This document is the User's Manual (UM) for the Enhanced Logistics Intratheater Support Tool (ELIST) Software Segment. It tells how to use the end-user and administrative features of the segment. The instructions in Sections 4.2.1, 5.3.1, and 5.3.2 for the end-user features (Run ELIST and Run ETEdit) only cover the launching of those features in the DII COE environment; full details on the operation of ELIST and ETEdit in any environment can be found in the documents listed in Section 2.1.3 and referenced elsewhere in this document. On the other hand, complete instructions for the administrative features (Add Map Data and Delete Map Data) are presented in Sections 4.2.2, 5.3.3, and 5.3.4 of this document.

This document is the User's Manual (UM) for the Enhanced Logistics Intratheater Support Tool (ELIST) Database Utility Segment. It tells how to use its features to administer ELIST database user accounts.

This document is the System Administrator's Manual (SAM) for the Enhanced Logistics Intratheater Support Tool (ELIST) Database Segment. It covers errors that can arise during the segment's installation and deinstallation, and it outlines appropriate recovery actions. It also tells how to extend the database storage available to Oracle if a datastore becomes filled during the use of ELIST. The latter subject builds on some of the actions that must be performed when installing this segment, as documented in the Installation Procedures (IP) for the Enhanced Logistics Intratheater Support Tool (ELIST) Global Data Segment, Database Instance Segment, Database Fill Segment, Database Segment, Database Utility Segment, Software Segment, and Reference Data Segment (referred to in portions of this document as the ELIST IP). The information in this document is expected to be of use only rarely. Other than errors arising from the failure to follow instructions, difficulties are not expected to be encountered during the installation or deinstallation of the segment. The need to extend database storage likewise typically arises infrequently. Most administrators will only need to be aware of the help that is provided in this document and will probably not actually need to read and make use of it.

This document is the System Administrator's Manual (SAM) for the Enhanced Logistics Intratheater Support Tool (ELIST) Database Instance Segment. It covers errors that can arise during the segment's installation and deinstallation, and it outlines appropriate recovery actions. It also tells how to change the password for the SYSTEM account of the database instance after the instance is created, and it discusses the creation of a suitable database instance for ELIST by means other than the installation of the segment. The latter subject is covered in more depth than its introductory discussion in the Installation Procedures (IP) for the Enhanced Logistics Intratheater Support Tool (ELIST) Global Data Segment, Database Instance Segment, Database Fill Segment, Database Segment, Database Utility Segment, Software Segment, and Reference Data Segment (referred to in portions of this document as the ELIST IP). The information in this document is expected to be of use only rarely. Other than errors arising from the failure to follow instructions, difficulties are not expected to be encountered during the installation or deinstallation of the segment. By the same token, the need to create a database instance for ELIST by means other than the installation of the segment is expected to be the …

This Corrective Action Investigation Plan contains the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Operations Office's approach to collect the data necessary to evaluate corrective action alternatives appropriate for the closure of Corrective Action Unit (CAU) 527, Horn Silver Mine, Nevada Test Site, Nevada, under the Federal Facility Agreement and Consent Order. Corrective Action Unit 527 consists of one Corrective Action Site (CAS): 26-20-01, Contaminated Waste Dump No.1. The site is located in an abandoned mine site in Area 26 (which is the most arid part of the NTS) approximately 65 miles northwest of Las Vegas. Historical documents may refer to this site as CAU 168, CWD-1, the Wingfield mine (or shaft), and the Wahmonie mine (or shaft). Historical documentation indicates that between 1959 and the 1970s, nonliquid classified material and unclassified waste was placed in the Horn Silver Mine's shaft. Some of the waste is known to be radioactive. Documentation indicates that the waste is present from 150 feet to the bottom of the mine (500 ft below ground surface). This CAU is being investigated because hazardous constituents migrating from materials and/or wastes disposed of in the Horn Silver Mine may pose a threat to human …

Boiler owners and operators who need additional generating capacity face a number of legal, political, environmental, economic, and technical challenges. Their key to success requires selection of an adequately sized low-emission boiler and combustion equipment that can be operated in compliance with emission standards established by state and federal regulatory agencies. Recognizing that many issues are involved in making informed selection decisions, the U.S. Department of Energy (DOE), Office of Industrial Technologies (OIT) sponsored efforts at the Oak Ridge National Laboratory (ORNL) to develop a guide for use in choosing low-emission boilers and combustion equipment. To ensure that the guide covers a broad range of technical and regulatory issues of particular interest to the commercial boiler industry, the guide was developed in cooperation with the American Boiler Manufacturers Association (ABMA), the Council of Industrial Boiler Owners (CIBO), and the U.S. Environmental Protection Agency (EPA). The guide presents topics pertaining to industrial, commercial, and institutional (ICI) boilers. Background information about various types of commercially available boilers is provided along with discussions about the fuels that they burn and the emissions that they produce. Also included are discussions about emissions standards and compliance issues, technical details related to emissions control techniques, and …

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This document is the Software Version Description (SVD) for the Enhanced Logistics Intratheater Support Tool (ELIST) Database Segment. It contains basic information about the segment.

This document is the Software Version Description (SVD) for the Enhanced Logistics Intratheater Support Tool (ELIST) Software Segment. It contains basic information about the segment.

This document is the Software Version Description (SVD) for the Enhanced Logistics Intratheater Support Tool (ELIST) Database Instance Segment. It contains basic information about the segment.

This document is the Software Version Description (SVD) for the Enhanced Logistics Intratheater Support Tool (ELIST) Database Utility Segment. It contains basic information about the segment.

This document is the Installation Procedures (IP) for the DII COE Enhanced Logistics Intraheater Support Tool (ELIST) mission application. It tells how to install and deinstall the seven segments of the mission application.

The ELIST mission application simulates and evaluates the feasibility of intratheater transportation logistics primarily for the theater portion of a course of action. It performs a discrete event simulation of a series of movement requirements over a constrained infrastructure network using specified transportation assets. ELIST addresses the question of whether transportation infrastructures and lift allocations are adequate to support the movements of specific force structures and supplies to their destinations on time.

This document is the Software Version Description (SVD) for the Enhanced Logistics Intratheater Support Tool (ELIST) Reference Data Segment. It contains basic information about the segment.

An 11.4% partial Siberian snake was used to successfully accelerate polarized proton through a strong intrinsic depolarizing spin resonance in the AGS. No noticeable depolarization was observed. This opens up the possibility of using a 20% to 30% partial Siberian snake in the AGS to overcome all weak and strong depolarizing spin resonances. Some design and operation issues of the new partial Siberian snake are discussed.

With a partial Siberian snake in the AGS and transport lines with interspersed horizontal and vertical bends, the incoming spin direction at the injection points of both the collider rings is not likely to match the ideal vertical stable spin direction of RHIC which has two full helical Siberian snakes per ring. In this paper we examine the matching of a polarized beam transferred from the AGS into RHIC. The present 5% partial solenoidal snake as well as a proposed 20% superconducting helical are considered for the AGS. Solutions with retuned snakes in RHIC to better match the incoming beam have been found.

Sampling residual waste after tank cleaning and analysis for analytes of concern to support closure and cleaning targets of large underground tanks used for storage of legacy high level radioactive waste (HLW) at Department of Energy (DOE) sites has been underway since about 1995. The DOE Tanks Focus Area (TFA) has been working with DOE tank sites to develop new sampling plans, and sampling methods for assessment of residual waste inventories. This paper discusses regulatory analytes of concern, sampling plans, and sampling methods that support closure and cleaning target activities for large storage tanks at the Hanford Site, the Savannah River Site (SRS), the Idaho National Engineering and Environmental Laboratory (INEEL), and the West Valley Demonstration Project (WVDP).

This document is the Database Design Document for the Enhanced Logistics Intratheater Support Tool (ELIST) Database Segment. It describes the physical database design used by the ELIST mission application.

This paper represents a summary of our methodology for Verification and Validation and Uncertainty Quantification. A graded scale methodology is presented and related to other concepts in the literature. We describe the critical nature of quantified Verification and Validation with Uncertainty Quantification at specified Confidence levels in evaluating system certification status. Only after Verification and Validation has contributed to Uncertainty Quantification at specified confidence can rational tradeoffs of various scenarios be made. Verification and Validation methods for various scenarios and issues are applied in assessments of Quantified Reliability at Confidence and we summarize briefly how this can lead to a Value Engineering methodology for investment strategy.

The P wells were installed in the late 80s as part of the SRP Baseline Hydrogeological Investigation for the purpose of updating and improving the current knowledge and understanding of the hydrogeological systems underlying the SRS. During the installation of the P well series wells, a total of more than 16,000 feet of unconsolidated geologic sediments were cored and are currently stored at the Core Facility and 129 wells were installed at eighteen widely spaced P well clusters. Each well cluster nominally consists of 8 observations wells screened at the water table down to the lower McQueen Branch aquifer (Middendorf Formation). The vertical distribution of the wells at each cluster not only provides information on the hydraulic head within each monitoring unit but also the vertical gradients between the different formations.

We successfully injected polarized protons in both RHIC rings and maintained polarization during acceleration up to 100 GeV per ring using two Siberian snakes in each ring. Each snake consists of four helical superconducting dipoles which rotate the polarization by 180{sup o} about a horizontal axis. This is the first time that polarized protons have been accelerated to 100 GeV.

One of the concerns facing accelerator-driven transmutation systems (ADSs) is whether the radiotoxicity of materials produced during the transmutation process poses more of a concern than does the radiotoxicity of the spent nuclear fuel (SNF) itself. Most of the common fission products (or FPs) are emitters of beta radiation, but additionally, some of the radionuclides generated during spallation are alpha emitters. Thus, both ingestion and inhalation radiotoxicity of the materials produced during spallation could be significant. Typically, ingestion is considered to be more significant than inhalation radiotoxicity for long-term storage/disposal (such as in a repository) because the greatest potential biological hazard to humans occurs when the isotope is absorbed in nearby ground water or brine and transported from the repository to drinking water. Nonetheless, inhalation radiotoxicity is also important to analyze in case of a breach of containment inside the accelerator facility and/or for short-term (i.e., above-ground) storage concerns. Thus, this study calculated the radiotoxicity of spallation products (or SPs) from three different targets: lead-bismuth eutectic (LBE), LBE-cooled tungsten, and LBE-cooled lead.

This document is the Software Test Plan/Description/Report (STP/STD/STR) for the DII COE Enhanced Logistics Intratheater Support Tool (ELIST) mission application. It combines in one document the information normally presented separately in a Software Test Plan, a Software Test Description, and a Software Test Report; it also presents this information in one place for all the segments of the ELIST mission application. The primary purpose of this document is to show that ELIST has been tested by the developer and found, by that testing, to install, deinstall, and work properly. The information presented here is detailed enough to allow the reader to repeat the testing independently. The remainder of this document is organized as follows. Section 1.1 identifies the ELIST mission application. Section 2 is the list of all documents referenced in this document. Section 3, the Software Test Plan, outlines the testing methodology and scope--the latter by way of a concise summary of the tests performed. Section 4 presents detailed descriptions of the tests, along with the expected and observed results; that section therefore combines the information normally found in a Software Test Description and a Software Test Report. The remaining small sections present supplementary information. Throughout this document, the …

This report documents the validation and comparison of KENO V.a and KENO-VI using the SCALE 27-group ENDF/B-IV and 238-group ENDF/B-V cross-section libraries against critical experiments. Experiments considered were primarily high- or low-enriched uranium systems. The results indicate that KENO V.a and KENO-VI Monte Carlo Criticality Programs accurately calculate a broad range of critical experiments. A number of the calculations showed a positive or negative bias in excess of 1 1/2% in k-effective (k{sub eff}). Classes of criticals that show a bias include 3% enriched green blocks, highly-enriched uranyl fluoride slab arrays, and highly-enriched uranyl nitrate arrays. If these biases are properly taken into account, KENO V.a and KENO-VI can be used with confidence for the design and criticality safety analysis of uranium-containing systems. KENO V.a and KENO-VI calculate the same k{sub eff} for a system within statistics and thus may be used interchangeably as long as the geometry of the problem can be modeled.