[en] Of the 177 tanks containing nuclear waste at the Hanford site, 68 have not been characterized based on sampling information. It may be possible to characterize 34 of the 68 unsampled tanks by using information from other sources, such as the Tank Characterization Database (TCD) and the Historical Tank Content Estimates (HTCE). This report lists predicted concentrations of 17 analytes along with the associated estimates of uncertainty for the T-200 series tanks (T-201, T-202, T-203, T-204), based on historical data and sample results from tanks other than the T-200 tanks. The main benefits of reduced sampling are reduced cost, reduced time to achieve acceptable characterization, and reduced exposure of sampling personnel. However, in order to characterize a tank on the basis of reducing sampling, the predicted tank averages and the associated uncertainties must be technically credible and useful. The objective of this report is to describe the approach to predict (without a sample) or estimate (from a single sample) the concentrations of the 17 analytes for the T-200 tanks. Sampling of these tanks and laboratory analysis of the samples is currently under way (sampling is scheduled for 03/27/97 through 04/21/97). This report briefly describes the statistical prediction techniques

[en] Measurement facilities performing nondestructive assay (NDA) of wastes intended for disposal at the United States Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) are required to demonstrate their ability to meet specific Quality Assurance Objectives (QAOs). This demonstration is performed, in part, by participation in the NDA Performance Demonstration Program (PDP). The PDP is funded and managed by the Carlsbad Area Office (CAO) of DOE and is conducted by the Idaho National Engineering Laboratory. It tests the characteristics of precision, system bias and/or total uncertainty through the measurement of variable, blind combinations of simulated waste drums and certified radioactive standards. Each facility must successfully participate in the PDP using each different type of measurement system planned for use in waste characterization. The first cycle of the PDP using each different type of measurement system planned for use in waste characterization. The first cycle of the PDP was completed in July 1996 and the second is scheduled for completion by December 1996. Seven sites reported data in cycle 1 for 11 different measurement systems. This paper describes the design and operation of the PDP and provides the performance data from cycle 1. It also describes the preliminary results from cycle 2 and updates the status and future plans for the NDA PDP. 4 refs., 9 figs., 11 tabs

[en] The LMSC Active Passive Neutron Examinations and Assay (APNEA) Data Logger is a VME-based data acquisition system using commercial-off-the-shelf hardware with the application-specific software. It receives TTL inputs from eighty-eight ³He detector tubes and eight timing signals. Two data sets are generated concurrently for each acquisition session: (1) List Mode recording of all detector and timing signals, timestamped to 3 microsecond resolution; (2) Event Accumulations generated in real-time by counting events into short (tens of microseconds) and long (seconds) time bins following repetitive triggers. List Mode data sets can be post-processed to: (1) determine the optimum time bins for TRU assay of waste drums, (2) analyze a given data set in several ways to match different assay requirements and conditions and (3) confirm assay results by examining details of the raw data. Data Logger events are processed and timestamped by an array of 15 TMS320C40 DSPs and delivered to an embedded controller (PowerPC604) for interim disk storage. Three acquisition modes, corresponding to different trigger sources are provided. A standard network interface to a remote host system (Windows NT or SunOS) provides for system control, status, and transfer of previously acquired data. 6 figs

[en] High energy photon interrogation of waste containers, with the aim of producing photo nuclear reactions, in specific materials, holds the potential of good penetration and rapid analysis. Compact high energy (≤ 10 MeV) photon sources in the form of electron linacs producing bremstrahlung radiation are readily available. Work with the Varitron variable energy accelerator at ISU will be described. Advantages and limitations of the technique will be discussed. Using positive ion induced neutron producing reactions, it is possible to generate neutrons in a specific energy range. By this means, variable penetration and specific reactions can be excited in the assayed material. Examples using the ³H(p,n) and ⁷Li(p,n) reactions as neutron sources will be discussed. 4 refs., 7 figs

[en] Expert system technology has been identified as a technique useful for filling certain types of technology/capability gaps in existing waste nondestructive assay (NDA) applications. In particular, expert system techniques are being investigated with the intent of providing on-line evaluation of acquired data and/or directed acquisition of data in a manner that mimics the logic and decision making process a waste NDA expert would employ. The space from which information and data sources utilized in this process is much expanded with respect to the algorithmic approach typically utilized in waste NDA. Expert system technology provides a mechanism to manage and reason with this expanded information/data set. The material presented in this paper concerns initial studies and a resultant prototype expert system that incorporates pertinent information, and evaluation logic and decision processes, for the purpose of validating acquired waste NDA measurement assays. 6 refs., 6 figs

[en] Transuranic waste (TRUW) loads and potential contaminant releases at and en route to treatment, storage, and disposal sites in the US Department of Energy (DOE) complex are important considerations in DOE's Waste Management Programmatic Environmental Impact Statement (WM PEIS). Waste loads are determined in part by the level of treatment the waste has undergone and the complex-wide configuration of origination, treatment, storage, and disposal sites selected for TRUW management. Other elements that impact waste loads are treatment volumes, waste characteristics, and the unit operation parameters of the treatment technologies. Treatment levels and site configurations have been combined into six TRUW management alternatives for study in the WM PEIS. This supplemental report to the WM PEIS gives the projected waste loads and contaminant release profiles for DOE treatment sites under each of the six TRUW management alternatives. It gives TRUW characteristics and inventories for current DOE generation and storage sites, describes the treatment technologies for three proposed levels of TRUW treatment, and presents the representative unit operation parameters of the treatment technologies. The data presented are primary inputs to developing the costs, health risks, and socioeconomic and environmental impacts of treating, packaging, and shipping TRUW for disposal

[en] The Mixed Waste Focus Area began operations in February of 1995. Its mission is to provide acceptable technologies that enable implementation of mixed waste treatment systems developed in partnership with end-users, stakeholders, tribal governments, and regulators. The MWFA will develop, demonstrate, and deliver implementable technologies for treatment of mixed waste within the DOE complex. Treatment refers to all post waste-generation activities including sampling and analysis, characterization, storage, processing, packaging, transportation, and disposal. The MWFA's mission arises from the Resources Conservation and Recovery Act (RCRA) as amended by the Federal Facility Compliance Act. Each DOE site facility that generates or stores mixed waste prepared a plan, the Site Treatment Plan, for developing treatment capacities and treating that waste. Agreements for each site were concluded with state regulators, resulting in Consent Orders providing enforceable milestones for achieving treatment of the waste. The paper discusses the implementation of the program, its status, accomplishments and goals for FY1996, and plans for 1997

[en] A factual description of the operation of British Nuclear Fuel's (BNFL) waste management division is offered in the article. The United Kingdom classification of low-, intermediate- and high-level wastes is explained and BNFL current practices and future plans for the disposal of each is discussed. The article also addresses BNFL's attitude to decommissioning of its various facilities, and the policies it intends to pursue in line with government regulations. U.K

[en] The US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (CRWM) has the unique mission of finding a permanent solution to the nation's high-level radioactive waste management problems. This paper explores a vital question: will OCRWM have sufficient scientific and technical resources as well as a sufficient level of public support to carry out its mission? An affirmative answer to this question will require that adequate numbers of science and engineering students enter the field of radioactive waste management and that overall scientific literacy also be enhanced. This paper outlines current activities and programs within DOE and OCRWM to increase scientific literacy and to recruit and develop scientists and engineers. While this paper offers only a summary inspection of the issues surrounding the solution of developing and maintaining the human technical capabilities to carry forth OCRWM's mission, it is meant to initiate a continuing examination by the American Nuclear Society, DOE, and professional and technical societies of fundamental scientific education issues

[en] This paper reports on a new law which has recently been passed at the end of 1991 by the French Parliament. It gives definite information on a detailed framework related to the long lived radioactive waste management. Studies will be carried out following three directions: sharper actinide separation and transmutation; waste conditioning; and researches in underground laboratories. These studies will be assessed within fifteen years. The law also sets up ANDRA as a Etablissement public and caractere industrial et commercial (independent state owned company) which is especially responsible for industrial realization and participation into the research program