ordering of alternatives determined in this study. Impacts and costs associated with transportation over long distances predominate over differences among alternatives, indicating the desireability of establishing regional waste disposal locations. The impacts presented are for generic comparisons among alternatives, and are not intended to be predictive of the performance of any actual waste disposal facility

Quality assurance guidance for low-level radioactive waste disposal facility: Final report

International Nuclear Information System (INIS)

Pittiglio, C.L. Jr.

1989-01-01

This document provides guidance to an applicant on meeting the quality control (QC) requirements for a low-level waste (LLW) disposal facility. The QC requirements are the basis for developing of a quality assurance (QA) program and for the guidance provided herein. The criteria are basic to any QA program. The document specifically establishes QA guidance for the design, construction, and operation of those structures, systems, components, as well as, for site characterization activities necessary to meet the performance objectives and to limit exposure to our release of radioactivity. 7 refs

Operational readiness review of the Low Level Waste vaults at Savannah River Site: A case study

International Nuclear Information System (INIS)

Ahmad, M.; McVay, C.; Venkatesh, S.

1994-01-01

Low Level radioactive Waste (LLW) at the Savannah River Site at Aiken, South Carolina, has traditionally been disposed of using engineered trenches in accordance with the guidelines and technology existing at the time. Recently, subgrade concrete vaults known as E-Area Vaults (EAV) have been constructed at SRS. The EAV project is a comprehensive effort for upgrading LLW disposal at SRS based on meeting the requirements of current Department of Energy (DOE) Orders, and addressing more stringent federal and state regulations. The EAV is a first of its kind state-of-the-art facility designed and built in the United States to receive LLW. Westinghouse Savannah River Company (WSRC) conducted an Operational Readiness Review (ORR) of the vaults prior to startup. The objective of the EAV ORR was to perform a comprehensive review of the operational readiness of the facilities per DOE guidelines including Defense Nuclear Facilities Safety Board (DNFSB) recommendations. This review included assessing construction of the vaults as per design, adequate approved procedures, and training of all the personnel associated with the facility operations. EAV ORR incorporated the lessons learned from other DOE ORRs, included DNFSB recommendations, used a graded approach, and utilized subject matter experts for each functional area of assessment

Groundwater monitoring in the Savannah River Plant Low Level Waste Burial Ground

Energy Technology Data Exchange (ETDEWEB)

Carlton, W.H.

1983-12-31

This document describes chemical mechanisms that may affect trace-level radionuclide migration through acidic sandy clay soils in a humid environment, and summarizes the extensive chemical and radiochemical analyses of the groundwater directly below the SRP Low-Level Waste (LLW) Burial Ground (643-G). Anomalies were identified in the chemistry of individual wells which appear to be related to small amounts of fission product activity that have reached the water table. The chemical properties which were statistically related to trace level transport of Cs-137 and Sr-90 were iron, potassium, sodium and calcium. Concentrations on the order of 100 ppM appear sufficient to affect nuclide migration. Several complexation mechanisms for plutonium migration were investigated.

Joint US Geological Survey, US Nuclear Regulatory Commission workshop on research related to low-level radioactive waste disposal, May 4-6, 1993, National Center, Reston, Virginia; Proceedings

Science.gov (United States)

Stevens, Peter R.; Nicholson, Thomas J.

1996-01-01

This report contains papers presented at the "Joint U.S. Geological Survey (USGS) and U.S. Nuclear Regulatory Commission (NRC) Technical Workshop on Research Related to Low-Level Radioactive Waste (LLW) Disposal" that was held at the USGS National Center Auditorium, Reston, Virginia, May 4-6, 1993. The objective of the workshop was to provide a forum for exchange of information, ideas, and technology in the geosciences dealing with LLW disposal. This workshop was the first joint activity under the Memorandum of Understanding between the USGS and NRC's Office of Nuclear Regulatory Research signed in April 1992.Participants included invited speakers from the USGS, NRC technical contractors (U.S. Department of Energy (DOE) National Laboratories and universities) and NRC staff for presentation of research study results related to LLW disposal. Also in attendance were scientists from the DOE, DOE National Laboratories, the U.S. Environmental Protection Agency, State developmental and regulatory agencies involved in LLW disposal facility siting and licensing, Atomic Energy Canada Limited (AECL), private industry, Agricultural Research Service, universities, USGS and NRC.

Treatment methods for radioactive mixed wastes in commercial low-level wastes - technical considerations

International Nuclear Information System (INIS)

MacKenzie, D.R.; Kempf, C.R.

1986-01-01

Treatment options for the management of three generic categories of radioactive mixed waste in commercial low-level wastes (LLW) have been identified and evaluated. These wastes were characterized as part of a BNL study in which LLW generators were surveyed for information on potential chemical hazards in their wastes. The general treatment options available for mixed wastes are destruction, immobilization, and reclamation. Solidification, absorption, incineration, acid digestion, wet-air oxidation, distillation, liquid-liquid solvent extraction, and specific chemical destruction techniques have been considered for organic liquid wastes. Containment, segregation, decontamination, and solidification or containment of residues, have been considered for lead metal wastes which have themselves been contaminated and are not used for purposes of waste disposal shielding, packaging, or containment. For chromium-containing wastes, solidification, incineration, wet-air oxidation, acid digestion, and containment have been considered. Fore each of these wastes, the management option evaluation has included an assessment of testing appropriate to determine the effect of the option on both the radiological and potential chemical hazards present

Issues and Recommendations Arising from the Idaho National Laboratory Remote-Handled Low-Level Waste Disposal Facility Composite Analysis - 13374

Energy Technology Data Exchange (ETDEWEB)

Rood, Arthur S.; Schafer, Annette L.; Sondrup, A. Jeff [Idaho National Laboratory, Battelle Energy Alliance, P.O. Box 1625, Idaho Falls, ID 83401-2107 (United States)

2013-07-01

Development of the composite analysis (CA) for the Idaho National Laboratory's (INLs) proposed remote-handled (RH) low-level waste (LLW) disposal facility has underscored the importance of consistency between analyses conducted for site-specific performance assessments (PAs) for LLW disposal facilities, sites regulated by the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) [1], and residual decontamination and decommissioning (D and D) inventories. Consistency is difficult to achieve because: 1) different legacy sources and compliance time-periods were deemed important for each of the sites evaluated at INL (e.g., 100 years for CERCLA regulated facilities vs. 1,000 years for LLW disposal facilities regulated under U.S. Department of Energy (DOE) Order 435.1 [2]); 2) fate and transport assumptions, parameters, and models have evolved through time at the INL including the use of screening-level parameters vs. site-specific values; and 3) evaluation objectives for the various CERCLA sites were inconsistent with those relevant to either the PA or CA including the assessment of risk rather than effective dose. The proposed single site-wide CA approach would provide needed consistency, allowing ready incorporation of new information and/or facilities in addition to being cost effective in terms of preparation of CAs and review by the DOE. A single site-wide CA would include a central database of all existing INL sources, including those from currently operating LLW facilities, D and D activities, and those from the sites evaluated under CERCLA. The framework presented for the INL RH-LLW disposal facility allows for development of a single CA encompassing air and groundwater impacts. For groundwater impacts, a site-wide MODFLOW/MT3D-MS model was used to develop unit-response functions for all potential sources providing responses for a grid of receptors. Convolution and superposition of the response functions are used to compute

Results of interagency effort to determine carbon-14 source term in low-level radioactive waste

International Nuclear Information System (INIS)

Gruhlke, J.M.; Meyer, G.L.; Neiheisel, J.

1987-01-01

A preliminary estimate of the risks from the shallow land disposal of low-level radioactive wastes by EPA in 1984-1985 indicated that Carbon-14 caused virtually all of the risk and that these risks were relatively high. Therefore, an informal interagency group, which included the US Department of Energy, US Geological Survey, US Nuclear Regulatory Commission, and US Environmental Protection Agency, formed in 1985 to obtain up-to-date information on the activity and chemical form of Carbon-14 in the different types of LLW and how Carbon-14 behaves after disposal. The EPA acted as a focal point for collating the information collected by all of the Agencies and will publish a report in Fall 1986 on the results of the Carbon-14 data collection effort. Of particular importance, the study showed that Carbon-14 activity in LLW was overestimated approximately 2000%. This paper summarizes results of the Carbon-14 data collection effort. 40 references, 1 figure, 3 tables

The Potential for Criticality Following Disposal of Uranium at Low-Level-Waste Facilities. Containerized Disposal

International Nuclear Information System (INIS)

Colten-Bradley, V.A.; Hopper, C.M.; Parks, C.V.; Toran, L.E.

1999-01-01

The purpose of this study was to evaluate whether or not fissile uranium in low-level-waste (LLW) facilities can be concentrated by hydrogeochemical processes to permit nuclear criticality. A team of experts in hydrology, geology, geochemistry, soil chemistry, and criticality safety was formed to develop and test some reasonable scenarios for hydrogeochemical increases in concentration of special nuclear material (SNM) and to use these scenarios to aid in evaluating the potential for nuclear criticality. The team's approach was to perform simultaneous hydrogeochemical and nuclear criticality studies to (1) identify some possible scenarios for uranium migration and concentration increase at LLW disposal facilities, (2) model groundwater transport and subsequent concentration increase via precipitation of uranium, and (3) evaluate the potential for nuclear criticality resulting from potential increase in uranium concentration over disposal limits. The analysis of SNM was restricted to 235 U in the present scope of work. The work documented in this report indicates that the potential for a criticality safety concern to arise in an LLW facility is extremely remote, but not impossible. Theoretically, conditions that lead to a potential criticality safety concern might arise. However, study of the hydrogeochemical mechanisms, the associated time frames, and the factors required for an actual criticality event indicate that proper emplacement of the SNM at the site can eliminate practical concerns relative to the occurrence and possible consequences of a criticality event

Assessment of concentration limit for the safe disposal of very low level wastes

International Nuclear Information System (INIS)

Nam, Yun Seog

2008-02-01

The large amounts of radionuclides are generated from the decommissioning of nuclear facilities (included the nuclear power plant). Because of this, countries or agencies using the nuclear power are one of considering issues for the effective disposal. Among decommissioning wastes, wastes have no or very limited radioactivity are disposed of in conventional landfill or recycled thought approval from regulatory control. And wastes like LILW (Low and Intermediate Level Wastes) or HLW (High Level Wastes) are sent the repository or the interim storage facilities. In order to solve the space problem of the LILW repository and reduce disposal costs, some LLW which are relatively lower than other LLW are classified as VLLW (Very Low Level Wastes). IAEA is added to the VLLW category of the radioactive waste classification and some countries are operating a VLLW disposal facility or will be operating. In this study, the VLLW acceptance criteria of each radionuclide are derived by considering the inadvertent human intrusion scenario applying to a study on the near-surface disposal (LILW). The effect of important parameter, especially, waste isolation period, dilution factor and food consumption rate, is considered. It is concluded that the concentration limits of radionuclides considering in this study are evaluated approximately between 1 and 100 Bq/g. These values are similar to the case of France and Spain and the IAEA's predicted values. Based on this study, acceptance criteria of VLLW disposal facilities are suggested. And this study is contributed to the public relations for the safety of the VLLW disposal facility

Operational Strategies for Low-Level Radioactive Waste Disposal Site in Egypt - 13513

International Nuclear Information System (INIS)

Mohamed, Yasser T.

2013-01-01

The ultimate aims of treatment and conditioning is to prepare waste for disposal by ensuring that the waste will meet the waste acceptance criteria of a disposal facility. Hence the purpose of low-level waste disposal is to isolate the waste from both people and the environment. The radioactive particles in low-level waste emit the same types of radiation that everyone receives from nature. Most low-level waste fades away to natural background levels of radioactivity in months or years. Virtually all of it diminishes to natural levels in less than 300 years. In Egypt, The Hot Laboratories and Waste Management Center has been established since 1983, as a waste management facility for LLW and ILW and the disposal site licensed for preoperational in 2005. The site accepts the low level waste generated on site and off site and unwanted radioactive sealed sources with half-life less than 30 years for disposal and all types of sources for interim storage prior to the final disposal. Operational requirements at the low-level (LLRW) disposal site are listed in the National Center for Nuclear Safety and Radiation Control NCNSRC guidelines. Additional procedures are listed in the Low-Level Radioactive Waste Disposal Facility Standards Manual. The following describes the current operations at the LLRW disposal site. (authors)

Final Design Report for the RH LLW Disposal Facility (RDF) Project, Revision 3

International Nuclear Information System (INIS)

Austad, Stephanie Lee

2015-01-01

The RH LLW Disposal Facility (RDF) Project was designed by AREVA Federal Services (AFS) and the design process was managed by Battelle Energy Alliance (BEA) for the Department of Energy (DOE). The final design report for the RH LLW Disposal Facility Project is a compilation of the documents and deliverables included in the facility final design.

Trends of radioactive waste management policy and disposal of LLW/ILW in the UK

International Nuclear Information System (INIS)

Miyasaka, Yasuhiko

2003-01-01

In 1997, the UK program for the deep disposal of radioactive waste was stopped with the refusal by the Secretary of State for the Environment to allow Nuclear Industry Radioactive Waste Executive, Ltd. (Nirex) to go ahead with its plans for an underground Rock Characterization Facility (RCF) at Sellafield, seen as the precursor of an underground repository for LLW/ILW. Department of Environment, Food and Rural Affairs (DEFRA) and the Developed Administrations published a white paper 'Managing Radioactive Waste Safety' Proposal for developing a policy for managing solid radioactive waste in the UK on 12 September 2001. The paper set out five-stage program of action for reaching decisions until 2007. It suggests their view can be sought via opinion polls, the Internet, workshops, citizens, juries, consensus conferences, stakeholder, local authority and community groups and research panels. With the exception of a disposal facility associated with the operation of the Dounreay site on the north coast of Scotland, essentially all LLW in the UK is disposed of at the Drigg site, near Sellafield. The site has been in operation since 1959. Until 1988, disposals were solely in trenches, cut into the glacial tills underlying the site. In 1988, an engineered concrete vault was brought into operation and is currently in use. Drigg only has a finite capacity in the currently area and may be full by about 2050, hence new arrangements will have to examine. This report describes the trends of radioactive waste management policy and disposal of LLW/ILW in the UK. These include: NDA(Nuclear Decommissioning Authority) organization plan, Feb. 2003; Encapsulation of LLW/ILW and safe store for ILW; Summary of LLW repository at the Drigg site; Nirex concept for underground storage/disposal of LLW/ILW. This information and new approach of the safe management of radioactive waste in the UK will prove helpful to the planning for future management and disposal of LLW in Japan. (author)

On-Site Decontamination System for Liquid Low Level Radioactive Waste - 13010

Energy Technology Data Exchange (ETDEWEB)

OSMANLIOGLU, Ahmet Erdal [Cekmece Nuclear Research and Training Center, Kucukcekmece Istanbul (Turkey)

2013-07-01

This study is based on an evaluation of purification methods for liquid low-level radioactive waste (LLLW) by using natural zeolite. Generally the volume of liquid low-level waste is relatively large and the specific activity is rather low when compared to other radioactive waste types. In this study, a pilot scale column was used with natural zeolite as an ion exchanger media. Decontamination and minimization of LLLW especially at the generation site decrease operational cost in waste management operations. Portable pilot scale column was constructed for decontamination of LLW on site. Effect of temperature on the radionuclide adsorption of the zeolite was determined to optimize the waste solution temperature for the plant scale operations. In addition, effect of pH on the radionuclide uptake of the zeolite column was determined to optimize the waste solution pH for the plant scale operations. The advantages of this method used for the processing of LLLW are discussed in this paper. (authors)

Hydrologic evaluation methodology for estimating water movement through the unsaturated zone at commercial low-level radioactive waste disposal sites

Energy Technology Data Exchange (ETDEWEB)

Meyer, P.D.; Rockhold, M.L.; Nichols, W.E.; Gee, G.W. [Pacific Northwest Lab., Richland, WA (United States)

1996-01-01

This report identifies key technical issues related to hydrologic assessment of water flow in the unsaturated zone at low-level radioactive waste (LLW) disposal facilities. In addition, a methodology for incorporating these issues in the performance assessment of proposed LLW disposal facilities is identified and evaluated. The issues discussed fall into four areas: estimating the water balance at a site (i.e., infiltration, runoff, water storage, evapotranspiration, and recharge); analyzing the hydrologic performance of engineered components of a facility; evaluating the application of models to the prediction of facility performance; and estimating the uncertainty in predicted facility performance. To illustrate the application of the methodology, two examples are presented. The first example is of a below ground vault located in a humid environment. The second example looks at a shallow land burial facility located in an arid environment. The examples utilize actual site-specific data and realistic facility designs. The two examples illustrate the issues unique to humid and arid sites as well as the issues common to all LLW sites. Strategies for addressing the analytical difficulties arising in any complex hydrologic evaluation of the unsaturated zone are demonstrated.

Hydrologic evaluation methodology for estimating water movement through the unsaturated zone at commercial low-level radioactive waste disposal sites

International Nuclear Information System (INIS)

Meyer, P.D.; Rockhold, M.L.; Nichols, W.E.; Gee, G.W.

1996-01-01

This report identifies key technical issues related to hydrologic assessment of water flow in the unsaturated zone at low-level radioactive waste (LLW) disposal facilities. In addition, a methodology for incorporating these issues in the performance assessment of proposed LLW disposal facilities is identified and evaluated. The issues discussed fall into four areas: estimating the water balance at a site (i.e., infiltration, runoff, water storage, evapotranspiration, and recharge); analyzing the hydrologic performance of engineered components of a facility; evaluating the application of models to the prediction of facility performance; and estimating the uncertainty in predicted facility performance. To illustrate the application of the methodology, two examples are presented. The first example is of a below ground vault located in a humid environment. The second example looks at a shallow land burial facility located in an arid environment. The examples utilize actual site-specific data and realistic facility designs. The two examples illustrate the issues unique to humid and arid sites as well as the issues common to all LLW sites. Strategies for addressing the analytical difficulties arising in any complex hydrologic evaluation of the unsaturated zone are demonstrated

40 Years of Experience of NIRAS / Belgoprocess on the Interim Storage of Low, Intermediate and High Level Waste

International Nuclear Information System (INIS)

Braeckeveldt, Marnix; Ghys, Bart

2016-01-01

Conclusion: • ONDRAF/NIRAS and Belgoprocess have gained over time an extended experience on the interim storage of Low-Intermediate and High level waste. • An systematic inspection strategy was developed in order the verify the conformity of the different waste-packages and corrective measures were taken to guarantee safe storage conditions. • From 2022 , ONDRAF/NIRAS will operate a surface disposal facility for LLW

Characterization of low-level waste from the industrial sector, and near-term projection of waste volumes and types

International Nuclear Information System (INIS)

MacKenzie, D.R.

1988-01-01

A telephone survey of low-level waste generators has been carried out in order to make useful estimates of the volume and nature of the waste which the generators will be shipping for disposal when the compacts and states begin operating new disposal facilities. Emphasis of the survey was on the industrial sector, since there has been little information available on characteristics of industrial LLW. Ten large industrial generators shipping to Richland, ten shipping to Barnwell, and two whose wastes had previously been characterized by BNL were contacted. The waste volume shipped by these generators accounted for about two-thirds to three-quarters of the total industrial volume. Results are given in terms of the categories of LLW represented and of the chemical characteristics of the different wastes. Estimates by the respondents of their near-term waste volume projections are presented

Characterization of low-level waste from the industrial sector, and near-term projection of waste volumes and types

International Nuclear Information System (INIS)

MacKenzie, D.R.

1988-01-01

A telephone survey of low-level waste generators has been carried out in order to make useful estimates of the volume and nature of the waste which the generators are shipping for disposal when the compacts and states begin operating new disposal facilities. Emphasis of the survey was on the industrial sector, since there has been little information available on characteristics of industrial LLW. Ten large industrial generators shipping to Richland, ten shipping to Barnwell, and two whose wastes had previously been characterized by BNL were contacted. The waste volume shipped by these generators accounted for about two-thirds to three-quarters of the total industrial volume. Results are given in terms of the categories of LLW represented and of the chemical characteristics of the different wastes. Estimates by the respondents of their near-term waste volume projections are presented

Licensing of alternative methods of disposal of low-level radioactive waste: Branch technical position, Low-Level Waste Licensing Branch

International Nuclear Information System (INIS)

Higginbotham, L.B.; Dragonette, K.S.; Pittiglio, C.L. Jr.

1986-12-01

This branch technical position statement identifies and describes specific methods of disposal currently being considered as alternatives to shallow land burial, provides general guidance on these methods of disposal, and recommends procedures that will improve and simplify the licensing process. The statement provides answers to certain questions that have arisen regarding the applicability of 10 CFR 61 to near-surface disposal of waste, using methods that incorporate engineered barriers or structures, and other alternatives to conventional shallow land burial disposal practices. This position also identifies a recently published NRC contractor report that addresses the applicability of 10 CFR 61 to a range of generic disposal concepts and which provides technical guidance that the staff intends to use for these concepts. This position statement combined with the above-mentioned NRC contractor report fulfills the requirements of Section 8(a) of Public Law 99-240, the Low-Level Radioactive Waste Policy Amendments Act of 1985

Test Plan: Phase 1 demonstration of 3-phase electric arc melting furnace technology for vitrifying high-sodium content low-level radioactive liquid wastes

Energy Technology Data Exchange (ETDEWEB)

Eaton, W.C. [ed.

1995-05-31

This document provides a test plan for the conduct of electric arc vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384216] is the US Bureau of Mines, Department of the Interior, Albany Research Center, Albany, Oregon. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes feed preparation activities and melting of glass with Hanford LLW Double-Shell Slurry Feed waste simulant in a 3-phase electric arc (carbon electrode) furnace.

Test Plan: Phase 1 demonstration of 3-phase electric arc melting furnace technology for vitrifying high-sodium content low-level radioactive liquid wastes

International Nuclear Information System (INIS)

Eaton, W.C.

1995-01-01

This document provides a test plan for the conduct of electric arc vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384216] is the US Bureau of Mines, Department of the Interior, Albany Research Center, Albany, Oregon. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes feed preparation activities and melting of glass with Hanford LLW Double-Shell Slurry Feed waste simulant in a 3-phase electric arc (carbon electrode) furnace

Nevada test site low-level and mixed waste repository design in the unsaturated zone

International Nuclear Information System (INIS)

Kawamura, T.A.; Warren, D.M.

1989-01-01

The Area 5 Radioactive Waste Management Site (RWMS) at the Nevada Test Site (NTS) is used for shallow land disposal of Low-Level Radioactive (LLW) and for retrievable disposal of Mixed Wastes (MW) from various Department of Energy (DOE) facilities. The site is situated in southern Nevada, one of the most arid regions of the United States. Design considerations include vadose zone monitoring in lieu of groundwater monitoring, stringent waste acceptance and packaging criteria, a waste examination and real-time radiography facility, and trench design. 4 refs

Model tracking system for low-level radioactive waste disposal facilities: License application interrogatories and responses

Energy Technology Data Exchange (ETDEWEB)

Benbennick, M.E.; Broton, M.S.; Fuoto, J.S.; Novgrod, R.L.

1994-08-01

This report describes a model tracking system for a low-level radioactive waste (LLW) disposal facility license application. In particular, the model tracks interrogatories (questions, requests for information, comments) and responses. A set of requirements and desired features for the model tracking system was developed, including required structure and computer screens. Nine tracking systems were then reviewed against the model system requirements and only two were found to meet all requirements. Using Kepner-Tregoe decision analysis, a model tracking system was selected.

Model tracking system for low-level radioactive waste disposal facilities: License application interrogatories and responses

International Nuclear Information System (INIS)

Benbennick, M.E.; Broton, M.S.; Fuoto, J.S.; Novgrod, R.L.

1994-08-01

This report describes a model tracking system for a low-level radioactive waste (LLW) disposal facility license application. In particular, the model tracks interrogatories (questions, requests for information, comments) and responses. A set of requirements and desired features for the model tracking system was developed, including required structure and computer screens. Nine tracking systems were then reviewed against the model system requirements and only two were found to meet all requirements. Using Kepner-Tregoe decision analysis, a model tracking system was selected

Low Level Waste Disposal Geological Studies At Inshas Site. Vol. 3

Energy Technology Data Exchange (ETDEWEB)

Al-Gamal, S A; Emara, A S [National Center for Nuclear Safety and Radiation Control, Nasr City, Atomic Energy Authority, Cairo (Egypt); Shehata, M G [Petroleum Research Institute, Nasr City, Al-Zohour District, Cairo (Egypt)

1996-03-01

The general potential of some selected layers such as the Miocene sediments and the Oligocene basalts is evaluated for the disposal of low level waste, (LLW). In this work, it is aimed to quantify the effect of some key parameters that are though to influence the migration of radionuclides in these layers. Homogeneity-isotopy and engineering properties of selected potential layers at Inshas were examined. Land form stability and collapsible soil were studied. Basaltic lava flows of Oligocene age were thoroughly investigated using petrographic and petrologic techniques and its suitability as a potential host rock for a waste repository is evaluated. 8 figs., 2 tabs.

Commercial processing and disposal alternatives for very low levels of radioactive waste in the United States

International Nuclear Information System (INIS)

Benda, G.A.

2005-01-01

The United States has several options available in the commercial processing and disposal of very low levels of radioactive waste. These range from NRC licensed low level radioactive sites for Class A, B and C waste to conditional disposal or free release of very low concentrations of material. Throughout the development of disposal alternatives, the US promoted a graded disposal approach based on risk of the material hazards. The US still promotes this approach and is renewing the emphasis on risk based disposal for very low levels of radioactive waste. One state in the US, Tennessee, has had a long and successful history of disposal of very low levels of radioactive material. This paper describes that approach and the continuing commercial options for safe, long term processing and disposal. (author)

Test plan for evaluation of plasma melter technology for vitrification of high-sodium content low-level radioactive liquid wastes

International Nuclear Information System (INIS)

McLaughlin, D.F.; Lahoda, E.J.; Gass, W.R.; D'Amico, N.

1994-01-01

This document provides a test plan for the conduct of plasma arc vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384212] is the Westinghouse Science and Technology Center (WSTC) in Pittsburgh, PA. WSTC authors of the test plan are D. F. McLaughlin, E. J. Lahoda, W. R. Gass, and N. D'Amico. The WSTC Program Manager for this test is D. F. McLaughlin. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes melting of glass frit with Hanford LLW Double-Shell Slurry Feed waste simulant in a plasma arc fired furnace

Low-level tank waste simulant data base

International Nuclear Information System (INIS)

Lokken, R.O.

1996-04-01

The majority of defense wastes generated from reprocessing spent N- Reactor fuel at Hanford are stored in underground Double-shell Tanks (DST) and in older Single-Shell Tanks (SST) in the form of liquids, slurries, sludges, and salt cakes. The tank waste remediation System (TWRS) Program has the responsibility of safely managing and immobilizing these tank wastes for disposal. This report discusses three principle topics: the need for and basis for selecting target or reference LLW simulants, tanks waste analyses and simulants that have been defined, developed, and used for the GDP and activities in support of preparing and characterizing simulants for the current LLW vitrification project. The procedures and the data that were generated to characterized the LLW vitrification simulants were reported and are presented in this report. The final section of this report addresses the applicability of the data to the current program and presents recommendations for additional data needs including characterization and simulant compositional variability studies

Geochemical factors affecting radionuclide transport through near and far fields at a Low-Level Waste Disposal Site

International Nuclear Information System (INIS)

Kaplan, D.I.; Seme, R.J.; Piepkho, M.G.

1995-03-01

The concentration of low-level waste (LLW) contaminants in groundwater is determined by the amount of contaminant present in the solid waste, rate of release from the waste and surrounding barriers, and a number of geochemical processes including adsorption, desorption, diffusion, precipitation, and dissolution. To accurately predict radionuclide transport through the subsurface, it is essential that the important geochemical processes affecting radionuclide transport be identified and, perhaps more importantly, accurately quantified and described in a mathematically defensible manner

What will we do with the low level waste from reactor decommissioning?

International Nuclear Information System (INIS)

Meehan, A. R.; Wilmott, S.; Crockett, G.; Watt, N. R.

2008-01-01

The decommissioning of the UK's Magnox reactor sites will produce large volumes of low level waste (LLW) arisings. The vast majority of this waste takes the form of concrete, building rubble and redundant plant containing relatively low levels of radioactivity. Magnox Electric Ltd (Magnox) is leading a strategic initiative funded by the Nuclear Decommissioning Authority (NDA) to explore opportunities for the disposal of such waste to suitably engineered facilities that might be located on or adjacent to the site of waste arising, if appropriate and subject to regulatory acceptance and stakeholder views. The strategic issues surrounding this initiative are described along with an update of progress with stakeholder consultations in relation to the proposed licensing of the first such facility at Hinkley Point A, which could be viewed as a test case for the development of similar disposal facilities at other nuclear sites in England and Wales. (authors)

An evaluation on the disposal alternatives for low- and intermediate- level radwaste (II)

International Nuclear Information System (INIS)

Park, Hun Hwee; Han, Kyung Won; Hahn, Pil Soo; Lee, Han Soo; Cho, Won Jin; Lee, Jae Dwan; Park, Chung Kyun; Lee, Myung Joo; Choi, Heui Joo; Lee, Youn Myoung

1988-02-01

An evaluation on the radioactive waste disposal alternatives for the low-and intermediate level wastes being produced from nuclear power generation and radioisotope application was carried out in view of the radiological safety, socio-political aspects and repository construction economics. Three types of possible alternatives-sample shallow land disposal method, engineered shallow land disposal method and engineered rock cavern disposal method are investigated. The safety assessment consists of radiological dose calculation and nonradiological impacts which is expressed as total number of injuries and fatalities during construction, operation and transportation. The sociopolitical assessment is done in terms of site conditions including easiness for land acquisition, technical feasibility and public acceptance. The economic assessment is performed by cost comparison regarding land acquisition, construction, operation and closure for each alternatives. The evaluation shows that engineered rock cavern disposal method has remarkable favour in safety than others. And also an integrated evaluation using AHP results the engineered rock cavern disposal method as the most favorable option

Greater-than-Class C low-level radioactive waste shipping package/container identification and requirements study

International Nuclear Information System (INIS)

Tyacke, M.

1993-08-01

This report identifies a variety of shipping packages (also referred to as casks) and waste containers currently available or being developed that could be used for greater-than-Class C (GTCC) low-level waste (LLW). Since GTCC LLW varies greatly in size, shape, and activity levels, the casks and waste containers that could be used range in size from small, to accommodate a single sealed radiation source, to very large-capacity casks/canisters used to transport or dry-store highly radioactive spent fuel. In some cases, the waste containers may serve directly as shipping packages, while in other cases, the containers would need to be placed in a transport cask. For the purpose of this report, it is assumed that the generator is responsible for transporting the waste to a Department of Energy (DOE) storage, treatment, or disposal facility. Unless DOE establishes specific acceptance criteria, the receiving facility would need the capability to accept any of the casks and waste containers identified in this report. In identifying potential casks and waste containers, no consideration was given to their adequacy relative to handling, storage, treatment, and disposal. Those considerations must be addressed separately as the capabilities of the receiving facility and the handling requirements and operations are better understood

Environmental assessment for DOE permission for the off-loading and transportation of commercial low-level radioactive waste across the Savannah River Site

International Nuclear Information System (INIS)

1997-10-01

The Department of Energy (DOE) prepared this Environmental Assessment (EA) to assess the potential environmental impacts associated with DOE allowing Chem-Nuclear Systems, L.L.C. (CNS) to off-load and transport low-level radioactive waste (LLW) packages across the Savannah River Site (SRS), located near Aiken, South Carolina, to the nearby CNS facility. The proposed action entails DOE granting permission to CNS to use SRS for landing shipping barges at the existing SRS boat ramp and off-loading trailered LLW packages for transportation across SRS to the CNS facility. Project activities would include modification of the SRS boat ramp on the Savannah River, as needed for off-loading activities, and construction of a bridge across Lower Three Runs. The proposed action also encompasses any similar future off-loading and transportation activities for LLW en route to the CNS facility. The National Environmental Policy Act requires the assessment of environmental consequences of Federal actions that may affect the quality of the human environment. Based on the potential for impacts described herein, DOE will either publish a Finding of No Significant Impact or prepare an Environmental Impact Statement (EIS)

Eleventh annual Department of Energy low-level waste management conference. Volume 2: Low-level waste strategy and planning, decontamination and decommissioning, compliance monitoring

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-11-01

Nineteen papers are presented in volume 2. The 11 papers in the LLW Strategy and Planning section discuss plans for disposal facilities in Texas, Pennsylvania, Hanford, the Southwest and Southeast Compacts, and others. Three papers discuss decontamination technology and activities. Environmental monitoring requirements and recommendations at LLW facilities are discussed in 5 papers. Papers have been processed separately for inclusion on the data base.

Metal recycling experience at Los Alamos National Laboratory. Reuse, release, and recycle of metals from radiological control areas

International Nuclear Information System (INIS)

Gogol, S.

1997-01-01

Approximately 15% of the Low-Level Waste (LLW) produced at Los Alamos consists of scrap metal equipment and materials. The majority of this material is produced by decommissioning and the modification of existing facilities. To reduce this waste stream, Department of Energy Headquarters, EM-77 Office, sponsored the Reuse, Recycle, and Release of Metals from Radiological Control Areas High Return on Investment (ROI) Project to implement recycle, reuse, and release of scrap metal at the laboratory. The goal of this project was to develop cost effective alternatives to LLW disposal of scrap metal and to avoid the disposal of 2,400 m 3 of scrap metal. The ROI for this project was estimated at 948%. The ROI project was funded in March 1996 and is scheduled for completion by October 1997. At completion, a total of 2,400 m 3 of LLW avoidance will have been accomplished and a facility to continue recycling activities will be operational. This paper will present the approach used to develop effective alternatives for scrap metal at Los Alamos and then discuss the tasks identified in the approach in detail. Current scrap metal inventory, waste projections, alternatives to LLW disposal, regulatory guidance, and efforts to institutionalize the alternatives to LLW disposal will be discussed in detail

Who pays the bill: insuring against the risks from low level nuclear waste disposal

International Nuclear Information System (INIS)

Cohen, L.

1981-01-01

Long-range financial liability for low-level waste (LLW) activities is not currently assured. Part of the problem with finding an acceptable solution to liability has been a tendency to lump all long-term financial commitments, both risky and anticipated, together. It is suggested that only risks arising from unforeseen technical problems require special federal policies. Other long-term costs are more efficiently handled by traditional private insurance. Special policies are needed, however, for the unforeseen risks. The analysis concludes that state insurance of operators with federal reinsurance may be the most reasonable concept. Reinsurance levels should be set to balance federal information requirements, relative control of the three main parties over outcomes, and solvency requirements

Overview of low level waste disposal facility costs

International Nuclear Information System (INIS)

Saverot, P.M.

1995-01-01

Economics and uncertainty go hand-in-hand and it is too soon to have conclusive data on the life cycle costs of a disposal facility. While LLW volumes from are decreasing year after year, the effect of the projected LLW volumes from decommissioning may have a significant impact on the final unit costs. This overview recognizes that countries see LLW disposal costs differently depending on the scale of their programs and on the geographical, political and economic frameworks within which they operate. The reasons for the cost differences arise from a number of factors: differences in designs and in technologies (near surface engineered vault, enhanced shallow land burial, silo type caverns,...), disposal capacities, programmatic and regulatory requirements, organizational, managerial and institutional frameworks, contractual arrangements, etc. Comparison of actual project costs, if done incorrectly, can lead to invalid conclusions and little purpose would be served by so doing since cost variations reflect the reality faced by each country

Incineration systems for low level and mixed wastes

International Nuclear Information System (INIS)

Vavruska, J.

1986-01-01

A variety of technologies has emerged for incineration of combustible radioactive, hazardous, and mixed wastes. Evaluation and selection of an incineration system for a particular application from such a large field of options are often confusing. This paper presents several current incineration technologies applicable to Low Level Waste (LLW), hazardous waste, and mixed waste combustion treatment. The major technologies reviewed include controlled-air, rotary kiln, fluidized bed, and liquid injection. Coupled with any incineration technique is the need to select a compatible offgas effluent cleaning system. This paper also reviews the various methods of treating offgas emissions for acid vapor, particulates, organics, and radioactivity. Such effluent control systems include the two general types - wet and dry scrubbing with a closer look at quenching, inertial systems, fabric filtration, gas absorption, adsorption, and various other filtration techniques. Selection criteria for overall waste incineration systems are discussed as they relate to waste characterization

Preliminary Project Execution Plan for the Remote-Handled Low-Level Waste Disposal Project

Energy Technology Data Exchange (ETDEWEB)

David Duncan

2011-05-01

This preliminary project execution plan (PEP) defines U.S. Department of Energy (DOE) project objectives, roles and responsibilities of project participants, project organization, and controls to effectively manage acquisition of capital funds for construction of a proposed remote-handled low-level waste (LLW) disposal facility at the Idaho National Laboratory (INL). The plan addresses the policies, requirements, and critical decision (CD) responsibilities identified in DOE Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets.' This plan is intended to be a 'living document' that will be periodically updated as the project progresses through the CD process to construction and turnover for operation.

Preliminary Project Execution Plan for the Remote-Handled Low-Level Waste Disposal Project

International Nuclear Information System (INIS)

Duncan, David

2011-01-01

This preliminary project execution plan (PEP) defines U.S. Department of Energy (DOE) project objectives, roles and responsibilities of project participants, project organization, and controls to effectively manage acquisition of capital funds for construction of a proposed remote-handled low-level waste (LLW) disposal facility at the Idaho National Laboratory (INL). The plan addresses the policies, requirements, and critical decision (CD) responsibilities identified in DOE Order 413.3B, 'Program and Project Management for the Acquisition of Capital Assets.' This plan is intended to be a 'living document' that will be periodically updated as the project progresses through the CD process to construction and turnover for operation.

State of the art review of alternatives to shallow land burial of low level radioactive waste

International Nuclear Information System (INIS)

1980-04-01

A review of alternatives to shallow land burial for disposal of low level radioactive waste was conducted to assist ORNL in developing a program for the evaluation, selection, and demonstration of the most acceptable alternatives. The alternatives were categorized as follows: (1) near term isolation concepts, (2) far term isolation concepts, (3) dispersion concepts, and (4) conversion concepts. Detailed descriptions of near term isolation concepts are provided. The descriptions include: (1) method of isolation, (2) waste forms that can be accommodated, (3) advantages and disadvantages, (4) facility and equipment requirements, (5) unusual operational or maintenance requirements, (6) information/technology development requirements, and (7) related investigations of the concept

Transport system for low level radioactive wastes in Japan

International Nuclear Information System (INIS)

Tanaka, K.; Yoshida, K.; Sanui, T.

1993-01-01

Nuclear Fuel Transport Co. (NFT) is to take charge of LLW transportation from each nuclear power plants to the final repository consigned by 10 electric power companies in Japan. In order to transport LLW safely and efficiently, NFT has developed and prepared various hardware, such as special packaging, an exclusive use vessel, automatic cranes and so forth together with software to use them. The procedure of transport is also described. (J.P.N.)

EPRI'S low-level waste management R ampersand D program

International Nuclear Information System (INIS)

Hornibrook, C.

1997-01-01

The immediate challenges facing every organization today are to improve its productivity and increase customer satisfaction. The Electric Power Research Institute (EPRI) responded to this challenge by broadening the scope of its low-level waste (LLW) management program. EPRI offered utilities on-site assistance in evaluating and optimizing their liquid- and solid-waste management programs. The goal is to identify open-quotes cheaper, better, and easierclose quotes solutions, which are documented in a series of reports. These provide step-by-step evaluation processes and straightforward implementation methods. Utility professionals are provided with the necessary technical information and justification for informed waste management decisions. The resulting average annual savings is consistently in excess of $700,000 per facility. The program continues to grow and serves as a model for a number of existing and emerging EPRI programs

Radiochemical methodologies applied to analytical characterization of low and intermediate level wastes from nuclear power plants

International Nuclear Information System (INIS)

Monteiro, Roberto Pellacani G.; Júnior, Aluísio Souza R.; Kastner, Geraldo F.; Temba, Eliane S.C.; Oliveira, Thiago C. de; Amaral, Ângela M.; Franco, Milton B.

2017-01-01

The aim of this work is to present radiochemical methodologies developed at CDTN/CNEN in order to answer a program for isotopic inventory of radioactive wastes from Brazilian Nuclear Power Plants. In this program some radionuclides, 3 H, 14 C, 55 Fe, 59 Ni, 63 Ni, 90 Sr, 93 Zr, 94 Nb, 99 Tc, 129 I, 235 U, 238 U, 238 Pu, 239 + 240 Pu, 241 Pu, 242 Pu, 241 Am, 242 Cm e 243 + 244 Cm, were determined in Low Level Wastes (LLW) and Intermediate Level Wastes (ILW) and a protocol of analytical methodologies based on radiochemical separation steps and spectrometric and nuclear techniques was established. (author)

IMPROVEMENTS IN CONTAINER MANAGEMENT OF TRANSURANIC (TRU) AND LOW LEVEL RADIOACTIVE WASTE STORED AT THE CENTRAL WASTE COMPLEX (CWC) AT HANFORD

International Nuclear Information System (INIS)

UYTIOCO EM

2007-01-01

The Central Waste Complex (CWC) is the interim storage facility for Resource Conservation and Recovery Act (RCRA) mixed waste, transuranic waste, transuranic mixed waste, low-level and low-level mixed radioactive waste at the Department of Energy's (DOE'S) Hanford Site. The majority of the waste stored at the facility is retrieved from the low-level burial grounds in the 200 West Area at the Site, with minor quantities of newly generated waste from on-site and off-site waste generators. The CWC comprises 18 storage buildings that house 13,000 containers. Each waste container within the facility is scanned into its location by building, module, tier and position and the information is stored in a site-wide database. As waste is retrieved from the burial grounds, a preliminary non-destructive assay is performed to determine if the waste is transuranic (TRU) or low-level waste (LLW) and subsequently shipped to the CWC. In general, the TRU and LLW waste containers are stored in separate locations within the CWC, but the final disposition of each waste container is not known upon receipt. The final disposition of each waste container is determined by the appropriate program as process knowledge is applied and characterization data becomes available. Waste containers are stored within the CWC based on their physical chemical and radiological hazards. Further segregation within each building is done by container size (55-gallon, 85-gallon, Standard Waste Box) and waste stream. Due to this waste storage scheme, assembling waste containers for shipment out of the CWC has been time consuming and labor intensive. Qualitatively, the ratio of containers moved to containers in the outgoing shipment has been excessively high, which correlates to additional worker exposure, shipment delays, and operational inefficiencies. These inefficiencies impacted the LLW Program's ability to meet commitments established by the Tri-Party Agreement, an agreement between the State of Washington

Incremental Risks of Transporting NARM to the LLW Disposal Facility at Hanford

International Nuclear Information System (INIS)

Weiner, R.F.

1999-01-01

This study models the incremental radiological risk of transporting NARM to the Hanford commercial LLW facility, both for incident-free transportation and for possible transportation accidents, compared with the radiological risk of transporting LLW to that facility. Transportation routes are modeled using HIGHWAY 3.1 and risks are modeled using RADTRAN 4. Both annual population doses and risks, and annual average individual doses and risks are reported. Three routes to the Hanford site were modeled from Albany, OR, from Coeur d'Alene, ID (called the Spokane route), and from Seattle, WA. Conservative estimates are used in the RADTRAN inputs, and RADTRAN itself is conservative

Low-Level Waste Forum notes and summary reports for 1994. Volume 9, Number 3, May-June 1994

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-06-01

This issue includes the following articles: Vermont ratifies Texas compact; Pennsylvania study on rates of decay for classes of low-level radioactive waste; South Carolina legislature adjourns without extending access to Barnwell for out-of-region generators; Southeast Compact Commission authorizes payments for facility development, also votes on petitions, access contracts; storage of low-level radioactive waste at Rancho Seco removed from consideration; plutonium estimates for Ward Valley, California; judgment issued in Ward Valley lawsuits; Central Midwest Commission questions court`s jurisdiction over surcharge rebates litigation; Supreme Court decides commerce clause case involving solid waste; parties voluntarily dismiss Envirocare case; appellate court affirms dismissal of suit against Central Commission; LLW Forum mixed waste working group meets; US EPA Office of Radiation and Indoor Air rulemakings; EPA issues draft radiation site cleanup regulation; EPA extends mixed waste enforcement moratorium; and NRC denies petition to amend low-level radioactive waste classification regulations.

Low-Level Waste Forum notes and summary reports for 1994. Volume 9, Number 3, May-June 1994

International Nuclear Information System (INIS)

1994-06-01

This issue includes the following articles: Vermont ratifies Texas compact; Pennsylvania study on rates of decay for classes of low-level radioactive waste; South Carolina legislature adjourns without extending access to Barnwell for out-of-region generators; Southeast Compact Commission authorizes payments for facility development, also votes on petitions, access contracts; storage of low-level radioactive waste at Rancho Seco removed from consideration; plutonium estimates for Ward Valley, California; judgment issued in Ward Valley lawsuits; Central Midwest Commission questions court's jurisdiction over surcharge rebates litigation; Supreme Court decides commerce clause case involving solid waste; parties voluntarily dismiss Envirocare case; appellate court affirms dismissal of suit against Central Commission; LLW Forum mixed waste working group meets; US EPA Office of Radiation and Indoor Air rulemakings; EPA issues draft radiation site cleanup regulation; EPA extends mixed waste enforcement moratorium; and NRC denies petition to amend low-level radioactive waste classification regulations

Low-level radioactive waste from nuclear power generating stations: Characterization, classification and assessment of activated metals and waste streams

International Nuclear Information System (INIS)

Thomas, V.W.; Robertson, D.E.; Thomas, C.W.

1993-02-01

Since the enactment of 10 CFR Part 61, additional difficult-to-measure long-lived radionuclides, not specified in Tables 1 2 of Part 61, have been identified (e.g., 108m Ag, 93 Mo, 36 Cl, 10 Be, 113m Cd, 121m Sn, 126 Sn, 93m Nb) that may be of concern in certain types of waste. These nuclides are primarily associated with activated metal and perhaps other nuclear power low-level waste (LLW) being sent to disposal facilities. The concentration of a radionuclide in waste materials is normally determined by direct measurement or by indirect calculational methods, such as using a scaling factor to relate inferred concentration of a difficult-to-measure radionuclide to another that is easily measured. The total disposal site inventory of certain difficult-to-measure radionuclides (e.g., 14 C, 129 I, and 99 Tc) often control the total quantities of radioactive waste permitted in LLW burial facilities. Overly conservative scaling factors based on lower limits of detection (LLD), often used in the nuclear power industry to estimate these controlling nuclides, could lead to premature closure of a disposal facility. Samples of LLW (Class B and C activated metals [AM] and other waste streams) are being collected from operating nuclear power stations and analyzed for radionuclides covered in 10 CFR Part 61 and the additional difficult-to-measure radionuclides. This analysis will enhance the NRC's understanding of the distribution and projected quantities of radionuclides within AM and LLW streams from commercial nuclear power stations. This research will also provide radiological characterization of AM specimens for others to use in leach-rate and lysimeter experiments to determine nuclide releases and subsequent movement in natural soil environments

Interim Storage Facility for LLW of Decommissioning Nuclear Research Facilities

Energy Technology Data Exchange (ETDEWEB)

Amato, S.; Ugolini, D.; Basile, F. [European Commission, Joint Research Centre, Nuclear Decommissioning and Facility Management Unit, TP 800, Via E. Fermi 2749, 21027 Ispra - VA (Italy)

2009-06-15

JRC-Ispra has initiated a Decommissioning and Waste Management (D and WM) Programme of all its nuclear facilities. In the frame of this programme, it has been decided to build an interim storage facility to host conditioned low level waste (LLW) that had been produced during the operation of JRC-Ispra nuclear research reactors and laboratories and that will be produced from their decommissioning. This paper presents the main characteristics of the facility. The storage ISFISF has a rectangular shape with uniform height and it is about 128 m long, 41 m wide and 9 m high. The entire surface affected by the facility, including screening area and access roads, is about 27.000 m{sup 2}. It is divided in three sectors, a central one, about 16 m long, for loading/unloading operations and operational services and two lateral sectors, each about 55 m long, for the conditioned LLW storage. Each storage sector is divided by a concrete wall in two transversal compartments. The ISFISF, whose operational lifetime is 50 years, is designed to host the conditioned LLW boxed in UNI CP-5.2 packages, 2,5 m long, 1.65 m wide, and 1,25 m high. The expected nominal inventory of waste is about 2100 packages, while the maximum storage is 2540 packages, thus a considerably large reserve capacity is available. The packages will be piled in stacks of maximum number of five. The LLW is going to be conditioned with a cement matrix. The maximum weight allowed for each package has been fixed at 16.000 kg. The total radioactivity inventory of waste to be hosted in the facility is about 30 TBq (mainly {beta}/{gamma} emitters). In order to satisfy the structural, seismic, and, most of all, radiological requirements, the external walls of the ISFISF are made of pre-fabricated panels, 32 cm thick, consisting of, from inside to outside, 20 cm of reinforced concrete, 7 cm of insulating material, and again 5 cm of reinforced concrete. For the same reason the roof is made with pre-fabricated panels in

Geotechnical reduction of void ratio in low-level radioactive waste burial sites: treatment alternatives

International Nuclear Information System (INIS)

Phillips, S.J.; Carlson, R.A.; McGuire, H.E.

1981-01-01

A substantial quantity of low-level radioactive and hazardous wastes has been interred in shallow land burial structures throughout the United States. Many of these structures (trenches, pits, and landfills) have proven to be unstable. Some surface feature manifestations such as large cracks, basins, and cave-ins are caused by voids filling and physico-chemical degradation and solubilization of the buried wastes which could result in the release of contamination. The surface features represent a potential for increased contamination transport to the biosphere via water, air, biologic, and direct pathways. Engineering alternatives for the reduction of buried waste and matrix materials voids are identified and discussed. As a guideline, a reduction of the voids within the waste to 80% or more of maximum relative dry density (a measure of in situ voids within the waste) is proposed. The advantages, disadvantages, and costs of each alternative are evaluated. Falling mass and pile driving engineering alternatives were selected for further development

Regionalization as a strategy for management of low-level and mixed wastes in the DOE system

International Nuclear Information System (INIS)

Bradford, J.D.; Garcia, E.C.; Gillins, R.L.

1988-01-01

The Department of Energy has been routinely performing low-level waste volume reduction and/or stabilization treatment at various sites for some time. In general, treatment is performed on waste generated onsite. Disposal is also usually performed onsite since most DOE sites have their own LLW disposal facilities. The DOE initiated studies to evaluate strategies for treatment, storage, and disposal of hazardous and mixed wastes covered in the Resource Conservation and Recovery Act (RCRA) and to ensure that DOE sites are in compliance with RCRA. These studies recommend regionalization as the most cost-effective solution to the treatment and disposal of hazardous and mixed wastes. The DOE's Defense Low-Level Waste Management Program conducted an additional survey of DOE sites to evaluate the status of one specific treatment method, incineration, at these sites. This study included facilities currently in use or intended for treatment of low-level and mixed wastes. A summary of the findings is presented in this paper

Fee structures for low-level radioactive waste disposal

International Nuclear Information System (INIS)

Sutherland, A.A.; Baird, R.D.; Rogers, V.C.

1988-01-01

Some compacts and states require that the fee system at their new low-level waste (LLW) disposal facility be based on the volume and radioactive hazard of the wastes. The fee structure discussed in this paper includes many potential fee elements that could be used to recover the costs of disposal and at the same time influence the volume and nature of waste that arrives at the disposal facility. It includes a base fee which accounts for some of the underlying administrative costs of disposal, and a broad range of charges related to certain parameters of the waste, such as volume, radioactivity, etc. It also includes credits, such as credits for waste with short-lived radionuclides or superior waste forms. The fee structure presented should contain elements of interest to all states and compacts. While no single disposal facility is likely to incorporate all of the elements discussed here in its fee structure, the paper presents a fairly exhaustive list of factors worth considering

Estimation of natural ground water recharge for the performance assessment of a low-level waste disposal facility at the Hanford Site

International Nuclear Information System (INIS)

Rockhold, M.L.; Fayer, M.J.; Kincaid, C.T.; Gee, G.W.

1995-03-01

In 1994, the Pacific Northwest Laboratory (PNL) initiated the Recharge Task, under the PNL Vitrification Technology Development (PVTD) project, to assist Westinghouse Hanford Company (WHC) in designing and assessing the performance of a low-level waste (LLW) disposal facility for the US Department of Energy (DOE). The Recharge Task was established to address the issue of ground water recharge in and around the LLW facility and throughout the Hanford Site as it affects the unconfined aquifer under the facility. The objectives of this report are to summarize the current knowledge of natural ground water recharge at the Hanford Site and to outline the work that must be completed in order to provide defensible estimates of recharge for use in the performance assessment of this LLW disposal facility. Recharge studies at the Hanford Site indicate that recharge rates are highly variable, ranging from nearly zero to greater than 100 mm/yr depending on precipitation, vegetative cover, and soil types. Coarse-textured soils without plants yielded the greatest recharge. Finer-textured soils, with or without plants, yielded the least. Lysimeters provided accurate, short-term measurements of recharge as well as water-balance data for the soil-atmosphere interface and root zone. Tracers provided estimates of longer-term average recharge rates in undisturbed settings. Numerical models demonstrated the sensitivity of recharge rates to different processes and forecast recharge rates for different conditions. All of these tools (lysimetry, tracers, and numerical models) are considered vital to the development of defensible estimates of natural ground water recharge rates for the performance assessment of a LLW disposal facility at the Hanford Site

Site selection handbook: Workshop on site selection for low-level radioactive waste disposal facilities

International Nuclear Information System (INIS)

1987-10-01

The Low-Level Radioactive Waste Policy Amendments Act of 1985 (LLRWPAA) requires the Department of Energy (DOE) to provide technical assistance to ''...those compact regions, host States and nonmember States determined by the Secretary to require assistance.'' Technical assistance has been defined to include, but not be limited to, ''technical guidelines for site selection.'' This site selection workshop was developed to assist States and Compacts in developing new low-level radioactive waste (LLW) disposal sites in accordance with the requirements of the LLRWPAA. The workshop comprises a series of lectures, discussion topics, and exercises, supported by this Site Selection Workshop Handbook, designed to examine various aspects of a comprehensive site selection program. It is not an exhaustive treatment of all aspects of site selection, nor is it prescriptive. The workshop focuses on the major elements of site selection and the tools that can be used to implement the site selection program

Technology, Safety and Costs of Decommissioning a Reference Low-Level Waste Burial Ground. Appendices

International Nuclear Information System (INIS)

None

1980-01-01

Safety and cost information are developed for the conceptual decommissioning of commercial low-level waste (LLW) burial grounds. Two generic burial grounds, one located on an arid western site and the other located on a humid eastern site, are used as reference facilities for the study. The two burial grounds are assumed to have the same site capacity for waste, the same radioactive waste inventory, and similar trench characteristics and operating procedures. The climate, geology. and hydrology of the two sites are chosen to be typical of real western and eastern sites. Volume 2 (Appendices) contains the detailed analyses and data needed to support the results given in Volume 1.

Radioisotope Characterization of HB Line Low Activity Waste

International Nuclear Information System (INIS)

Snyder, S.J.

1999-01-01

The purpose of this document is to provide a physical, chemical, hazardous and radiological characterization of Low-Level Waste (LLW) generated in HB-Line as required by the 1S Manual, Savannah River Site Waste Acceptance Criteria Manual

DOE Low-Level Waste Management Program

International Nuclear Information System (INIS)

Mezga, L.J.

1983-01-01

The Oak Ridge National Laboratory (ORNL) in its role as associate lead contractor of the DOE LLWMP has responsibility for the management of program-funded technology development activities. In this role with general guidance provided by DOE and the lead contractor (EG and G Idaho), the ORNL program office is charged with the responsibility to (1) develop program plans for the major technology areas, (2) recommend allocations for the program resources, (3) review the technology development tasks to ensure that program objectives are being met, and (4) to assist the lead contractor in coordinating the DOE LLWMP with other on-going US and foreign waste technology programs. Although the ORNL office generally assists the lead laboratory in management of the total program, our emphasis is on management of R and D for development of basic technology and to assess concepts for alternative systems of processing and disposal of LLW. Technical progress for each of the tasks of this program for FY 1982 is summarized

Low-Cost Alternative for the Measurement of Water Levels in Surface Water Streams

Directory of Open Access Journals (Sweden)

Luis E. PEÑA

2017-11-01

Full Text Available Flood risk management and water resources planning involve a deep knowledge of surface streams so that mitigation strategies and climate change adaptations can be implemented. Commercially, there is a wide range of technologies for the measurement of hydroclimatic variables; however, many of these technologies may not be affordable for institutions with limited budgets. This paper has two main objectives: 1 Present the design of an ultrasound-based water level measurement system, and 2 Propose a methodological alternative for the development of instruments, according to the needs of institutions conducting monitoring of surface waterbodies. To that end, the proposed methodology is based on selection processes defined according to the specific needs of each waterbody. The prototype was tested in real-world scale, with the potential to obtain accurate measurements. Lastly, we present the design of the ultrasound-based water level measurement instrument, which can be built at a low cost. Low-cost instruments can potentially contribute to the sustainable instrumental autonomy of environmental entities and help define measurement and data transmission standards based on the specific requirements of the monitoring.

Land disposal alternatives for low-level waste

International Nuclear Information System (INIS)

Alexander, P.; Lindeman, R.; Saulnier, G.; Adam, J.; Sutherland, A.; Gruhlke, J.; Hung, C.

1982-01-01

The objective of this project is to develop data regarding the effectiveness and costs of the following options for disposing of specific low-level nuclear waste streams; sanitary landfill; improved shallow land burial; intermediate depth disposal; deep well injection; conventional shallow land burial; engineered surface storage; deep geological disposal; and hydrofracturing. This will be accomplished through the following steps: (1) characterize the properties of the commercial low-level wastes requiring disposal; (2) evaluate the various options for disposing of this waste, characterize selected representative waste disposal sites and design storage facilities suitable for use at those sites; (3) calculate the effects of various waste disposal options on population health risks; (4) estimate the costs of various waste disposal options for specific sites; and (5) perform trade-off analyses of the benefits of various waste disposal options against the costs of implementing these options. These steps are described. 2 figures, 2 tables

Conditioning of low level radioactive waste at the Research Centre Seibersdorf

International Nuclear Information System (INIS)

Chalupa, G.; Petschnik, G.

1986-09-01

The conditioning (solidification) of LLW at the Austrian Research Centre Seibersdorf are explained. In first part of this paper the comentation of ashes are described and criterias for the application of recipes for conditioning, quality inspection, determination of leaching rates are given. Enclosed to that some figures show you the installed equipment and the handling for conditioning of LLW at the Research Centre. (Author)

Hydrologic evaluation methodology for estimating water movement through the unsaturated zone at commercial low-level radioactive waste disposal site

Science.gov (United States)

Meyer, P.D.; Rockhold, M.L.; Nichols, W.E.; Gee, G.W.

1996-01-01

This report identifies key technical issues related to hydrologic assessment of water flow in the unsaturated zone at low-level radioactive waste (LLW) disposal facilities. In addition, a methodology for incorporating these issues in the performance assessment of proposed LLW disposal facilities is identified and evaluated. The issues discussed fall into four areas:Estimating the water balance at a site (i.e., infiltration, runoff, water storage, evapotranspiration, and recharge);Analyzing the hydrologic performance of engineered components of a facility;Evaluating the application of models to the prediction of facility performance; andEstimating the uncertainty in predicted facility performance.An estimate of recharge at a LLW site is important since recharge is a principal factor in controlling the release of contaminants via the groundwater pathway. The most common methods for estimating recharge are discussed in Chapter 2. Many factors affect recharge; the natural recharge at an undisturbed site is not necessarily representative either of the recharge that will occur after the site has been disturbed or of the flow of water into a disposal facility at the site. Factors affecting recharge are discussed in Chapter 2.At many sites engineered components are required for a LLW facility to meet performance requirements. Chapter 3 discusses the use of engineered barriers to control the flow of water in a LLW facility, with a particular emphasis on cover systems. Design options and the potential performance and degradation mechanisms of engineered components are also discussed.Water flow in a LLW disposal facility must be evaluated before construction of the facility. In addition, hydrologic performance must be predicted over a very long time frame. For these reasons, the hydrologic evaluation relies on the use of predictive modeling. In Chapter 4, the evaluation of unsaturated water flow modeling is discussed. A checklist of items is presented to guide the evaluation

Permitting plan for the immobilized low-activity waste project

International Nuclear Information System (INIS)

Deffenbaugh, M.L.

1997-01-01

This document addresses the environmental permitting requirements for the transportation and interim storage of the Immobilized Low-Activity Waste (ILAW) produced during Phase 1 of the Hanford Site privatization effort. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage and disposal of Tank Waste Remediation Systems (TWRS) immobilized low-activity tank waste (ILAW) and (2) interim storage of TWRS immobilized HLW (IHLW) and other canistered high-level waste forms. Low-activity waste (LAW), low-level waste (LLW), and high-level waste (HLW) are defined by the TWRS, Hanford Site, Richland, Washington, Final Environmental Impact Statement (EIS) DOE/EIS-0189, August 1996 (TWRS, Final EIS). By definition, HLW requires permanent isolation in a deep geologic repository. Also by definition, LAW is ''the waste that remains after separating from high-level waste as much of the radioactivity as is practicable that when solidified may be disposed of as LLW in a near-surface facility according to the NRC regulations.'' It is planned to store/dispose of (ILAW) inside four empty vaults of the five that were originally constructed for the Group Program. Additional disposal facilities will be constructed to accommodate immobilized LLW packages produced after the Grout Vaults are filled. The specifications for performance of the low-activity vitrified waste form have been established with strong consideration of risk to the public. The specifications for glass waste form performance are being closely coordinated with analysis of risk. RL has pursued discussions with the NRC for a determination of the classification of the Hanford Site's low-activity tank waste fraction. There is no known RL action to change law with respect to onsite disposal of waste

Alternative solidified forms for nuclear wastes

International Nuclear Information System (INIS)

McElroy, J.L.; Ross, W.A.

1976-01-01

Radioactive wastes will occur in various parts of the nuclear fuel cycle. These wastes have been classified in this paper as high-level waste, intermediate and low-level waste, cladding hulls, and residues. Solidification methods for each type of waste are discussed in a multiple barrier context of primary waste form, applicable coatings or films, matrix encapsulation, canister, engineered structures, and geological storage. The four major primary forms which have been most highly developed are glass for HLW, cement for ILW, organics for LLW, and metals for hulls

Technology, Safety and Costs of Decommissioning a Reference Low-Level Waste Burial Ground. Main Report

International Nuclear Information System (INIS)

Murphy, E. S.; Holter, G. M.

1980-01-01

Safety and cost information are developed for the conceptual decommissioning of commercial low-level waste (LLW) burial grounds. Two generic burial grounds, one located on an arid western site and the other located on a humid eastern site, are used as reference facilities for the study. The two burial grounds are assumed to have the same site capacity for waste, the same radioactive waste inventory, and similar trench characteristics and operating procedures. The climate, geology. and hydrology of the two sites are chosen to be typical of real western and eastern sites. Volume 1 (Main Report) contains background information and study results in summary form.

Technology, Safety and Costs of Decommissioning a Reference Low-Level Waste Burial Ground. Main Report

Energy Technology Data Exchange (ETDEWEB)

Murphy, E. S.; Holter, G. M.

1980-06-01

Safety and cost information are developed for the conceptual decommissioning of commercial low-level waste (LLW) burial grounds. Two generic burial grounds, one located on an arid western site and the other located on a humid eastern site, are used as reference facilities for the study. The two burial grounds are assumed to have the same site capacity for waste, the same radioactive waste inventory, and similar trench characteristics and operating procedures. The climate, geology. and hydrology of the two sites are chosen to be typical of real western and eastern sites. Volume 1 (Main Report) contains background information and study results in summary form.

[Alternative nutrition and glutathione levels].

Science.gov (United States)

Krajcovicová-Kudlácková, M; Simoncic, R; Béderová, A; Brtková, A; Magálová, T; Barteková, S

1999-08-30

Low protein quality and quantity is reported to be a possible risk of alternative nutrition. Pulses contain 18-41% of methionine in relation to reference protein, moreover, its content in cereals is by one half lower. Therefore vegetarians and vegans may have an insufficient intake of sulphur-containing amino acids that may subsequently affect glutathione values (precursors of its synthesis). In groups of adults on an alternative diet--lactoovovegetarians (n = 47) and vegans (n = 44) aged 19-62 years with average duration on a vegetarian or vegan diet of 7.6 and 4.9 years, respectively, glutathione levels (GSH) were measured in erythrocytes (spectrophotometrically), as well as the activity of GSH-dependent enzymes. As nutritional control (n = 42) served an average sample of omnivores selected from a group of 489 examined, apparently healthy subjects of the same age range living in the same region. One to low protein intake (56% of RDA) exclusively of plant origin significantly lower levels of total proteins were observed in vegans with a 16% frequency of hypoproteinaemia (vs 0% in omnivores). In comparison to omnivores a significantly lower glutathione level was found (4.28 +/- 0.12 vs 4.84 +/- 0.14 mumol/g Hb, P vegan diet also in adult age.

The potential for criticality following disposal of uranium at low-level waste facilities: Uranium blended with soil

Energy Technology Data Exchange (ETDEWEB)

Toran, L.E.; Hopper, C.M.; Naney, M.T. [and others

1997-06-01

The purpose of this study was to evaluate whether or not fissile uranium in low-level-waste (LLW) facilities can be concentrated by hydrogeochemical processes to permit nuclear criticality. A team of experts in hydrology, geology, geochemistry, soil chemistry, and criticality safety was formed to develop achievable scenarios for hydrogeochemical increases in concentration of special nuclear material (SNM), and to use these scenarios to aid in evaluating the potential for nuclear criticality. The team`s approach was to perform simultaneous hydrogeochemical and nuclear criticality studies to (1) identify some achievable scenarios for uranium migration and concentration increase at LLW disposal facilities, (2) model groundwater transport and subsequent concentration increase via sorption or precipitation of uranium, and (3) evaluate the potential for nuclear criticality resulting from potential increases in uranium concentration over disposal limits. The analysis of SNM was restricted to {sup 235}U in the present scope of work. The outcome of the work indicates that criticality is possible given established regulatory limits on SNM disposal. However, a review based on actual disposal records of an existing site operation indicates that the potential for criticality is not a concern under current burial practices.

The potential for criticality following disposal of uranium at low-level waste facilities: Uranium blended with soil

International Nuclear Information System (INIS)

Toran, L.E.; Hopper, C.M.; Naney, M.T.

1997-06-01

The purpose of this study was to evaluate whether or not fissile uranium in low-level-waste (LLW) facilities can be concentrated by hydrogeochemical processes to permit nuclear criticality. A team of experts in hydrology, geology, geochemistry, soil chemistry, and criticality safety was formed to develop achievable scenarios for hydrogeochemical increases in concentration of special nuclear material (SNM), and to use these scenarios to aid in evaluating the potential for nuclear criticality. The team's approach was to perform simultaneous hydrogeochemical and nuclear criticality studies to (1) identify some achievable scenarios for uranium migration and concentration increase at LLW disposal facilities, (2) model groundwater transport and subsequent concentration increase via sorption or precipitation of uranium, and (3) evaluate the potential for nuclear criticality resulting from potential increases in uranium concentration over disposal limits. The analysis of SNM was restricted to 235 U in the present scope of work. The outcome of the work indicates that criticality is possible given established regulatory limits on SNM disposal. However, a review based on actual disposal records of an existing site operation indicates that the potential for criticality is not a concern under current burial practices

Control of water infiltration into near surface LLW disposal units: Task report, A discussion

International Nuclear Information System (INIS)

Schulz, R.K.; Ridky, R.W.; O'Donnell, E.

1988-03-01

The principal pathway for water entry into LLW disposal units in the humid eastern United States is through their covers. Two types of sub-surface features that may be constructed to enhance run-off (surface or sub-surface run-off) and thus reduce percolation are the resistive layer barrier, and the conductive layer barrier. The resistive layer barrier is the compacted soil or compacted clay layer and depends on compaction of permeable porous material to obtain low flow rates. The conductive layer barrier is a special case of the capillary barrier. Use is made of the capillary barrier phenomenon not only to increase the moisture content above an interface but to divert water away from the waste. During such diversion the water is at all times at negative capillary potential or under tension in the flow layer. A very effective barrier system might be constructed by placing a resistive barrier over a conductive barrier. Such a system must fail if appreciable subsidence takes place. An alternate procedure called bioengineering management utilizes engineered features at the surface (as opposed to the subsurface) to ensure adequate run-off. The engineered features are combined with stressed vegetation, that is, vegetation in an overdraft condition, to control deep percolation. (59 refs., 10 figs.)

Implementation of Waste Tracking System for LLW and MLW

International Nuclear Information System (INIS)

Won, Y. S.; Lee, K. H.; Kim, H. J.; Lee, K. H.

2010-01-01

The real-time Waste Tracking System (WTS) has been implemented for the integrated management of LLW and MLW from the receiving time at the production area till the managing period after the shutdown of disposal site. The relevant information by each process on take-over and receiving plan, preliminary inspection, receiving, transportation, site inspection, disposal and shutdown is over all managed by WTS

Large Item Disposal At The Drigg Low Level Waste Repository, United Kingdom

International Nuclear Information System (INIS)

Griffiths, Steve

2012-01-01

suitable and the activity either sufficiently low or sufficiently short-lived, a recycling route has potential and also fits in with policy concerning opening up of alternative routes for very low level radioactive waste. Delay and decay to achieve this and or free-release criteria are met would potentially generate revenue that could partly offset the cost of the process itself and where the specific activity precludes this route the material could feasibly be recycled into packaging for other LLW (or even ILW) items destined for repository disposal, such that the additional activity burden of the recycled material would be negligible

Clean option: An alternative strategy for Hanford Tank Waste Remediation. Volume 2, Detailed description of first example flowsheet

Energy Technology Data Exchange (ETDEWEB)

Swanson, J.L.

1993-09-01

Disposal of high-level tank wastes at the Hanford Site is currently envisioned to divide the waste between two principal waste forms: glass for the high-level waste (HLW) and grout for the low-level waste (LLW). The draft flow diagram shown in Figure 1.1 was developed as part of the current planning process for the Tank Waste Remediation System (TWRS), which is evaluating options for tank cleanup. The TWRS has been established by the US Department of Energy (DOE) to safely manage the Hanford tank wastes. It includes tank safety and waste disposal issues, as well as the waste pretreatment and waste minimization issues that are involved in the ``clean option`` discussed in this report. This report describes the results of a study led by Pacific Northwest Laboratory to determine if a more aggressive separations scheme could be devised which could mitigate concerns over the quantity of the HLW and the toxicity of the LLW produced by the reference system. This aggressive scheme, which would meet NRC Class A restrictions (10 CFR 61), would fit within the overall concept depicted in Figure 1.1; it would perform additional and/or modified operations in the areas identified as interim storage, pretreatment, and LLW concentration. Additional benefits of this scheme might result from using HLW and LLW disposal forms other than glass and grout, but such departures from the reference case are not included at this time. The evaluation of this aggressive separations scheme addressed institutional issues such as: radioactivity remaining in the Hanford Site LLW grout, volume of HLW glass that must be shipped offsite, and disposition of appropriate waste constituents to nonwaste forms.

Glass optimization for vitrification of Hanford Site low-level tank waste

International Nuclear Information System (INIS)

Feng, X.; Hrma, P.R.; Westsik, J.H. Jr.

1996-03-01

The radioactive defense wastes stored in 177 underground single-shell tanks (SST) and double-shell tanks (DST) at the Hanford Site will be separated into low-level and high-level fractions. One technology activity underway at PNNL is the development of glass formulations for the immobilization of the low-level tank wastes. A glass formulation strategy has been developed that describes development approaches to optimize glass compositions prior to the projected LLW vitrification facility start-up in 2005. Implementation of this strategy requires testing of glass formulations spanning a number of waste loadings, compositions, and additives over the range of expected waste compositions. The resulting glasses will then be characterized and compared to processing and performance specifications yet to be developed. This report documents the glass formulation work conducted at PNL in fiscal years 1994 and 1995 including glass formulation optimization, minor component impacts evaluation, Phase 1 and Phase 2 melter vendor glass development, liquidus temperature and crystallization kinetics determination. This report also summarizes relevant work at PNNL on high-iron glasses for Hanford tank wastes conducted through the Mixed Waste Integrated Program and work at Savannah River Technology Center to optimize glass formulations using a Plackett-Burnam experimental design

Restraint effect of water infiltration by soil cover types of LLW disposal facility

International Nuclear Information System (INIS)

Park, S. M.; Lee, E. Y.; Lee, C. K.; Kim, C. L.

2002-01-01

Since soil cover for LLW disposal vault shows quite different restraint effect of water infiltration depending on its type, four different types of soil cover were studied and simulated using HELP code. Simulation result showed that Profile B1 is the most effective type in restraint of water infiltration to the disposal vault. Profile B1 is totally 6m thick and composed of silt, gravelly sand, pea gravel, sand and clayey soil mixed with bentonite 20%. Profile B1 also includes artificial layers, such as asphalt and geomembrane layers. This profile is designed conceptually by NETEC for the soil cover of the near surface disposal facility of the low-level radioactive waste. For comparison, 3 types of different profile were tested. One profile includes bentonite mixed layer only as water barrier layer, or one as same as profile B1 but without geomembrane layer or one without asphalt layer respectively. The simulation using HELP code showed that the water balance in profile B1 was effectively controlled

Management of defense beta-gamma contaminated solid low-level wastes

International Nuclear Information System (INIS)

Sease, J.D.

1983-01-01

In DOE defense operations, approx. 70,000 m 3 of beta-gamma low-level radioactive waste are disposed of annually by shallow land burial operations at six primary sites. Waste generated at other DOE sites are transported on public roads to the primary sites for disposal. In the practice of low-level waste (LLW) disposal in the US, the site hydrology and geology are the primary barriers to radioactive migration. To date, little emphasis has been placed on waste form improvements or engineered site modifications to reduce migration potential. Compaction is the most common treatment step employed. The performance of ground disposal of radioactive waste in this country, in spite of many practices that we would consider unacceptable in today's light, has resulted in very little migration of radioactivity outside site boundaries. Most problems with previously used burial grounds have been from subsidence at the arid sites and subsidence and groundwater contact at the humid sites. The radionuclides that have shown the most significant migration are tritium, 90 Sr, and 99 Tc. The unit cost for disposal operations at a given DOE site is dependent on many variables, but the annual volume to be disposed is probably the major factor. The average cost for current DOE burial operation is approximately $170/m 3 . 23 figures

Comparative life-cycle cost analysis for low-level mixed waste remediation alternatives

International Nuclear Information System (INIS)

Jackson, J.A.; White, T.P.; Kloeber, J.M.; Toland, R.J.; Cain, J.P.; Buitrago, D.Y.

1995-03-01

The purpose of this study is two-fold: (1) to develop a generic, life-cycle cost model for evaluating low-level, mixed waste remediation alternatives, and (2) to apply the model specifically, to estimate remediation costs for a site similar to the Fernald Environmental Management Project near Cincinnati, OH. Life-cycle costs for vitrification, cementation, and dry removal process technologies are estimated. Since vitrification is in a conceptual phase, computer simulation is used to help characterize the support infrastructure of a large scale vitrification plant. Cost estimating relationships obtained from the simulation data, previous cost estimates, available process data, engineering judgment, and expert opinion all provide input to an Excel based spreadsheet for generating cash flow streams. Crystal Ball, an Excel add-on, was used for discounting cash flows for net present value analysis. The resulting LCC data was then analyzed using multi-attribute decision analysis techniques with cost and remediation time as criteria. The analytical framework presented allows alternatives to be evaluated in the context of budgetary, social, and political considerations. In general, the longer the remediation takes, the lower the net present value of the process. This is true because of the time value of money and large percentage of the costs attributed to storage or disposal

Investigating the effect of the London living wage on the psychological wellbeing of low-wage service sector employees: a feasibility study.

Science.gov (United States)

Flint, Ellen; Cummins, Steven; Wills, Jane

2014-06-01