Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “nuclear”

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.

At least 289 records · Page 16
All sourcesNASA NTRSDOE OSTI
DOE OSTI2020

IAEA ITC28 Project Report. 28th International Training Course on the Physical Protection of Nuclear Materials and Nuclear Facilities

Sandia National Laboratories (SNL) has hosted the International Training Course on the Physical Protection of Nuclear Materials and Nuclear Facilities since 1978. This course is the flagship training course of the International Atomic Energy Agency (IAEA). On behalf of the National Nuclear Security Administration (NNSA), SNL manages, develops, and coordinates all course materials, and works closely with the IAEA to arrange all logistical details for the course. ITC-28 incorporated several new approaches based on feedback and experience with ITC-27 and earlier versions of the course. For ITC-28, an addition to the Integrated Security Facility (ISF) at SNL was a mock reactor hall with a mock reactor pool. Other facilities at the ISF include a mock processing facility, material receiving area, and central alarm station. The physical protection system at the ISF—an area that formerly housed Category I nuclear material—provides many opportunities for hands-on, real world training in the design and evaluation of a physical protection system (PPS). This document provides a brief description of ITC-28, including a summary of lessons learned and key recommendations for future development efforts.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2012

Nuclear Safeguards Infrastructure Required for the Next Generation Nuclear Plant (NGNP)

The Next Generation Nuclear Plant (NGNP) is a Very High Temperature Gas-Cooled Reactor (VHTR) to be constructed near Idaho Falls, Idaho The NGNP is intrinsically safer than current reactors and is planned for startup ca. 2021 Safety is more prominent in the minds of the Public and Governing Officials following the nuclear reactor meltdown accidents in Fukushima, Japan The authors propose that the NGNP should be designed with International (IAEA) Safeguards in mind to support export to Non-Nuclear-Weapons States There are two variants of the NGNP design; one using integral Prismatic-shaped fuel assemblies in a fixed core; and one using recirculating fuel balls (or Pebbles) The following presents the infrastructure required to safeguard the NGNP This infrastructure is required to safeguard the Prismatic and Pebble-fueled NGNP (and other HTGR/VHTR) The infrastructure is based on current Safeguards Requirements and Practices implemented by the International Atomic Energy Agency (IAEA) for similar reactors The authors of this presentation have worked for decades in the area of International Nuclear Safeguards and are recognized experts in this field Presentation for INMM conference in July 2012.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗
DOE OSTI2013

Nuclear Industry Input to the Development of Concepts for the Consolidated Storage of Used Nuclear Fuel - 13411

EnergySolutions and its team partners, NAC International, Exelon Nuclear Partners, Talisman International, TerranearPMC, Booz Allen Hamilton and Sargent and Lundy, have carried out a study to develop concepts for a Consolidated Storage Facility (CSF) for the USA's stocks of commercial Used Nuclear Fuel (UNF), and the packaging and transport provisions required to move the UNF to the CSF. The UNF is currently stored at all 65 operating nuclear reactor sites in the US, and at 10 shutdown sites. The study was funded by the US Department of Energy and followed the recommendations of the Blue Ribbon Commission on America's Nuclear Future (BRC), one of which was that the US should make prompt efforts to develop one or more consolidated storage facilities for commercial UNF. The study showed that viable schemes can be devised to move all UNF and store it at a CSF, but that a range of schemes is required to accommodate the present widely varying UNF storage arrangements. Although most UNF that is currently stored at operating reactor sites is in water-filled pools, a significant amount is now dry stored in concrete casks. At the shutdown sites, the UNF is dry stored at all but two of the ten sites. Various types of UNF dry storage configurations are used at the operating sites and shutdown sites that include vertical storage casks that are also licensed for transportation, vertical casks that are licensed for storage only, and horizontally orientated storage modules. The shutdown sites have limited to nonexistent UNF handling infrastructure and several no longer have railroad connections, complicating UNF handling and transport off the site. However four methods were identified that will satisfactorily retrieve the UNF canisters within the storage casks and transport them to the CSF. The study showed that all of the issues associated with the transportation and storage of UNF from all sites in the US can be accommodated by adopting a staged approach to the construction of the CSF. Stage 1 requires only a cask storage pad and railroad interface to be constructed, and the CSF can then receive the UNF that is in transportable storage casks. Stage 2 adds a canister handling facility, a storage cask fabrication facility and an expanded storage pad, and enables the receipt of all canistered UNF from both operating and shutdown sites. Stage 3 provides a repackaging facility with a water-filled pool that provides flexibility for a range of repackaging scenarios. This includes receiving and repackaging 'bare' UNF into suitable canisters that can be placed into interim storage at the CSF, and enables UNF that is being received, or already in storage onsite, to be repackaged into canisters that are suitable for disposal at a geologic repository. The study used the 'Total System Model' (TSM) to analyze a range of CSF capacities and operating scenarios with differing parameters covering UNF pickup orders, one or more CSF sites, CSF start dates, CSF receipt rates and geologic repository start dates. The TSM was originally developed to model movement of UNF to the Yucca Mountain repository and was modified for this study to enable the CSF to become the 'gateway' to a future geologic repository. The TSM analysis enabled costs to be estimated for each scenario and showed how these are influenced by each of the parameters. This information will provide essential underpinning for a future Conceptual Design preparation. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2016

Summary of Industry Task Orders Completed by the U.S. Department of Energy, Office of Nuclear Energy's Nuclear Fuel Storage and Transportation Planning Project

The Administration released its Strategy for the Management and Disposal of Used Nuclear Fuel and High- Level Radioactive Waste in January 2013. The Strategy includes a phased, adaptive, and consent-based approach to siting, and implementing a comprehensive management and disposal system. These plans include activities to establish one or more ISFs using consent-based siting and to prepare for large-scale transport of spent nuclear fuel (SNF). Nuclear Fuels Storage and Transportation Planning Project (NFST) completed the following three Task Orders, using industry Advisory and Assistance Contracts related interim storage and transportation. These design concepts provide important information to the waste management systems analysis regarding throughput capacities, operational considerations, and cost estimates. - Generic Design Alternatives for Dry Storage of Used Nuclear Fuel- Chicago Bridge and Iron (CBandI) developed and documented generic design alternatives for receipt and storage of SNF and greater-than-class-C (GTCC) waste contained in dual-purpose canisters. - Generic Design for Small Size Standard Transportation, Aging, and Disposal Canister System- EnergySolutions developed a generic design of a small capacity (4 PWR/9 BWR) Standard Transportation, Aging, and Disposal (STAD) canister. - Operational Requirements for Standardized Dry Fuel Canister Systems- EnergySolutions developed solutions to address operational impacts of using a standardized canister at utility sites with a smaller capacity than conventional, dual-purpose canisters (DPC). (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2015

JRC-IRMM/ORNL Collaboration on Nuclear Data for Nuclear Criticality Safety - 14486

Concerns about using cross sections recommended in the main evaluated data libraries (i.e. ENDF/B, JEFF and JENDL) for nuclear criticality calculations have been a prime motivator for new cross section measurements. The measurements and evaluations discussed in this work are part of a collaboration between the Oak Ridge National Laboratory (ORNL) and the Institute for Reference Material and Measurements of the Joint Research Center (JRC-IRMM) of the European Commission (EC). They are performed in response to the US Nuclear Criticality Safety Program (NCSP) data needs. In particular, the NCSP five-year plan encompasses a listing of elements that have been identified for measurements and evaluations to address issues on criticality safety applications. This listing is based on data deficiency concerns in practical applications that are conveyed by criticality safety practitioners. In general these deficiencies are obtained through the analysis of benchmark calculations. A wealth of evaluations in the main libraries were derived from results of measurements made with poor time-of-flight resolution, and also the description of some data in the neutron energy range above several tens of keV is crude. This impacts both the resolved and unresolved resonance region, and leads to bias effects when resonance structures play an important role. As a consequence only average corrections can be applied in calculations for nuclear criticality calculations where self-shielding, multiple scattering, or Doppler broadening are important. This can lead to erroneous results. Furthermore, many evaluations for nuclides having small neutron-capture cross sections show erroneously high cross sections because the influence of the neutron sensitivity of the old measurement systems was underestimated. Although their neutron capture cross sections are small, these nuclides, if occurring in large amounts, can be important absorbers in criticality calculations, so an accurate determination of these cross sections is required. Over the last seven years the JRC-IRMM/ORNL collaboration has produced many neutron induced cross section data using the Geel Electron Linear Accelerator (GELINA) neutron time-of-flight facility. This facility is ideally suited to measure total, fission and capture cross sections in the energy range from 1 eV to ∼600 keV, which is important for nuclear criticality calculations. In this paper the facility and experimental set-ups at GELINA will be described together with the data reduction and analysis procedures which result in experimental observables including their full covariance information. The importance of combining transmission and partial cross section data will be emphasized. We will give a list of the measured nuclides and discuss the impact of the resulting data and evaluations. (authors)

42 ENGINEERING↗
DOE OSTI2011

Nuclear Data Sheets for A = 207

Evaluated nuclear structure and decay data for all nuclei within the A=207 mass chain are presented. The experimental data are evaluated and best values for level and gamma-ray energies, quantum numbers, lifetimes, gamma-ray intensities, and other nuclear properties are recommended. Inconsistencies and discrepancies that exist in the literature are noted. This work supersedes the earlier evaluation by M.J. Martin (1993Ma73), published in Nuclear Data Sheets70, 315 (1993).

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2011

Nuclear Resonance Fluorescence to Measure Plutonium Mass in Spent Nuclear Fuel

The Next Generation Safeguard Initiative (NGSI) of the U.S Department of Energy is supporting a multi-lab/university collaboration to quantify the plutonium (Pu) mass in spent nuclear fuel (SNF) assemblies and to detect the diversion of pins with non-destructive assay (NDA) methods. The following 14 NDA techniques are being studied: Delayed Neutrons, Differential Die-Away, Differential Die-Away Self-Interrogation, Lead Slowing Down Spectrometer, Neutron Multiplicity, Passive Neutron Albedo Reactivity, Total Neutron (Gross Neutron), X-Ray Fluorescence, {sup 252}Cf Interrogation with Prompt Neutron Detection, Delayed Gamma, Nuclear Resonance Fluorescence, Passive Prompt Gamma, Self-integration Neutron Resonance Densitometry, and Neutron Resonance Transmission Analysis. Understanding and maturity of the techniques vary greatly, ranging from decades old, well-understood methods to new approaches. Nuclear Resonance Fluorescence (NRF) is a technique that had not previously been studied for SNF assay or similar applications. Since NRF generates isotope-specific signals, the promise and appeal of the technique lies in its potential to directly measure the amount of a specific isotope in an SNF assay target. The objectives of this study were to design and model suitable NRF measurement methods, to quantify capabilities and corresponding instrumentation requirements, and to evaluate prospects and the potential of NRF for SNF assay. The main challenge of the technique is to achieve the sensitivity and precision, i.e., to accumulate sufficient counting statistics, required for quantifying the mass of Pu isotopes in SNF assemblies. Systematic errors, considered a lesser problem for a direct measurement and only briefly discussed in this report, need to be evaluated for specific instrument designs in the future. Also, since the technical capability of using NRF to measure Pu in SNF has not been established, this report does not directly address issues such as cost, size, development time, nor concerns related to the use of Pu in measurement systems. This report discusses basic NRF measurement concepts, i.e., backscatter and transmission methods, and photon source and {gamma}-ray detector options in Section 2. An analytical model for calculating NRF signal strengths is presented in Section 3 together with enhancements to the MCNPX code and descriptions of modeling techniques that were drawn upon in the following sections. Making extensive use of the model and MCNPX simulations, the capabilities of the backscatter and transmission methods based on bremsstrahlung or quasi-monoenergetic photon sources were analyzed as described in Sections 4 and 5. A recent transmission experiment is reported on in Appendix A. While this experiment was not directly part of this project, its results provide an important reference point for our analytical estimates and MCNPX simulations. Used fuel radioactivity calculations, the enhancements to the MCNPX code, and details of the MCNPX simulations are documented in the other appendices.

46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND ↗
DOE OSTI2011

Nuclear binding energy and symmetry energy of nuclear matter with modern nucleon-nucleon potentials

Research Highlights: > The nuclear matter is studied within the Brueckner-Hartree-Fock (BHF) approach employing the most recent accurate nucleon-nucleon potentials. > The results come out by approximating the single particle self-consistent potential with a parabolic form. > We discuss the current status of the Coester line, i.e., density and energy of the various saturation points being strongly linearly correlated. > The nuclear symmetry energy is calculated as the difference between the binding energy of pure neutron matter and that of symmetric nuclear matter. - Abstract: The binding energy of nuclear matter at zero temperature in the Brueckner-Hartree-Fock approximation with modern nucleon-nucleon potentials is studied. Both the standard and continuous choices of single particle energies are used. These modern nucleon-nucleon potentials fit the deuteron properties and are phase shifts equivalent. Comparison with other calculations is made. In addition we present results for the symmetry energy obtained with different potentials, which is of great importance in astrophysical calculation.

71 CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSIC↗
DOE OSTI2019

Nuclear physics without high-momentum potentials: Constructing the nuclear effective interaction directly from scattering observables

The traditional approach to nuclear physics encodes phase shift information in a nucleon-nucleon (NN) potential, producing a nucleon-level interaction that captures the sub-GeV consequences of QCD. A further reduction to the nuclear scale is needed to produce an effective interaction for soft Hilbert spaces, such as those employed in the shell model. Here we describe an alternative construction of the effective interaction that is simple and quite precise, proceeding from the QCD scale directly to the nuclear scale. This eliminates the need for constructing and renormalizing the high-momentum NN potential. Instead, continuum phase shifts and mixing angles are used directly at the nuclear scale. The method exploits the analytic continuity in energy of HOBET (Harmonic-Oscillator-Based Effective Theory) to connect bound states to continuum solutions at specific energies. The procedure is systematic, cutoff independent, and convergent, yielding keV accuracy at NNLO or N 3 LO, depending on the channel. Lepage plots are provided.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2020

Biomolecular complex viewed by dynamic nuclear polarization solid-state NMR spectroscopy

Solid-state nuclear magnetic resonance (ssNMR) is an indispensable tool for elucidating the structure and dynamics of insoluble and non-crystalline biomolecules. The recent advances in the sensitivity-enhancing technique magic-angle spinning dynamic nuclear polarization (MAS-DNP) have substantially expanded the territory of ssNMR investigations and enabled the detection of polymer interfaces in a cellular environment. This article highlights the emerging MAS-DNP approaches and their applications to the analysis of biomolecular composites and intact cells to determine the folding pathway and ligand binding of proteins, the structural polymorphism of low-populated biopolymers, as well as the physical interactions between carbohydrates, proteins, and lignin. Furthermore, these structural features provide an atomic-level understanding of many cellular processes, promoting the development of better biomaterials and inhibitors. It is anticipated that the capabilities of MAS-DNP in biomolecular and biomaterial research will be further enlarged by the rapid development of instrumentation and methodology.

36 MATERIALS SCIENCE↗
DOE OSTI2015

Comparison of nuclear electric resonance and nuclear magnetic resonance in integer and fractional quantum Hall states

Electric-field-induced nuclear resonance (NER: nuclear electric resonance) involving quantum Hall states (QHSs) was studied at various filling factors by exploiting changes in nuclear spins polarized at quantum Hall breakdown. Distinct from the magnetic dipole interaction in nuclear magnetic resonance, the interaction of the electric-field gradient with the electric quadrupole moment plays the dominant role in the NER mechanism. The magnitude of the NER signal strongly depends on whether electronic states are localized or extended. This indicates that NER is sensitive to the screening capability of the electric field associated with QHSs.

75 CONDENSED MATTER PHYSICS, SUPERCONDUCTIVITY AND↗
DOE OSTI2018

Automated defect detection in spent nuclear fuel using combine Cerenkov and Gamma Emission Tomography data

Spent fuel monitoring and characterization has been a pillar of safeguards and nuclear facility monitoring for many years. The Digital Cerenkov Viewing Device (DCVD) has been used since the 1980s as a method of defect detection in spent fuel. In recent years, the accounting of large quantities of spent fuel before storage has renewed interest in this relatively quick and inexpensive method. This has an impact not only in safeguards, but also in for nuclear power facilities, as accounting can be a long and arduous process. Additionally, the DCVD demonstrates limited accuracy in more complex cases such as substitution of a fuel rod with steel, or a partial defect detection. A second method, Gamma Emission Tomography (GET) has been explored as an improved defect detection method, but is much more expensive and invasive than DCVD. This work identifies deficiencies in both methods, and proposes a combination of data gathered from each method to address these deficiencies for improved spent fuel characterization. Initial results are promising, showing 97% detection of a single missing fuel rod when the data types are combined, versus approximately 50% and 70%respectively for DCVD and GET data on their own. Finally, these classification results are obtained with algorithms derived from facial recognition and applied to this problem, yielding unique accuracy in near real-time while also maintaining the information barrier between output and measurement desired in safeguards.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2021

The Manhattan Project Nuclear Science and Technology Developments at Los Alamos: A Special Issue of Nuclear Technology

The year 2020 marked the 75th anniversary of the Trinity experiment, the world’s first nuclear explosion, on July 16, 1945, near Alamogordo, New Mexico. Trinity was a vital proof step toward the culmination of the Manhattan Project and the end of World War II. The technical accomplishments made by scientists and engineers from the United States, United Kingdom, and Canada (some originating in Germany, Hungary, Italy, France, and other countries) were recognized by many events in 2020, including a visit to New Mexico’s Los Alamos National Laboratory by U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA) dignitaries; historical documentaries. The importance of Trinity as a foundational accomplishment for the broad nuclear science and engineering community is clear; indeed, New Mexico’s chapter of the American Nuclear Society (ANS) is referred to as the Trinity Section. The events surrounding Trinity have even entered into high culture with recent performances of John Adams’s opera Doctor Atomic in San Francisco, Amsterdam, Chicago, New York, and Santa Fe.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2018

NCRP Program Area Committee 3: Nuclear and Radiological Security and Safety [Update on the Ncrp Program Area Committee 3 Activities: Nuclear And Radiological Security and Safety]

The National Council on Radiation Protection and Measurements (NCRP) Program Area Committee (PAC) 3 covers the broad subject of nuclear and radiological security and safety and provides guidance and recommendations for response to nuclear and radiological incidents of both an accidental and deliberate nature. In 2017, PAC 3 Scientific Committee 3-1 completed the development of Guidance for Emergency Responder Dosimetry, and began development of a companion commentary on operational aspects of that guidance. PAC 3 members also organized the technical program for the 2017 Annual Meeting of the NCRP on “Assessment of National Efforts in Emergency Preparedness for Nuclear Terrorism: Is There a Need for Realignment to Close Remaining Gaps.” Based on discussions and presentations at the annual meeting, PAC 3 is working to develop a commentary on the subject that could serve as a roadmap for focusing our national efforts on the most pressing needs for preparing the nation for nuclear and radiological emergencies. PAC 3 is also engaged in active discussions, exploring the landscape of priority issues for its future activities. Lastly, an important consideration in this discussion is the extent of NCRP’s present and potential future resources to support the work of its scientific committees.

98 NUCLEAR DISARMAMENT, SAFEGUARDS, AND PHYSICAL P↗
DOE OSTI2011

Nuclear modification factors of phi mesons in d + Au, Cu + Cu, and Au + Au collisions at root sNN = 200 GeV

The PHENIX experiment at the Relativistic Heavy Ion Collider has performed systematic measurements of {phi} meson production in the K{sup +}K{sup -} decay channel at midrapidity in p+p, d+Au, Cu+Cu, and Au+Au collisions at {radical}s{sub NN} = 200 GeV. Results are presented on the {phi} invariant yield and the nuclear modification factor R{sub AA} for Au+Au and Cu+Cu, and R{sub dA} for d+Au collisions, studied as a function of transverse momentum (1 < p{sub T} < 7 GeV/c) and centrality. In central and midcentral Au+Au collisions, the R{sub AA} of {phi} exhibits a suppression relative to expectations from binary scaled p+p results. The amount of suppression is smaller than that of the {pi}{sup 0} and the {eta} in the intermediate p{sub T} range (2-5 GeV/c), whereas, at higher p{sub T}, the {phi}, {pi}{sup 0}, and {eta} show similar suppression. The baryon (proton and antiproton) excess observed in central Au+Au collisions at intermediate p{sub T} is not observed for the {phi} meson despite the similar masses of the proton and the {phi}. This suggests that the excess is linked to the number of valence quarks in the hadron rather than its mass. The difference gradually disappears with decreasing centrality, and, for peripheral collisions, the R{sub AA} values for both particle species are consistent with binary scaling. Cu+Cu collisions show the same yield and suppression as Au+Au collisions for the same number of N{sub part}. The R{sub dA} of {phi} shows no evidence for cold nuclear effects within uncertainties.

72 PHYSICS OF ELEMENTARY PARTICLES AND FIELDS↗
DOE OSTI2011

Nuclear transparency and effective kaon-nucleon cross section from the A(e,e{sup '}K{sup +}) reaction

We have determined the transparency of the nuclear medium to kaons from A(e,e{sup '}K{sup +}) measurements on {sup 12}C, {sup 63}Cu, and {sup 197}Au targets. The measurements were performed at the Jefferson Laboratory and span a range in four-momentum-transfer squared Q{sup 2}=1.1-3.0 GeV{sup 2}. The nuclear transparency was defined as the ratio of measured kaon electroproduction cross sections with respect to deuterium ({sigma}{sup A}/{sigma}{sup D}). We further extracted the atomic number (A) dependence of the transparency as parametrized by T=(A/2){sup {alpha}-1} and, within a simple model assumption, the in-medium effective kaon-nucleon cross sections. The effective cross sections extracted from the electroproduction data were found to be smaller than the free cross sections determined from kaon-nucleon scattering experiments, and the parameter {alpha} was found to be significantly larger than those obtained from kaon-nucleus scattering. We have included similar comparisons between pion- and proton-nucleon effective cross sections as determined from electron-scattering experiments and pion-nucleus and proton-nucleus scattering data.

73 NUCLEAR PHYSICS AND RADIATION PHYSICS↗
DOE OSTI2016

Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms

This is the final report of the NEUP project “Radiation and Thermal Effects on Used Nuclear Fuel and Nuclear Waste Forms.” This project started on July 1, 2012 and was successfully completed on June 30, 2016. This report provides an overview of the main achievements, results and findings through the duration of the project. Additional details can be found in the main body of this report and in the individual Quarterly Reports and associated Deliverables of this project, which have been uploaded in PICS-NE. The objective of this research was to advance understanding and develop validated models on the effects of self-radiation from beta and alpha decay on the response of used nuclear fuel and nuclear waste forms during high-temperature interim storage and long-term permanent disposition. To achieve this objective, model used-fuel materials and model waste form materials were identified, fabricated, and studied.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗