Engineering Papers⌕ Search

SEARCH · Engineering Papers

Results for “Program Development”

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 955 records · Page 53

The Expanded Capabilities Of The Cementitious Barriers Partnership Software Toolbox Version 2.0 - 14331

The Cementitious Barriers Partnership (CBP) Project is a multi-disciplinary, multi-institutional collaboration supported by the U.S. Department of Energy (US DOE) Office of Tank Waste Management. The CBP program has developed a set of integrated tools (based on state-of-the-art models and leaching test methods) that help improve understanding and predictions of the long-term structural, hydraulic and chemical performance of cementitious barriers used in nuclear applications. The CBP Software Toolbox – “Version 1.0” was released early in FY2013 and was used to support DOE-EM performance assessments in evaluating various degradation mechanisms that included sulfate attack, carbonation and constituent leaching. The sulfate attack analysis predicted the extent and damage that sulfate ingress will have on concrete vaults over extended time (i.e., > 1000 years) and the carbonation analysis provided concrete degradation predictions from rebar corrosion. The new release “Version 2.0” includes upgraded carbonation software and a new software module to evaluate degradation due to chloride attack. Also included in the newer version are a dual regime module allowing evaluation of contaminant release in two regimes – both fractured and un-fractured. The integrated software package has also been upgraded with new plotting capabilities and many other features that increase the “user-friendliness” of the package. Experimental work has been generated to provide data to calibrate the models to improve the credibility of the analysis and reduce the uncertainty. Tools selected for and developed under this program have been used to evaluate and predict the behavior of cementitious barriers used in near-surface engineered waste disposal systems for periods of performance up to or longer than 100 years for operating facilities and longer than 1000 years for waste disposal. The CBP Software Toolbox is and will continue to produce tangible benefits to the working DOE Performance Assessment (PA) community.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

The Cementitious Barriers Partnership (CBP) Software Toolbox Capabilities in Assessing the Degradation of Cementitious Barriers - 13487

The Cementitious Barriers Partnership (CBP) Project is a multi-disciplinary, multi-institutional collaboration supported by the U.S. Department of Energy (US DOE) Office of Tank Waste and Nuclear Materials Management. The CBP program has developed a set of integrated tools (based on state-of-the-art models and leaching test methods) that help improve understanding and predictions of the long-term structural, hydraulic and chemical performance of cementitious barriers used in nuclear applications. Tools selected for and developed under this program have been used to evaluate and predict the behavior of cementitious barriers used in near-surface engineered waste disposal systems for periods of performance up to 100 years and longer for operating facilities and longer than 1000 years for waste disposal. The CBP Software Toolbox has produced tangible benefits to the DOE Performance Assessment (PA) community. A review of prior DOE PAs has provided a list of potential opportunities for improving cementitious barrier performance predictions through the use of the CBP software tools. These opportunities include: 1) impact of atmospheric exposure to concrete and grout before closure, such as accelerated slag and Tc-99 oxidation, 2) prediction of changes in K{sub d}/mobility as a function of time that result from changing pH and redox conditions, 3) concrete degradation from rebar corrosion due to carbonation, 4) early age cracking from drying and/or thermal shrinkage and 5) degradation due to sulfate attack. The CBP has already had opportunity to provide near-term, tangible support to ongoing DOE-EM PAs such as the Savannah River Saltstone Disposal Facility (SDF) by providing a sulfate attack analysis that predicts the extent and damage that sulfate ingress will have on the concrete vaults over extended time (i.e., > 1000 years). This analysis is one of the many technical opportunities in cementitious barrier performance that can be addressed by the DOE-EM sponsored CBP software tools. Modification of the existing tools can provide many opportunities to bring defense in depth in prediction of the performance of cementitious barriers over time. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Savannah River nuclear solutions criticality safety training and qualification program and professional development/retention - 14507

Many years ago, at the Savannah River Site, the need for technically competent and qualified criticality safety (CS) staff was identified. Over the intervening years an extensive training and qualification (T and Q) program was developed. In 2008 Savannah River Nuclear Solutions (SRNS), the current site M and O contractor, inherited the T and Q program developed by the prior site contractors. Since then SRNS has initiated changes to the T and Q program to better fit the current regulatory environment, ensuring compliance with ANSI/ANS-8.26 [1], and implementing the idea of continuous improvement. Currently, a significant fraction of the SRNS CS staff either will be or are eligible for retirement. Therefore, SRNS is pursuing recent Nuclear Engineering college graduates and/or experienced criticality engineers. The challenges associated with hiring and maintaining criticality staff include, but are not limited to, increased workforce mobility and increased competition for fewer criticality resources. For example, the recent trend in company benefits is to eliminate longer term benefits such as pensions to make the benefits more transportable in terms of 401 Ks and Health Savings Accounts. In addition, there have been reductions in DOE funding for professional development through participation in ANS committees or attendance at Criticality related conferences. SRNS has investigated a number of possibilities on how to retain CS staff, but in the current environment has not identified any 'golden eggs'. Regardless, SRNS is exploring additional paths to incentivize the engineers to stay long term. SRNS is working to improve/maintain its workforce by creating a CS engineer pipeline. SRNS provides a training budget for new engineers and offers a formalized and mentored training program. For experienced criticality engineers, the SRNS T and Q program is flexible enough to allow 'credit' for previous accomplishments at other sites. SRNS is also striving to be proactive in supporting professional development by identifying specific monies in the planning phases of the annual budget requests. The current posture of SRNS is to maintain 'open' requisitions for both experienced staff looking for other opportunities, and for recent college graduates. As opportunities arise, either from within or without, SRNS evaluates the potential candidates and advances offers of employment. Until the longer term need is met SRNS intends to hire at least two staff members per year. Those staff members then enter the T and Q program and when appropriate, based on their experience and/or training accomplishments, begin assisting the current staff with program/facility CS support. (authors)

42 ENGINEERING↗

Advanced Hydrogen Fueling Station Supply: Tube Trailers

Air Products and Chemicals, Inc. (Air Products) is reporting on the results of a DOE-funded program to develop and validate Advanced Hydrogen Fueling Station hydrogen tube trailers to support hydrogen and fuel cell market applications. The project involved the engineering design and development of a new composite over-wrapped pressure vessel to increase the pressure capability of tube trailers to deliver hydrogen to greater than 8500 psi (586 bar). The new composite over-wrapped pressure vessel tube trailer was expected to provide improved delivery technology and reduce the cost of transporting hydrogen from central hydrogen production sources. The project aimed to meet or exceed DOE’s 2020 delivery targets for tube trailer hydrogen distribution. A gated approach was taken for the project, with early project Go/No-Go decision points. Specific goals for this four-stage product development project included: Preliminary Study, Modeling, and Analysis: Complete a preliminary design analysis and cost viability of a >8500 psi (586 bar) hydrogen storage vessel with an appropriate frame and chassis configuration for a complete trailer to US DOT requirements; Develop New Tube Size for >8500 psi (586 bar) Vessel: Fabricate tubes for test units, perform testing, and submit test results for a DOT Special Permit; Design, fabricate, and test a delivery trailer unit; Deploy the delivery trailer to hydrogen stations and collect data. Work conducted under DE-EE0006524 established costs for US DOT Type III vessels at 8500 psi (586 bar), 12500 psi (862 bar), and 14000 psi (965 bar) with manufactured water volumes up to 375 liters. Trailer module designs were established for the maximum US DOT design limits and for Air Products’ design limit of a 40-foot trailer length that addresses California hydrogen fueling station ingress and egress operating constraints. Conceptual trailer designs were not capable of achieving the DOE 2020 capacity and cost targets, but they did exceed the DOE pressure target of 500 bar. Based on new trailer cost and simulated operating performance, the 8500 psi (586 bar) new trailer design is not feasible in comparison to Air Products’ DOT-approved 7500 psi (520 bar) trailer design in operation today. Also, the project was expected to incur significantly higher product development costs associated with new US DOT vessel development and approval. Alternative trailer design concepts were explored that included 700 bar compression-less mobile fueling that could be promising for early-market hydrogen infrastructure fueling station placement and development and niche military applications. Due to the economic and budget challenges identified in the feasibility phase of the program, Air Products, in agreement with the Department of Energy, decided to terminate this development program.

08 HYDROGEN↗

Overview of the multifaceted activities towards development and deployment of nuclear-grade FeCrAl alloys

A large effort is underway under the leadership of US DOE Fuel Cycle Research program to develop advanced FeCrAl alloys as accident tolerant fuel (ATF) cladding to replace Zr-based alloys in light water reactors. The primary motivation is the excellent oxidation resistance of these alloys in high-temperature steam environments right up to their melting point (roughly three orders of magnitude slower oxidation kinetics than zirconium). A multifaceted effort is ongoing to rapidly advance FeCrAl alloys as a mature ATF concept. The activities span the broad spectrum of alloy development, environmental testing (high-temperature high-pressure water and elevated temperature steam), detailed mechanical characterization, material property database development, neutron irradiation, thin tube production, and multiple integral fuel test campaigns. Instead of off-the-shelf commercial alloys that might not prove optimal for the LWR fuel cladding application, a large amount of effort has been placed on the alloy development to identify the most optimum composition and microstructure for this application. The development program is targeting a cladding that offers performance comparable to or better than modern Zr-based alloys under normal operating and off-normal conditions. This paper provides a comprehensive overview of the systematic effort to advance nuclear-grade FeCrAl alloys as an ATF cladding in commercial LWRs. (authors)

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Overview of the multifaceted activities towards development and deployment of nuclear-grade FeCrAl Alloys

A large effort is underway under the leadership of US DOE Fuel Cycle R&D program to develop advanced FeCrAl alloys as accident tolerant fuel (ATF) cladding to replace Zr-based alloys in light water reactors. The primary motivation is the excellent oxidation resistance of these alloys in high-temperature steam environments right up to their melting point (roughly three orders of magnitude slower oxidation kinetics than zirconium). A multifaceted effort is ongoing to rapidly advance FeCrAl alloys as a mature ATF concept. The activities span the broad spectrum of alloy development, environmental testing (high-temperature high-pressure water and elevated temperature steam), detailed mechanical characterization, material property database development, neutron irradiation, thin tube production, and multiple integral fuel test campaigns. Instead of off-the-shelf commercial alloys that might not prove optimal for the LWR fuel cladding application, a large amount of effort has been placed on the alloy development to identify the most optimum composition and microstructure for this application. The development program is targeting a cladding that offers performance comparable to or better than modern Zr-based alloys under normal operating and off-normal conditions. This paper provides a comprehensive overview of the systematic effort to advance nuclear-grade FeCrAl alloys as an ATF cladding in commercial LWRs.

Field, Kevin G↗

Implementation of the Port Hope Area Initiative Biophysical and Socioeconomic Environmental Assessment Follow-up Programs - 13209

The Port Hope Initiative (PHAI) involves the cleanup of historic low-level radioactive waste in various locations throughout the communities of Port Hope and Clarington, Ontario, as well as the construction of two engineered aboveground mounds for safe long-term management. The PHAI is comprised of two major projects - the Port Hope Project and the Port Granby Project. An Environmental Assessment (EA) was undertaken for each project and as a result EA Follow-up Programs were developed and are being implemented addressing both biophysical and socioeconomic aspects. This paper provides insight on elements of the EA Follow-up Program development, and its implementation. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Analysis of irradiated U-7wt%Mo dispersion fuel microstructures using automated image processing

The High Performance Research Reactor Fuel Development (HPPRFD) program is responsible for developing low enriched uranium (LEU) fuel substitutes for high performance reactors fueled with highly enriched uranium (HEU) that have not yet been converted to LEU. The uranium-molybdenum (U-Mo) fuel system was selected for this effort. In this study, fission gas pore segmentation was performed on U-7wt%Mo dispersion fuel samples at three separate fission densities using an automated image processing interface developed in MATLAB. Pore size distributions were attained that showed both expected and unexpected fission gas behavior. In general, it proved challenging to identify any dominant trends when comparing fission bubble data across samples from different fuel plates due to varying compositions and fabrication techniques. Here, the results exhibited fair agreement with the fission density vs. porosity correlation developed by the Russian reactor conversion program.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Summary of Structural Material Modeling Development for the NEAMS Program in Fiscal Year 2020

This report summarizes work performed during Fiscal Year (FY) 2020 at Idaho National Laboratory (INL) for the U.S. Department of Energy?s Nuclear Engineering Advanced Modeling and Simulation (NEAMS) program for the Structural Materials and Chemistry Technical Area in the work package entitled "MS- 20IN050104 - Structural Materials - INL." The Structural Materials and Chemistry Technical Area is a relatively new component of the NEAMS program, and is currently focusing on developing simulation capabilities to support the deployment of nuclear energy in the areas of molten salt reactor chemistry, light water reactor (LWR) structural material degradation, and structural material behavior for advanced reactor applications. INL performed work for to advance capabilities for simulation of structural material behavior in both LWR and advanced reactor applications in the work described here.

22 GENERAL STUDIES OF NUCLEAR REACTORS↗