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DOE OSTI2018

Xyce TM Parallel Electronic Simulator Reference Guide, Version 6.9

This document is a reference guide to the Xyce Parallel Electronic Simulator, and is a companion document to the Xyce Users' Guide. The focus of this document is (to the extent possible) exhaustively list device parameters, solver options, parser options, and other usage details of Xyce . This document is not intended to be a tutorial. Users who are new to circuit simulation are better served by the Xyce Users' Guide.

42 ENGINEERING↗
DOE OSTI2019

The Historic Water, Sewer, and Steam/HTHW Systems in Mercury, Area 23, Nevada National Security Site, Nye County, Nevada (Appendix B - Resource Forms)

This report provides documentation intended to satisfy the mitigation requirements for a substantial portion of the above- and belowground utilities in Mercury on the Nevada National Security Site (NNSS) outlined in the associated Memorandum of Agreement (MOA). The U.S. Department of Energy, National Nuclear Security Administration Nevada Field Office (NNSA/NFO) manages the property and anticipates conducting activities in the future that will affect these resources. These structures are entirely within the Mercury Historic District, which is eligible to the National Register of Historic Places. The district is considered eligible under Criteria A and C for the theme of nuclear testing, with a period of significance from 1951 through 1992. The utilities addressed here include the systems related to potable water and steam/high temperature hot water distribution, as well as the sewage system. More specifically, this documentation covers these underground utilities that were installed in Mercury from 1951 through 1977 and above-ground components installed from 1951 through 1992. Introduction The information in this report is intended to meet the requirements of the Memorandum of Agreement between the National Nuclear Security Administration Nevada Field Office (NNSA/NFO) and the Nevada State Historic Preservation Officer Regarding Water and Sewer Upgrades at Mercury in Nye County, Nevada (MOA) signed on January 30, 2018. The purpose of the MOA is to mitigate the adverse effects of proposed activities on utilities in the Mercury Historic District. The MOA covers the potable water, sewage, and steam/high temperature hot water (HTHW) systems in Mercury. A historic context related to the district as a whole is documented in Reno et al. The State Historic Preservation Officer (SHPO) has concurred with NNSA/NFO’s determination that the district is eligible for listing in the National Register of Historic Places (NRHP) under Criteria A and C at the national level, with a period of significance of 1951 to 1992, which encompasses the period of nuclear testing at the Nevada National Security Site. The utility systems are not considered individually eligible for the National Register, but are contributing components to the eligibility of the district. This report combines information from an unpublished preliminary historic context on the underground utilities written prior to the initiation of recording activities and included as an attachment to the MOA and new data acquired during the course of meeting the MOA requirements. In addition to documenting the underground utility components exposed during excavation of discovery holes to verify pipe locations, Desert Research Institute (DRI) also recorded numerous above-ground elements and equipment in accessible vaults to develop a more complete representation of the historic utilities in Mercury. The information below is organized in the order it is discussed in the MOA.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2019

Xyce Parallel Electronic Simulator Reference Guide (V.6.12)

This document is a reference guide to the Xyce Parallel Electronic Simulator, and is a companion document to the Xyce Users' Guide [1]. The focus of this document is (to the extent possible) exhaustively list device parameters, solver options, parser options, and other usage details of Xyce. This document is not intended to be a tutorial. Users who are new to circuit simulation are better served by the Xyce Users' Guide.

47 OTHER INSTRUMENTATION↗
DOE OSTI2019

MELCOR Code Change History: Revision 11932 to 14959 Patch Release Addendum

This document summarily provides brief descriptions of the MELCOR code enhancement made between code revision number 11932 and 14959. Revision 11932 represents the last official code release; therefore, the modeling features described within this document are provided to assist users that update to the newest official MELCOR code release, 14959. Along with the newly updated MELCOR Users' Guide and Reference Manual, users will be aware and able to assess the new capabilities for their modeling and analysis applications. Following the official release an addendum section has been added to this report detailing modifications made to the official release which support the accompanying patch release. The addendums address user reported issues and previously known issues within the official code release which extends the original Quick look document to also support the patch release. Furthermore, the addendums section documents the recent changes to input records in the Users' Guide applicable to the patch release and corrects a few issues in the revision 14959 release as well.

97 MATHEMATICS AND COMPUTING↗
DOE OSTI2019

SNL CSP Library Archive Project (FY19 Report)

Sandia National Laboratories (SNL) National Solar Thermal Test Facility (NSTTF) and Tech Library have been collaborating over the course of the FY19 period to establish and maintain the first and only digital collection in the world of Concentrating Solar Power (CSP) related historical documents, dating back to the CSP program inception here at Sandia in the 1970's thru to the present. The unclassified, unrestricted (UUR) collection, comprised of internally generated Sandia documents as well as a significant number of external reports will be searchable via both the Sandia website and OSTI, DOE's document repository. DOE is currently championing efforts to get the collection launched, where international partners, which include Australia and Germany, plan to forward related documents to be included in the CSP archive. Advancing this transformative project will make the CSP collection accessible to the Sandia and global communities.

14 SOLAR ENERGY↗
DOE OSTI2020

MCNP6 Source Primer: Release 1.0

This document contains examples of MCNP general source usage to support the MCNP6 User’s Manual. The examples range from basic to advanced sources with different applications. There are also examples of how MCNP can fail and warnings for the users to look for at the output to ensure proper results are being created. The overall aim of this document is to provide solid examples of how to define sources with MCNP as well as how to verify the sources are setup properly. The reasoning for needing such complex sources is not discussed in the present work. Also, this document is not meant to be exhaustive of every MCNP source option and combinations of source options possible. However, it is intended to frequently update this document with new source examples provided by users. Please feel free to contact the MCNP6 development team to learn about how to submit a new or updated source example. Please include “General Sources Primer” in the subject line to route the request to the appropriate developers.

97 MATHEMATICS AND COMPUTING↗
DOE OSTI2020

Scan of an Unpublished Report: "Fission Product Behavior During Severe LWR Accidents: Recommendations for the MELCOR Code System"

This document provides a scanned version of a 1987 SAND report that was never formally published. However, this report was referenced within the MELCOR Reference Manual and, therefore, provides historical information and technical basis for the MELCOR code. This document is being made available to permit users of the MELCOR code access to the information. The title page has been edited to prevent any confusion with regards to the possible documentation identifiers, such as the SAND report number or the intended date of publication. Beyond these modifications, a cover, distribution, and back cover are prepended and appended to the document to conform to modern SAND report style guidelines. The first four chapters of this report were updated and released under the title "Fission Product Behavior During Severe LWR Accidents: Recommendations for the MELCOR Code System. Volume I" and were made available by the U.S. NRC through the Adams database under accession number ML19227A327. No prior release of the remaining content of this report has occurred.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2020

Verification and Validation of the PLTEMP/ANL Code for Thermal-Hydraulic Analysis of Experimental and Test Reactors

The document compiles in a single volume the verification and validation works done for the PLTEMP/ANL code during the years of its development and improvement. The verification of sixteen capabilities of the PLTEMP/ANL Version 4.3 code that were identified by research reactor analysts as frequently used in their thermal-hydraulic analysis are described and documented. Each chapter of the document deals with the verification or validation of a specific model. The model verification is usually done by comparing the code with hand calculation, Microsoft spreadsheet calculation, or Mathematica calculation. The model validation is done by comparing the code with experimental data or a widely tested code like the RELAP5 code. In addition, some PLTEMP/ANL verification works that are available in the open literature are simply referenced and not included in the document. PLTEMP/ANL has been used in conversion safety analysis reports of several US and foreign research reactors that have been licensed and converted. A list of such reactors is given.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2020

Vadose Zone Model for B-3A/B Pond for Composite Analysis

The objectives of the vadose modeling for the updated Hanford Site composite analysis (CA) are to simulate the flow and transport of water and radionuclide releases from the surface to the water table and to provide radionuclide transfer rates for the plateau to river (P2R) model, version 8.3 (CP-57037, Model Package Report: Plateau to River Groundwater Model, Version 8.3). Water additions include natural recharge and water discharged to the ground as a result of industrial processes associated with Hanford Site operations. Contaminant sources include radionuclides in water discharged to the ground during operations and radionuclides disposed “dry” in solid waste burial grounds or other means. The following 16 radionuclides were selected for this modeling effort; carbon-14 (C-14), chlorine-36 (Cl-36), tritium (H-3), iodine-129 (I-129), neptunium-237 (Np-237), rhenium-187 (Re-187), strontium-90 (Sr-90), technetium-99 (Tc-99), uranium-232 (U-232), uranium-233 (U-233), uranium-234 (U-234), uranium-235 (U-235), uranium-236 (U-236), uranium-238 (U-238), radium-226 (Ra-226), and thorium-230 (Th-230). The simulation time starts in 1943 and ends at 12070, which is 10,000 years after assumed Hanford Site closure in 2070. The parallel version of the Subsurface Transport Over Multiple Phases (STOMP) simulator officially named the exascale Subsurface Transport Over Multiple Phases (eSTOMP), is used to simulate flow and transport for the vadose models. The documentation for the STOMP code is comprehensive. The theoretical and numerical approaches applied in the STOMP code are documented in a published theory guide (PNNL-12030, STOMP Subsurface Transport Over Multiple Phases Version 2.0 Theory Guide). The code has undergone a rigorous verification procedure against analytical solutions, laboratory-scale experiments, and field-scale demonstrations. The application guide (PNNL-11216, STOMP Subsurface Transport Over Multiple Phases Application Guide) provides instructive examples in the application of the code to classical groundwater problems. The user’s guide (PNNL-15782, STOMP: Subsurface Transport Over Multiple Phases Version 4.0: User’s Guide) describes the general use, input file formatting, compilation, and execution of the code. The primary output of the vadose zone modeling is radionuclide transfer rates to the groundwater for input into the P2R model. The rates will be summed over the 100 by 100 m P2R grid cells that fall within the vadose zone model source domain. The Hanford Site Central Plateau was subdivided into 26 individual vadose zone models, with 13 in the 200 East Area and 13 in the 200 West Area. Waste sites that have a completed performance assessment (PA) or past-leak analysis were not included as sources of radionuclides. Instead the vadose zone to groundwater transfer rates of the Environmental Restoration Disposal Facility, Integrated Disposal Facility, US Ecology, and Waste Management Area C (WMA C) PAs and the past-leak analysis for WMA C were used as direct input to the P2R model. Each of the vadose zone models is documented in separate environmental calculation files (ECFs). This ECF describes the B-3A/B Ponds model. The scope of this ECF is to document the development and results of the B-3 A/B Ponds vadose zone model. CP-63515, Model Package Report: Central Plateau Vadose Zone Models, describes the approach, assumptions, process of determining the number of models required and domain of each model, input data, and processing common to all the models.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

Review of Amendment Delivery and Distribution Methods, and Relevance to Potential In Situ Source Area Treatment at the Hanford Site

The U.S. Department of Energy’s Hanford Site in southeastern Washington State is a complex of multiple facilities where historical release events in the Central Plateau area have resulted in subsurface contamination of the vadose zone, a perched-water zone, and underlying aquifer. Although some contaminants have already migrated through the vadose zone into the groundwater, contaminants remaining in the unsaturated zone are a potential long-term risk as a source for further groundwater contamination. Moreover, a perched-water zone located in the 200-DV-1 Operable Unit at Hanford creates further remediation difficulties. Remediation options are limited for contaminants located in the vadose and perched-water zones within the Central Plateau due to considerable depth, co-located contaminants, and complexities associated with physical and biogeochemical heterogeneities. Existing comprehensive reviews discuss potential remedial technologies relevant to Hanford Site conditions (e.g., deep vadose zone and perched water) and provide treatment technology recommendations. Many of the recommended in situ remediation technologies rely on introduction of amendments into the subsurface to achieve remedial goals. However, there are currently few review or guidance documents that provide a comprehensive look at mechanisms and considerations related to amendment delivery and distribution. This document summarizes amendment types, delivery techniques, subsurface access methods, and the applicability of delivery methods and amendments for specific subsurface target zones, including in the context of Hanford Central Plateau applications. Guidance on the appropriateness of a remedial technology for a specific site and contaminant is not included within this document. Rather, this document is intended to be used when considering remediation technologies and the associated amendments. An overview of amendment types (i.e., liquid, gas, and solids) and access/distribution methods used in subsurface remediation is provided, along with discussion of the maturity level (low, medium, or high), advantages, and limitations that relate to the potential effectiveness of each approach in the context of site-specific factors (subsurface geology, geochemistry, contaminant properties, etc.). There are many Hanford Site-specific factors that influence the suitability and appropriateness of amendment delivery strategies. Excluding amendment delivery approaches that are unsuitable for the Hanford context, each approach was assessed for applicability to the following target zones: unsaturated high permeability, unsaturated low permeability, perched water, saturated high permeability, and saturated low permeability zones. This compilation and discussion related to amendment delivery mechanisms provides a useful resource for evaluating remedial alternatives for source area contamination in the Hanford Central Plateau.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2020

Vadose Zone Model for SALDS for Composite Analysis

The objectives of the vadose modeling for the updated Hanford Site composite analysis (CA) are to simulate the flow and transport of water and radionuclide releases from the surface to the water table and to provide radionuclide transfer rates for the plateau to river (P2R) model, version 8.3 (CP-57037, Model Package Report: Plateau to River Groundwater Model, Version 8.3). Water additions include natural recharge and water discharged to the ground as a result of industrial processes associated with Hanford Site operations. Contaminant sources include radionuclides in water discharged to the ground during operations and radionuclides disposed “dry” in solid waste burial grounds or other means. The following 16 radionuclides were selected for this modeling effort: carbon-14 (C-14), chlorine-36 (Cl-36), tritium (H-3), iodine-129 (I-129), neptunium-237 (Np-237), rhenium-187 (Re-187), strontium-90 (Sr-90), technetium-99 (Tc-99), uranium-232 (U-232), uranium-233 (U-233), uranium-234 (U-234), uranium-235 (U-235), uranium-236 (U-236), uranium-238 (U-238), radium-226 (Ra-226), and thorium-230 (Th-230). The simulation time starts in 1943 and ends at 12070, which is 10,000 years after assumed Hanford Site closure in 2070. The parallel version of the Subsurface Transport Over Multiple Phases (STOMP1) simulator, officially named the exascale Subsurface Transport Over Multiple Phases (eSTOMP) is used to simulate flow and transport for the vadose models. The documentation for the STOMP code is comprehensive. The theoretical and numerical approaches applied in the STOMP code are documented in a published theory guide (PNNL-12030, STOMP Subsurface Transport Over Multiple Phases Version 2.0 Theory Guide). The code has undergone a rigorous verification procedure against analytical solutions, laboratory-scale experiments, and field-scale demonstrations. The application guide (PNNL-11216, STOMP Subsurface Transport Over Multiple Phases Application Guide) provides instructive examples in the application of the code to classical groundwater problems. The user’s guide (PNNL-15782, STOMP: Subsurface Transport Over Multiple Phases Version 4.0: User’s Guide) describes the general use, input file formatting, compilation, and execution of the code. The primary output of the vadose zone modeling is radionuclide transfer rates to the groundwater for input into the P2R model. The rates will be summed over the 100 by 100 m P2R grid cells that fall within the vadose zone model source domain. The Hanford Site Central Plateau was subdivided into 26 individual vadose zone models, with 13 in the 200 East Area and 13 in the 200 West Area. Waste sites that have a completed performance assessment (PA) or past-leak analysis were not included as sources of radionuclides. Instead the vadose zone to groundwater transfer rates of the Environmental Restoration Disposal Facility, Integrated Disposal Facility, US Ecology, and Waste Management Area C (WMA C) PAs and the past-leak analysis for WMA C were used as direct input to the P2R model. Each of the vadose zone models is documented in separate environmental calculation files (ECFs). This ECF describes the State-Approved Land Disposal Site (SALDS) model. The scope of this ECF is to document the development and results of the SALDS vadose zone model. CP-63515, Model Package Report: Central Plateau Vadose Zone Models, describes the approach, assumptions, process of determining the number of models required and domain of each model, input data, and processing common to all the models.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2020

Data call questions related to potential NEPA/Data gaps

Based on review of the related NEPA documents, and consideration of the potential gaps in NEPA coverage, a number of questions have been generated. These questions are generally higher level (less detailed) questions that should help to establish the applicability of analyses in existing NEPA documents and the ability of these documents to provide NEPA coverage for the Proposed Action. These questions do not request detailed information about SRS facilities/activities and the Proposed Action like typically would be requested when performing impacts analyses for an EIS. We do not believe detail information is needed; if it is needed, it may be an indication that an SA is not the appropriate level of NEPA documentation for the Proposed Action.

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2020

Xyce Parallel Electronic Simulator Reference Guide (Version 7.2)

This document is a reference guide to the Xyce Parallel Electronic Simulator, and is a companion document to the Xyce Users Guide. The focus of this document is (to the extent possible) exhaustively list device parameters, solver options, parser options, and other usage details of Xyce. This document is not intended to be a tutorial. Users who are new to circuit simulation are better served by the Xyce Users Guide.

42 ENGINEERING↗
DOE OSTI2021

G3P3 Phase 3 Project Execution Plan. Issue 1

The National Solar Thermal Test Facility (NSTTF) at Sandia National Laboratories New Mexico (SNL/NM) developed this Project Execution Plan (PEP) to document its process for executing, monitoring, controlling and closing-out Phase 3 of the Gen 3 Particle Pilot Plant G3P3. This plan serves as a resource for stakeholders who wish to be knowledgeable of project objectives and how they will be accomplished. The plan is intended to be used by the development partners, principal investigator, and the federal project director. Project objectives are derived from the mission needs statement, and an integrated project team assists in development of the PEP. This plan is a living document and will be updated throughout the project to describe current and future processes and procedures. The scope of the PEP covers: Cost, schedule, and scope Project reporting Staffing plan Quality assurance plan Environment, safety, security, and health This document is a tailored approach for the Facilities Management and Operations Center (FMOC) to meet the project management principles of DOE Order 413.3B, Program and Project Management for the Acquisition of Capital Assets , and DOE G 413.3-15, DOE Guide for Project Execution Plans. This document will elaborate on content as knowledge of the project is gained or refined.

14 SOLAR ENERGY↗
DOE OSTI2015

Draft Operating Procedures for a Generic Repository Licensing Organization

This document is milestone M4FT-15SN0826021: Draft Summary of principle operating procedures for a generic repository licensing organization, the result of efforts under work package FT-15SN082602 DOE Managed HLW and SNF Research: Generic Operating Procedures; e.g., Quality Assurance — Sandia National Laboratories (SNL). The objective of this effort was to develop this draft document identifying and summarizing the principle operating procedures for a generic repository licensing organization. The FY16 follow on work package is FT-165N050303: Develop and Implement Operating Procedures — SNL, having a consistent objective to develop a draft document identifying and summarizing the principle operating procedures for a generic repository licensing organization. This document identifies and describes the principle operating procedures for a hypothetical and generic organization with the responsibility to site, characterize, design, license, construct and operate a repository for the disposal of high-level radioactive waste (HLW) and spent nuclear fuel (SNF) managed by the Department of Energy. These principle operating procedures reflect practices that facilitate compliance with U.S. Nuclear Regulatory Commission (NRC) expectations and NQA-1 quality standards.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2015

Draft Infrastructure Framework for a Generic Repository Licensing Organization

This document is milestone M4FT-15SN0826011: Draft Summary of generic repository licensing infrastructure, the result of efforts under work Package FT-15SN082601 DOE Managed HLW and SNF Research: Establish a generic organization framework for records management, IT infrastructure, quality assurance, and systems engineering - Sandia National Laboratories (SNL). The objective of this effort was to develop this draft document identifying and summarizing the principle elements of a generic repository licensing infrastructure organizational framework. The FY16 follow on work package is FT-16SN050302- Establish organizational framework to meet regulator expectations - SNL, having the consistent objective to 'Develop a draft document identifying and summarizing the principle elements of a generic repository licensing infrastructure and organizational framework.' This document describes the framework for a generic hypothetical organization with the responsibility to site, characterize, design, license construct and operate a repository for the disposal of high-level radioactive waste (HLW) and spent nuclear fuel ( F) managed by the Department of Energy. organizational framework suggested is intended to be agnostic of the facility location and disposal medium. It is assumed that the facility is to be licensed under U.S. Nuclear Regulatory Commission (NRC) regulation with DOE as the applicant (licensee). Detailed organizational elements reflect a workforce composition and practices that facilitate compliance with NRC expectations and NQA-1 quality standards.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2019

Waste stream knowledge assessment memorandum

To ensure that the Acceptable Knowledge (AK) documentation relating to the management of potentially reactive, corrosive, ignitable, and incompatible transuranic (TRU) waste materials is adequate, current, and accurately described in existing AK Summary Reports (AKSR), an Acceptable Knowledge Assessment (AKA) will be performed for each waste stream with unshipped containers or containers that are not emplaced. The primary focus of the AKA will be to review and verify the AK documentation associated with the historic and current use of absorbents, immobilization products, and neutralization agents used in the management of potentially corrosive, ignitable, or reactive liquids. In addition, the AKA will assess the specific management of other potentially incompatible or reactive materials generated at the Building 6580 Hot Cell Facility (HCF) and repackaged at the Auxiliary Hot Cell Facility (AHCF) at the Sandia National Laboratory (SNL). The AKA is performed in accordance with Section 4.13 of the Central Characterization Procedure (CCP) CCPTP- 005, CCP Acceptable Knowledge Documentation. This AKA specifically addresses the subpopulation of containers previously certified by CCP for waste stream SNL-HCF-S5400-RH during AHCF repackaging campaigns 11, 12, 14, and 17 and primarily consists of fuel examination waste (FEW). This subpopulation of containers was generated primarily at the HCF from the late 1970s to mid-1990s, and repackaging history as well as historical information are listed in Attachment 1, Waste Stream SNL-HCF-S5400-RH (FEW lnventory) Containers List. Attachment 2, Waste Stream SNL-HCF-S5400-RH (FEW lnventory) Container Evaluations, presents a summary review of site container documentation and the descriptions from the CCP visual examination (VE) during repackaging at the AHCF.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2019

Sandia National Laboratories Advanced Simulation and Computing (ASC) Appraisal Method for the Implementation of the ASC Software Quality Engineering Practices (V.2.0)

This document provides a guide to the process of conducting software appraisals under the Sandia National Laboratories (SNL) ASC Program. The goal of this document is to describe a common methodology for planning, conducting, and reporting results of software appraisals thereby enabling: 1) Identification of improvements in implementation of the software quality engineering (SQE) practices identified in the ASC Software Quality Plan across the ASC Program against objective baselines. 2) Feedback from project teams on SQE opportunities for improvement. 3) Identification of strengths and opportunities for improvement for individual project teams. 4) Guidance to the ASC Program on the focus of future SQE activities. Document contents include process descriptions, templates to promote consistent conduct of appraisals, and an explanation of the relationship of this procedure to the SNL ASC software program. The activities described by this document are under the oversight of SNL ASC Program Director and SNL ASC Program Manager.

42 ENGINEERING↗