Aqueous Homogeneous Reactor (AHR) Benchmarks
This report describes some of the benchmarks and observations related to the AHR reactor.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
SEARCH · Engineering Papers
Results for “benchmarks”
Search indexed NASA NTRS and DOE OSTI research on propulsion, heat transfer, battery materials and energy systems. Follow report and document links to the original sources.
Quote a phrase for an exact phrase match. Source license links do not imply unrestricted reuse.
Data Testing Revised 235 U, 239 Pu and 63,65 Cu Files with ICSBEP Benchmarks
We review recent critical benchmark calculations with revised 235 U, 239 Pu and 63,65 Cu evaluated data files.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Discussion Regarding Aqueous Homogeneous Reactor (AHR) Benchmarks
“Characteristics of Fissile Solution Systems”, LA-UR-14-21513, published by the same authors, detailed the behavior of the subject systems that distinguishes them from those employing solid fuels. This Report, a companion to the presentation by the same name published by the authors as LA-UR-14- 21529, extends that discussion to illustrate this behavior with reference to the operation of historic aqueous homogeneous reactors (AHR). In this report the term “benchmark” refers to those systems for which it is judged that sufficient experimental data exists to serve as a reference for the behavior of the class of fissile solution systems called AHR. As has been discussed in the previous report, AHR exhibit a range of modes of operation generally determined by the amount of excess reactivity inserted into the system from a steady-state condition, such as sub-critical startup, and the rate of that insertion. The amount of reactivity inserted may fall in the range of $\$0.00$ < Reactivity ≤ $\$1.00$, in the usual units of “dollars” and “cents” or > $\$1.00$. The initial region is called “delayed critical” while the latter is referenced as “super prompt critical”. Excess reactivity may be inserted in rates ranging from slow ramp to step, which drives system dynamics; however, regardless of either of these factors, amplitude or rate of insertion, the ultimate result will be steady-state operation.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Benchmark Measurements of the BeRP Ball in Various Reflectors
Details of benchmark neutron multiplicity measurements of the 4.484 kg Beryllium Reflected Plutonium (BeRP) ball inside of various reflectors. Measurements were performed with an Ortec Fission Meter neutron multiplicity counter. Measurements were made of the bare BeRP Ball, the BeRP Ball inside 3 inch thick polyethylene, nickel, and tungsten, and the polyethylene with an additional 2 inch thick steel reflector. For every measurement, the mass m S of 240 Pu, k eff , multiplication M, and escape multiplication ME are reported. For each individual measurement, the measured mass mS of 240 Pu in the BeRP Ball was within 20.7 grams (closest edge of measurement errorbar to closest edge of errorbar for reference mS from isotopics). The combined measurement of the mass of 240 Pu m S = 267 ± 7 grams which compared very favorably to the known value from isotopics of m S = 266.8 ± 0.5 grams.
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
Neutron Reference Benchmark Field Specifications: ACRR Polyethylene-Lead-Graphite (PLG) Bucket Environment (ACRR-PLG-CC-32-CL)
This report was put together to support the International Atomic Energy Agency (IAEA) REAL- 2016 activity to validate the dosimetry community’s ability to use a consistent set of activation data and to derive consistent spectral characterizations. The report captures details of integral measurements taken in the Annular Core Research Reactor (ACRR) central cavity with the Polyethylene-Lead-Graphite (PLG) bucket, reference neutron benchmark field. The field is described and an “a priori” calculated neutron spectrum is reported, based on MCNP6 calculations, and a subject matter expert (SME) based covariance matrix is given for this “a priori” spectrum. The results of 37 integral dosimetry measurements in the neutron field are reported.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Neutron Reference Benchmark Field Specification: ACRR 44 Inch Lead-Boron (LB44) Bucket Environment (ACRR-LB44-CC-32-CL)
This report was put together to support the International Atomic Energy Agency (IAEA) REAL- 2016 activity to validate the dosimetry community’s ability to use a consistent set of activation data and to derive consistent spectral characterizations. The report captures details of integral measurements taken in the Annular Core Research Reactor (ACRR) central cavity with the 44 inch Lead-Boron (LB44) bucket, reference neutron benchmark field. The field is described and an “a priori” calculated neutron spectrum is reported, based on MCNP6 calculations, and a subject matter expert (SME) based covariance matrix is given for this “a priori” spectrum. The results of 31 integral dosimetry measurements in the neutron field are reported.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Neutron Reference Benchmark Field Specification: ACRR Free-Field Environment (ACRR-FF-CC-32-CL)
This report was put together to support the International Atomic Energy Agency (IAEA) REAL- 2016 activity to validate the dosimetry community’s ability to use a consistent set of activation data and to derive consistent spectral characterizations. The report captures details of integral measurements taken in the Annular Core Research Reactor (ACRR) central cavity free-field reference neutron benchmark field. The field is described and an “a priori” calculated neutron spectrum is reported, based on MCNP6 calculations, and a subject matter expert (SME) based covariance matrix is given for this “a priori” spectrum. The results of 31 integral dosimetry measurements in the neutron field are reported.
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
Summary of FY15 Results of Benchmark Modeling Activities
Sandia is participating in the third phase of and is a contributing partner to a U.S.- German “Joint Project” entitled “Comparison of current constitutive models and simulation procedures on the basis of model calculations of the thermo-mechanical behavior and healing of rock salt.” The first goal of the project is to check the ability of numerical modeling tools to correctly describe the relevant deformation phenomena in rock salt under various influences. Achieving this goal will lead to increased confidence in the results of numerical simulations related to the secure storage of radioactive wastes in rock salt, thereby enhancing the acceptance of the results. These results may ultimately be used to make various assertions regarding both the stability analysis of an underground repository in salt, during the operating phase, and the long-term integrity of the geological barrier against the release of harmful substances into the biosphere, in the post-operating phase. Among the numerical modeling tools required to address this are constitutive models that are used in computer simulations for the description of the thermal, mechanical, and hydraulic behavior of the host rock under various influences and for the long-term prediction of this behavior into the future. A second goal of the project is to investigate and demonstrate the possibilities for further potential development and improvement of these constitutive models. This report summarizes the efforts undertaken during FY15 in support of this international U.S.-German benchmark initiative.
58 GEOSCIENCES↗
U.S. Photovoltaic Prices and Cost Breakdowns. Q1 2015 Benchmarks for Residential, Commercial, and Utility-Scale Systems
The price of photovoltaic (PV) systems in the United States (i.e., the cost to the system owner) has continued to decline across all major market sectors. This report provides a Q1 2015 update regarding the prices of residential, commercial, and utility scale PV systems, based on an objective methodology that closely approximates the book value of a PV system. Several cases are benchmarked to represent common variations in business models, labor rates, and system architecture choice. We estimate a weighted-average cash purchase price of $3.09/W for residential scale rooftop systems, $2.15/W for commercial scale rooftop systems, $1.77/W for utility scale systems with fixed mounting structures, and $1.91/W for utility scale systems using single-axis trackers. All systems are modeled assuming standard-efficiency, polycrystalline-silicon PV modules, and further assume installation within the United States.
14 SOLAR ENERGY↗
East Bay Area Benchmark Study
This report is a benchmarking studying for the Sandia Create Project provided by Cornerstone Project Management, Inc.
99 GENERAL AND MISCELLANEOUS↗
The Benchmark Extensible Tractable Testbed Engineering Resource (BETTER)
The Benchmark Extensible Tractable Testbed Engineering Resource (BETTER) is proposed as a family of modular test bodies that are intended to support engineering capability development by helping to identify weaknesses and needs. Weapon systems, subassemblies, and components are often complex and difficult to test and analyze, resulting in low confidence and high uncertainties in experimental and simulated results. The complexities make it difficult to distinguish between inherent uncertainties and errors due to insufficient capabilities. BETTER test bodies will first use simplified geometries and materials such that testing, data collection, modeling and simulation can be accomplished with high confidence and low uncertainty. Modifications and combinations of simple and well-characterized BETTER test bodies can then be used to increase complexity in order to reproduce relevant mechanics and identify weaknesses. BETTER can provide both immediate and long-term improvements in testing and simulation capabilities. This document presents the motivation, concept, benefits and examples for BETTER.
45 MILITARY TECHNOLOGY, WEAPONRY, AND NATIONAL DEF↗
U.S. Solar Photovoltaic System Cost Benchmark: Q1 2016
NREL has been modeling U.S. photovoltaic (PV) system costs since 2009. This report benchmarks costs of U.S. solar PV for residential, commercial, and utility-scale systems built in the first quarter of 2016 (Q1 2016). Our methodology includes bottom-up accounting for all system and project-development costs incurred when installing residential, commercial, and utility-scale systems, and it models the capital costs for such systems.
14 SOLAR ENERGY↗
Challenges and Successes of Solving Binary Quadratic Programming Benchmarks on the DW2X QPU
This presentation discusses some of the challenges and successes of the quantitative benchmarking efforts performed at LANL.
97 MATHEMATICS AND COMPUTING↗
Engine Benchmarking - Final CRADA Report
Detailed benchmarking of the powertrains of three light-duty vehicles was performed. Results were presented and provided to CRADA partners. The vehicles included a MY2011 Audi A4, a MY2012 Mini Cooper and a MY2014 Nissan Versa.
33 ADVANCED PROPULSION SYSTEMS↗
Benchmarking transition energies and emission strengths for X-ray astrophysics with measurements at the Livermore EBITs
K-shell transitions in astrophysically abundant metals and L-shell transitions in Fe group elements show characteristic signatures in the soft X-ray spectrum in the energy range 0.1–10 keV. These signatures have great diagnostic value for plasma parameters such as electron and ion temperatures and densities, and can thus help understand the physics controlling the energetic processes in astrophysical sources. This diagnostic power increases with advances in spectral resolution and effective area of the employed X-ray observatories. However, to make optimal use of the diagnostic potential – whether through global spectral modeling or through diagnostics from local modeling of individual lines – the underlying atomic physics has to be complete and well known. With the next generation of soft X-ray observatories featuring micro-calorimeters such as the SXS on Astro- H/Hitomi and the X-IFU on Athena, broadband high-resolution spectroscopy with large effective area will become more commonly available in the next decade. With these spectrometers, the accuracy of the plasma parameters derived from spectral modeling will be limited by the uncertainty of the reference atomic data rather than by instrumental factors, as is sometimes already the case for the high-resolution grating observations with Chandra-HETG and XMM-Newton-RGS. To take full advantage of the measured spectra, assessment of the accuracy of and improvements to the available atomic reference data are therefore important. Dedicated measurements in the laboratory are essential to benchmark the theoretical calculations providing the bulk of the reference data used in astrophysics. Experiments at the Lawrence Livermore National Laboratory electron beam ion traps (EBIT-I and SuperEBIT) have a long history of providing this service. In this work, I present new measurements of transition energies and absolute electron impact excitation cross sections geared towards currently open atomic physics data needs.
70 PLASMA PHYSICS AND FUSION TECHNOLOGY↗
Benchmarking of DFLAW Solid Secondary Wastes and Processes with UK/Europe Counterparts
This report provides information and background on UK solid wastes and waste processes that are similar to those which will be generated by the Direct-Feed Low Activity Waste (DFLAW) facilities at Hanford. The aim is to further improve the design case for stabilizing and immobilizing of solid secondary wastes, establish international benchmarking and review possibilities for innovation.
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
BIGHORN Computational Fluid Dynamics Theory, Methodology, and Code Verification & Validation Benchmark Problems
This document presents the theoretical background for a hybrid finite-element / finite-volume fluid flow solver, namely BIGHORN, based on the Multiphysics Object Oriented Simulation Environment (MOOSE) computational framework developed at the Idaho National Laboratory (INL). An overview of the numerical methods used in BIGHORN are discussed and followed by a presentation of the formulation details. The document begins with the governing equations for the compressible fluid flow, with an outline of the requisite constitutive relations. A second-order finite volume method used for solving the compressible fluid flow problems is presented next. A Pressure-Corrected Implicit Continuous-fluid Eulerian (PCICE) formulation for time integration is also presented. The multi-fluid formulation is being developed. Although multi-fluid is not fully-developed, BIGHORN has been designed to handle multi-fluid problems. Due to the flexibility in the underlying MOOSE framework, BIGHORN is quite extensible, and can accommodate both multi-species and multi-phase formulations. This document also presents a suite of verification & validation benchmark test problems for BIGHORN. The intent for this suite of problems is to provide baseline comparison data that demonstrates the performance of the BIGHORN solution methods on problems that vary in complexity from laminar to turbulent flows. Wherever possible, some form of solution verification has been attempted to identify sensitivities in the solution methods, and suggest best practices when using BIGHORN.
97 MATHEMATICS AND COMPUTING↗
L2 Milestone: Neutron Capture Cross Sections from Surrogate (p, d) Measurements: Determination of the Unknown 87 Y(n, g) Cross Section and Assessment of the Method Via the 90 Zr(n, g) Benchmark Case: Theory Report
Cross sections for compound-nuclear reactions involving unstable targets are important for many applications, but can often not be measured directly. Here we describe a method for extracting cross sections for neutron-capture on unstable isotopes from indirect (surrogate) measurements. The surrogate reaction, which produces the compound nucleus of interest, has to be described and the decay of the nucleus has to be modeled. We outline the approach for one-neutron pickup and report on the determination of the 90 Zr(n, γ ) reaction from surrogate 92 Zr(p,d) data, which is compared to the directly-measured capture cross section and thus provides a benchmark for the method. We then apply the method to determine the 87 Y(n, γ ) cross section, which has not been measured directly. The work was carried out in the context of an LLNL L2 Milestone. This report addresses the theory aspects of the milestone. A complementary document summarizes the experimental efforts [1].
73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗