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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.

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At least 595 records · Page 33
All sourcesNASA NTRSDOE OSTI
DOE OSTI2013

Ceph Parallel File System Evaluation Report

We used Data Direct Networks’ (DDN) SFA10K as the storage backend during this evaluation. It consists of 200 SAS drives and 280 SATA drives, organized into various RAID levels by two active-active RAID controllers. The exported RAID groups by these controllers are driven by four hosts. Each host has two InfiniBand (IB) QDR connections to the storage backend. We used a single dualport Mellanox connectX IB card per host. By our calculation, this setup can saturate SFA10K’s maximum theoretical throughput (~12 GB/s). Our Ceph testbed employs a collection of testing nodes. These nodes and their roles are summarized in Table 1. In the following discussion, we use “servers”, “osd servers”, “server hosts” interchangeably. We will emphasize with “client” prefix when we want to distinguish it from above. All hosts (client and servers) were configured with Redhat 6.3 and kernel version 3.5.1 initially, and later upgraded to 3.9 (rhl-ceph image), Glibc 2.12 with syncfs support, locally patched. We used the Ceph 0.48 and 0.55 release in the initial tests, upgraded to 0.64 and then to 0.67RC for a final round of tests.

Wang, Feiyi↗
DOE OSTI2014

Clay Generic Disposal System Model - Sensitivity Analysis for 32 PWR Assembly Canisters (+2 associated model files).

The Used Fuel Disposition Campaign (UFDC), as part of the DOE Office of Nuclear Energy’s (DOE-NE) Fuel Cycle Technology program (FCT) is investigating the disposal of high level radioactive waste (HLW) and spent nuclear fuela (SNF) in a variety of geologic media. The feasibility of disposing SNF and HLW in clay media has been investigated and has been shown to be promising [Ref. 1]. In addition the disposal of these wastes in clay media is being investigated in Belgium, France, and Switzerland. Thus, Argillaceous media is one of the environments being considered by UFDC. As identified by researchers at Sandia National Laboratory, potentially suitable formations that may exist in the U.S. include mudstone, clay, shale, and argillite formations [Ref. 1]. These formations encompass a broad range of material properties. In this report, reference to clay media is intended to cover the full range of material properties. This report presents the status of the development of a simulation model for evaluating the performance of generic clay media. The clay Generic Disposal System Model (GDSM) repository performance simulation tool has been developed with the flexibility to evaluate not only different properties, but different waste streams/forms and different repository designs and engineered barrier configurations/ materials that could be used to dispose of these wastes.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2017

File-Based One-Way BISON Coupling Through VERA: User's Manual

Activities to incorporate fuel performance capabilities into the Virtual Environment for Reactor Applications (VERA) are receiving increasing attention [1–6]. The multiphysics emphasis is expanding as the neutronics (MPACT) and thermal-hydraulics (CTF) packages are becoming more mature. Capturing the finer details of fuel phenomena (swelling, densification, relocation, gap closure, etc.) is the natural next step in the VERA development process since these phenomena are currently not directly taken into account. While several codes could be used to accomplish this, the BISON fuel performance code [8,9] being developed by the Idaho National Laboratory (INL) is the focus of ongoing work in the Consortium for Advanced Simulation of Light Water Reactors (CASL). Built on INL’s MOOSE framework [10], BISON uses the finite element method for geometric representation and a Jacobian-free Newton-Krylov (JFNK) scheme to solve systems of partial differential equations for various fuel characteristic relationships. There are several modes of operation in BISON, but, this work uses a 2D azimuthally symmetric (R-Z) smeared-pellet model. This manual is intended to cover (1) the procedure pertaining to the standalone BISON one-way coupling from VERA and (2) the procedure to generate BISON fuel temperature tables that VERA can use.

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS↗
DOE OSTI2017

Final Project Report: Composition and Realization of Source-to-Sink High-Performance Flows: File Systems, Storage, Hosts, LAN and WAN

A number of Department of Energy (DOE) science applications, involving exascale computing systems and large experimental facilities, are expected to generate large volumes of data, in the range of petabytes to exabytes, which will be transported over wide-area networks for the purpose of storage, visualization, and analysis. The objectives of this proposal are to (1) develop and test the component technologies and their synthesis methods to achieve source-to-sink high-performance flows, and (2) develop tools that provide these capabilities through simple interfaces to users and applications. In terms of the former, we propose to develop (1) optimization methods that align and transition multiple storage flows to multiple network flows on multicore, multibus hosts; and (2) edge and long-haul network path realization and maintenance using advanced provisioning methods including OSCARS and OpenFlow. We also propose synthesis methods that combine these individual technologies to compose high-performance flows using a collection of constituent storage-network flows, and realize them across the storage and local network connections as well as long-haul connections. We propose to develop automated user tools that profile the hosts, storage systems, and network connections; compose the source-to-sink complex flows; and set up and maintain the needed network connections.

97 MATHEMATICS AND COMPUTING↗
DOE OSTI2018

ENDF-6 Formats Manual: Data Formats and Procedures for the Evaluated Nuclear Data Files

In December 2006 and again in December 2011, the Cross Section EvaluationWorking Group (CSEWG) of the United States released new versions of the ENDF/B-VII library. Each major release with minor revision number “0” coincides with the release of a new Neutron Standards Library. In December 2017, CSEWG released a new major version of ENDF/B, ENDF/B-VIII.0, again coinciding with the release of the Neutron Stanards Library. This ENDF release also contains the results of the Collaborative International Evaluation Library Organization (CIELO) Pilot Project, namely standards level full evaluations of 1 H, 16 O, 56 Fe, 235 U, 238 U and 239 Pu. It is our expectation that this major revision will be embraced by the data evaluators as well as members of numerous nuclear data user communities worldwide.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2018

Release of ENDF/B-VIII.0-Based ACE Data Files

In February 2018, the National Nuclear Data Center released ENDF/B-VIII.0 in the standard Evaluated Nuclear Data Format (ENDF). This represents the advances made in nuclear data since the release of ENDF/B-VII.1 in 2011.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2018

2004 and 2009 TRU Files Combined

Washingon TRU Solutions (WTS) Central Characterization Project (CCP), hereafter referred to as the Supplier, will develop and provide a stand-alone program to characterize and certify Lawrence Livermore National Laboratory (LLNL) TRU Waste.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2018

NJOY Processing of ENDF/B VIII.0 Thermal Scattering Files

“ENDF/B-VIII.0 provides a major update to the ENDF thermal scattering library. Indeed, it is nearly a completely new sub-library. Only the legacy evaluations for Al, Fe, liquid and solid methane, ortho- and para-hydrogen and deuterium and benzene and the ENDF/B-VII.1 evaluations for SiO 2 are unchanged.”

36 MATERIALS SCIENCE↗