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LAGRANGIAN PARTICLE DISPERSION MODEL (LPDM) TECHNICAL DESCRIPTION (U)

Description: The Savannah River National Laboratory (SRNL) uses the Lagrangian Particle Dispersion Model (LPDM) in conjunction with the Regional Atmospheric Modeling System as an operational tool for emergency response consequence assessments for the Savannah River Site (SRS). The LPDM is an advanced stochastic atmospheric transport model used to transport and disperse passive tracers subject to the meteorological field generated by RAMS from sources of varying number and shape. The Atmospheric Technologies Group (ATG) of the SRNL is undertaking the task of reviewing documentation and code for LPDM Quality Assurance (QA). The LPDM QA task will include a model technical description, computer coding descriptions, model applications, and configuration control. This report provides a comprehensive technical description of the LPDM model.
Date: July 20, 2006
Creator: Chen, K
Partner: UNT Libraries Government Documents Department

NGNP Risk Management Database: A Model for Managing Risk

Description: To facilitate the implementation of the Risk Management Plan, the Next Generation Nuclear Plant (NGNP) Project has developed and employed an analytical software tool called the NGNP Risk Management System (RMS). A relational database developed in Microsoft® Access, the RMS provides conventional database utility including data maintenance, archiving, configuration control, and query ability. Additionally, the tool’s design provides a number of unique capabilities specifically designed to facilitate the development and execution of activities outlined in the Risk Management Plan. Specifically, the RMS provides the capability to establish the risk baseline, document and analyze the risk reduction plan, track the current risk reduction status, organize risks by reference configuration system, subsystem, and component (SSC) and Area, and increase the level of NGNP decision making.
Date: September 1, 2009
Creator: Collins, John
Partner: UNT Libraries Government Documents Department

Inside an environmental data archive WWW site

Description: The Oak Ridge National Laboratory (ORNL) Distributed Active Archive Center (DAAC), which is associated with NASA`s Earth Observing System Data and Information System (EOSDIS), provides access to tabular and imagery datasets used in ecological and environmental research. Because of its large and diverse data holdings, twin challenges for the ORNL DAAC are to help users find data of interest from the hundreds of thousands of files available at the DAAC without overwhelming them and to manage such a large collection of data. Therefore, the ORNL DAAC has developed a number of World Wide Web (WWW) tools such as the Biogeochemical Information Ordering Management Environment (BIOME), a WWW search and order system, as well as WWW-based data management and configuration control tools. This paper describes the specialized attributes incorporated into these systems that allow for easy access to and management of the data.
Date: March 1, 1997
Creator: Grubb, J.W.; Jennings, S.V.; Yow, T.G. & Smith, A.W.
Partner: UNT Libraries Government Documents Department

Characterization engineering status report october 1998 - december 1998

Description: Characterization Engineering (CE) continues to make progress in support of the project goal of characterizing the Hanford high-level waste tanks. Two core sampling systems were operational during this reporting period-push mode core sampling system No. 1 and rotary mode core sampling system No. 4. The availability average for core sampling systems No. 1 , No. 3 and No. 4, combined, was 45 percent, down from 79percent for the previous quarter and 58 percent for FY 1998. System No. 2 did not have scope during the quarter, and availability was not hacked. System No. 3 was out of service the entire quarter for corrective maintenance. Two tanks were core sampled during the reporting period, and 24 samples were retrieved. Core sample recovery increased slightly during the quarter. System No. 1 average sample recovery increased from 80percent to 81 percent, The rotary mode core sampling average recovery increased to 62 percent from 55 percent for the previous quarter. sampling six tanks, one more than scheduled. Vapor Sampling was utilized in support of the sluicing of tank 241-C-106 and for emissions monitoring of three exhaust stacks. Increased support was provided for Vapor Sampling the Standard Hydrogen Monitoring Systems. The sampling was necessary due to freezing problems with the field-installed systems. Preparations are continuing for the Light-Duty Utility Arm (LDUA) deployment with configuration and minor hardware upgrades. The LDUA Operational Readiness Review continues. The oversight of the Nested, Fixed-Depth Sampler system development has started to increase in order to ensure that a usable system is received when the project is completed. To improve configuration control, 92 drawing sheet revisions were completed along with the generation of nine new drawing sheets. The number of outstanding Engineering Change Notices increased slightly because of the addition of more drawings into the project. continues to develop. Organizational responsibilities ...
Date: May 13, 1999
Creator: Boger, R. M.
Partner: UNT Libraries Government Documents Department

An Accelerator Control Middle Layer Using MATLAB

Description: Matlab is a matrix manipulation language originally developed to be a convenient language for using the LINPACK and EISPACK libraries. What makes Matlab so appealing for accelerator physics is the combination of a matrix oriented programming language, an active workspace for system variables, powerful graphics capability, built-in math libraries, and platform independence. A number of software toolboxes for accelerators have been written in Matlab--the Accelerator Toolbox (AT) for machine simulations, LOCO for accelerator calibration, Matlab Channel Access Toolbox (MCA) for EPICS connections, and the Middle Layer. This paper will describe the ''middle layer'' software toolbox that resides between the high-level control applications and the low-level accelerator control system. This software was a collaborative effort between ALS (LBNL) and SPEAR3 (SSRL) but easily ports to other machines. Five accelerators presently use this software. The high-level Middle Layer functionality includes energy ramp, configuration control (save/restore), global orbit correction, local photon beam steering, insertion device compensation, beam-based alignment, tune correction, response matrix measurement, and script-based programs for machine physics studies.
Date: March 15, 2005
Creator: Portmann, Gregory J.; Corbett, Jeff & Terebilo, Andrei
Partner: UNT Libraries Government Documents Department

Risk Management Plan

Description: The purpose of this Risk Management Plan (RMP) is to establish the concept and define the process to assure that National Nuclear Security Administration Nevada Operations Office Environmental Management (NNSA/NV EM) programs and projects incorporate appropriate, efficient, cost-effective measures to mitigate the impact of program-and/or project-related risks. In addition, it describes the roles and responsibilities of program personnel in performing the risk management functions, and defines reporting and tracking requirements for risk-related information. The product of this risk analysis will be a risk analysis report listing the various risks with their classification, mitigation and handling strategies, impact on cost and schedule, and action items. The risk management process will identify potential risk sources; assess individual risks and impacts on performance, cost, and schedule; evaluate alternative approaches to mitigate high and moderate risks; develop action plans to handle individual risks; and interface risks with other programs and/or projects. Risk management and risk assessment will be consistent with DOE Orders 430.1 and 413.3 and their associated guidance documentation. The RMP will remain valid for the life cycle of the program and/or projects and will be under configuration control with revisions to be conducted as required and approved.
Date: December 1, 2001
Creator: Stephenson, G. R.
Partner: UNT Libraries Government Documents Department

THE CREATIVE APPLICATION OF SCIENCE TECHNOLOGY & WORK FORCE INNOVATIONS TO THE D&D OF PLUTONIUM FINISHING PLANT (PFP) AT THE HANFORD NUCLEAR RESERVATION

Description: The Plutonium Finishing Plant (PFP) consists of a number of process and support buildings for handling plutonium. Building construction began in the late 1940's to meet national priorities and became operational in 1950 producing refined plutonium salts and metal for the United States nuclear weapons program. The primary mission of the PFP was to provide plutonium used as special nuclear material for fabrication into a nuclear device for the war effort. Subsequent to the end of World War II, the PFP's mission expanded to support the Cold War effort through plutonium production during the nuclear arms race. PFP has now completed its mission and is fully engaged in deactivation, decontamination and decommissioning (D&D). At this time the PFP buildings are planned to be reduced to ground level (slab-on-grade) and the site remediated to satisfy national, Department of Energy (DOE) and Washington state requirements. The D&D of a highly contaminated plutonium processing facility presents a plethora of challenges. PFP personnel approached the D&D mission with a can-do attitude. They went into D&D knowing they were facing a lot of challenges and unknowns. There were concerns about the configuration control associated with drawings of these old process facilities. There were unknowns regarding the location of electrical lines and process piping containing chemical residues such as strong acids and caustics. The gloveboxes were highly contaminated with plutonium and chemical residues. Most of the glovebox windows were opaque with splashed process chemicals that coated the windows or etched them, reducing visibility to near zero. Visibility into the glovebox was a serious worker concern. Additionally, all the gloves in the gloveboxes were degraded and unusable. Replacing gloves in gloveboxes was necessary to even begin glovebox cleanout. The sheer volume of breathing air needed was also an issue. These and other challenges and PFP's approach to ...
Date: February 1, 2006
Creator: CHARBONEAU, S.L.
Partner: UNT Libraries Government Documents Department

Software solutions manage the definition, operation, maintenance and configuration control of the National Ignition Facility

Description: The National Ignition Facility (NIF) is the world's largest laser composed of millions of individual parts brought together to form one massive assembly. Maintaining control of the physical definition, status and configuration of this structure is a monumental undertaking yet critical to the validity of the shot experiment data and the safe operation of the facility. The NIF business application suite of software provides the means to effectively manage the definition, build, operation, maintenance and configuration control of all components of the National Ignition Facility. State of the art Computer Aided Design software applications are used to generate a virtual model and assemblies. Engineering bills of material are controlled through the Enterprise Configuration Management System. This data structure is passed to the Enterprise Resource Planning system to create a manufacturing bill of material. Specific parts are serialized then tracked along their entire lifecycle providing visibility to the location and status of optical, target and diagnostic components that are key to assessing pre-shot machine readiness. Nearly forty thousand items requiring preventive, reactive and calibration maintenance are tracked through the System Maintenance & Reliability Tracking application to ensure proper operation. Radiological tracking applications ensure proper stewardship of radiological and hazardous materials and help provide a safe working environment for NIF personnel.
Date: July 25, 2011
Creator: Dobson, D; Churby, A; Krieger, E; Maloy, D & White, K
Partner: UNT Libraries Government Documents Department

Long Length Contaminated Equipment Retrieval System Receiver Trailer and Transport Trailer Operations and Maintenance Manual

Description: A system to accommodate the removal of long-length contaminated equipment (LLCE) from Hanford underground radioactive waste storage tanks was designed, procured, and demonstrated, via a project activity during the 1990s. The system is the Long Length Contaminated Equipment Removal System (LLCERS). LLCERS will be maintained and operated by Tank Farms Engineering and Operations organizations and other varied projects having a need for the system. The responsibility for the operation and maintenance of the LLCERS Receiver Trailer (RT) and Transport Trailer (TT) resides with the RPP Characterization Project Operations organization. The purpose of this document is to provide vendor supplied operating and maintenance (O & M) information for the RT and TT in a readily retrievable form. This information is provided this way instead of in a vendor information (VI) file to maintain configuration control of the operations baseline as described in RPP-6085, ''Configuration Management Plan for Long Length Contaminated Equipment Receiver and Transport Trailers''. Additional Operations Baseline documents are identified in RPP-6085.
Date: May 1, 2000
Creator: DALE, R.N.
Partner: UNT Libraries Government Documents Department

Software Configuration Management Plan for the K West Basin Integrated Water Treatment System (IWTS) Project A.9

Description: This document provides a configuration control plan for the software associated with the operation and control of the Integrated Water Treatment System (IWTS). It establishes requirements for ensuring configuration item identification, configuration control, configuration status accounting, defect reporting and resolution of computer software. It is written to comply with HNF-SD-SNF-CM-001, Spent Nuclear Fuel Configuration Management Plan (Forehand 1998) and HNF-PRO-309 Computer Software Quality Assurance Requirements, and applicable sections of administrative procedure CM-6-037-00, SNF Project Process Automation Software and Equipment.
Date: May 1, 2000
Creator: GREEN, J.W.
Partner: UNT Libraries Government Documents Department

WinCal system configuration control board (SCCB) operating procedure

Description: This document describes the operating procedure for the System Configuration Control Board (SCCB) performed in support of the Windows Calorimeter Control (WinCal) system. This board will consist of representatives from Babcock & Wilcox Hanford Company Babcock & Wilcox Protec, Inc.; and Lockheed Martin Services, Inc. In accordance with agreements for the joint use of the Babcock & Wilcox Hanford Company calorimeters located in the Hanford Site Plutonium Finishing Plant (PFP) Nondestructive Assay Laboratory, concurrence regarding changes to the WinCal system will be obtained from the International Atomic Energy Agency (IAEA). Further, changes to the WinCal software will be communicated to Los Alamos National Laboratory.
Date: March 26, 1997
Creator: Westsik, G.A.
Partner: UNT Libraries Government Documents Department

An Accelerator Control Middle Layer Using MATLAB

Description: Matlab is an interpretive programming language originally developed for convenient use with the LINPACK and EISPACK libraries. Matlab is appealing for accelerator physics because it is matrix-oriented, provides an active workspace for system variables, powerful graphics capabilities, built-in math libraries, and platform independence. A number of accelerator software toolboxes have been written in Matlab -- the Accelerator Toolbox (AT) for model-based machine simulations, LOCO for on-line model calibration, and Matlab Channel Access (MCA) to connect with EPICS. The function of the MATLAB ''MiddleLayer'' is to provide a scripting language for machine simulations and on-line control, including non-EPICS based control systems. The MiddleLayer has simplified and streamlined development of high-level applications including configuration control, energy ramp, orbit correction, photon beam steering, ID compensation, beam-based alignment, tune correction and response matrix measurement. The database-driven Middle Layer software is largely machine-independent and easy to port. Six accelerators presently use the software package with more scheduled to come on line soon.
Date: May 15, 2005
Creator: Portmann, Gregory J.; Corbett, Jeff & Terebilo, Andrei
Partner: UNT Libraries Government Documents Department

System Configuration Management Implementation Procedure for the Canister Storage Building (CSB)

Description: This document provides configuration management for the Distributed Control System (DCS), the Gaseous Effluent Monitoring System (GEMS-100) System, the Heating Ventilation and Air Conditioning (HVAC) Programmable Logic Controller (PLC), the Canister Receiving Crane (CRC) CRN-001 PLC, and both North and South vestibule door interlock system PLCs at the Canister Storage Building (CSB). This procedure identifies and defines software configuration items in the CSB control and monitoring systems, and defines configuration control throughout the system life cycle. Components of this control include: configuration status accounting; physical protection and control; and verification of the completeness and correctness of these items.
Date: November 28, 2000
Creator: GARRISON, R.C.
Partner: UNT Libraries Government Documents Department

Spent Nuclear Fuel Project document control and Records Management Program Description

Description: The Spent Nuclear Fuel (SNF) Project document control and records management program, as defined within this document, is based on a broad spectrum of regulatory requirements, Department of Energy (DOE) and Project Hanford and SNF Project-specific direction and guidance. The SNF Project Execution Plan, HNF-3552, requires the control of documents and management of records under the auspices of configuration control, conduct of operations, training, quality assurance, work control, records management, data management, engineering and design control, operational readiness review, and project management and turnover. Implementation of the controls, systems, and processes necessary to ensure compliance with applicable requirements is facilitated through plans, directives, and procedures within the Project Hanford Management System (PHMS) and the SNF Project internal technical and administrative procedures systems. The documents cited within this document are those which directly establish or define the SNF Project document control and records management program. There are many peripheral documents that establish requirements and provide direction pertinent to managing specific types of documents that, for the sake of brevity and clarity, are not cited within this document.
Date: May 18, 2000
Creator: MARTIN, B.M.
Partner: UNT Libraries Government Documents Department

System Configuration Management Implementation Procedure for the Canister Storage Building (CSB)

Description: This document implements the procedure for providing configuration control for the monitoring and control systems associated with the operation of the Canister Storage Building (CSB). It identifies and defines the configuration items in the monitoring and control systems, provides configuration control of these items throughout the system life cycle, provides configuration status accounting, physical protection and control, and verifies the completeness and correctness of the items. It is written to comply with HNF-SD-SNF-CM-001, Spent Nuclear Fuel Configuration Management Plan (Forehand 1998), HNF-PRO-309, Computer Software Quality Assurance Requirements, HNF-PRO-2778, IRM Application Software System Life Cycle Standards, and applicable sections of administrative procedure AP-CM-6-037-00, SNF Project Process Automation Software and Equipment Configuration Management.
Date: September 22, 2000
Creator: GARRISON, R.C.
Partner: UNT Libraries Government Documents Department

Risk-based configuration control: Application of PSA in improving technical specifications and operational safety

Description: Risk-based configuration control is the management of component configurations using a risk perspective to control risk and assure safety. A configuration, as used here, is a set of component operability statuses that define the state of a nuclear power plant. If the component configurations that have high risk implications do not occur, then the risk from the operation of nuclear power plants would be minimal. The control of component configurations, i.e., the management of component statuses, to minimize the risk from components being unavailable, becomes difficult, because the status of a standby safety system component is often not apparent unless it is tested. Controlling plant configuration from a risk-perspective can provide more direct risk control and also more operational flexibility by allowing looser controls in areas unimportant to risk. Risk-based configuration control approaches can be used to replace parts of nuclear power plant Technical Specifications. With the advances in probabilistic safety assessment (PSA) technology, such approaches to improve Technical Specifications and operational safety are feasible. In this paper, we present an analysis of configuration risks, and a framework for risk-based configuration control to achieve the desired control of risk-significant configurations during plant operation.
Date: November 1, 1992
Creator: Samanta, P. K.; Kim, I. S. & Vesely, W. E.
Partner: UNT Libraries Government Documents Department

Assessing Risk and Driving Risk Mitigation for First-of-a-Kind Advanced Reactors

Description: Planning and decision making amidst programmatic and technological risks represent significant challenges for projects. This presentation addresses the four step risk-assessment process needed to determine clear path forward to mature needed technology and design, license, and construct advanced nuclear power plants, which have never been built before, including Small Modular Reactors. This four step process has been carefully applied to the Next Generation Nuclear Plant. STEP 1 - Risk Identification Risks are identified, collected, and categorized as technical risks, programmatic risks, and project risks, each of which result in cost and schedule impacts if realized. These include risks arising from the use of technologies not previously demonstrated in a relevant application. These risks include normal and accident scenarios which the SMR could experience including events that cause the disablement of engineered safety features (typically documented in Phenomena Identification Ranking Tables (PIRT) as produced with the Nuclear Regulatory Commission) and design needs which must be addressed to further detail the design. Product - Project Risk Register contained in a database with sorting, presentation, rollup, risk work off functionality similar to the NGNP Risk Management System . STEP 2 - Risk Quantification The risks contained in the risk register are then scored for probability of occurrence and severity of consequence, if realized. Here the scoring methodology is established and the basis for the scoring is well documented. Product - Quantified project risk register with documented basis for scoring. STEP 3 - Risk Handling Strategy Risks are mitigated by applying a systematic approach to maturing the technology through Research and Development, modeling, test, and design. A Technology Readiness Assessment is performed to determine baseline Technology Readiness Levels (TRL). Tasks needed to mature the technology are developed and documented in a roadmap. Product - Risk Handling Strategy. STEP 4 - Residual Risk Work off ...
Date: September 1, 2011
Creator: Collins, John W.
Partner: UNT Libraries Government Documents Department

Civilian Radioactive Waste Management System Requirements Document

Description: The CRD addresses the requirements of Department of Energy (DOE) Order 413.3-Change 1, ''Program and Project Management for the Acquisition of Capital Assets'', by providing the Secretarial Acquisition Executive (Level 0) scope baseline and the Program-level (Level 1) technical baseline. The Secretarial Acquisition Executive approves the Office of Civilian Radioactive Waste Management's (OCRWM) critical decisions and changes against the Level 0 baseline; and in turn, the OCRWM Director approves all changes against the Level 1 baseline. This baseline establishes the top-level technical scope of the CRMWS and its three system elements, as described in section 1.3.2. The organizations responsible for design, development, and operation of system elements described in this document must therefore prepare subordinate project-level documents that are consistent with the CRD. Changes to requirements will be managed in accordance with established change and configuration control procedures. The CRD establishes requirements for the design, development, and operation of the CRWMS. It specifically addresses the top-level governing laws and regulations (e.g., ''Nuclear Waste Policy Act'' (NWPA), 10 Code of Federal Regulations (CFR) Part 63, 10 CFR Part 71, etc.) along with specific policy, performance requirements, interface requirements, and system architecture. The CRD shall be used as a vehicle to incorporate specific changes in technical scope or performance requirements that may have significant program implications. Such may include changes to the program mission, changes to operational capability, and high visibility stakeholder issues. The CRD uses a systems approach to: (1) identify key functions that the CRWMS must perform, (2) allocate top-level requirements derived from statutory, regulatory, and programmatic sources, and (3) define the basic elements of the system architecture and operational concept. Project-level documents address CRD requirements by further defining system element functions, decomposing requirements into significantly greater detail, and developing designs of system components, facilities, and equipment. The CRD addresses ...
Date: May 10, 2006
Creator: Kouts, C.A.
Partner: UNT Libraries Government Documents Department

NIF Projects Controls and Information Systems Software Quality Assurance Plan

Description: Quality achievement for the National Ignition Facility (NIF) and the National Ignition Campaign (NIC) is the responsibility of the NIF Projects line organization as described in the NIF and Photon Science Directorate Quality Assurance Plan (NIF QA Plan). This Software Quality Assurance Plan (SQAP) is subordinate to the NIF QA Plan and establishes quality assurance (QA) activities for the software subsystems within Controls and Information Systems (CIS). This SQAP implements an activity level software quality assurance plan for NIF Projects as required by the LLNL Institutional Software Quality Assurance Program (ISQAP). Planned QA activities help achieve, assess, and maintain appropriate quality of software developed and/or acquired for control systems, shot data systems, laser performance modeling systems, business applications, industrial control and safety systems, and information technology systems. The objective of this SQAP is to ensure that appropriate controls are developed and implemented for management planning, work execution, and quality assessment of the CIS organization's software activities. The CIS line organization places special QA emphasis on rigorous configuration control, change management, testing, and issue tracking to help achieve its quality goals.
Date: March 18, 2011
Creator: Fishler, B
Partner: UNT Libraries Government Documents Department

Safety and Security Interface Technology Initiative

Description: Safety and Security Interface Technology Initiative Mr. Kevin J. Carroll Dr. Robert Lowrie, Dr. Micheal Lehto BWXT Y12 NSC Oak Ridge, TN 37831 865-576-2289/865-241-2772 carrollkj@y12.doe.gov Work Objective. Earlier this year, the Energy Facility Contractors Group (EFCOG) was asked to assist in developing options related to acceleration deployment of new security-related technologies to assist meeting design base threat (DBT) needs while also addressing the requirements of 10 CFR 830. NNSA NA-70, one of the working group participants, designated this effort the Safety and Security Interface Technology Initiative (SSIT). Relationship to Workshop Theme. “Supporting Excellence in Operations Through Safety Analysis,” (workshop theme) includes security and safety personnel working together to ensure effective and efficient operations. One of the specific workshop elements listed in the call for papers is “Safeguards/Security Integration with Safety.” This paper speaks directly to this theme. Description of Work. The EFCOG Safety Analysis Working Group (SAWG) and the EFCOG Security Working Group formed a core team to develop an integrated process involving both safety basis and security needs allowing achievement of the DBT objectives while ensuring safety is appropriately considered. This effort garnered significant interest, starting with a two day breakout session of 30 experts at the 2006 Safety Basis Workshop. A core team was formed, and a series of meetings were held to develop that process, including safety and security professionals, both contractor and federal personnel. A pilot exercise held at Idaho National Laboratory (INL) in mid-July 2006 was conducted as a feasibility of concept review. Work Results. The SSIT efforts resulted in a topical report transmitted from EFCOG to DOE/NNSA in August 2006. Elements of the report included: Drivers and Endstate, Control Selections Alternative Analysis Process, Terminology Crosswalk, Safety Basis/Security Documentation Integration, Configuration Control, and development of a shared ‘tool box’ of information/successes. Specific Benefits. The expectation ...
Date: May 1, 2007
Creator: Lehto, Dr. Michael A.; Carroll, Kevin J. & Lowrie, Dr. Robert
Partner: UNT Libraries Government Documents Department

Status Report on the Creation of a Preliminary Data Model and Dictionary for a New Petrologic Database

Description: A preliminary database has been developed that will allow mineralogy and bulk-rock geochemical information to be managed under configuration control and facilitate electronic querying. The database is currently developed in Microsoft Access as a collection of tables, views, and entry forms. Each field and table has been described in a data dictionary.
Date: June 30, 2008
Creator: Mackley, Rob D.; Serkowski, John A. & Last, George V.
Partner: UNT Libraries Government Documents Department

Selection and Traceability of Parameters To Support Hanford-Specific RESRAD Analyses -- Fiscal Year 2008 Status Report

Description: In fiscal years 2007 and 2008, the Hanford Site Groundwater Remediation Project, formerly managed by Fluor Hanford, Inc., requested the Pacific Northwest National Laboratory (PNNL) to support the development and initial implementation of a strategy to establish and maintain, under configuration control, a set of Hanford-specific flow and transport parameter estimates that can be used to support Hanford Site assessments. This document provides a summary of those efforts, culminating in a set of best-estimate Hanford-specific parameters for use in place of the default parameters used in the RESRAD code. The RESRAD code is a computer model designed to estimate radiation doses and risks from RESidual RADioactive materials. The long-term goals of the PNNL work are to improve the consistency, defensibility, and traceability of parameters and their ranges of variability, and to ensure a sound basis for assigning parameters for flow and transport models in the code. The strategy was to start by identifying the existing parameter data sets most recently used in site assessments, documenting these parameter data sets and the raw data sets on which they were based, and using the existing parameter sets to define best-estimate parameters for use in the RESRAD code. The Hanford-specific assessment parameters compiled for use in RESRAD are traceable back to the professional judgment of the authors of published documents. Within the references, parameters are often not directly traceable back to the raw data and analytical approaches used to derive the assessment parameters. Future activities will work to continuously improve the defensibility and traceability of the parameter data sets and to address limitations and technical issues associated with the existing assessment parameter data sets.
Date: July 24, 2009
Creator: Last, George V.; Rockhold, Mark L.; Murray, Christopher J. & Cantrell, Kirk J.
Partner: UNT Libraries Government Documents Department