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DOE OSTI2012

Validation of SCALE for High Temperature Gas-Cooled Reactors Analysis

This report documents verification and validation studies carried out to assess the performance of the SCALE code system methods and nuclear data for modeling and analysis of High Temperature Gas-Cooled Reactor (HTGR) configurations. Validation data were available from the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhE Handbook), prepared by the International Reactor Physics Experiment Evaluation Project, for two different HTGR designs: prismatic and pebble bed. SCALE models have been developed for HTTR, a prismatic fuel design reactor operated in Japan and HTR-10, a pebble bed reactor operated in China. The models were based on benchmark specifications included in the 2009, 2010, and 2011 releases of the IRPhE Handbook. SCALE models for the HTR-PROTEUS pebble bed configuration at the PROTEUS critical facility in Switzerland have also been developed, based on benchmark specifications included in a 2009 IRPhE draft benchmark. The development of the SCALE models has involved a series of investigations to identify particular issues associated with modeling the physics of HTGRs and to understand and quantify the effect of particular modeling assumptions on calculation-to-experiment comparisons.

Ilas, Germina↗

DOE OSTI2015

NSRD-06. Computational Capability to Substantiate DOE-HDBK-3010 Data

Safety basis analysts throughout the U.S. Department of Energy (DOE) complex rely heavily on the information provided in the DOE Hand book, DOE-HDBK-3010, Airborne Release Fractions/Rates and Resp irable Fractions for Nonreactor Nuclear Facilities , to determine source terms. In calcula ting source terms, analysts tend to use the DOE Handbook's bounding values on airbor ne release fractions (ARFs) and respirable fractions (RFs) for various cat egories of insults (representing potential accident release categories). This is typica lly due to both time constraints and the avoidance of regulatory critique. Unfort unately, these bounding ARFs/RFs represent extremely conservative values. Moreover, th ey were derived from very limited small- scale table-top and bench/labo ratory experiments and/or fr om engineered judgment. Thus the basis for the data may not be re presentative to the actual unique accident conditions and configura tions being evaluated. The goal of this res earch is to develop a more ac curate method to identify bounding values for the DOE Handbook using the st ate-of-art multi-physics-based high performance computer codes. This enable s us to better understand the fundamental physics and phenomena associated with the ty pes of accidents for the data described in it. This research has examined two of the DOE Handbook's liquid fire experiments to substantiate the airborne release frac tion data. We found th at additional physical phenomena (i.e., resuspension) need to be included to derive bounding values. For the specific cases of solid powder under pre ssurized condition and mechanical insult conditions the codes demonstrated that we can simulate the phenomena. This work thus provides a low-cost method to establis h physics-justified sa fety bounds by taking into account specific geometri es and conditions that may not have been previously measured and/or are too costly to do so.

97 MATHEMATICS AND COMPUTING↗

DOE OSTI2018

NSRD-15:Computational Capability to Substantiate DOE-HDBK-3010 Data

97 MATHEMATICS AND COMPUTING↗

DOE OSTI2018

Criticality Safety Validation of SCALE 6.2.2

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

DOE OSTI2016

Benchmark Development for TREAT Minimum Critical Mass Core Loading to Support Validation of TREAT Operations

Benchmark experiment data is necessary to validate modeling and simulation activities to support Transient Reactor Experiment Test (TREAT) Facility restart and operations. Key measurements of interest include criticality, control rod worth, excess reactivity, and shutdown margin for varying core loading sizes. Benchmark evaluations are being developed according the guidelines provided in the International Handbook of Evaluated Reactor Physics Benchmark Experiments (IRPhEP Handbook) that can also support advanced modeling and simulation activities, new experiment design for advanced reactors and accident tolerant fuel, and potential low-enriched uranium conversion of the TREAT reactor. This summary discusses development activities supporting a benchmark evaluation of the TREAT minimum critical mass core loading, which will be submitted for peer-review and publication in the IRPhEP Handbook with the identifier TREAT-FUND-RESR-001. Detailed models of TREAT were developed and evaluated to prepare benchmark models of the minimum critical mass configuration. Calculations were performed using MCNP6.1 with ENDF/B-VII.1 nuclear data libraries. Discussion of results.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

DOE OSTI2022

FY21 Progress of the Oak Ridge Health Physics Research Reactor CAAS Benchmark Evaluation [Slides]

The FY21 version of the evaluation, focusing on element 57 dose at 3 meters, was presented at the ICSBEP Technical Review Group meeting in October 2021 and was not accepted for 2022 publication in the handbook. The main issue was identified and replacement of the element 57 neutron dose benchmark metric by neutron fluence (closer to what was measured) is required. A subgroup was formed, confident for the updated neutron fluence evaluation to be accepted in the ICSBEP handbook. The updated evaluation will be presented again at the 2022 ICSBEP TRG for publication in the 2023 handbook.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗

DOE OSTI2022

SCALE 6.2.4 Validation: Nuclear Criticality Safety

The computational bias of criticality safety computer codes must be established through the validation of the codes to critical experiments. A large collection of suitable experiments has been vetted by the International Criticality Safety Benchmark Evaluation Project (ICSBEP) and made available in the International Handbook of Evaluated Criticality Safety Benchmark Experiments (ICSBEP Handbook). More than 600 cases from this handbook have been prepared and reviewed within the Verified, Archived Library of Inputs and Data (VALID), which is maintained by the Reactor and Nuclear Systems Division at Oak Ridge National Laboratory. The performance of the KENO V.a and KENO-VI Monte Carlo codes within the SCALE 6.2.4 code system is assessed using the VALID models of benchmark experiments. A range of nuclear cross section libraries based on Evaluated Nuclear Data File (ENDF)/B-VII.1 in both multigroup (MG) and continuous energy (CE) formats is considered. The critical experiments available to validate the KENO V.a code cover 15 broad categories of systems. These systems use a range of fissile materials, including a range of uranium enrichments, various plutonium isotopic vectors, and some mixed uranium/plutonium oxides. The physical forms of the fissile material also vary and are represented as metal, solutions, or arrays of rods or plates in a water moderator. The neutron energy spectra of the systems also vary and cover fast, intermediate, mixed, and thermal spectra. Over 550 of the total cases use the KENO V.a code for the four nuclear data libraries considered in this report.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗

DOE OSTI2025

Final Design for Thermal/Epithermal eXperiments (TEX) with Lithium Absorbers to Provide Validation Benchmarks for Y-12 Electrorefining Facility

One of the main goals of the Thermal/Epithermal eXperiments (TEX) project is to use existing Nuclear Criticality Safety Program (NCSP) assets to create critical experiment plutonium and uranium test beds for materials important to criticality safety that have insufficient benchmark evaluations. The plutonium test bed experiments were completed in 2018 and are published in the 2020 edition of the International Criticality Safety Benchmark Evaluation Project (ICSBEP) Handbook. The uranium test bed assemblies were completed in 2023 and accepted in the 2024 edition of the ICSBEP Handbook. The Nuclear Criticality Safety (NCS) group at Y-12 National Security Complex has identified programmatic need for validation cases for uranium electrorefining operations at Y-12. The electrorefining operation credits lithium enriched in 6 Li in addition to 35 Cl as absorbers in the design criticality safety evaluation for precluding criticality under upset conditions in the large and geometrically unfavorable electro-refiner. There is, however, inadequate experimental validation for the 6 Li absorbers. As an extension of the TEX uranium test bed, TEX-Cl critical experiments were performed with sodium chloride salt to address the 35 Cl thermal absorption as well as other validation needs at Los Alamos National Laboratory (LANL). These experiments were completed in 2024 and accepted into the 2025 ICSBEP Handbook. To continue the methodology used in TEX-Cl, TEX-Li aims to accomplish the same. The overall design of both experiments was to use commercially available, high purity, salts with polyethylene moderator and HEU plates to configure a critical assembly. Three experiments are planned for TEX-Li using encapsulated lithium carbonate (Li 2 CO 3 ), with natural 6 Li abundance. For all experiments, the highly enriched uranium (HEU) Jemima plates will be used as fissile material. Multiple layers will be stacked together with encapsulated Li 2 CO 3 alternated with polyethylene in standard configurations. Standard stacking was found to be optimal in matching the different sensitivity profiles provided by the Y-12 models. Three configurations are proposed with varying polyethylene moderation and a constant 1/4” absorber thickness. The first uses 11 layers of 5/4” polyethylene, the second uses 9 layers of 3/4” polyethylene, and the third uses 10 layers of 1/2” polyethylene. Calculations showed that some alternative forms of lithium-based materials provided slightly less-optimal sensitivity profiles when compared to lithium carbonate but come with other drawbacks. These alternatives included lithium aluminate (LiAlO 2 ), Aluminum-2050 alloy, Aluminum-8090, Aluminum-2095, lithium hydride (LiH), and lithium fluoride (LiF). Lithium aluminate and aluminum-2050 provided comparable sensitivity profiles when compared to lithium carbonate and can be used instead if lithium carbonate cannot be readily procured. After a broad material study, lithium carbonate outperformed any alternative material with a balance in affordability and workability. The assessment of experimental uncertainties of the non-absorber and absorber components was predicted to be 0.00089 and 0.00093 Δk eff , respectively. The largest uncertainties may be reduced with precision dimensional inspection of the components. Many of the parts and equipment for IER 575 have already been fabricated or procured for previous projects and therefore do not contribute significantly to the overall cost of this experiment. This includes the Jemima plates and Comet critical assembly machine, which are existing NCSP assets, as well as the aluminum platen and polyethylene reflector rings, which were fabricated and authorized for the TEX experiment involving HEU with polyethylene. Lithium carbonate containers will be procured by LANL and will be filled by LLNL. The total material costs for TEX-Li experiments are estimated to be on the order of $\$$47,400. Precision inspection, including dimensional, mass, density, and impurity, is recommended for all components for an estimated cost of $\$$12,000.

35Cl↗

DOE OSTI2023

Intrinsic value of the international benchmark projects, ICSBEP and IRPhEP, for advanced reactor development

The International Criticality Safety Benchmark Evaluation Project, a sanctioned program under the auspices of the Nuclear Energy Agency of the Organisation for Economic Co-operation and Development, has been a highly successful and productive collaboration, now encompassing over 5,000 evaluated experimental benchmarks trusted and relied upon throughout the international nuclear communities. The success of this project led to the development of the International Reactor Physics Experiment Evaluation Project, which is dedicated to the evaluation of benchmark experiment data to sustain current and future reactor physics validation needs. These exemplary programs, and their widely utilized handbooks, serve as gold standards to which other databases strive to emulate. The purpose of the two projects is to preserve modern and legacy experimental data and evaluate it in a standardized handbook format to provide quality benchmarks to support modern and future criticality safety and reactor physics validation. These two projects have often served as the mechanism through which historic and modern neutronics experiments are evaluated and shared across international borders, to best provide unique, high-quality peer-reviewed, and often otherwise unavailable, benchmark data. The contents of these handbooks are utilized not only in validating criticality safety, reactor physics, and advanced reactor calculations, but are used to validate neutronics calculations and nuclear data for most other nuclear applications. This paper discusses both international programs and available content to enable advanced reactor design validation.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗

NASA NTRS1988

Pilot factors guidelines for the operational inspection of navigation systems

A computerized human engineered inspection technique is developed for use by FAA inspectors in evaluating the pilot factors aspects of aircraft navigation systems. The short title for this project is Nav Handbook. A menu-driven checklist, computer program and data base (Human Factors Design Criteria) were developed and merged to form a self-contained, portable, human factors inspection checklist tool for use in a laboratory or field setting. The automated checklist is tailored for general aviation navigation systems and can be expanded for use with other aircraft systems, transports or military aircraft. The Nav Handbook inspection concept was demonstrated using a lap-top computer and an Omega/VLF CDU. The program generates standardized inspection reports. Automated checklists for LORAN/C and R NAV were also developed. A Nav Handbook User's Guide is included.

Sadler, J. F.↗

NASA NTRS1989

Utilization and Maintenance of the Federal Catalog System (FCS)

The Federal Catalog System (FCS) was established and substantiated by law to aid the national economy and promote greater efficiency in supply management operations throughout the Federal Government. This Handbook establishes policies and procedures to be followed by NASA installations and certain contractors in cataloging items of supply in the Federal Catalog System and prescribes use of the system in supply management operations. This Handbook is not intended to duplicate the Federal Cataloging Manuals or Federal Cataloging Handbooks. For the most part, it describes actions that are peculiar to NASA.

Source record↗

NASA NTRS1991

Safety, Reliability, and Quality Assurance Provisions for the Office of Aeronautics, Exploration and Technology Centers

This Handbook establishes general safety, reliability, and quality assurance (SR&QA) guidelines for use on flight and ground-based projects conducted at the Ames, Langley, and Lewis Research Centers, hereafter identified as the Office of Aeronautics, Exploration and Technology (OAET) Centers. This document is applicable to all projects and operations conducted at these Centers except for those projects covered by more restrictive provisions such as the Space Shuttle, Space Station, and unmanned spacecraft programs. This Handbook is divided into two parts. The first (Chapters 1 and 2) establishes the SR&QA guidelines applicable to the OAET Centers, and the second (Appendices A, B, C, and D) provides examples and definitions for the total SR&QA program. Each center should implement SR&QA programs using these guidelines with tailoring appropriate to the special projects conducted by each Center. This Handbook is issued in loose-leaf form and will be revised by page changes.

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NASA NTRS1986

Uniform relocation assistance and real property acquisition for Federal and federally-assisted programs

The 'Uniform Relocation Assistance and Real Property Acquisition for Federal and Federally-Assisted Programs' (14 CFR Part 1208) is set forth in this handbook and is hereby incorporated into the NASA Directives System. This handbook is applicable to all NASA installations. An initial supply of this handbook has been furnished to all NASA installations. Additional copies for internal use may be obtained through normal distribution channels.

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NASA NTRS1988

Implementing the Provisions of the National Environmental Policy Act

This handbook provides guidance and assistance to NASA officials in carrying out their responsibilities under the National Environmental Policy Act and the applicable NASA procedures (14 CFR 1216.3, Attachment A to NMI 8800.7). The handbook, as was contemplated by the regulations of the Council on Environmental Quality, stresses the need for environmental analysis from the time of early planning through environmental assessment and environmental impact statement preparation to implementation of the subject action, and provides for necessary follow up. It stresses the need for NASA officials to draw upon all the appropriate disciplines from the natural and social sciences plus the environmental design arts in planning and decision making on actions which may have an impact on the human environment. The handbook is applicable to NASA Headquarters and field installations.

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NASA NTRS1987

NASA Uniform Files Index

This handbook is a guide for the use of all personnel engaged in handling NASA files. It is issued in accordance with the regulations of the National Archives and Records Administration, in the Code of Federal Regulations Title 36, Part 1224, Files Management; and the Federal Information Resources Management Regulation, Subpart 201-45.108, Files Management. It is intended to provide a standardized classification and filing scheme to achieve maximum uniformity and ease in maintaining and using agency records. It is a framework for consistent organization of information in an arrangement that will be useful to current and future researchers. The NASA Uniform Files Index coding structure is composed of the subject classification table used for NASA management directives and the subject groups in the NASA scientific and technical information system. It is designed to correlate files throughout NASA and it is anticipated that it may be useful with automated filing systems. It is expected that in the conversion of current files to this arrangement it will be necessary to add tertiary subjects and make further subdivisions under the existing categories. Established primary and secondary subject categories may not be changed arbitrarily. Proposals for additional subject categories of NASA-wide applicability, and suggestions for improvement in this handbook, should be addressed to the Records Program Manager at the pertinent installation who will forward it to the NASA Records Management Office, Code NTR, for approval. This handbook is issued in loose-leaf form and will be revised by page changes.

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NASA NTRS1987

Standards of conduct for NASA employees

'Standards of Conduct' for employees (14 CFR Part 1207) is set forth in this handbook and is hereby incorporated in the NASA Directives System. This handbook incorporates, for the convenience of NASA employees, the regulations now in effect prescribing standards of conduct for NASA employees. These regulations set forth the high ethical standards of conduct required of NASA employees in carrying out their duties and responsibilities. These regulations have been approved by the Office of Government Ethics, Office of Personnel Management. The regulations incorporated in this handbook were first published in the Federal Register on October 21, 1967 (32 FR 14648-14659); Part B concerning the acceptance of gifts, gratuities, or entertainment was extensively revised on January 19, 1976 (41 FR 2631-2633) to clarify and generally to restrict the exceptions to the general rule against the acceptance by a NASA employee from persons or firms doing or seeking business with NASA. Those regulations were updated on January 29, 1985 (50 FR 3887) to ensure conformity to the Ethics in Government Act of 1978 regarding the public financial disclosure statement. These regulations were published in the Federal Register on June 16, 1987 (52 FR 22755-764) and a correction was printed on Sept. 28, 1987 (52 FR 36234).

John E O'Brien↗

NASA NTRS1992

Index of NASA prefixed forms

This Handbook sets forth information for the guidance of all users of the NASA Forms Management Program System. It is issued in accordance with the Federal Information Resources Management Regulation (FIRMR), Subpart 201-9.1. This Handbook sets forth an alpha-functional index of NASA-prefixed forms by title, identifying number, and unit of issue. The automated processing two-letter code (NF) has been substituted for the spelling out of the NASA form-prefix preceding the form number. To indicate a description in lieu of a distinct title, the entire reference under the Form Title/Description column has been enclosed in parentheses. A list of current forms, shown by number and page, is included for cross-reference and to preclude the ordering of those forms which have been deleted from the system. This Handbook will be updated, as appropriate. NHB 1420.2H dated July 1986, is cancelled.

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NASA NTRS1993

Management of government quality assurance functions for NASA contracts

This handbook sets forth requirements for NASA direction and management of government quality assurance functions performed for NASA contracts and is applicable to all NASA installations. These requirements will standardize management to provide the minimum oversight and effective use of resources. This handbook implements Federal Acquisition Regulation (FAR) Part 46, NASA FAR Supplement 18-46, Quality Assurance, and NMI 7410.1. Achievement of established quality and reliability goals at all levels is essential to the success of NASA programs. Active participation by NASA and other agency quality assurance personnel in all phases of contract operations, including precontract activity, will assist in the economic and timely achievement of program results. This involves broad participation in design, development, procurement, inspection, testing, and preventive and corrective actions. Consequently, government, as well as industry, must place strong emphasis on the accomplishment of all functions having a significant bearing on quality and reliability from program initiation through end-use of supplies and services produced. For purposes of implementing NASA and other agency agreements, and to provide for uniformity and consistency, the terminology and definitions prescribed herein and in a future handbook shall be utilized for all NASA quality assurance delegations and subsequent redelegations.

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