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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 109 records · Page 6
All sourcesNASA NTRSDOE OSTI
DOE OSTI2016

Examining Supply Chain Resilience for the Inter-modal Shipment of Spent Nuclear Fuel and High Level Radioactive Materials - 16309

The U.S. Department of Energy (DOE) has a significant programmatic interest in the safe and secure routing and transportation of Spent Nuclear Fuel (SNF) and High Level Waste (HLW) in the United States, including shipments entering the country from locations outside U.S borders. In any shipment of SNF/HLW, there are multiple 'chains'; a jurisdictional chain as the material moves between jurisdictions (state, federal, tribal, administrative), a physical supply chain (which mode), as well as a custody chain (which stakeholder is in charge/possession) of the materials being transported. Given these interconnected networks, there lies vulnerabilities, whether in lack of communication between interested stakeholders or physical vulnerabilities such as interdiction. By identifying key links and nodes as well as administrative weaknesses, decisions can be made to 'harden' the physical network and improve communication between stakeholders. This paper examines the parallel chains of oversight and custody as well as the chain of stakeholder interests for the shipments of SNF/HLW and the potential impacts on systemic resiliency. Using the Crystal River shutdown location as well as a hypothetical international shipment brought into the United States, this paper illustrates the parallel chains and maps them out visually. (authors)

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

A WM Facility for the Processing of Radioactive Materials Arising from the Decommissioning Activities of the Belgian Nuclear Power Plant of Doel - 16042

Doel Nuclear Power Plant is located in the northern part of Belgium in the harbour of Antwerp on the Scheldt River. On this 80-hectare site Electrabel, the Belgian utility, operates four PWRs with a total generation capacity of 2911 MWe. Those nuclear power units were commissioned in 1975 (Doel 1 and 2 - twin units), in 1982 (Doel 3) and in 1985 (Doel 4). In light of the Belgian governments decision to definitively shutdown the oldest units of the site (Doel 1 and 2 - 433 MWe each) in 2015 at the end of their 40-year design lifetime, Electrabel launched a D and D program in partnership with Tractebel Engineering in July 2012. During the D and D preparation phase prior to the final shutdown, studies performed by Tractebel Engineering showed the added benefit of a purpose-built Waste Management Facility (WMF) specifically equipped to process contaminated and activated components generated by the in-situ dismantling activities. The WMF is a key infrastructure contributing to a large extent to the Waste Minimization Policy within the global D and D program. The present paper aims at presenting its strategic, logistic, infra-structural, and design principles. At the end of 2014, the Belgian government and Electrabel entered into discussions to envisage a 10-year lifetime extension of Doel 1 and 2 units. Therefore, Electrabel decided to put the D and D program on hold. Nevertheless, the preparatory studies for the future D and D activities on Doel site are set on solid assumptions and pave the way towards a safe, cost-effective and waste minimizing decommissioning process. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗
DOE OSTI2022

Processes controlling helium bubble dynamics at varying temperatures in simulated radioactive materials

Alpha-radiation damage is known to degrade materials exposed to harsh radiation environments via swelling and embrittlement by nano-scale helium bubbles. How these bubbles grow under varying temperature is essential to understanding and predicting material failure and optimization. Using in situ X-ray scattering, we probed ≈1012 bubbles before, during and after annealing at different temperatures in He-implanted aluminum to reveal a critical growth activation temperature that depends strongly on the helium implantation conditions. An analysis of the data aided by our molecular dynamics simulations identifies multiple temperature-dependent bubble growth mechanisms above and below the critical growth activation temperature. Moreover, the irreversible bubble growth that occurs after annealing for ≈4 h was evaluated using dislocation dynamics and found to negligibly affect the yield strength but may affect subsequent bubble growth at temperature. These in situ results provide valuable insight into bubble growth never observed before and reveal, for the first time, bubble shrinkage after cooling.

36 MATERIALS SCIENCE↗
DOE OSTI2018

Combination of thermal and electric properties’ measurement techniques in a single setup suitable for radioactive materials in controlled environments and based on the 3 ω approach

We have designed and developed a new experimental setup, based on the 3 Omega method, to measure thermal conductivity, heat capacity and electrical resistivity of variety of samples in a broad temperature range (2 to 600 K) and under magnetic fields up to 9 T. The validity of this method is tested by measuring various kinds of metallic (copper, platinum and constantan) and insulating (SiO 2 ) materials, which have a wide range of thermal conductivity values (1-400 Wm -1 K -1 ). We have successfully employed this technique for measuring thermal conductivity of two actinide single crystals, uranium dioxide and uranium nitride. Thus, this new experimental approach for studying nuclear materials will help to advance reactor fuel development and understanding. Here, we have also shown that this experimental setup can be adapted to Quantum Design PPMS measurement environment and/or cryocooler systems.

3 Omega Method↗
DOE OSTI2025

Evaluation of the Radioactive Material Released in the Harborview Research and Training Building and Some Implications for Emergency Response

On 2 May 2019, during the 137 Cs source recovery operation, a source capsule in a research irradiator containing approximately 77.1 TBq was breached. Based on a geometric reconstruction analysis of the damage to the capsule, approximately 46.3 GBq (0.04%) was impacted by the chop saw (grinder) inside a mobile hot cell on the loading dock at the University of Washington Harborview Research and Training (HRT) Building. A very small fraction of the material impacted, less than 1%, was released from the mobile hot cell and then to the rest of the HRT Building. The objectives of this project were to assess the accidental release of 137 CsCl and its implications related to emergency response methods and the ramifications of 137 CsCl transport. The phenomenology of this event was also compared with past alkali halide dispersal events. The vast number of measurements and samples collected by the remediation contractors, the Department of Energy’s Nuclear Emergency Support Team, and the small number of retrospective samples collected by the authors informed the analysis. The techniques included (1) autoradiography and electron microscopy of samples collected from the HRT Building and the irradiator, (2) 3D visualization of deposition on surfaces and within the ventilation system, and (3) a study of the damage to the source capsule to evaluate the Cs particle size and particle composition due to the grinding accident. Subsequently, the cesium contaminant transport through the numerous pathways in the building was reconstructed to assess the deposition on surfaces as a function of particle size. Furthermore, the implications for emergency response are relevant to data quality and management. A Data Quality Objective guides data collection methods so that they have appropriate accuracy and precision for the intended application. Recommendations were made with respect to the sample collection protocols and archiving of samples.

46 - INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AN↗
DOE OSTI2011

Definition of "Small Gram Quantity Contents" for Type B Radioactive Material Transportation Packages: Activity-Based Content Limitations, Rev. 1

The results presented are a compendium of allowable masses (and activities) of a variety of different isotopes ( with varying impurity levels of beryllium in some of the actinide isotopes) that, when loaded in an unshielded packaging, do not result in an external dose rate on the surface of the package that exceeds 190 mrem/hr.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗
DOE OSTI2010

BNFL 3013 Containers for Radioactive material Transportation

The DOE Standard, Stabilization, Packaging, and Storage of Plutonium-Bearing Materials, DOE-STD-3013-1994 — i.e., the 3013 Standard — was issued in December 1994, by the DOE weapons complex for the stabilization, packaging and safe storage of excess plutonium-bearing metal and oxides. Based on the 3013 Standard, the BNFL container was designed and developed to remove excess plutonium material from the Hanford and Rocky Flats Sites. The BNFL 3013 containers were put into certified transportation packages and sent to the Savannah River Site for storage and later disposition.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗
DOE OSTI2020

Radioactive Material Dynamics @ NSLS-II [Slides]

RMD @ NSLS-II helps pave the path to a DMMSC: Developing expertise in techniques and experimental methods for DMMSC science; Improving capabilities for models to become microstructurally aware; Workforce training and development; Help refine DMMSC scientific requirements; Complementary to DMMSC XFEL science (EDXD/EXAFS)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗