Validation of Reanalysis-Based Offshore Wind Resource Characterization Using Lidar Buoy Observations

2020 ◽  
Vol 54 (6) ◽  
pp. 44-61
Author(s):  
Lindsay M. Sheridan ◽  
Raghavendra Krishnamurthy ◽  
Alicia M. Gorton ◽  
Will J. Shaw ◽  
Rob K. Newsom
Keyword(s):  
Pacific Northwest ◽  
National Laboratory ◽  
Pacific Northwest National Laboratory ◽  
The United States ◽  
Department Of Energy ◽  
Offshore Wind ◽  
Approximation Techniques ◽  
The North ◽  
Wind Resource

AbstractThe offshore wind industry in the United States is gaining strong momentum to achieve sustainable energy goals, and the need for observations to provide resource characterization and model validation is greater than ever. Pacific Northwest National Laboratory (PNNL) operates two lidar buoys for the U.S. Department of Energy (DOE) in order to collect hub height wind data and associated meteorological and oceanographic information near the surface in areas of interest for offshore wind development. This work evaluates the performance of commonly used reanalysis products and spatial approximation techniques using lidar buoy observations off the coast of New Jersey and Virginia, USA. Reanalysis products are essential tools for setting performance expectations and quantifying the wind resource variability at a given site. Long-term accurate observations at typical wind turbine hub heights have been lacking at offshore locations. Using wind speed observations from both lidar buoy deployments, biases and degrees of correspondence for the Modern-Era Retrospective Analysis for Research and Applications-2 (MERRA-2), the North American Regional Reanalysis (NARR), ERA5, and the analysis system of the Rapid Refresh (RAP) are examined both at hub height and near the surface. Results provide insights on the performance and uncertainty of using reanalysis products for long-term wind resource characterization. A slow bias is seen across the reanalyses at both deployment sites. Bias magnitudes near the surface are on the order of 0.5 m s−1 greater than their hub height counterparts. RAP and ERA5 produce the highest correlations with the observations, around 0.9, followed by MERRA-2 and NARR.

Enhanced VVER-1000 Fuel Technology and Performance

2009 ◽  
Author(s):  
H. Shah ◽  
R. Latorre ◽  
G. Raspopin ◽  
J. Sparrow
Keyword(s):  
Pacific Northwest ◽  
Nuclear Power ◽  
Power Plants ◽  
National Laboratory ◽  
Pacific Northwest National Laboratory ◽  
The United States ◽  
Department Of Energy ◽  
United States Department ◽  
Safety Level ◽  
And Performance

The United States Department of Energy, through the Pacific Northwest National Laboratory (PNNL), provides management and technical support for the International Nuclear Safety Program (INSP) to improve the safety level of VVER-1000 nuclear power plants in Central and Eastern Europe.

Advancing Offshore Wind Resource Characterization Using Buoy-Based Observations

2020 ◽  
Vol 54 (6) ◽  
pp. 37-43
Author(s):  
Alicia M. Gorton ◽  
Will J. Shaw
Keyword(s):  
Data Collection ◽  
Wind Energy ◽  
Model Validation ◽  
Performance Testing ◽  
Pacific Northwest National Laboratory ◽  
Economic Benefits ◽  
Department Of Energy ◽  
Offshore Wind ◽  
Wind Resource ◽  
The U.S

AbstractAs countries continue to implement sustainable and renewable energy goals, the need for affordable low-carbon technologies, including those related to offshore wind energy, is accelerating. The U.S. federal government recognizes the environmental and economic benefits of offshore wind development and is taking the necessary steps to overcome critical challenges facing the industry to realize these benefits. The U.S. Department of Energy (DOE) is investing in buoy-mounted lidar systems to facilitate offshore measurement campaigns that will advance our understanding of the offshore environment and provide the observational data needed for model validation, particularly at hub height where offshore observations are particularly lacking. On behalf of the DOE, the Pacific Northwest National Laboratory manages a Lidar Buoy Program that facilitates meteorological and oceanographic data collection using validated methods to support the U.S. offshore wind industry. Since being acquired in 2014, two DOE lidar buoys have been deployed on the U.S. east and west coasts, and their data represent the first publicly available multi-seasonal hub height data to be collected in U.S. waters. In addition, the buoys have undergone performance testing, significant upgrades, and a lidar validation campaign to ensure the accuracy and reliability of the lidar data needed to support wind resource characterization and model validation (the lidars were validated against a reference lidar installed on the Air-Sea Interaction Tower operated by the Woods Hole Oceanographic Institution). The Lidar Buoy Program is providing valuable offshore data to the wind energy community, while focusing data collection on areas of acknowledged high priority.

Code Acceptance of a New Joining Technology for Storage Containments

2009 ◽  
Author(s):  
Gary R. Cannell ◽  
Glenn J. Grant ◽  
Burton E. Hill
Keyword(s):  
Pacific Northwest ◽  
National Laboratory ◽  
Pacific Northwest National Laboratory ◽  
Department Of Energy ◽  
Fusion Welding ◽  
Radioactive Materials ◽  
Friction Stir ◽  
Joining Technology ◽  
Consistent Basis ◽  
Remote Operations

One of the activities associated with cleanup throughout the Department of Energy (DOE) complex is packaging radioactive materials into storage containers. Much of this work will be performed in high-radiation environments requiring fully remote operations for which existing, proven systems do not currently exist. These conditions require a process that is capable of producing acceptable (defect-free) welds on a consistent basis; the need to perform weld repair, under fully-remote operations can be extremely costly and time consuming. Current closure-welding technologies (fusion welding) are not well suited for this application and will present risk to cleanup cost and schedule. To address this risk, Fluor and the Pacific Northwest National Laboratory (PNNL) are proposing that a new and emerging joining technology, Friction Stir Welding (FSW), be considered for this work. FSW technology has been demonstrated in other industries (aerospace and marine) to produce near flaw-free welds on a consistent basis. FSW is judged capable of providing the needed performance for fully-remote closure welding of containers for radioactive materials. The performance characteristics of FSW, i.e., high weld quality, simple machine-tool equipment and increased welding efficiency, suggest that this new technology should be considered for radioactive materials packaging campaigns. FSW technology will require some development/adaptation for this application, along with several activities needed for commercialization. One of these activities will be to obtain approval from the governing construction code to use the FSW technology. The American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME B&PVC) will govern this work; however, rules for the use of FSW are not currently addressed. A code case will be required to define appropriate process variables within prescribed limits for submittal to the Code for review/approval and incorporation.

Modeling Shock and Vibration on Used Nuclear Fuel During Normal Conditions of Transportation

2019 ◽  
Author(s):  
Nicholas Klymyshyn ◽  
Pavlo Ivanusa ◽  
Kevin Kadooka ◽  
Casey Spitz
Keyword(s):  
Nuclear Fuel ◽  
Numerical Models ◽  
National Laboratory ◽  
Pacific Northwest National Laboratory ◽  
The United States ◽  
Lessons Learned ◽  
Department Of Energy ◽  
United States Department ◽  
Fuel Cladding ◽  
Used Nuclear Fuel

Abstract In 2017, the United States Department of Energy (DOE) collaborated with Spanish and Korean organizations to perform a multimodal transportation test to measure shock and vibration loads imparted to used nuclear fuel (UNF) assemblies. This test used real fuel assembly components containing surrogate fuel mass to approximate the response characteristics of real, irradiated used nuclear fuel. Pacific Northwest National Laboratory was part of the test team and used the data collected during this test to validate numerical models needed to predict the response of real used nuclear fuel in other transportation configurations. This paper summarizes the modeling work and identifies lessons learned related to the modeling and analysis methodology. The modeling includes railcar dynamics using the NUCARS software code and explicit dynamic finite element modeling of used nuclear fuel cladding in LS-DYNA. The NUCARS models were validated against railcar dynamics data collected during captive track testing at the Federal Railroad Administration’s Transportation Technology Center in Pueblo, CO. The LS-DYNA models of the fuel cladding were validated against strain gage data collected throughout the test campaign. One of the key results of this work was an assessment of fuel cladding fatigue, and the methods used to calculate fatigue are detailed in this paper. The validated models and analysis methodologies described in this paper will be applied to evaluate future UNF transportation systems.

Sulfur Polymer Cement as a Low-Level Waste Glass Matrix Encapsulant, Part I: Thermal Processing

1995 ◽  
Vol 412 ◽  
Author(s):  
Paul Sliva ◽  
Y. Benjamin Peng ◽  
L. Roy Bunnell ◽  
David K. Peeler ◽  
Xiangdong Feng ◽  
...  
Keyword(s):  
Pacific Northwest ◽  
Thermal Processing ◽  
National Laboratory ◽  
Pacific Northwest National Laboratory ◽  
Northwest National Laboratory ◽  
Glass Cullet ◽  
Low Level ◽  
Long Term Stability ◽  
Additional Barrier

AbstractSulfur polymer cement (SPC) is a candidate material to encapsulate low-level waste (LLW) glass. Molten SPC will be poured into a LLW glass cullet-filled canister, surrounding the glass to act as an additional barrier to groundwater intrusion. This paper covers the first part of a study performed at Pacific Northwest National Laboratory concerned with the fundamental aspects of embedding LLW glass in SPC. Part one is a study of the SPC itself. Variations in SPC properties are discussed, especially in relation to long-term stability and controlling crystallization in a cooling canister.

Structural Analysis Approach for the Defense Programs Package 3 (DPP-3)

2020 ◽  
Author(s):  
Peter J. Sakalaukus ◽  
Nathan P. Barrett ◽  
Brian J. Koeppel
Keyword(s):  
Pacific Northwest ◽  
National Laboratory ◽  
Pacific Northwest National Laboratory ◽  
Analytical Techniques ◽  
Nuclear Regulatory Commission ◽  
Department Of Energy ◽  
Design Criteria ◽  
Element Analysis ◽  
Regulatory Testing ◽  
Regulatory Commission

Abstract The Pacific Northwest National Laboratory (PNNL) is the design authority for a new Type B hazardous materials transportation package designated as the Defense Programs Package 3 (DPP-3) for the U.S. Department of Energy (DOE) National Nuclear Security Administration (NNSA). The DPP-3 has been developed using similar materials and fabrication methods employed in previous U.S. Nuclear Regulatory Commission (NRC), DOE, and NNSA certified packages. The DPP-3 design criteria are derived from the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC), NNSA guidance and NRC regulatory guides in order to safely and securely transport a variety of payloads. Final regulatory approval by the NNSA will require regulatory testing to demonstrate that the containment vessel (CV) remains leaktight after enduring the entire regulatory testing sequence prescribed in Title 10 of the Code of Federal Regulations Part 71 (10 CFR 71). In order to gain confidence that the DPP-3 will remain leaktight after testing, the DPP-3 has been structurally analyzed using the Finite Element Analysis (FEA) software LS-DYNA. The FEA analyses serve two general purposes: first, they aid in design and development of the package, and second, they advise as to which drop orientations are expected to cause the most damage during regulatory testing. This paper will discuss how the design criteria are incorporated into analytical techniques needed to evaluate the FEA structural simulation results for 10 CFR 71 conditions to give confidence the DPP-3 testing campaign will be successful.

Modeling Approach to Determine Short- and Long-Term Thermal and Thermomechanical Effects of Waste Emplacement in a Repository in Basalt

1981 ◽  
Vol 11 ◽  
Author(s):  
Terry F. Lehnhoff ◽  
K. Thirumalai ◽  
Alan D. Krug
Keyword(s):  
Pacific Northwest ◽  
United States Of America ◽  
The United States ◽  
Department Of Energy ◽  
Nuclear Waste Repository ◽  
Columbia River Basalts ◽  
The Pacific ◽  
Short And Long Term ◽  
Selection Of

The Columbia River basalts, which underlie a large portion of the Pacific Northwest of the United States of America, are being investigated as one of the candidate media for a nuclear waste repository. The Basalt Waste Isolation Project (BWIP) of Rockwell Hanford Operations (Rockwell) is conducting these investigations for the U.S. Department of Energy (DOE). Since the inception of the program in 1976, a number of studies have led to the selection of a reference repository location and the start of construction of an exploratory shaft.1-3

New Progress of Study in Energy Storage Area of Volcanic Rocks

2012 ◽  
Vol 616-618 ◽  
pp. 100-103
Author(s):  
Fang Lu ◽  
Xin Jiang Du ◽  
Yan Zhou ◽  
Yang Yang Du
Keyword(s):  
Energy Storage ◽  
Pacific Northwest ◽  
Large Scale ◽  
Oil And Gas ◽  
Rapid Development ◽  
National Laboratory ◽  
Volcanic Rocks ◽  
Pacific Northwest National Laboratory ◽  
Economic Feasibility ◽  
Department Of Energy

With the rapid development of national economy, combined with the construction of strategic reservation of petroleum in China, difficulty of large-scale energy storage and peak-shaving comes up. In recent years, the U.S. Department of Energy (DOE), the Bonneville Power Administration (BPA), the Pacific Northwest National Laboratory (PNNL) and a number of energy companies launched two projects in the Columbia Basin to evaluate the technical and economic feasibility of underground gas and wind power storage in basalt interflow aquifers. These projects reveal the potential of volcanic rocks in the underground energy storage areas. This paper briefly describes the new progress of study in underground gas storage (UGS), compressed air energy storage (CAES) and underground thermal energy storage (UTES) of volcanic rocks. We point out that depleted volcanic oil and gas reservoirs could be another complementary type of UGS and CAES, and volcanic rocks types should be included extrusive rocks and pyroclastic rocks. At last, volcanic energy storage technologies used in some domestic related areas of enlightenment is summarized to provide theoretical basis for building green, efficient and low-consumption economy.

NDE Assessment of PWSCC in Control Rod Drive Mechanism Housings

2006 ◽  
Author(s):  
Steven R. Doctor ◽  
Stephen E. Cumblidge ◽  
George J. Schuster ◽  
Robert V. Harris ◽  
Susan L. Crawford
Keyword(s):  
Pacific Northwest ◽  
National Laboratory ◽  
Pacific Northwest National Laboratory ◽  
Nuclear Regulatory Commission ◽  
The United States ◽  
Primary Objective ◽  
Control Rod ◽  
Drive Mechanism ◽  
Nondestructive Examination ◽  
Service Inspection

Studies being conducted at the Pacific Northwest National Laboratory (PNNL) in Richland, Washington are focused on assessing the effectiveness of nondestructive examination (NDE) techniques for inspecting control rod drive mechanism (CRDM) nozzles and J-groove weldments. The primary objective of this work is to provide information to the United States Nuclear Regulatory Commission (US NRC) on the effectiveness of NDE methods as related to the in-service inspection of CRDM nozzles and J-groove weldments, and to enhance the knowledge base of primary water stress corrosion cracking (PWSCC) through destructive characterization of the CRDM assemblies. In describing two CRDM assemblies removed from service, decontaminated, and then used in a series of NDE measurements, this paper will address the following questions: 1) What did each technique detect?, 2) What did each technique miss?, and 3) How accurately did each technique characterize the detected flaws? Two CRDM assemblies including the CRDM nozzle, the J-groove weld, buttering, and a portion of the ferritic head material were selected for this study. One contained suspected PWSCC, based on in-service inspection data and through-wall leakage; the other contained evidence suggesting through-wall leakage, but this was unconfirmed. The two CRDMs used in this study were cut from a pressure vessel head that has since been replaced. The selected NDE measurements follow standard industry techniques for conducting in-service inspections of CRDM nozzles and the crown of the J-groove welds and buttering. In addition, laboratory based NDE methods were employed to conduct inspections of the CRDM assemblies, with particular emphasis on inspecting the J-groove weld and buttering. This paper will also describe the NDE methods used and discuss the NDE results. Future work will involve using the results from these NDE studies to guide the development of a destructive characterization plan to reveal the crack morphology and a comparison of the degradation found by the destructive evaluation with the recorded NDE responses.

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