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1

Inspection of Used Fuel Dry Storage Casks  

SciTech Connect

ABSTRACT The U.S. Nuclear Regulatory Commission (NRC) regulates the storage of used nuclear fuel, which is now and will be increasingly placed in dry storage systems. Since a final disposition pathway is not defined, the fuel is expected to be maintained in dry storage well beyond the time frame originally intended. Due to knowledge gaps regarding the viability of current dry storage systems for long term use, efforts are underway to acquire the technical knowledge and tools required to understand the issues and verify the integrity of the dry storage system components. This report summarizes the initial efforts performed by researchers at Idaho National Laboratory and Argonne National Laboratory to identify and evaluate approaches to in-situ inspection dry storage casks. This task is complicated by the design of the current storage systems that severely restrict access to the casks.

Dennis C. Kunerth; Tim McJunkin; Mark McKay; Sasan Bakhtiari

2012-09-01T23:59:59.000Z

2

Managing Aging Effects on Dry Cask Storage Systems for Extended...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Managing Aging Effects on Dry Cask Storage Systems for Extended Long Term Storage and Transportation of Used Fuel Rev0 Managing Aging Effects on Dry Cask Storage Systems for...

3

Dry Cask Storage Probabilistic Risk Assessment Scoping Study  

Science Conference Proceedings (OSTI)

This report describes and evaluates the current state of risk assessment methodologies applicable to dry cask storage probabilistic risk assessment (PRA) and suggests appropriate approaches for performing the various aspects of a dry cask storage PRA.

2002-03-20T23:59:59.000Z

4

Dry Cask Storage Characterization Project  

Science Conference Proceedings (OSTI)

Nuclear utilities have developed independent spent fuel storage installations (ISFSIs) as a means of expanding their spent-fuel storage capacity on an interim basis until a geologic repository is available to accept the fuel for permanent storage. This report provides a technical basis for demonstrating the feasibility of extended spent-fuel storage in ISFSIs.

2002-09-26T23:59:59.000Z

5

Managing Aging Effects on Dry Cask Storage  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Managing Aging Effects Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel Rev. 0 Prepared for U.S. Department of Energy Used Fuel Disposition Campaign O.K. Chopra, D. Diercks, R. Fabian, D. Ma, V. Shah, S-W Tam, and Y.Y. Liu Argonne National Laboratory June 30, 2012 FCRD-USED-2012-000119 ANL-12/29 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately

6

Dry Cask Storage Study Feb 1989 | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Dry Cask Storage Study Feb 1989 Dry Cask Storage Study Feb 1989 Dry Cask Storage Study Feb 1989 This report on the use of dry-cask-storage technologies at the sites of civilian nuclear power reactors has been prepared by the U.S. Department of Energy (DOE} in response to the requirements of the Nuclear Waste Policy Amendments Act of 1987 (P.L. 100-203). In particular, Section 5064 of the Amendments Act directs the Secretary of Energy to conduct a study and evaluation of using these technologies for the temporary storage of spent nuclear fuel until such time as a permanent geologic repository has been constructed and licensed by the Nuclear Regulatory Commission (NRC). In conducting this study, the DOE is required to consider such factors as costs, effects on human health and the environment, effects on the costs

7

Viability of Existing INL Facilities for Dry Storage Cask Handling  

SciTech Connect

This report evaluates existing capabilities at the INL to determine if a practical and cost effective method could be developed for opening and handling full-sized dry storage casks. The Idaho Nuclear Technology and Engineering Center (INTEC) CPP-603, Irradiated Spent Fuel Storage Facility, provides the infrastructure to support handling and examining casks and their contents. Based on a reasonable set of assumptions, it is possible to receive, open, inspect, remove samples, close, and reseal large bolted-lid dry storage casks at the INL. The capability can also be used to open and inspect casks that were last examined at the TAN Hot Shop over ten years ago. The Castor V/21 and REA-2023 casks can provide additional confirmatory information regarding the extended performance of low-burnup (<45 GWD/MTU) used nuclear fuel. Once a dry storage cask is opened inside CPP-603, used fuel retrieved from the cask can be packaged in a shipping cask, and sent to a laboratory for testing. Testing at the INL’s Materials and Fuels Complex (MFC) can occur starting with shipment of samples from CPP-603 over an on-site road, avoiding the need to use public highways. This reduces cost and reduces the risk to the public. The full suite of characterization methods needed to establish the condition of the fuel exists and MFC. Many other testing capabilities also exist at MFC, but when those capabilities are not adequate, samples can be prepared and shipped to other laboratories for testing. This report discusses how the casks would be handled, what work needs to be done to ready the facilities/capabilities, and what the work will cost.

Randy Bohachek; Charles Park; Bruce Wallace; Phil Winston; Steve Marschman

2013-04-01T23:59:59.000Z

8

Dry Cask Storage Characterization Project - Phase 1: CASTOR V/21 Cask Opening and Examination  

Science Conference Proceedings (OSTI)

This report documents visual examination and testing conducted in 1999 and early 2000 at the Idaho National Engineering and Environmental Laboratory (INEEL) on a Gesellschaft für Nuklear Service (GNS) CASTOR V/21 pressurized water reactor (PWR) spent fuel dry storage cask. The purpose of the examination and testing is to develop a technical basis for renewal of licenses and Certificates of Compliance for dry storage systems for spent nuclear fuel and high-level waste at independent spent fuel storage installation sites. The examination and testing was conducted to assess the condition of the cask internal and external surfaces, cask contents consisting of 21 Westinghouse PWR spent fuel assemblies from Dominion’s (formerly named Virginia Power) Surry Power Station and cask concrete storage pad. The assemblies have been continuously stored in the CASTOR cask since 1985. Cask exterior surface and selected fuel assembly temperatures, and cask surface gamma and neutron dose rates were measured. Cask external/internal surfaces, fuel basket components including accessible weldments, fuel assembly exteriors, and primary lid seals were visually examined. Selected fuel rods were removed from one fuel assembly, visually examined, and then shipped to Argonne National Laboratory for nondestructive, destructive, and mechanical examination. Cask interior crud samples and helium cover gas samples were collected and analyzed. The results of the examination and testing indicate the concrete storage pad, CASTOR V/21 cask, and cask contents exhibited sound structural and seal integrity and that long-term storage has not caused detectable degradation of the spent fuel cladding or the release of gaseous fission products between 1985 and 1999.

Bare, Walter Claude; Ebner, Matthias Anthony; Torgerson, Laurence Dale

2001-08-01T23:59:59.000Z

9

Directory of Certificates of Compliance for dry spent fuel storage casks  

Science Conference Proceedings (OSTI)

This directory contains Certificates of Compliance for all dry spent fuel storage casks approved by the US Nuclear Regulatory Commission and Summary Reports of each approved cask model. Later directories will contain a list of cask users, and a list of cask locations. The purpose of this directory is to make available a convenient source of information on spent fuel storage casks which have been approved by the US Nuclear Regulatory Commission. Storage of fuel assemblies using these casks must be in accordance with the provisions of 10 CFR Part 72.

Not Available

1992-02-01T23:59:59.000Z

10

Viability of Existing INL Facilities for Dry Storage Cask Handling R1 |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Viability of Existing INL Facilities for Dry Storage Cask Handling Viability of Existing INL Facilities for Dry Storage Cask Handling R1 Viability of Existing INL Facilities for Dry Storage Cask Handling R1 While dry storage technologies are some of the safest in the world, the U.S. Department of Energy is planning a confirmatory dry storage project for high burnup fuel. This report evaluates existing capabilities at Idaho National Laboratory (INL) to determine if a practical and cost effective method could be developed for handling and opening full-sized dry storage casks. Existing facilities at the Idaho Nuclear Technology and Engineering Center provide the infrastructure to support handling and examining of casks and their contents. Based on a reasonable set of assumptions, it is possible to receive, open, inspect, remove samples, close, and reseal

11

Managing Aging Effects on Dry Cask Storage Systems for Extended Long Term  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Managing Aging Effects on Dry Cask Storage Systems for Extended Managing Aging Effects on Dry Cask Storage Systems for Extended Long Term Storage and Transportation of Used Fuel Rev0 Managing Aging Effects on Dry Cask Storage Systems for Extended Long Term Storage and Transportation of Used Fuel Rev0 The report is intended to help assess and establish the technical basis for extended long-term storage and transportation of used nuclear fuel. It provides: 1) an overview of the ISFSI license renewal process based on 10 CFR 72 and the guidance provided in NUREG-1927; 2) definitions and terms for structures and components in DCSSs, materials, environments, aging effects, and aging mechanisms; 3) TLAAs and AMPs, respectively, that have been developed for managing aging effects on the SSCs important to safety in the dry cask storage system designs; and 4) AMPs and TLAAs for the SSCs

12

Regulators Experiences in Licensing and Inspection of Dry Cask Storage Facilities  

SciTech Connect

The United States Nuclear Regulatory Commission (NRC), through the combination of a rigorous licensing and inspection program, ensures the safety and security of dry cask storage. NRC authorizes the storage of spent fuel at an independent spent fuel storage installation (ISFSI) under two licensing options: site-specific licensing and general licensing. In July 1986, the NRC issued the first site-specific license to the Surry Nuclear Power Plant in Virginia authorizing the interim storage of spent fuel in a dry storage cask configuration. Today, there are over 30 ISFSIs currently licensed by the NRC with over 700 loaded dry casks. Current projections identify over 50 ISFSIs by the year 2010. No releases of spent fuel dry storage cask contents or other significant safety problems from the storage systems in use today have been reported. This paper discusses the NRC licensing and inspection experiences. (authors)

Baggett, S.; Brach, E.W. [Spent Fuel Project Office, U.S. Nuclear Regulatory Commission, Washington, DC 20555 (United States)

2006-07-01T23:59:59.000Z

13

Dry Cask Storage Characterization Project: Interim Progress Report - October 2001  

Science Conference Proceedings (OSTI)

With some independent spent-fuel storage installations (ISFSIs) approaching their U.S. Nuclear Regulatory Commission (NRC) licensing limit of 20 years, utilities will need to apply for a license extension to keep existing spent fuel in a dry storage system. At present, however, the NRC has not fully developed a recommended license extension approach for ISFSI licensees. In addition, the U.S. Department of Energy (DOE) has requested information on the long-term behavior of spent fuel stored in dry conditi...

2001-10-25T23:59:59.000Z

14

Failure Modes and Effects Analysis (FMEA) of Welded Stainless Steel Canisters for Dry Cask Storage Systems  

Science Conference Proceedings (OSTI)

Due to the delayed opening of a final geological repository for spent nuclear fuel, the lifespan of dry cask storage systems may be increased to 120 years or longer. To ensure safety over this extended period of interim storage, degradation mechanisms that have the potential to cause penetration of the canister confinement boundary must be evaluated and understood. To address this issue, the Electric Power Research Institute (EPRI) performed a failure modes and effects analysis (FMEA) to identify ...

2013-12-17T23:59:59.000Z

15

Testing of the dual slab verification detector for attended measurements of the BN-350 dry storage casks  

Science Conference Proceedings (OSTI)

The Dual Slab Verification Detector (DSVD) has been developed and built by Los Alamos National Laboratory in cooperation with the International Atomic Energy Agency (IAEA) as part of the dry storage safeguards system for the spent fuel from the BN-350 fast reactor. The detector consists of two rows of {sup 3}He tubes embedded in a slab of polyethylene which has been designed to be placed on the outer surface of the dry storage cask. The DSVD will be used to perform measurements of the neutron flux emanating from inside the dry storage cask at several locations around each cask to establish a neutron 'fingerprint' that is sensitive to the contents of the cask. The sensitivity of the fingerprinting technique to the removal of specific amount of nuclear material from the cask is determined by the characteristics of the detector that is used to perform the measurements, the characteristics of the spent fuel being measured, and systematic uncertainties that are associated with the dry storage scenario. MCNPX calculations of the BN-350 dry storage asks and layout have shown that the neutron fingerprint verification technique using measurements from the DSVD would be sensitive to both the amount and location of material that is present within an individual cask. To confirm the performance of the neutron fingerprint technique in verifying the presence of BN-350 spent fuel in dry storage, an initial series of measurements have been performed to test the performance and characteristics of the DSVD. Results of these measurements will be presented and compared with MCNPX results.

Santi, Peter A [Los Alamos National Laboratory; Browne, Michael C [Los Alamos National Laboratory; Williams, Richard B [Los Alamos National Laboratory; Parker, Robert F [Los Alamos National Laboratory

2009-01-01T23:59:59.000Z

16

Analysis of dose consequences arising from the release of spent nuclear fuel from dry storage casks.  

SciTech Connect

The resulting dose consequences from releases of spent nuclear fuel (SNF) residing in a dry storage casks are examined parametrically. The dose consequences are characterized by developing dose versus distance curves using simplified bounding assumptions. The dispersion calculations are performed using the MELCOR Accident Consequence Code System (MACCS2) code. Constant weather and generic system parameters were chosen to ensure that the results in this report are comparable with each other and to determine the relative impact on dose of each variable. Actual analyses of site releases would need to accommodate local weather and geographic data. These calculations assume a range of fuel burnups, release fractions (RFs), three exposure scenarios (2 hrs and evacuate, 2 hrs and shelter, and 24 hrs exposure), two meteorological conditions (D-4 and F-2), and three release heights (ground level - 1 meter (m), 10 m, and 100 m). This information was developed to support a policy paper being developed by U.S. Nuclear Regulatory Commission (NRC) staff on an independent spent fuel storage installation (ISFSI) and monitored retrievable storage installation (MRS) security rulemaking.

Durbin, Samuel G.; Morrow, Charles W.

2013-01-01T23:59:59.000Z

17

Initial measurements of BN-350 spent fuel in dry storage casks using the dual slab verification detonator  

Science Conference Proceedings (OSTI)

The Dual Slab Verification Detector (DSVD) has been developed, built, and characterized by Los Alamos National Laboratory in cooperation with the International Atomic Energy Agency (IAEA) as part of the dry storage safeguards system for the spent fuel from the BN-350 fast reactor. The detector consists of two rows of 3He tubes embedded in a slab of polyethylene which has been designed to be placed on the outer surface of the dry storage cask. By performing DSVD measurements at several different locations around the outer surface of the DUC, a signature 'fingerprint' can be established for each DUC based on the neutron flux emanating from inside the dry storage cask. The neutron fingerprint for each individual DUC will be dependent upon the spatial distribution of nuclear material within the cask, thus making it sensitive to the removal of a certain amount of material from the cask. An initial set of DSVD measurements have been performed on the first set of dry storage casks that have been loaded with canisters of spent fuel and moved onto the dry storage pad to both establish an initial fingerprint for these casks as well as to quantify systematic uncertainties associated with these measurements. The results from these measurements will be presented and compared with the expected results that were determined based on MCNPX simulations of the dry storage facility. The ability to safeguard spent nuclear fuel is strongly dependent on the technical capabilities of establishing and maintaining continuity of knowledge (COK) of the spent fuel as it is released from the reactor core and either reprocessed or packaged and stored at a storage facility. While the maintenance of COK is often done using continuous containment and surveillance (C/S) on the spent fuel, it is important that the measurement capabilities exist to re-establish the COK in the event of a significant gap in the continuous CIS by performing measurements that independently confirm the presence and content of Plutonium (Pu) in the spent fuel. The types of non-destructive assay (NDA) measurements that can be performed on the spent fuel are strongly dependent on the type of spent fuel that is being safeguarded as well as the location in which the spent fuel is being stored. The BN-350 Spent Fuel Disposition Project was initiated to improve the safeguards and security of the spent nuclear fuel from the BN-350 fast-breeder reactor and was developed cooperatively to meet the requirements of the International Atomic Energy Agency (IAEA) as well as the terms of the 1993 CTR and MPC&A Implementing Agreements. The unique characteristics of fuel from the BN-350 fast-breeder reactor have allowed for the development of an integrated safeguards measurement program to inventory, monitor, and if necessary, re-verify Pu content of the spent fuel throughout the lifetime of the project. This approach includes the development of a safeguards measurement program to establish and maintain the COK on the spent fuel during the repackaging and eventual relocation of the spent-fuel assemblies to a long-term storage site. As part of the safeguards measurement program, the Pu content of every spent-fuel assembly from the BN-350 reactor was directly measured and characterized while the spent-fuel assemblies were being stored in the spent-fuel pond at the BN-350 facility using the Spent Fuel Coincidence Counter (SFCC). Upon completion of the initial inventory of the Pu content of the individual spent-fuel assemblies, the assemblies were repackaged into welded steel canisters that were filled with inert argon gas and held either four or six individual spent-fuel assemblies depending on the type of assembly that was being packaged. This repackaging of the spent-fuel assemblies was performed in order to improve the stability of the spent-fuel assemblies for long-term storage and increase the proliferation resistance of the spent fuel. To maintain the capability of verifying the presence of the spent-fuel assemblies inside the welded steel canisters, measurements were performed on the canis

Santi, Peter Angelo [Los Alamos National Laboratory; Browne, Michael C [Los Alamos National Laboratory; Freeman, Corey R [Los Alamos National Laboratory; Parker, Robert F [Los Alamos National Laboratory; Williams, Richard B [Los Alamos National Laboratory

2010-01-01T23:59:59.000Z

18

Managing aging effects on dry cask storage systems for extended long-term storage and transportation of used fuel - rev. 0  

Science Conference Proceedings (OSTI)

The cancellation of the Yucca Mountain repository program in the United States raises the prospect of extended long-term storage (i.e., >120 years) and deferred transportation of used fuel at operating and decommissioned nuclear power plant sites. Under U.S. federal regulations contained in Title 10 of the Code of Federal Regulations (CFR) 72.42, the initial license term for an Independent Spent Fuel Storage Installation (ISFSI) must not exceed 40 years from the date of issuance. Licenses may be renewed by the U.S. Nuclear Regulatory Commission (NRC) at the expiration of the license term upon application by the licensee for a period not to exceed 40 years. Application for ISFSI license renewals must include the following: (1) Time-limited aging analyses (TLAAs) that demonstrate that structures, systems, and components (SSCs) important to safety will continue to perform their intended function for the requested period of extended operation; and (2) a description of the aging management program (AMP) for management of issues associated with aging that could adversely affect SSCs important to safety. In addition, the application must also include design bases information as documented in the most recent updated final safety analysis report as required by 10 CFR 72.70. Information contained in previous applications, statements, or reports filed with the Commission under the license may be incorporated by reference provided that those references are clear and specific. The NRC has recently issued the Standard Review Plan (SRP) for renewal of used-fuel dry cask storage system (DCSS) licenses and Certificates of Compliance (CoCs), NUREG-1927, under which NRC may renew a specific license or a CoC for a term not to exceed 40 years. Both the license and the CoC renewal applications must contain revised technical requirements and operating conditions (fuel storage, surveillance and maintenance, and other requirements) for the ISFSI and DCSS that address aging effects that could affect the safe storage of the used fuel. The information contained in the license and CoC renewal applications will require NRC review to verify that the aging effects on the SSCs in DCSSs/ ISFSIs are adequately managed for the period of extended operation. To date, all of the ISFSIs located across the United States with more than 1,500 dry casks loaded with used fuel have initial license terms of 20 years; three ISFSIs (Surry, H.B. Robinson and Oconee) have received their renewed licenses for 20 years, and two other ISFSIs (Calvert Cliffs and Prairie Island) have applied for license renewal for 40 years. This report examines issues related to managing aging effects on the SSCs in DCSSs/ISFSIs for extended long-term storage and transportation of used fuels, following an approach similar to that of the Generic Aging Lessons Learned (GALL) report, NUREG-1801, for the aging management and license renewal of nuclear power plants. The report contains five chapters and an appendix on quality assurance for aging management programs for used-fuel dry storage systems. Chapter I of the report provides an overview of the ISFSI license renewal process based on 10 CFR 72 and the guidance provided in NUREG-1927. Chapter II contains definitions and terms for structures and components in DCSSs, materials, environments, aging effects, and aging mechanisms. Chapter III and Chapter IV contain generic TLAAs and AMPs, respectively, that have been developed for managing aging effects on the SSCs important to safety in the dry cask storage system designs described in Chapter V. The summary descriptions and tabulations of evaluations of AMPs and TLAAs for the SSCs that are important to safety in Chapter V include DCSS designs (i.e., NUHOMS{reg_sign}, HI-STORM 100, Transnuclear (TN) metal cask, NAC International S/T storage cask, ventilated storage cask (VSC-24), and the Westinghouse MC-10 metal dry storage cask) that have been and continue to be used by utilities across the country for dry storage of used fuel to date. The goal of this report is to help establish the technical

Chopra, O.K.; Diercks, D.; Fabian, R.; Ma, D.; Shah, V.; Tam, S.W.; Liu, Y. (Decision and Information Sciences); ( EVS); ( NE)

2012-07-06T23:59:59.000Z

19

Managing aging effects on dry cask storage systems for extended long-term storage and transportation of used fuel - rev. 0  

SciTech Connect

The cancellation of the Yucca Mountain repository program in the United States raises the prospect of extended long-term storage (i.e., >120 years) and deferred transportation of used fuel at operating and decommissioned nuclear power plant sites. Under U.S. federal regulations contained in Title 10 of the Code of Federal Regulations (CFR) 72.42, the initial license term for an Independent Spent Fuel Storage Installation (ISFSI) must not exceed 40 years from the date of issuance. Licenses may be renewed by the U.S. Nuclear Regulatory Commission (NRC) at the expiration of the license term upon application by the licensee for a period not to exceed 40 years. Application for ISFSI license renewals must include the following: (1) Time-limited aging analyses (TLAAs) that demonstrate that structures, systems, and components (SSCs) important to safety will continue to perform their intended function for the requested period of extended operation; and (2) a description of the aging management program (AMP) for management of issues associated with aging that could adversely affect SSCs important to safety. In addition, the application must also include design bases information as documented in the most recent updated final safety analysis report as required by 10 CFR 72.70. Information contained in previous applications, statements, or reports filed with the Commission under the license may be incorporated by reference provided that those references are clear and specific. The NRC has recently issued the Standard Review Plan (SRP) for renewal of used-fuel dry cask storage system (DCSS) licenses and Certificates of Compliance (CoCs), NUREG-1927, under which NRC may renew a specific license or a CoC for a term not to exceed 40 years. Both the license and the CoC renewal applications must contain revised technical requirements and operating conditions (fuel storage, surveillance and maintenance, and other requirements) for the ISFSI and DCSS that address aging effects that could affect the safe storage of the used fuel. The information contained in the license and CoC renewal applications will require NRC review to verify that the aging effects on the SSCs in DCSSs/ ISFSIs are adequately managed for the period of extended operation. To date, all of the ISFSIs located across the United States with more than 1,500 dry casks loaded with used fuel have initial license terms of 20 years; three ISFSIs (Surry, H.B. Robinson and Oconee) have received their renewed licenses for 20 years, and two other ISFSIs (Calvert Cliffs and Prairie Island) have applied for license renewal for 40 years. This report examines issues related to managing aging effects on the SSCs in DCSSs/ISFSIs for extended long-term storage and transportation of used fuels, following an approach similar to that of the Generic Aging Lessons Learned (GALL) report, NUREG-1801, for the aging management and license renewal of nuclear power plants. The report contains five chapters and an appendix on quality assurance for aging management programs for used-fuel dry storage systems. Chapter I of the report provides an overview of the ISFSI license renewal process based on 10 CFR 72 and the guidance provided in NUREG-1927. Chapter II contains definitions and terms for structures and components in DCSSs, materials, environments, aging effects, and aging mechanisms. Chapter III and Chapter IV contain generic TLAAs and AMPs, respectively, that have been developed for managing aging effects on the SSCs important to safety in the dry cask storage system designs described in Chapter V. The summary descriptions and tabulations of evaluations of AMPs and TLAAs for the SSCs that are important to safety in Chapter V include DCSS designs (i.e., NUHOMS{reg_sign}, HI-STORM 100, Transnuclear (TN) metal cask, NAC International S/T storage cask, ventilated storage cask (VSC-24), and the Westinghouse MC-10 metal dry storage cask) that have been and continue to be used by utilities across the country for dry storage of used fuel to date. The goal of this report is to help establish the technical

Chopra, O.K.; Diercks, D.; Fabian, R.; Ma, D.; Shah, V.; Tam, S.W.; Liu, Y. (Decision and Information Sciences); ( EVS); ( NE)

2012-07-06T23:59:59.000Z

20

Probabilistic Risk Assessment (PRA) of Bolted Storage Casks: Quantification and Analysis Report  

Science Conference Proceedings (OSTI)

Since the U.S. Nuclear Regulatory Commission (NRC) approved dry storage of spent fuel, dry casks stored at U.S. sites have increased significantly in number since the 1980s. This project, a spent fuel cask probabilistic risk assessment (PRA), was designed to obtain insights related to the risks associated with the dry storage of spent fuel.

2003-12-31T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


21

Probabilistic Risk Assessment (PRA) of Bolted Storage Casks: Updated Quantification and Analysis Report  

Science Conference Proceedings (OSTI)

Since the 1980s, when the U.S. Nuclear Regulatory Commission (NRC) approved dry storage of spent fuel, dry casks stored at U.S. sites have increased significantly in number. This report and its predecessor — a spent fuel cask probabilistic risk assessment (PRA) (EPRI report 1002877) — are designed to provide insights related to the risks associated with dry storage of spent fuel.

2004-11-30T23:59:59.000Z

22

Radiant heat transfer from storage casks to the environment  

SciTech Connect

A spent fuel storage cask must efficiently transfer the heat released by the fuel assemblies through the cask walls to the environment. This heat must be transferred through passive means, limiting the energy transfer mechanisms from the cask to natural convection and radiation heat transfer.. Natural convection is essentially independent of the characteristics of the array of casks, provided there is space between casks to permit a convection loop. Radiation heat transfer, however, depends on the geometric arrangement of the array of casks because the peripheral casks will shadow the interior casks and restrict radiant heat transfer from all casks to the environment. The shadowing of one cask by its neighbors is determined by a view factor that represents the fraction of radiant energy that leaves the surface of a cask and reaches the environment. This paper addresses the evaluation of the view factor between a centrally located spent fuel storage cask and the environment. By combining analytic expressions for the view factor of (1) infinitely long cylinders and (2) finite cylinders with a length-to-diameter ratio of 2 to represent spent fuel storage casks, the view factor can be evaluated for any practical array of spent fuel storage casks.

Carlson, R W; Hovingh, J; Thomas, G R

1999-05-10T23:59:59.000Z

23

European experience in transport/storage cask for vitrified residues  

SciTech Connect

Available in abstract form only. Full text of publication follows: Because of the evolution of burnup of spent fuel to be reprocessed, the high activity vitrified residues would not be transported in the existing cask designs. Therefore, TN International has decided in the late nineties to develop a brand new design of casks with optimized capacity able to store and transport the most active and hottest canisters: the TN{sup TM}81 casks currently in use in Switzerland and the TN{sup TM}85 cask which shall permit in the near future in Germany the storage and the transport of the most active vitrified residues defining a thermal power of 56 kW (kilowatts). The challenges for the TN{sup TM}81 and TN{sup TM}85 cask designs were that the geometry entry data were very restrictive and were combined with a fairly wide range set by the AREVA NC Specification relative to vitrified residue canister. The TN{sup TM}81 and the TN{sup TM}85 casks have been designed to fully anticipate shipment constraints of the present vitrified residue production. It also used the feedback of current shipments and the operational constraints and experience of receiving and shipping facilities. The casks had to fit as much as possible in the existing procedures for the already existing flasks such as the TN{sup TM}28 cask and TS 28 V cask, all along the logistics chain of loading, unloading, transport and maintenance. (authors)

Otton, Camille; Sicard, Damien [AREVA - TN International (France)

2007-07-01T23:59:59.000Z

24

European experience in transport / storage cask for vitrified residues  

Science Conference Proceedings (OSTI)

Because of the evolution of burnup of spent fuel to be reprocessed, the high activity vitrified residues would not be transported in the existing cask designs. Therefore, TN International has decided in the late nineties to develop a brand new design of casks with optimized capacity able to store and transport the most active and hottest canisters: the TN{sup TM}81 casks currently in use in Switzerland and the TN{sup TM}85 cask which shall permit in the near future in Germany the storage and the transport of the most active vitrified residues defining a thermal power of 56 kW (kilowatts). The challenges for the TN{sup TM}81 and TN{sup TM}85 cask designs were that the geometry entry data were very restrictive and were combined with a fairly wide range set by the AREVA NC Specification relative to vitrified residue canister. The TN{sup TM}81 and the TN{sup TM}85 casks have been designed to fully anticipate shipment constraints of the present vitrified residue production. It also used the feedback of current shipments and the operational constraints and experience of receiving and shipping facilities. The casks had to fit as much as possible in the existing procedures for the already existing flasks such as the TN{sup TM}28 cask and TS 28 V cask, all along the logistics chain of loading, unloading, transport and maintenance. In addition, years of feedback and experience in design and operations - together with ever improved materials - have allowed finding further optimization of this type of cask design. In order to increase the loading capacity in terms of radioactive source terms and heat load by 40%, the cask design relies on innovative solutions and benchmarks from the current shipping campaigns. Currently, TN{sup TM}81 and TN{sup TM}85 are the only licensed casks that can transport and store 28 canisters with a total decay heat of 56 kW. It contributes to optimise the number of required transports to bring back high level waste residues to their producers. Three units have already been loaded and transported to ZWILAG (Zwischenlager Wuerenlingen AG) in Switzerland where they are stored for 40 years. Based on the same design but integrating the German Authorities and German users specificities, the TN{sup TM}85 cask is dedicated to the transport and storage of vitrified residues to Germany. It is presently at the final licensing stage. The transport cask approval expertise has now been granted, and the storage expertise is in the final steps. The first transport with TN{sup TM}85 cask is scheduled up to now in 2007 and the commissioning operations are under preparation. These two casks are key elements for the whole reprocessing system of AREVA as they enable the transport and the storage of the vitrified residues. (authors)

Blachet, L.; Otton, C.; Sicard, D. [AREVA TN International (France)

2007-07-01T23:59:59.000Z

25

Comparative economics for DUCRETE spent fuel storage cask handling, transportation, and capital requirements  

SciTech Connect

This report summarizes economic differences between a DUCRETE spent nuclear fuel storage cask and a conventional concrete storage cask in the areas of handling, transportation, and capital requirements. The DUCRETE cask is under evaluation as a new technology that could substantially reduce the overall costs of spent fuel and depleted U disposal. DUCRETE incorporates depleted U in a Portland cement mixture and functions as the cask`s primary radiation barrier. The cask system design includes insertion of the US DOE Multi-Purpose Canister inside the DUCRETE cask. The economic comparison is from the time a cask is loaded in a spent fuel pool until it is placed in the repository and includes the utility and overall US system perspectives.

Powell, F.P. [Sierra Nuclear Corp., Roswell, GA (United States)

1995-04-01T23:59:59.000Z

26

Behavior of spent nuclear fuel and storage system components in dry interim storage. Revision 1  

SciTech Connect

Irradiated nuclear fuel has been handled under dry conditions since the early days of nuclear reactor operation, and use of dry storage facilities for extended management of irradiated fuel began in 1964. Irradiated fuel is currently being stored dry in four types of facilities: dry wells, vaults, silos, and metal casks. Essentially all types of irradiated nuclear fuel are currently stored under dry conditions. Gas-cooled reactor (GCR) and liquid metal fast breeder reactor (LMFBR) fuels are stored in vaults and dry wells. Certain types of fuel are being stored in licensed dry storage facilities: Magnox fuel in vaults in the United Kingdom; organic-cooled reactor (OCR) fuel (clad with a zirconium alloy) in silos in Canada; and boiling water reactor (BWR) fuel (clad with Zircaloy) in a metal storage cask in Germany. Dry storage demonstrations are under way for Zircaloy-clad fuel from BWRs, pressurized heavy-water reactors (PHWRs), and pressurized water reactors (PWRs) in all four types of dry storage facilities. The demonstrations and related hot cell and laboratory tests are directed toward expanding the data base and establishing a licensing basis for dry storage of water reactor fuel. This report reviews the scope of dry interim storage technology, the performance of fuel and facility materials, the status of programs in several countries to license dry storage of water reactor fuel, and the characteristics of water reactor fuel that relate to dry storage conditions. 110 refs., 22 figs., 28 tabs.

Johnson, A.B. Jr.; Gilbert, E.R.; Guenther, R.J.

1983-02-01T23:59:59.000Z

27

Managing Aging Effects on Dry Cask Storage  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

... III.4-5 III.5 Time-Dependent Degradation of Radiation-Shielding Materials ... III.5-1 III.5.1 Description of the...

28

Integrated Used Nuclear Fuel Storage, Transportation, and Disposal ...  

dry cask storage of used nuclear fuel at existing plant ... achievement of geologic disposal thermal management ... Senior Technology Commercialization Manager ...

29

Licensing of spent fuel dry storage and consolidated rod storage: A Review of Issues and Experiences  

Science Conference Proceedings (OSTI)

The results of this study, performed by Pacific Northwest Laboratory (PNL) and sponsored by the US Department of Energy (DOE), respond to the nuclear industry's recommendation that a report be prepared that collects and describes the licensing issues (and their resolutions) that confront a new applicant requesting approval from the US Nuclear Regulatory Commission (NRC) for dry storage of spent fuel or for large-scale storage of consolidated spent fuel rods in pools. The issues are identified in comments, questions, and requests from the NRC during its review of applicants' submittals. Included in the report are discussions of (1) the 18 topical reports on cask and module designs for dry storage fuel that have been submitted to the NRC, (2) the three license applications for dry storage of spent fuel at independent spent fuel storage installations (ISFSIs) that have been submitted to the NRC, and (3) the three applications (one of which was later withdrawn) for large-scale storage of consolidated fuel rods in existing spent fuel storage pools at reactors that were submitted tot he NRC. For each of the applications submitted, examples of some of the issues (and suggestions for their resolutions) are described. The issues and their resolutions are also covered in detail in an example in each of the three subject areas: (1) the application for the CASTOR V/21 dry spent fuel storage cask, (2) the application for the ISFSI for dry storage of spent fuel at Surry, and (3) the application for full-scale wet storage of consolidated spent fuel at Millstone-2. The conclusions in the report include examples of major issues that applicants have encountered. Recommendations for future applicants to follow are listed. 401 refs., 26 tabs.

Bailey, W.J.

1990-02-01T23:59:59.000Z

30

CHARACTERISTICS OF NEXT-GENERATION SPENT NUCLEAR FUEL (SNF) TRANSPORT AND STORAGE CASKS  

SciTech Connect

The design of spent nuclear fuel (SNF) casks used in the present SNF disposition systems has evolved from early concepts about the nuclear fuel cycle. The reality today is much different from that envisioned by early nuclear scientists. Most SNF is placed in pool storage, awaiting reprocessing (as in Russia) or disposal at a geologic SNF repository (as in the United States). Very little transport of SNF occurs. This paper examines the requirements for SNF casks from today's perspective and attempts to answer this question: What type of SNF cask would be produced if we were to start over and design SNF casks based on today's requirements? The characteristics for a next-generation SNF cask system are examined and are found to be essentially the same in Russia and the United States. It appears that the new depleted uranium dioxide (DUO2)-steel cermet material will enable these requirements to be met. Depleted uranium (DU) is uranium in which a portion of the 235U isotope has been removed during a uranium enrichment process. The DUO2-steel cermet material is described. The United States and Russia are cooperating toward the development of a next-generation, dual-purpose, storage and transport SNF system.

Haire, M.J.; Forsberg, C.W.; Matveev, V.Z.; Shapovalov, V.I.

2004-10-03T23:59:59.000Z

31

Dry Storage Demonstration for High-Burnup Spent Nuclear Fuel: Feasibility Study  

Science Conference Proceedings (OSTI)

Initially, casks for dry storage of spent fuel were licensed for assembly-average burnup of about 35 GWd/MTU. Over the last two decades, the discharge burnup of fuel has increased steadily and now routinely exceeds 45 GWd/MTU. This feasibility study examines the options available for conducting a confirmatory experimental program supporting regulatory acceptance of practical approaches for storing, and later transporting, spent fuel with burnup well in excess of 45 GWd/MTU under a dry, inert atmosphere.

2003-09-19T23:59:59.000Z

32

Nondestructive Evaluation of the VSC-17 Cask  

Science Conference Proceedings (OSTI)

In 2003, representatives from the Central Research Institute of Electric Power Industry (CRIEPI) requested development of a project with the objective of determining the performance of a concrete spent nuclear fuel storage cask. Radiation and environmental effects may cause chemical alteration of the concrete that could result in excessive cracking, spalling, and loss of compressive strength. The Idaho National Laboratory (INL) project team and CRIEPI representatives identified the Ventilated Storage Cask (VSC 17) spent nuclear fuel storage cask, originally located at the INL Test Area North, as a candidate to study cask performance because it had been used to store fuel as part of a dry cask storage demonstration project for over 15 years. The project involved investigating the properties of the concrete shield. INL performed a survey of the cask in the summers of 2003 and 2004. The INL team met with the CRIEPI representatives in December of 2004 to discuss the next steps. As a result of that meeting, CRIEPI requested that in the summer 2005 INL perform additional surveys on the VSC 17 cask with participation of CRIEPI scientists. This document summarizes the evaluation methods used on the VSC 17 to evaluate the cask for compressive strength, concrete cracking, concrete thickness, and temperature distribution.

Sheryl Morton; Al Carlson; Cecilia Hoffman; James Rivera; Phil Winston; Koji Shirai; Shin Takahashi; Masaharo Tanaka

2006-01-01T23:59:59.000Z

33

Use of depleted uranium metal as cask shielding in high-level waste storage, transport, and disposal systems  

SciTech Connect

The US DOE has amassed over 555,000 metric tons of depleted uranium from its uranium enrichment operations. Rather than dispose of this depleted uranium as waste, this study explores a beneficial use of depleted uranium as metal shielding in casks designed to contain canisters of vitrified high-level waste. Two high-level waste storage, transport, and disposal shielded cask systems are analyzed. The first system employs a shielded storage and disposal cask having a separate reusable transportation overpack. The second system employs a shielded combined storage, transport, and disposal cask. Conceptual cask designs that hold 1, 3, 4 and 7 high-level waste canisters are described for both systems. In all cases, cask design feasibility was established and analyses indicate that these casks meet applicable thermal, structural, shielding, and contact-handled requirements. Depleted uranium metal casting, fabrication, environmental, and radiation compatibility considerations are discussed and found to pose no serious implementation problems. About one-fourth of the depleted uranium inventory would be used to produce the casks required to store and dispose of the nearly 15,400 high-level waste canisters that would be produced. This study estimates the total-system cost for the preferred 7-canister storage and disposal configuration having a separate transportation overpack would be $6.3 billion. When credits are taken for depleted uranium disposal cost, a cost that would be avoided if depleted uranium were used as cask shielding material rather than disposed of as waste, total system net costs are between $3.8 billion and $5.5 billion.

Yoshimura, H.R.; Ludwigsen, J.S.; McAllaster, M.E. [and others

1996-09-01T23:59:59.000Z

34

REVIEW OF FAST FLUX TEST FACILITY (FFTF) FUEL EXPERIMENTS FOR STORAGE IN INTERIM STORAGE CASKS (ISC)  

SciTech Connect

Appendix H, Section H.3.3.10.11 of the Final Safety Analysis Report (FSAR), provides the limits to be observed for fueled components authorized for storage in the Fast Flux Test Facility (FFTF) spent fuel storage system. Currently, the authorization basis allows standard driver fuel assemblies (DFA), as described in the FSAR Chapter 17, Section 17.5.3.1, to be stored provided decay power per assembly is {le} 250 watts, post-irradiation time is four years minimum, average assembly burn-up is 150,000 MWD/MTHM maximum and the pre-irradiation enrichment is 29.3% maximum (per H.3.3.10.11). In addition, driver evaluation (DE), core characterizer assemblies (CCA), and run-to-cladding-breach (RTCB) assemblies are included based on their similarities to a standard DFA. Ident-69 pin containers with fuel pins from these DFAs can also be stored. Section H.3.3.10.11 states that fuel types outside the specification criteria above will be addressed on a case-by-case basis. There are many different types of fuel and blanket experiments that were irradiated in the FFTF which now require offload to the spent fuel storage system. Two reviews were completed for a portion of these special type fuel components to determine if placement into the Core Component Container (CCC)/Interim Storage Cask (ISC) would require any special considerations or changes to the authorization basis. Project mission priorities coupled with availability of resources and analysts prevented these evaluations from being completed as a single effort. Areas of review have included radiological accident release consequences, radiological shielding adequacy, criticality safety, thermal limits, confinement, and stress. The results of these reviews are available in WHC-SD-FF-RPT-005, Rev. 0 and 1, ''Review of FFTF Fuel Experiments for Storage at ISA'', (Reference I), which subsequently allowed a large portion of these components to be included in the authorization basis (Table H.3.3-21). The report also identified additional components and actions in Section 3.0 and Table 3 that require further evaluation. The purpose of this report is to evaluate another portion of the remaining inventory (i.e., delayed neutron signal fuel, blanket assemblies, highly enriched assemblies, newly loaded Ident-69 pin containers, and returned fuel) to ensure it can be safely off loaded to the FFTF spent fuel storage system.

CHASTAIN, S.A.

2005-10-24T23:59:59.000Z

35

Conceptual design report for the ICPP spent nuclear fuel dry storage project  

Science Conference Proceedings (OSTI)

The conceptual design is presented for a facility to transfer spent nuclear fuel from shipping casks to dry storage containers, and to safely store those containers at ICPP at INEL. The spent fuels to be handled at the new facility are identified and overall design and operating criteria established. Physical configuration of the facility and the systems used to handle the SNF are described. Detailed cost estimate for design and construction of the facility is presented.

NONE

1996-07-01T23:59:59.000Z

36

Concrete Shield Performance of the VSC-17 Spent Nuclear Fuel Cask  

Science Conference Proceedings (OSTI)

In 2003, representatives from the Central Research Institute of Electric Power Industry (CRIEPI) requested development of a project with the objective of determining the performance of a concrete spent nuclear fuel storage cask. Radiation and environmental effects may cause chemical alteration of the concrete that could result in excessive cracking, spalling, and loss of compressive strength. The Idaho National Laboratory (INL) project team and CRIEPI representatives identified the Ventilated Storage Cask (VSC-17) spent nuclear fuel storage cask as a candidate to study cask performance, because it had been used to store fuel as part of a dry cask storage demonstration project for more than 15 years. The project involved investigating the properties of the concrete shield. INL performed a survey of the cask in the summers of 2003 and 2004. Preliminary cask evaluations performed in 2003 indicated that the cask has no visual degradation. However, a 4-5 mrem/hr step-change in the radiation levels about halfway up the cask and a localized hot spot beneath an upper air vent indicate that there may be variability in the density of the concrete or localized cracking. In 2005, INL and CRIEPI scientists performed additional surveys on the VSC-17 cask. This document summarizes the methods used on the VSC-17 to evaluate the cask for compressive strength, concrete cracking, concrete thickness, and temperature distribution.

Sheryl L. Morton; Philip L. Winston; Toshiari Saegusa; Koji Shirai; Akihiro Sasahara; Takatoshi Hattori

2006-04-01T23:59:59.000Z

37

Comparison of cask and drywell storage concepts for a monitored retrievable storage/interim storage system  

SciTech Connect

The Department of Energy, through its Richland Operations Office is evaluating the feasibility, timing, and cost of providing a federal capability for storing the spent fuel, high-level wastes, and transuranic wastes that DOE may be obligated by law to manage until permanent waste disposal facilities are available. Three concepts utilizing a monitored retrievable storage/interim storage (MRS/IS) facility have been developed and analyzed. The first concept, co-location with a reprocessing plant, has been developed by staff of Allied General Nuclear Services. the second concept, a stand-alone facility, has been developed by staff of the General Atomic Company. The third concept, co-location with a deep geologic repository, has been developed by the Pacific Northwest Laboratory with the assistance of the Westinghouse Hanford Company and Kaiser Engineers. The objectives of this study are: to develop preconceptual designs for MRS/IS facilities: to examine various issues such as transportation of wastes, licensing of the facilities, and environmental concerns associated with operation of such facilities; and to estimate the life-cycle costs of the facilities when operated in response to a set of scenarios that define the quantities and types of waste requiring storage in specific time periods, generally spanning the years 1989 to 2037. Three scenarios are examined to develop estimates of life-cycle costs for the MRS/IS facilities. In the first scenario, the reprocessing plant is placed in service in 1989 and HLW canisters are stored until a repository is opened in the year 1998. Additional reprocessing plants and repositories are placed in service at intervals as needed to meet the demand. In the second scenario, the reprocessing plants are delayed in starting operations by 10 years, but the repositories open on schedule. In the third scenario, the repositories are delayed 10 years, but the reprocessing plants open on schedule.

Rasmussen, D.E.

1982-12-01T23:59:59.000Z

38

Design and Manufacture of the Storage Cask for the Old Reactor Internals  

SciTech Connect

Mitsubishi Heavy Industries, Ltd. (MHI) completed replacement work of upper reactor internals (UCI) and lower reactor internals (LCI) of the pressurized water reactor in Shikoku Electric Power Company's Ikata Unit No.1 by 'the all-in-one-piece extraction method' introduced in the document of [ICONE14-89233]. In the pressurized water reactor (PWR) plant, the UCI are usually removed from the reactor vessel (RV) independently and reinstalled into the RV again every refueling outage. The LCI are independently able to be removed from the RV and reinstalled again during in-service inspection, too. In the boiling water reactor (BWR) plant, there are several cases of replacing BWR shrouds by cutting small and containing in a container. But no replacement of all reactor internals (CI) for the PWR, in one piece without splitting or cutting, has been reported. The purpose of this paper is to introduce the key points about the design and manufacture of the storage cask for old reactor internals in the replacement work by 'the all-in-one-piece extraction method'. (author)

Yasuhiro Tomiita [Mitsubishi Heavy Industries, Ltd. (Japan)

2006-07-01T23:59:59.000Z

39

Heat Transfer Modeling of Dry Spent Nuclear Fuel Storage Facilities  

Science Conference Proceedings (OSTI)

The present work was undertaken to provide heat transfer model that accurately predicts the thermal performance of dry spent nuclear fuel storage facilities. One of the storage configurations being considered for DOE Aluminum-clad Spent Nuclear Fuel (Al-SNF), such as the Material and Testing Reactor (MTR) fuel, is in a dry storage facility. To support design studies of storage options a computational and experimental program has been conducted at the Savannah River Site (SRS). The main objective is to develop heat transfer models including natural convection effects internal to an interim dry storage canister and to geological codisposal Waste Package (WP). Calculated temperatures will be used to demonstrate engineering viability of a dry storage option in enclosed interim storage and geological repository WP and to assess the chemical and physical behaviors of the Al-SNF in the dry storage facilities. The current paper describes the modeling approaches and presents the computational results along with the experimental data.

Lee, S.Y.

1999-01-13T23:59:59.000Z

40

Hydrogen storage materials and method of making by dry homogenation  

DOE Green Energy (OSTI)

Dry homogenized metal hydrides, in particular aluminum hydride compounds, as a material for reversible hydrogen storage is provided. The reversible hydrogen storage material comprises a dry homogenized material having transition metal catalytic sites on a metal aluminum hydride compound, or mixtures of metal aluminum hydride compounds. A method of making such reversible hydrogen storage materials by dry doping is also provided and comprises the steps of dry homogenizing metal hydrides by mechanical mixing, such as be crushing or ball milling a powder, of a metal aluminum hydride with a transition metal catalyst. In another aspect of the invention, a method of powering a vehicle apparatus with the reversible hydrogen storage material is provided.

Jensen, Craig M. (Kailua, HI); Zidan, Ragaiy A. (Honolulu, HI)

2002-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


41

Cold Demonstration of a Spent Nuclear Fuel Dry Transfer System  

Science Conference Proceedings (OSTI)

The development of a spent nuclear fuel dry transfer system (DTS) has moved from the design phase to demonstration of major components. Use of an on-site DTS allows utilities with limited crane capacities or other plant restrictions to take advantage of large efficient storage systems. This system also permits utilities to transfer spent fuel from loaded storage casks to transport casks without returning to their fuel storage pool, a circumstance that may arise during the decommissioning process.

1999-09-24T23:59:59.000Z

42

Validation of EPRI Methodology for Analysis of Spend-Fuel Cask Drop and Tipover Events  

Science Conference Proceedings (OSTI)

Dry storage pads(typically consisting of reinforced concrete slabs constructed on engineered fill(ultimately serve as in situ impact limiters which can be designed to minimize the impact forces on a spent-fuel storage cask. This report presents experimental validation of a previously developed EPRI method for calculating deceleration forces sustained by a spent-fuel cask during its accidental drop or tipover onto a concrete storage pad. The report also describes a step-by-step procedure for applying the ...

1997-09-12T23:59:59.000Z

43

Aging Tests of Neutron-Shielding Materials for Transport of Storage Casks  

Science Conference Proceedings (OSTI)

Special Issue Technical Paper / Second Seminar on Accelerated Testing of Materials in Spent Nuclear Fuel and High-Level Waste Storage Systems / Materials for Nuclear Systems

Herve Issard; Pascale Abadie

44

Business Case Slide 16: High-Volume: Casks - Basis  

NLE Websites -- All DOE Office Websites (Extended Search)

Basis Previous Slide Next Slide Table of Contents High-Volume: Casks - Basis Basis Storage casks with high-density shielding can be directly loaded in reactor pools Eliminates a...

45

Storage capacity in hot dry rock reservoirs  

DOE Patents (OSTI)

A method is described for extracting thermal energy, in a cyclic manner, from geologic strata which may be termed hot dry rock. A reservoir comprised of hot fractured rock is established and water or other liquid is passed through the reservoir. The water is heated by the hot rock, recovered from the reservoir, cooled by extraction of heat by means of heat exchange apparatus on the surface, and then re-injected into the reservoir to be heated again. Water is added to the reservoir by means of an injection well and recovered from the reservoir by means of a production well. Water is continuously provided to the reservoir and continuously withdrawn from the reservoir at two different flow rates, a base rate and a peak rate. Increasing water flow from the base rate to the peak rate is accomplished by rapidly decreasing backpressure at the outlet of the production well in order to meet periodic needs for amounts of thermal energy greater than a baseload amount, such as to generate additional electric power to meet peak demands. The rate of flow of water provided to the hot dry rock reservoir is maintained at a value effective to prevent depletion of the liquid inventory of the reservoir. 4 figs.

Brown, D.W.

1997-11-11T23:59:59.000Z

46

Storage capacity in hot dry rock reservoirs  

DOE Patents (OSTI)

A method of extracting thermal energy, in a cyclic manner, from geologic strata which may be termed hot dry rock. A reservoir comprised of hot fractured rock is established and water or other liquid is passed through the reservoir. The water is heated by the hot rock, recovered from the reservoir, cooled by extraction of heat by means of heat exchange apparatus on the surface, and then re-injected into the reservoir to be heated again. Water is added to the reservoir by means of an injection well and recovered from the reservoir by means of a production well. Water is continuously provided to the reservoir and continuously withdrawn from the reservoir at two different flow rates, a base rate and a peak rate. Increasing water flow from the base rate to the peak rate is accomplished by rapidly decreasing backpressure at the outlet of the production well in order to meet periodic needs for amounts of thermal energy greater than a baseload amount, such as to generate additional electric power to meet peak demands. The rate of flow of water provided to the hot dry rock reservoir is maintained at a value effective to prevent depletion of the liquid

Brown, Donald W. (Los Alamos, NM)

1997-01-01T23:59:59.000Z

47

The impact of dry spent-fuel storage on decommissioning  

Science Conference Proceedings (OSTI)

Several utilities have made decisions to decommission nuclear plants. Other utilities are currently investigating the economic and technical feasibility of decommissioning versus continued operations. As a result, assessments are being made to determine the impact of dry spent-fuel storage on decommissioning. This assessment is being made on a comparison of wet and dry storage (including modifications to current wet storage systems). Not only are the capital and operating costs of the equipment or modifications being evaluated, but staffing levels, interference with other decommissioning activities, and the ability to eventually transfer the fuel to the U.S. Department of Energy (DOE) all factor into the assessments. In the case of the Rancho Seco nuclear generating station, the Sacramento Municipal Utility District (SMUD) developed three objectives related to spent-fuel disposition to support the safe and economical closure of the plant. These objectives are as follows: 1. Minimize occupational and public radiation exposure. 2. Minimize decommissioning costs, including the need to maintain the spent-fuel pool. 3. Prepare the fuel for DOE acceptance. These rather universal goals are being met for Rancho Seco through the use of a canister-based spent-fuel storage and transportation system, the NUHOMS system. This paper discusses the economic and technical impacts of dry spent-fuel storage on decommissioning, more specifically as it relates to the decommissioning of the Rancho Seco plant.

Bowser, R.C.; Taylor, M. Jr. (Pacific Nuclear, San Jose, CA (United States)); Miller, K.R. (Sacramento Municipal Utility District, Herald, CA (United States))

1993-01-01T23:59:59.000Z

48

SNF shipping cask shielding analysis  

Science Conference Proceedings (OSTI)

The Waste Management and Remedial Action Division has planned a modification sequence for storage facility 7827 in the Solid Waste Storage Area (SWSA). The modification cycle is: (1) modify an empty caisson, (2) transfer the spent nuclear fuel (SNF) of an occupied caisson to a hot cell in building 3525 for inspection and possible repackaging, and (3) return the package to the modified caisson in the SWSA. Although the SNF to be moved is in the solid form, it has different levels of activity. Thus, the following 5 shipping casks will be available for the task: the Loop Transport Carrier, the In- Pile Loop LITR HB-2 Carrier, the 6.5-inch HRLEL Carrier, the HFIR Hot Scrap Carrier, and the 10-inch ORR Experiment Removal Shield Cask. This report describes the shielding tasks for the 5 casks: determination of shielding characteristics, any streaming avenues, estimation of thermal limits, and shielding calculational uncertainty for use in the transportation plan.

Johnson, J.O.; Pace, J.V. III

1996-01-01T23:59:59.000Z

49

Desiccant grain applied to the storage of solar drying potential  

Science Conference Proceedings (OSTI)

Sorption storage of solar heat using a layer of wheat as the desiccant was analyzed by means of a deep-bed model. Intended to be applied to solar-assisted in-storage drying of agricultural bulk materials, the probability of the persistence of unfavorable weather periods was quantified statistically for Potsdam for the month of August, as an example. Simulation results demonstrate that a relative humidity of the drying air of 65% can be maintained day and night for weeks without combustion of fossil fuels. Using a simple strategy of control, periods with insufficient solar radiation can be bridged over. The desiccant grain is not endangered by mold growth as a matter of principle. Simple solar air heaters can be used to avoid economic losses due to overdrying and to reduce the danger of decay to a minimum even at unfavorable climatic conditions.

Ziegler, T.; Richter, I.G.; Pecenka, R.

1999-09-01T23:59:59.000Z

50

Cooperative Project on Burnup Credit -- Data and Analysis for Spent Nuclear Fuel Transport and Storage in Burnup Credit Casks  

Science Conference Proceedings (OSTI)

For the past two years, the Department of Energy's Office of Civilian Radioactive Waste Management (DOE/RW), the Nuclear Regulatory Commission's Office of Nuclear Regulatory Research (NRC/RES) and the Electric Power Research Institute (EPRI) have pursued a coordinated project having as its objective to develop and/or obtain the scientific and technical information necessary to support preparation and review of a safety evaluation for cask designs that use full (actinide and fission product) burnup credit...

2006-12-06T23:59:59.000Z

51

Dry Transfer Systems for Used Nuclear Fuel  

Science Conference Proceedings (OSTI)

The potential need for a dry transfer system (DTS) to enable retrieval of used nuclear fuel (UNF) for inspection or repackaging will increase as the duration and quantity of fuel in dry storage increases. This report explores the uses for a DTS, identifies associated general functional requirements, and reviews existing and proposed systems that currently perform dry fuel transfers. The focus of this paper is on the need for a DTS to enable transfer of bare fuel assemblies. Dry transfer systems for UNF canisters are currently available and in use for transferring loaded canisters between the drying station and storage and transportation casks.

Brett W. Carlsen; Michaele BradyRaap

2012-05-01T23:59:59.000Z

52

MODELING HEAT TRANSFER IN SPENT FUEL TRANSFER CASK NEUTRON SHIELDS – A CHALLENGING PROBLEM IN NATURAL CONVECTION  

SciTech Connect

In the United States, commercial spent nuclear fuel is typically moved from spent fuel pools to outdoor dry storage pads within a transfer cask system that provides radiation shielding to protect personnel and the surrounding environment. The transfer casks are cylindrical steel enclosures with integral gamma and neutron radiation shields. Since the transfer cask system must be passively cooled, decay heat removal from spent nuclear fuel canister is limited by the rate of heat transfer through the cask components, and natural convection from the transfer cask surface. The primary mode of heat transfer within the transfer cask system is conduction, but some cask designs incorporate a liquid neutron shield tank surrounding the transfer cask structural shell. In these systems, accurate prediction of natural convection within the neutron shield tank is an important part of assessing the overall thermal performance of the transfer cask system. The large-scale geometry of the neutron shield tank, which is typically an annulus approximately 2 meters in diameter but only 10-15 cm in thickness, and the relatively small scale velocities (typically less than 5 cm/s) represent a wide range of spatial and temporal scales that contribute to making this a challenging problem for computational fluid dynamics (CFD) modeling. Relevant experimental data at these scales are not available in the literature, but some recent modeling studies offer insights into numerical issues and solutions; however, the geometries in these studies, and for the experimental data in the literature at smaller scales, all have large annular gaps that are not prototypic of the transfer cask neutron shield. This paper proposes that there may be reliable CFD approaches to the transfer cask problem, specifically coupled steady-state solvers or unsteady simulations; however, both of these solutions take significant computational effort. Segregated (uncoupled) steady state solvers that were tested did not accurately capture the flow field and heat transfer distribution in this application. Mesh resolution, turbulence modeling, and the tradeoff between steady state and transient solutions are addressed. Because of the critical nature of this application, the need for new experiments at representative scales is clearly demonstrated.

Fort, James A.; Cuta, Judith M.; Bajwa, C.; Baglietto, E.

2010-07-18T23:59:59.000Z

53

Effect of residual stress on the life prediction of dry storage canisters for used nuclear fuel  

E-Print Network (OSTI)

Used nuclear fuel dry storage canisters will likely be tasked with holding used nuclear fuel for a period longer than originally intended. Originally designed for 20 years, the storage time will likely approach 100 years. ...

Black, Bradley P. (Bradley Patrick)

2013-01-01T23:59:59.000Z

54

Instrumented, Shielded Test Canister System for Evaluation of Spent Nuclear Fuel in Dry Storage  

SciTech Connect

This document describes the development of an instrumented, shielded test canister system to store and monitor aluminum-based spent nuclear duel under dry storage conditions.

Sindelar, R.L.

1999-10-21T23:59:59.000Z

55

Dry matter losses during hay production and storage of sweet sorghum used for methane production  

SciTech Connect

Losses from production and storage of large round hay bales from sweet sorghum were measured. Dry matter losses from hay production were 55.3%. Storage losses were 18.1% and 10.1% for outdoor and indoor storage, respectively. It was concluded hay storage of sweet sorghum used for anaerobic digestion is not a viable option.

Coble, C.G.; Egg, R.

1987-01-01T23:59:59.000Z

56

Initial evaluation of dry storage issues for spent nuclear fuels in wet storage at the Idaho Chemical Processing Plant  

SciTech Connect

The Pacific Northwest Laboratory has evaluated the basis for moving selected spent nuclear fuels in the CPP-603 and CPP-666 storage pools at the Idaho Chemical Processing Plant from wet to dry interim storage. This work is being conducted for the Lockheed Idaho Technologies Company as part of the effort to determine appropriate conditioning and dry storage requirements for these fuels. These spent fuels are from 22 test reactors and include elements clad with aluminum or stainless steel and a wide variety of fuel materials: UAl{sub x}, UAl{sub x}-Al and U{sub 3}O{sub 8}-Al cermets, U-5% fissium, UMo, UZrH{sub x}, UErZrH, UO{sub 2}-stainless steel cermet, and U{sub 3}O{sub 8}-stainless steel cermet. The study also included declad uranium-zirconium hydride spent fuel stored in the CPP-603 storage pools. The current condition and potential failure mechanisms for these spent fuels were evaluated to determine the impact on conditioning and dry storage requirements. Initial recommendations for conditioning and dry storage requirements are made based on the potential degradation mechanisms and their impacts on moving the spent fuel from wet to dry storage. Areas needing further evaluation are identified.

Guenther, R.J.; Johnson, A.B. Jr.; Lund, A.L.; Gilbert, E.R. [and others

1994-11-01T23:59:59.000Z

57

A 2-D Test Problem for CFD Modeling Heat Transfer in Spent Fuel Transfer Cask Neutron Shields  

SciTech Connect

In the United States, commercial spent nuclear fuel is typically moved from spent fuel pools to outdoor dry storage pads within a transfer cask system that provides radiation shielding to protect personnel and the surrounding environment. The transfer casks are cylindrical steel enclosures with integral gamma and neutron radiation shields. Since the transfer cask system must be passively cooled, decay heat removal from spent nuclear fuel canister is limited by the rate of heat transfer through the cask components, and natural convection from the transfer cask surface. The primary mode of heat transfer within the transfer cask system is conduction, but some cask designs incorporate a liquid neutron shield tank surrounding the transfer cask structural shell. In these systems, accurate prediction of natural convection within the neutron shield tank is an important part of assessing the overall thermal performance of the transfer cask system. The large-scale geometry of the neutron shield tank, which is typically an annulus approximately 2 meters in diameter but only 5-10 cm in thickness, and the relatively small scale velocities (typically less than 5 cm/s) represent a wide range of spatial and temporal scales that contribute to making this a challenging problem for computational fluid dynamics (CFD) modeling. Relevant experimental data at these scales are not available in the literature, but some recent modeling studies offer insights into numerical issues and solutions; however, the geometries in these studies, and for the experimental data in the literature at smaller scales, all have large annular gaps that are not prototypic of the transfer cask neutron shield. This paper presents results for a simple 2-D problem that is an effective numerical analog for the neutron shield application. Because it is 2-D, solutions can be obtained relatively quickly allowing a comparison and assessment of sensitivity to model parameter changes. Turbulence models are considered as well as the tradeoff between steady state and transient solutions. Solutions are compared for two commercial CFD codes, FLUENT and STAR-CCM+. The results can be used to provide input to the CFD Best Practices for this application. Following study results for the 2-D test problem, a comparison of simulation results is provided for a high Rayleigh number experiment with large annular gap. Because the geometry of this validation is significantly different from the neutron shield, and due to the critical nature of this application, the argument is made for new experiments at representative scales

Zigh, Ghani; Solis, Jorge; Fort, James A.

2011-01-14T23:59:59.000Z

58

A cask maintenance facility feasibility study  

SciTech Connect

The Oak Ridge National Laboratory (ORNL) is developing a transportation system for spent nuclear fuel (SNF) and defense high level waste (HLW) as a part of the Federal Waste Management System (FWMS). In early 1988, a feasibility study was undertaken to design a stand-alone, ''green field'' facility for maintaining the FWMS casks. The feasibility study provided an initial layout facility design, an estimate of the construction cost, and an acquisition schedule for a Cask Maintenance Facility (CMF). The study also helped to define the interfaces between the transportation system and the waste generators, the repository, and a Monitored Retrievable Storage (MRS) facility. The data, design, and estimated costs resulting from the study have been organized for use in the total transportation system decision-making process. Most importantly, the feasibility study also provides a foundation for continuing design and planning efforts. Fleet servicing facility studies, operational studies from current cask system operators, a definition of the CMF system requirements, and the experience of others in the radioactive waste transportation field were used as a basis for the feasibility study. In addition, several cask handling facilities were visited to observe and discuss cask operations to establish the functions and methods of cask maintenance expected to be used in the facility. Finally, a peer review meeting was held at Oak Ridge, Tennessee in August, 1988, in which the assumptions, design, layout, and functions of the CMF were significantly refined. Attendees included representatives from industry, the repository and transportation operations.

Rennich, M.J.; Medley, L.G.; Attaway, C.R.

1989-01-01T23:59:59.000Z

59

On the Criticality Safety of Transuranic Sodium Fast Reactor Fuel Transport Casks  

SciTech Connect

This work addresses the neutronic performance and criticality safety issues of transport casks for fuel pertaining to low conversion ratio sodium cooled fast reactors, conventionally known as Advanced Burner Reactors. The criticality of a one, three, seven and 19-assembly cask capacity is presented. Both dry “helium” and flooded “water” filled casks are considered. No credit for fuel burnup or fission products was assumed. As many as possible of the conservatisms used in licensing light water reactor universal transport casks were incorporated into this SFR cask criticality design and analysis. It was found that at 7-assemblies or more, adding moderator to the SFR cask increases criticality margin. Also, removal of MAs from the fuel increases criticality margin of dry casks and takes a slight amount of margin away for wet casks. Assuming credit for borated fuel tube liners, this design analysis suggests that as many as 19 assemblies can be loaded in a cask if limited purely by criticality safety. If no credit for boron is assumed, the cask could possibly hold seven assemblies if low conversion ratio fast reactor grade fuel and not breeder reactor grade fuel is assumed. The analysis showed that there is a need for new cask designs for fast reactors spent fuel transportation. There is a potential of modifying existing transportation cask design as the starting point for fast reactor spent fuel transportation.

Samuel Bays; Ayodeji Alajo

2010-05-01T23:59:59.000Z

60

Foreign experience on effects of extended dry storage on the integrity of spent nuclear fuel  

SciTech Connect

This report summarizes the results of a survey of foreign experience in dry storage of spent fuel from nuclear power reactors that was carried out for the US Department of Energy's (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The report reviews the mechanisms for degradation of spent fuel cladding and fuel materials in dry storage, identifies the status and plans of world-wide experience and applications, and documents the available information on the expected long-term integrity of the dry-stored spent fuel from actual foreign experience. Countries covered in this survey are: Argentina, Canada, Federal Republic of Germany (before reunification with the former East Germany), former German Democratic Republic (former East Germany), France, India, Italy, Japan, South Korea, Spain, Switzerland, United Kingdom, and the former USSR (most of these former Republics are now in the Commonwealth of Independent States (CIS)). Industrial dry storage of Magnox fuels started in 1972 in the United Kingdom; Canada began industrial dry storage of CANDU fuels in 1980. The technology for safe storage is generally considered to be developed for time periods of 30 to 100 years for LWR fuel in inert gas and for some fuels in oxidizing gases at low temperatures. Because it will probably be decades before countries will have a repository for spent fuels and high-level wastes, the plans for expanded use of dry storage have increased significantly in recent years and are expected to continue to increase in the near future.

Schneider, K.J.; Mitchell, S.J.

1992-04-01T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
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61

Foreign experience on effects of extended dry storage on the integrity of spent nuclear fuel  

SciTech Connect

This report summarizes the results of a survey of foreign experience in dry storage of spent fuel from nuclear power reactors that was carried out for the US Department of Energy`s (DOE) Office of Civilian Radioactive Waste Management (OCRWM). The report reviews the mechanisms for degradation of spent fuel cladding and fuel materials in dry storage, identifies the status and plans of world-wide experience and applications, and documents the available information on the expected long-term integrity of the dry-stored spent fuel from actual foreign experience. Countries covered in this survey are: Argentina, Canada, Federal Republic of Germany (before reunification with the former East Germany), former German Democratic Republic (former East Germany), France, India, Italy, Japan, South Korea, Spain, Switzerland, United Kingdom, and the former USSR (most of these former Republics are now in the Commonwealth of Independent States [CIS]). Industrial dry storage of Magnox fuels started in 1972 in the United Kingdom; Canada began industrial dry storage of CANDU fuels in 1980. The technology for safe storage is generally considered to be developed for time periods of 30 to 100 years for LWR fuel in inert gas and for some fuels in oxidizing gases at low temperatures. Because it will probably be decades before countries will have a repository for spent fuels and high-level wastes, the plans for expanded use of dry storage have increased significantly in recent years and are expected to continue to increase in the near future.

Schneider, K.J.; Mitchell, S.J.

1992-04-01T23:59:59.000Z

62

Engineering and cost analysis of a dry cooling system augmented with a thermal storage pond  

DOE Green Energy (OSTI)

An engineering and cost study of the capacitive thermal storage pond added to a state-of-the-art dry cooling system is described. The purpose of the study was to assess the potential for reducing the cost of all-dry cooling for thermal electric power plants using a dry cooling system that includes a thermal storage pond. Using the modified BNW-I computer code, the effect of varying significant design parameters was investigated. The parametric study included studying the effects of varying turbine type, pond size, replacement energy costing, capacity penalty methodology, pond location with respect to the dry cooling tower, design temperature, and site location (meteorology). Incremental power production costs for dry cooling (i.e., the portion of the cost of bus-bar electricity from the plant which is attributable to the cost of building and operating the heat rejection system) with a thermal storage pond system were determined for meteorologies of both Wyodak, Wyoming and Phoenix, Arizona. For Wyodak the incremental cost of dry cooling with a thermal storage pond was 2.81 mills/kWh as compared to 2.55 mills/kWh for a system without a thermal storage pond. For Phoenix the incremental cost of dry cooling with a thermal storage pond was 3.66 mills/kWh as compared to 4.31 mills/kWh for a system without a thermal storage pond. If the use of a modified conventional turbine with the dry-cooled system is stipulated in order to stay with proven technology for large turbines, then results of this study show that in extremely hot climates the thermal storage pond can reduce the cost of dry cooling. If no cost penalty is assigned to high back pressure turbines and it can be used, then the thermal storage pond has no advantage in hot climates. However, collateral use of the pond for makeup or emergency cooling water storage may decreae the cost. (LCL)

Drost, M.K.; Allemann, R.T.

1978-09-01T23:59:59.000Z

63

Evaluation of cover gas impurities and their effects on the dry storage of LWR (light-water reactor) spent fuel  

DOE Green Energy (OSTI)

The purposes of this report are to (1) identify the sources of impurity gases in spent fuel storage casks; (2) identify the expected concentrations and types of reactive impurity gases from these sources over an operating lifetime of 40 years; and (3) determine whether these impurities could significantly degrade cladding or exposed fuel during this period. Four potential sources of impurity gases in the helium cover gas in operating casks were identified and evaluated. Several different bounding cases have been considered, where the reactive gas inventory is either assumed to be completely gettered by the cladding or where all oxygen is assumed to react completely with the exposed fuel. It is concluded that the reactive gas inventory will have no significant effect on the cladding unless all available oxygen reacts with the UO/sub 2/ fuel to produce U/sub 3/O/sub 8/ at one or two cladding breaches. Based on Zircaloy oxidation data, the oxygen inventory in a fully loaded pressurized water reactor cask such as the Castor-V/21 will be gettered by the Zircaloy cladding in about 1 year if the peak cladding temperature within the task is greater than or equal to300/sup 0/C. Only a negligible decrease in the thickness of the cladding would result. 24 refs., 4 tabs.

Knoll, R.W.; Gilbert, E.R.

1987-11-01T23:59:59.000Z

64

Safeguards-by-Design: Guidance for Independent Spent Fuel Dry Storage Installations (ISFSI)  

SciTech Connect

This document summarizes the requirements and best practices for implementing international nuclear safeguards at independent spent fuel storage installations (ISFSIs), also known as Away-from- Reactor (AFR) storage facilities. These installations may provide wet or dry storage of spent fuel, although the safeguards guidance herein focuses on dry storage facilities. In principle, the safeguards guidance applies to both wet and dry storage. The reason for focusing on dry independent spent fuel storage installations is that this is one of the fastest growing nuclear installations worldwide. Independent spent fuel storage installations are typically outside of the safeguards nuclear material balance area (MBA) of the reactor. They may be located on the reactor site, but are generally considered by the International Atomic Energy Agency (IAEA) and the State Regulator/SSAC to be a separate facility. The need for this guidance is becoming increasingly urgent as more and more nuclear power plants move their spent fuel from resident spent fuel ponds to independent spent fuel storage installations. The safeguards requirements and best practices described herein are also relevant to the design and construction of regional independent spent fuel storage installations that nuclear power plant operators are starting to consider in the absence of a national long-term geological spent fuel repository. The following document has been prepared in support of two of the three foundational pillars for implementing Safeguards-by-Design (SBD). These are: i) defining the relevant safeguards requirements, and ii) defining the best practices for meeting the requirements. This document was prepared with the design of the latest independent dry spent fuel storage installations in mind and was prepared specifically as an aid for designers of commercial nuclear facilities to help them understand the relevant international requirements that follow from a country’s safeguards agreement with the IAEA. If these requirements are understood at the earliest stages of facility design, it will help eliminate the costly retrofit of facilities that has occurred in the past to accommodate nuclear safeguards, and will help the IAEA implement nuclear safeguards worldwide, especially in countries building their first nuclear facilities. It is also hoped that this guidance document will promote discussion between the IAEA, State Regulator/SSAC, Project Design Team, and Facility Owner/Operator at an early stage to ensure that new ISFSIs will be effectively and efficiently safeguarded. This is intended to be a living document, since the international nuclear safeguards requirements may be subject to revision over time. More importantly, the practices by which the requirements are met are continuously modernized by the IAEA and facility operators for greater efficiency and cost effectiveness. As these improvements are made, it is recommended that the subject guidance document be updated and revised accordingly.

Trond Bjornard; Philip C. Durst

2012-05-01T23:59:59.000Z

65

Status of the Virginia Power/DOE Cooperative Cask Testing/Demonstration Program: A video presentation  

SciTech Connect

This paper is documentation of a video presentation and provides a brief summary of the Virginia power/US Department of Energy Cooperative Cask Testing/Demonstration Program. The program consists of two phases. The first phase has been completed and involved the unlicensed performance testing (heat transfer and shielding) of three metal spent fuel storage casks at the federally owned Idaho National Engineering Laboratory. The second phase is ongoing and consists of licensed demonstrations of standard casks from two different vendors and of one or two enhanced capacity casks. 6 refs., 1 tab.

McKinnon, M.A.; Creer, J.M. (Pacific Northwest Lab., Richland, WA (USA)); Collantes, C.E. (Department of Energy, Richland, WA (USA). Richland Operations Office)

1990-01-01T23:59:59.000Z

66

Developing a Regulatory Framework for Extended Storage and Transportation  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Developing a Regulatory Framework Developing a Regulatory Framework for Extended Storage and Transportation National Transportation Stakeholders Forum May 10-12, 2011 Denver, Colorado Earl Easton Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Outline * Current Regulatory Framework * Future Regulatory Needs * Technical Basis (with some examples) * Path Forward 2 Current NRC Regulatory Framework for Storage * Renewable Term Licenses * Aging Management Plan - Time-limited aging analyses - Design for prevention - Monitoring - how, how often, in-situ - Maintenance - what type - Corrective Actions - when 3 Dry Cask Storage * 63 licensed ISFSIs (8 more than 2010) * Expect 10 sites pursuing General License * Over 1400 loaded storage casks 0 10 20 30 40 50 60 70 80 Number of ISFSIs Year Specific Licensees

67

Measurements and Characterization of Neutron and Gamma Dose Quantities in the Vicinity of an Independent Spent Fuel Storage Installation  

SciTech Connect

As part of the decommissioning of the Maine Yankee Atomic Power Company (MYAPCo) nuclear power plant, the spent nuclear fuel is being temporarily stored in a dry cask storage facility on a portion of the original licensed property. Each of the spent nuclear fuel (SNF) storage casks hold approximately 25 spent fuel assemblies. Additional storage casks for the greater-than-Class C waste (GTCC) are also used. This waste is contained in 64 casks (60 SNF, 4 GTCC), each of which contain a substantial amount of concrete for shielding and structural purposes. The vertical concrete casks (VCCs) are typically separated by a distance of 4 and 6 feet. The storage casks are effective personnel radiation shields for most of the gamma and neutron radiation emitted from the fuel. However measurable gamma and neutron radiation levels are present in the vicinity of the casks. In order to establish a controlled area boundary around the facility such that a member of the public annual dose level of 0.25-mSv could be demonstrated, measurements of gamma and neutron dose equivalents were conducted. External gamma exposure rates were measured with a Pressurized Ion Chamber (PIC). Neutron absorbed dose and dose equivalent rates were measured with a Rossi-type tissue equivalent proportional counter (TEPC). Both gamma and neutron measurements were made at increasing distances from the facility as well as at a background location. The results of the measurements show that the distance to the 0.25-mSv per year boundary for 100% occupancy conditions varies from 321 feet to 441 feet from the geometric center of the storage pads, depending on the direction from the pad. For the TEPC neutron measurements, the average quality factor from the facilities was approximately 7.4. This quality factor compares well with the average quality factor of 7.6 that was measured during a calibration performed with a bare Cf-252 source. (authors)

Darois, E.L.; Keefer, D.G.; Plazeski, P.E. [Radiation Safety and Control Services, 91 Portsmouth Avenue, Stratham, NH 03885 (United States); Connell, J. [Maine Yankee Atomic Power Company, Wiscasset, ME 04568 (United States)

2006-07-01T23:59:59.000Z

68

Use of filler materials to aid spent nuclear fuel dry storage  

Science Conference Proceedings (OSTI)

The use of filler materials (also known as stabilizer or encapsulating materials) was investigated in conjunction with the dry storage of irradiated light water reactor (LWR) fuel. The results of this investigation appear to be equally valid for the wet storage of fuel. The need for encapsulation and suitable techniques for closing was also investigated. Various materials were reviewed (including solids, liquids, and gases) which were assumed to fill the void areas within a storage can containing either intact or disassembled spent fuel. Materials were reviewed and compared on the basis of cost, thermal characteristics, and overall suitability in the proposed environment. A thermal analysis was conducted to yield maximum centerline and surface temperatures of a design basis fuel encapsulated within various filler materials. In general, air was found to be the most likely choice as a filler material for the dry storage of spent fuel. The choice of any other filler material would probably be based on a desire, or need, to maximize specific selection criteria, such as surface temperatures, criticality safety, or confinement.

Anderson, K.J.

1981-09-01T23:59:59.000Z

69

Concrete Shield Performance of the VSC-17 Spent Nuclear Fuel Cask  

Science Conference Proceedings (OSTI)

The VSC-17 Spent Nuclear Fuel Storage Cask was surveyed for degradation of the concrete shield by radiation measurement, temperature measurement, and ultrasonic testing. No general loss of shielding function was identified.

Koji Shirai

2006-04-01T23:59:59.000Z

70

Cost Estimate for an Away-From-Reactor Generic Interim Storage Facility (GISF) for Spent Nuclear Fuel  

Science Conference Proceedings (OSTI)

As nuclear power plants began to run out of storage capacity in spent nuclear fuel (SNF) storage pools, many nuclear operating companies added higher density pool storage racks to increase pool capacity. Most nuclear power plant storage pools have been re-racked one or more times. As many spent fuel storage pools were re-racked to the maximum extent possible, nuclear operating companies began to employ interim dry storage technologies to store SNF in certified casks and canister-based systems outside of ...

2009-05-20T23:59:59.000Z

71

Re-evaluation of monitored retrievable storage concepts  

SciTech Connect

In 1983, as a prelude to the monitored retrievable storage (MRS) facility conceptual design, the Pacific Northwest Laboratory (PNL) conducted an evaluation for the US Department of Energy (DOE) that examined alternative concepts for storing spent LWR fuel and high- level wastes from fuel reprocessing. The evaluation was made considering nine concepts for dry away-from-reactor storage. The nine concepts evaluated were: concrete storage cask, tunnel drywell, concrete cask-in-trench, open-cycle vault, metal casks (transportable and stationary), closed-cycle vault, field drywell, and tunnel-rack vault. The purpose and scope of the re-evaluation did not require a repetition of the expert-based examinations used earlier. Instead, it was based on more detailed technical review by a small group, focusing on changes that had occurred since the initial evaluation was made. Two additional storage concepts--the water pool and the horizontal modular storage vault (NUHOMS system)--were ranked along with the original nine. The original nine concepts and the added two conceptual designs were modified as appropriate for a scenario with storage capacity for 15,000 MTU of spent fuel. Costs, area requirements, and technical and historical data pertaining to MRS storage were updated for each concept.

Fletcher, J.F.; Smith, R.I.

1989-04-01T23:59:59.000Z

72

Spent Nuclear Fuel Dry Transfer System Cold Demonstration Project Final Report  

SciTech Connect

The spent nuclear fuel dry transfer system (DTS) provides an interface between large and small casks and between storage-only and transportation casks. It permits decommissioning of reactor pools after shutdown and allows the use of large storage-only casks for temporary onsite storage of spent nuclear fuel irrespective of reactor or fuel handling limitations at a reactor site. A cold demonstration of the DTS prototype was initiated in August 1996 at the Idaho National Engineering and Environmental Laboratory (INEEL). The major components demonstrated included the fuel assembly handling subsystem, the shield plug/lid handling subsystem, the cask interface subsystem, the demonstration control subsystem, a support frame, and a closed circuit television and lighting system. The demonstration included a complete series of DTS operations from source cask receipt and opening through fuel transfer and closure of the receiving cask. The demonstration included both normal operations and recovery from off-normal events. It was designed to challenge the system to determine whether there were any activities that could be made to jeopardize the activities of another function or its safety. All known interlocks were challenged. The equipment ran smoothly and functioned as designed. A few "bugs" were corrected. Prior to completion of the demonstration testing, a number of DTS prototype systems were modified to apply lessons learned to date. Additional testing was performed to validate the modifications. In general, all the equipment worked exceptionally well. The demonstration also helped confirm cost estimates that had been made at several points in the development of the system.

Christensen, Max R; McKinnon, M. A.

1999-12-01T23:59:59.000Z

73

Predictions of dry storage behavior of zircaloy clad spent fuel rods using deformation and fracture map analyses  

Science Conference Proceedings (OSTI)

Predictions of the maximum initial allowable temperature required to achieve a 40-year life in dry storage are made for Zircaloy clad spent fuel. Maximum initial dry storage temperatures of 420/sup 0/C for 1 year fuel cladding subjected to a constant stress of 70 MPa are predicted. The technique utilized in this work is based on the deformation and fracture map methodology. Maps are presented for temperatures between 50 and 850/sup 0/C stresses between 5 and 500 MPa. These maps are combined with a life fraction rule to predict the time to rupture of Zircaloy clad spent Light Water Reactor (LWR) fuel subjected to various storage conditions.

Tarn, J.C.L.; Madsen, N.H.; Chin, B.A.

1986-03-01T23:59:59.000Z

74

Business Case Slide 14: High-Volume: Casks - DUCRETE (cont)  

NLE Websites -- All DOE Office Websites (Extended Search)

DUCRETE (cont.) Previous Slide Next Slide Table of Contents High-Volume: Casks - DUCRETE(tm) (cont.) DUCRETE Casks are Considerably Smaller and Lighter than Casks Constructed of...

75

Business Case Slide 12: High-Volume: Casks - Description  

NLE Websites -- All DOE Office Websites (Extended Search)

Casks - Description Previous Slide Next Slide Table of Contents High-Volume: Casks - Description Description Use DUO2 to enhance the shielding efficiency in spent fuel casks for...

76

Energy Department Announces New Investment in Nuclear Fuel Storage Research  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Announces New Investment in Nuclear Fuel Storage Announces New Investment in Nuclear Fuel Storage Research Energy Department Announces New Investment in Nuclear Fuel Storage Research April 16, 2013 - 12:19pm Addthis NEWS MEDIA CONTACT (202) 586-4940 WASHINGTON - As part of its commitment to developing an effective strategy for the safe and secure storage and management of used nuclear fuel, the Energy Department today announced a new dry storage research and development project led by the Electric Power Research Institute (EPRI). The project will design and demonstrate dry storage cask technology for high burn-up spent nuclear fuels that have been removed from commercial nuclear power plants. "The Energy Department is committed to advancing clean, reliable and safe nuclear power - which provides the largest source of low-carbon

77

Energy Department Announces New Investment in Nuclear Fuel Storage Research  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Investment in Nuclear Fuel Storage Investment in Nuclear Fuel Storage Research Energy Department Announces New Investment in Nuclear Fuel Storage Research April 16, 2013 - 12:19pm Addthis NEWS MEDIA CONTACT (202) 586-4940 WASHINGTON - As part of its commitment to developing an effective strategy for the safe and secure storage and management of used nuclear fuel, the Energy Department today announced a new dry storage research and development project led by the Electric Power Research Institute (EPRI). The project will design and demonstrate dry storage cask technology for high burn-up spent nuclear fuels that have been removed from commercial nuclear power plants. "The Energy Department is committed to advancing clean, reliable and safe nuclear power - which provides the largest source of low-carbon

78

CARRIER/CASK HANDLING SYSTEM DESCRIPTION DOCUMENT  

Science Conference Proceedings (OSTI)

The Carrier/Cask Handling System receives casks on railcars and legal-weight trucks (LWTs) (transporters) that transport loaded casks and empty overpacks to the Monitored Geologic Repository (MGR) from the Carrier/Cask Transport System. Casks that come to the MGR on heavy-haul trucks (HHTs) are transferred onto railcars before being brought into the Carrier/Cask Handling System. The system is the interfacing system between the railcars and LWTs and the Assembly Transfer System (ATS) and Canister Transfer System (CTS). The Carrier/Cask Handling System removes loaded casks from the cask transporters and transfers the casks to a transfer cart for either the ATS or CTS, as appropriate, based on cask contents. The Carrier/Cask Handling System receives the returned empty casks from the ATS and CTS and mounts the casks back onto the transporters for reshipment. If necessary, the Carrier/Cask Handling System can also mount loaded casks back onto the transporters and remove empty casks from the transporters. The Carrier/Cask Handling System receives overpacks from the ATS loaded with canisters that have been cut open and emptied and mounts the overpacks back onto the transporters for disposal. If necessary, the Carrier/Cask Handling System can also mount empty overpacks back onto the transporters and remove loaded overpacks from them. The Carrier/Cask Handling System is located within the Carrier Bay of the Waste Handling Building System. The system consists of cranes, hoists, manipulators, and supporting equipment. The Carrier/Cask Handling System is designed with the tooling and fixtures necessary for handling a variety of casks. The Carrier/Cask Handling System performance and reliability are sufficient to support the shipping and emplacement schedules for the MGR. The Carrier/Cask Handling System interfaces with the Carrier/Cask Transport System, ATS, and CTS as noted above. The Carrier/Cask Handling System interfaces with the Waste Handling Building System for building structures and space allocations. The Carrier/Cask Handling System interfaces with the Waste Handling Building Electrical System for electrical power.

E.F. Loros

2000-06-23T23:59:59.000Z

79

FUEL CASK IMPACT LIMITER VULNERABILITIES  

Science Conference Proceedings (OSTI)

Cylindrical fuel casks often have impact limiters surrounding just the ends of the cask shaft in a typical 'dumbbell' arrangement. The primary purpose of these impact limiters is to absorb energy to reduce loads on the cask structure during impacts associated with a severe accident. Impact limiters are also credited in many packages with protecting closure seals and maintaining lower peak temperatures during fire events. For this credit to be taken in safety analyses, the impact limiter attachment system must be shown to retain the impact limiter following Normal Conditions of Transport (NCT) and Hypothetical Accident Conditions (HAC) impacts. Large casks are often certified by analysis only because of the costs associated with testing. Therefore, some cask impact limiter attachment systems have not been tested in real impacts. A recent structural analysis of the T-3 Spent Fuel Containment Cask found problems with the design of the impact limiter attachment system. Assumptions in the original Safety Analysis for Packaging (SARP) concerning the loading in the attachment bolts were found to be inaccurate in certain drop orientations. This paper documents the lessons learned and their applicability to impact limiter attachment system designs.

Leduc, D; Jeffery England, J; Roy Rothermel, R

2009-02-09T23:59:59.000Z

80

CONTAINMENT EVALUATION OF BREACHED AL-SNF FOR CASK TRANSPORT  

Science Conference Proceedings (OSTI)

Aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors (FRR/DRR) is being shipped to the Savannah River Site. To enter the U.S., the cask with loaded fuel must be certified to comply with the requirements in the Title 10 of the U.S. Code of Federal Regulations, Part 71. The requirements include demonstration of containment of the cask with its contents under normal and accident conditions. Al-SNF is subject to corrosion degradation in water storage, and many of the fuel assemblies are ''failed'' or have through-clad damage. A methodology has been developed with technical bases to show that Al-SNF with cladding breaches can be directly transported in standard casks and maintained within the allowable release rates. The approach to evaluate the limiting allowable leakage rate, L{sub R}, for a cask with breached Al-SNF for comparison to its test leakage rate could be extended to other nuclear material systems. The approach for containment analysis of Al-SNF follows calculations for commercial spent fuel as provided in NUREG/CR-6487 that adopts ANSI N14.5 as a methodology for containment analysis. The material-specific features and characteristics of damaged Al-SNF (fuel materials, fabrication techniques, microstructure, radionuclide inventory, and vapor corrosion rates) that were derived from literature sources and/or developed in laboratory testing are applied to generate the four containment source terms that yield four separate cask cavity activity densities; namely, those from fines; gaseous fission product species; volatile fission product species; and fuel assembly crud. The activity values, A{sub 2}, are developed per the guidance of 10CFR71. The analysis is performed parametrically to evaluate maximum number of breached assemblies and exposed fuel area for a proposed shipment in a cask with a test leakage rate.

Vinson, D. W.; Sindelar, R. L.; Iyer, N. C.

2005-11-07T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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81

Documentation for initial testing and inspections of Beneficial Uses Shipping System (BUSS) Cask  

SciTech Connect

The purpose of this report is to compile data generated during the initial tests and inspections of the Beneficial Uses Shipping System (BUSS) Cask. In addition, this report will verify that the testing criteria identified in section 8.1 of the BUSS Cask Safety Analysis Report for Packaging (SARP) was met. The BUSS Cask Model R-1 is a type B shipping container used for shipment of radioactive cesium-137 and strontium-90 capsules to Waste Encapsulation and Storage Facility (WESF). The BUSS Cask body and lid are each one-piece forgings fabricated from ASTM A473, Type 304 stainless steel. The primary purpose of the BUSS Cask is to provide shielding and confinement as well as impact, puncture, and thermal protection for the capsules under both normal and accident conditions. Chapter 8 of the BUSS Cask SARP requires several acceptance tests and inspections, each intended to evaluate the performance of different components of the BUSS Cask system, to be performed before its first use. The results of the tests and inspections required are included in this document.

Lundeen, J.E.

1994-08-25T23:59:59.000Z

82

THERMAL MODELING ANALYSIS OF SRS 70 TON CASK  

SciTech Connect

The primary objective of this work was to perform the thermal calculations to evaluate the Material Test Reactor (MTR) fuel assembly temperatures inside the SRS 70-Ton Cask loaded with various bundle powers. MTR fuel consists of HFBR, MURR, MIT, and NIST. The MURR fuel was used to develop a bounding case since it is the fuel with the highest heat load. The results will be provided for technical input for the SRS 70 Ton Cask Onsite Safety Assessment. The calculation results show that for the SRS 70 ton dry cask with 2750 watts total heat source with a maximum bundle heat of 670 watts and 9 bundles of MURR bounding fuel, the highest fuel assembly temperatures are below about 263 C. Maximum top surface temperature of the plastic cover is about 112 C, much lower than its melting temperature 260 C. For 12 bundles of MURR bounding fuel with 2750 watts total heat and a maximum fuel bundle of 482 watts, the highest fuel assembly temperatures are bounded by the 9 bundle case. The component temperatures of the cask were calculated by a three-dimensional computational fluid dynamics approach. The modeling calculations were performed by considering daily-averaged solar heat flux.

Lee, S.; Jordan, J.; Hensel, S.

2011-03-08T23:59:59.000Z

83

Assessment of the Fingerprinting Method for Spent Fuel Verification in MACSTOR KN-400 CANDU Dry Storage  

E-Print Network (OSTI)

The Korea Hydro and Nuclear Power has built a new modular type of dry storage facility, known as MACSTOR KN-400 at Wolsong reactor site. The building has the capacity to store up to 24000 CANDU spent fuel bundles in a 4 rows by 10 columns arrangement of silos. The MACSTOR KN-400 consists of 40 silos; each silo has 10 storage baskets, each of which can store 60 CANDU spent fuel bundles. The development of an effective method for spent fuel verification at the MACSTOR KN-400 storage facility is necessary in order for the International Atomic Energy Agency (IAEA) to meet with safeguards regulations. The IAEA is interested in having a new effective method of re-verification of the nuclear material in the MACSTOR KN-400 dry storage facility in the event of any loss of continuity of knowledge, which occasionally happens when the installed seals fail. In the thesis work, MCNP models of central and corner structures of the MACSTOR KN-400 facility are developed, since both have different types of re-verification system. Both gamma and neutron simulations were carried out using the MCNP models developed for MACSTOR KN-400. The CANDU spent fuel bundle with discharge burnup of 7.5 GWD/t (burned at specific power of 28.39 MW/t) and 10 years cooled was considered for radiation source term estimation. For both the structures, MCNP simulations of gamma transport were done by including Cadmium-Zinc-Telluride (CZT) detector inside the re-verification tube. Gamma analyses for different spent fuel bundle diversion scenarios were carried out. It was observed that for diversion scenarios wherein the bundles are removed from the inner portions of the basket (opposite side of the collimator of the re-verification tube), it was difficult to conclude whether diversion has taken place based on the change in gamma radiation signals. Similar MCNP simulations of neutron transport were carried out by integrating helium-3 detector inside the re-verification tube and the results obtained for various diversion scenarios were encouraging and can be used to detect some spent fuel diversion cases. In the central structure, it was observed that addition of moderating material between the spent fuel and the detector increased the sensitivity of the detecting system for various diversion cases for neutron simulations. In the worst scenario, the diverting state could divert 14 spent fuel bundles from each of 10 baskets in a silo from the basket region opposite to the collimator of the re-verification tube. The non-detection probability for this scenario is close to 1. This diversion cannot be easily detected using the currently designed detection system. In order to increase the detection probability, either the design of the facility must be changed or other safeguard methods, such as containment and surveillance methods must be used for safeguarding the nuclear material at the facility.

Gowthahalli Chandregowda, Nandan

2012-08-01T23:59:59.000Z

84

Spent nuclear fuel shipping cask handling capabilities of commercial light water reactors  

Science Conference Proceedings (OSTI)

This report describes an evaluation of the cask handling capabilities of those reactors which are operating or under construction. A computerized data base that includes cask handling information was developed with information from the literature and utility-supplied data. The capability of each plant to receive and handle existing spent fuel shipping casks was then evaluated. Modal fractions were then calculated based on the results of these evaluations and the quantities of spent fuel projected to be generated by commercial nuclear power plants through 1998. The results indicated that all plants are capable of receiving and handling truck casks. Up to 118 out of 130 reactors (91%) could potentially handle the larger and heavier rail casks if the maximum capability of each facility is utilized. Design and analysis efforts and physical modifications to some plants would be needed to achieve this high rail percentage. These modifications would be needed to satisfy regulatory requirements, increase lifting capabilities, develop rail access, or improve other deficiencies. The remaining 12 reactors were determined to be capable of handling only the smaller truck casks. The percentage of plants that could receive and handle rail casks in the near-term would be reduced to 64%. The primary reason for a plant to be judged incapable of handling rail casks in the near-term was a lack of rail access. The remaining 36% of the plants would be limited to truck shipments. The modal fraction calculations indicated that up to 93% of the spent fuel accumulated by 1998 could be received at federal storage or disposal facilities via rail (based on each plant's maximum capabilities). If the near-term cask handling capabilities are considered, the rail percentage is reduced to 62%.

Daling, P.M.; Konzek, G.J.; Lezberg, A.J.; Votaw, E.F.; Collingham, M.I.

1985-04-01T23:59:59.000Z

85

Impacts Associated with Transfer of Spent Nuclear Fuel from Spent Fuel Storage Pools to Dry Storage After Five Years of Cooling, Revision 1  

Science Conference Proceedings (OSTI)

In 2010, EPRI performed a study of the accelerated transfer of spent fuel from pools to dry storage in response to the threat of terrorist activities at nuclear power plants (report 1021049). Following the March 2011 Great East Japan Earthquake and the subsequent accident at the Fukushima Daiichi nuclear power plant, some organizations issued a renewed call for accelerated transfer of used fuel from spent fuel ...

2012-08-31T23:59:59.000Z

86

Fire resistant nuclear fuel cask  

DOE Patents (OSTI)

The disclosure is directed to a fire resistant nuclear fuel cask employing reversibly thermally expansible bands between adjacent cooling fins such that normal outward flow of heat is not interfered with, but abnormal inward flow of heat is impeded or blocked.

Heckman, Richard C. (Albuquerque, NM); Moss, Marvin (Albuquerque, NM)

1979-01-01T23:59:59.000Z

87

Method for the production of electrodes for lead--acid storage batteries. [drying by inert gas at high temperature  

SciTech Connect

A method for the production of lead--acid storage batteries having a grid of lead alloy filled with active materials consisting of lead oxides, lead powder, sulfuric acid, and water is described. The electrodes are subjected to a jet of an inert gas at a high temperature and velocity for several seconds to dry the surface of the electrodes while leaving the interior thereof moist.

Nikolaou, P.

1978-08-29T23:59:59.000Z

88

Cask system design guidance for robotic handling  

SciTech Connect

Remote automated cask handling has the potential to reduce both the occupational exposure and the time required to process a nuclear waste transport cask at a handling facility. The ongoing Advanced Handling Technologies Project (AHTP) at Sandia National Laboratories is described. AHTP was initiated to explore the use of advanced robotic systems to perform cask handling operations at handling facilities for radioactive waste, and to provide guidance to cask designers regarding the impact of robotic handling on cask design. The proof-of-concept robotic systems developed in AHTP are intended to extrapolate from currently available commercial systems to the systems that will be available by the time that a repository would be open for operation. The project investigates those cask handling operations that would be performed at a nuclear waste repository facility during cask receiving and handling. The ongoing AHTP indicates that design guidance, rather than design specification, is appropriate, since the requirements for robotic handling do not place severe restrictions on cask design but rather focus on attention to detail and design for limited dexterity. The cask system design features that facilitate robotic handling operations are discussed, and results obtained from AHTP design and operation experience are summarized. The application of these design considerations is illustrated by discussion of the robot systems and their operation on cask feature mock-ups used in the AHTP project. 11 refs., 11 figs.

Griesmeyer, J.M.; Drotning, W.D.; Morimoto, A.K.; Bennett, P.C.

1990-10-01T23:59:59.000Z

89

COMPILATION OF DISPOSABLE SOLID WASTE CASK EVALUATIONS  

SciTech Connect

The Disposable Solid Waste Cask (DSWC) is a shielded cask capable of transporting, storing, and disposing of six non-fuel core components or approximately 27 cubic feet of radioactive solid waste. Five existing DSWCs are candidates for use in storing and disposing of non-fuel core components and radioactive solid waste from the Interim Examination and Maintenance Cell, ultimately shipping them to the 200 West Area disposal site for burial. A series of inspections, studies, analyses, and modifications were performed to ensure that these casks can be used to safely ship solid waste. These inspections, studies, analyses, and modifications are summarized and attached in this report. Visual inspection of the casks interiors provided information with respect to condition of the casks inner liners. Because water was allowed to enter the casks for varying lengths of time, condition of the cask liner pipe to bottom plate weld was of concern. Based on the visual inspection and a corrosion study, it was concluded that four of the five casks can be used from a corrosion standpoint. Only DSWC S/N-004 would need additional inspection and analysis to determine its usefulness. The five remaining DSWCs underwent some modification to prepare them for use. The existing cask lifting inserts were found to be corroded and deemed unusable. New lifting anchor bolts were installed to replace the existing anchors. Alternate lift lugs were fabricated for use with the new lifting anchor bolts. The cask tiedown frame was modified to facilitate adjustment of the cask tiedowns. As a result of the above mentioned inspections, studies, analysis, and modifications, four of the five existing casks can be used to store and transport waste from the Interim Examination and Maintenance Cell to the disposal site for burial. The fifth cask, DSWC S/N-004, would require further inspections before it could be used.

THIELGES, J.R.; CHASTAIN, S.A.

2007-06-21T23:59:59.000Z

90

Business Case Slide 19: High-Volume: Casks - Program Focus  

NLE Websites -- All DOE Office Websites (Extended Search)

Volume: Casks - Program Focus Previous Slide Next Slide Table of Contents High-Volume: Casks - Program Focus ORNL furnace for cermet development ORNL furnace for cermet development...

91

Heat Transfer Correlation for Finned Casks  

SciTech Connect

Design of finned casks for dissipation of heat from radioactive decay usually requires reliance on generalized correlations in the literature which do not necessarily apply to the specific cask design. A correlation was developed, based on temperature profile measurements, for the design of upright cylindrical casks with vertical fins for convective and radiant heat transfer to ambient air. Temperature data at various heat loads were obtained for two different cask sizes of the same basic design. Each cask is mounted on a steel pallet and contained within a steel mesh cage. The smaller cask, which has 23 fins, has been approved (DOT-SP-6321) for shipment of up to 1400 W (th), and approval is being obtained (AEC AL USA/9503 BLF) for shipment of up to 3500 W heat load in the larger, 60-fin cask. The applicable theoretical equations were fit to the temperature data for both casks by simply adjusting the value used for the number of fins. The resulting correlation provides a reliable method for interpolation and extrapolation and for design of similar finned casks.

Griffin, J. F.

1974-04-01T23:59:59.000Z

92

Control of degradation of spent LWR (light-water reactor) fuel during dry storage in an inert atmosphere  

DOE Green Energy (OSTI)

Dry storage of Zircaloy-clad spent fuel in inert gas (referred to as inerted dry storage or IDS) is being developed as an alternative to water pool storage of spent fuel. The objectives of the activities described in this report are to identify potential Zircaloy degradation mechanisms and evaluate their applicability to cladding breach during IDS, develop models of the dominant Zircaloy degradation mechanisms, and recommend cladding temperature limits during IDS to control Zircaloy degradation. The principal potential Zircaloy cladding breach mechanisms during IDS have been identified as creep rupture, stress corrosion cracking (SCC), and delayed hydride cracking (DHC). Creep rupture is concluded to be the primary cladding breach mechanism during IDS. Deformation and fracture maps based on creep rupture were developed for Zircaloy. These maps were then used as the basis for developing spent fuel cladding temperature limits that would prevent cladding breach during a 40-year IDS period. The probability of cladding breach for spent fuel stored at the temperature limit is less than 0.5% per spent fuel rod. 52 refs., 7 figs., 1 tab.

Cunningham, M.E.; Simonen, E.P.; Allemann, R.T.; Levy, I.S.; Hazelton, R.F.

1987-10-01T23:59:59.000Z

93

Cask system maintenance in the Federal Waste Management System  

SciTech Connect

In early 1988, in support of the development of the transportation system for the Office of Civilian Radioactive Waste Management System (OCRWM), a feasibility study was undertaken to define a the concept for a stand-alone, green-field'' facility for maintaining the Federal Waste Management System (FWMS) casks. This study provided and initial layout facility design, an estimate of the construction costs, and an acquisition schedule for a Cask Maintenance Facility (CMF). It also helped to define the interfaces between the transportation system and the waste generators, the repository, and a Monitored Retrievable Storage (MRS) facility. The data, design, and estimated costs derived from the study have been organized for use in the total transportation system decision-making process. Most importantly, they also provide a foundation for continuing design and planning efforts. The feasibility study was based on an assumed stand-alone, green-field'' configuration. This design approach provides a comprehensive design evaluation, to guide the development of a cost estimate and to permit flexibility in locating the facility. The following sections provide background information on cask system maintenance, briefly summarizes some of the functional requirements that a CMF must satisfy, provides a physical description of the CMF, briefly discusses the cost and schedule estimates and then reviews the findings of the efforts undertaken since the feasibility study was completed. 15 refs., 3 figs.

Pope, R.B.; Rennich, M.J.; Medley, L.G.; Attaway, C.R.

1991-01-01T23:59:59.000Z

94

Numerical analysis of temperature and flow effects in a dry, one-dimensional aquifer used for compressed air energy storage  

DOE Green Energy (OSTI)

A detailed description of the method of analysis and the results obtained for an investigation of the hydrodynamic and thermodynamic response of a model of a dry porous media reservoir used for compressed air energy storage (CAES) is presented. Results were obtained from a one-dimensional simulation of the cycling of heated air to and from a radial flow field surrounding a single well in a porous rock. It was assumed that the performance of the bulk of the reservoir could be characterized by the performance of a single well.

Smith, G.C.; Wiles, L.E.; Loscutoff, W.V.

1979-02-01T23:59:59.000Z

95

Report to Congress on Plan for Interim Storage of Spent Nuclear Fuel from Decommissioned Reactors  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

6 6 Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel from Decommissioned Nuclear Power Reactor Sites December 2008 U.S. Department of Energy Office of Civilian Radioactive Waste Management Washington, D.C. Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel The picture on the cover is the Connecticut Yankee Independent Spent Fuel Storage Installation site in Haddam, Connecticut, with 43 dry storage NRC-licensed dual-purpose (storage and transport) casks. ii Report to Congress on the Demonstration of the Interim Storage of Spent Nuclear Fuel EXECUTIVE SUMMARY The House Appropriations Committee Print that accompanied the Consolidated Appropriations Act, 2008, requests that the U.S. Department of Energy (the Department):

96

Guidelines for Fabrication, Examination, Testing and Oversight of Spent Nuclear Fuel Dry Storage Systems  

Science Conference Proceedings (OSTI)

The Nuclear Waste Policy Act (NWPA) of 1982 and subsequent amendments require the U. S. Department of Energy (DOE) to receive and be responsible for disposal of spent commercial nuclear power plant fuel from U.S. utilities. However, because of delays in the siting of a permanent federal repository, and with no federal interim storage facilities designated, U.S. utilities have been forced to provide additional spent nuclear fuel (SNF) storage capability to accommodate spent fuel discharge requirements. At...

1999-12-10T23:59:59.000Z

97

Radiological consequences of a hypothetical disruption of a maximally loaded FFTF fuel cask  

Science Conference Proceedings (OSTI)

Radiological consequences at the site boundary were estimated for non-mechanistic disruption of an Interim Storage Cask (ISC) loaded with 7 assemblies at the maximum available burnup. The hypothetical disruption consisted of a crushing/shearing of the Core Component Container (CCC) along with all 7 assemblies and the creation of a large escape path out of the cask. The resulting site boundary dose of 1.6 mSv is far below the 250 mSv risk guidelines for highly unlikely events.

Scott, P.A.

1995-09-22T23:59:59.000Z

98

Capability of environmental sampling to detect undeclared cask openings  

Science Conference Proceedings (OSTI)

The goal of this study is to determine the signatures that would allow monitors to detect diversion of nuclear fuel (by a diverter) from a storage area such as a geological repository. Due to the complexity of operations surrounding disposal of spent nuclear fuel in a geologic repository, there are several places that a diversion of fuel could take place. After the canister that contains the fuel rods is breached, the diverter would require a hot cell to process or repackage the fuel. A reference repository and possible diversion scenarios are discussed. When a canister is breached, or during reprocessing to extract nuclear weapons material (primarily Pu), several important isotopes or signatures including tritium, {sup 85}Kr, and {sup 129}I are released to the surrounding environment and have the potential for analysis. Estimates of release concentrations of the key signatures from the repository under a hypothetical diversion scenario are presented and discussed. Gas analysis data collected from above-ground storage casks at Idaho National Engineering and Environmental Laboratory (INEEL) Test Area North (TAN) are included and discussed in the report. In addition, LANL participated in gas sampling of one TAN cask, the Castor V/21, in July 1997. Results of xenon analysis from the cask gas sample are presented and discussed. The importance of global fallout and recent commercial reprocessing activities and their effects on repository monitoring are discussed. Monitoring and instrumental equipment for analysis of the key signature isotopes are discussed along with limits of detection. A key factor in determining if diversion activities are in progress at a repository is the timeliness of detection and analysis of the signatures. Once a clandestine operation is suspected, analytical data should be collected as quickly as possible to support any evidence of diversion.

Beckstead, L.W.; Efurd, D.W.; Hemberger, P.H.; Abhold, M.E.; Eccleston, G.W.

1997-12-01T23:59:59.000Z

99

Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Storage Storage DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Storage A discussion of depleted UF6 cylinder storage activities and associated risks. Management Activities for Cylinders in Storage The long-term management of the existing DUF6 storage cylinders and the continual effort to remediate and maintain the safe condition of the DUF6 storage cylinders will remain a Departmental responsibility for many years into the future. The day to day management of the DUF6 cylinders includes actions designed to cost effectively maintain and improve their storage conditions, such as: General storage cylinder and storage yard maintenance; Performing regular inspections of cylinders; Restacking and respacing the cylinders to improve drainage and to

100

Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Environmental Risks » Storage Environmental Risks » Storage Depleted UF6 Environmental Risks line line Storage Conversion Manufacturing Disposal Environmental Risks of Depleted UF6 Storage Discussion of the potential environmental impacts from storage of depleted UF6 at the three current storage sites, as well as potential impacts from the storage of depleted uranium after conversion to an oxide form. Impacts Analyzed in the PEIS The PEIS included an analysis of the potential environmental impacts from continuing to store depleted UF6 cylinders at the three current storage sites, as well as potential impacts from the storage of depleted uranium after conversion to an oxide form. Impacts from Continued Storage of UF6 Cylinders Continued storage of the UF6 cylinders would require extending the use of a

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


101

Record of Decision for a Dry Storage Container System for the Management of Navel Spent Nuclear Fuel, January 7, 1997  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

5 5 Federal Register / Vol. 62, No. 5 / Wednesday, January 8, 1997 / Notices Department of the Navy Record of Decision for a Dry Storage Container System for the Management of Naval Spent Nuclear Fuel SUMMARY: Pursuant to section 102(2) of the National Environmental Policy Act (NEPA) of 1969; the Council on Environmental Quality regulations implementing NEPA procedures, 40 CFR Parts 1500-1508; and Chief of Naval Operations Environmental and Natural Resources Program Manual, OPNAV Instruction 5090.1B; the Department of the Navy announces its decision to implement the preferred alternative (dual-purpose canisters) identified in the final Environmental Impact Statement for a Container System for the Management of Naval Spent Nuclear Fuel (EIS) dated November 1996. The Department of

102

DATING: A computer code for determining allowable temperatures for dry storage of spent fuel in inert and nitrogen gases  

Science Conference Proceedings (OSTI)

The DATING (Determining Allowable Temperatures in Inert and Nitrogen Gases) code can be used to calculate allowable initial temperatures for dry storage of light-water-reactor spent fuel. The calculations are based on the life fraction rule using both measured data and mechanistic equations as reported by Chin et al. (1986). The code is written in FORTRAN and utilizes an efficient numerical integration method for rapid calculations on IBM-compatible personal computers. This report documents the technical basis for the DATING calculations, describes the computational method and code statements, and includes a user's guide with examples. The software for the DATING code is available through the National Energy Software Center operated by Argonne National Laboratory, Argonne, Illinois 60439. 5 refs., 8 figs., 5 tabs.

Simonen, E.P.; Gilbert, E.R.

1988-12-01T23:59:59.000Z

103

Radioactive materials shipping cask anticontamination enclosure  

DOE Patents (OSTI)

An anticontamination device for use in storing shipping casks for radioactive materials comprising (1) a seal plate assembly; (2) a double-layer plastic bag; and (3) a water management system or means for water management.

Belmonte, Mark S. (Irwin, PA); Davis, James H. (Pittsburgh, PA); Williams, David A. (Pittsburgh, PA)

1982-01-01T23:59:59.000Z

104

Information handbook on independent spent fuel storage installations  

Science Conference Proceedings (OSTI)

In this information handbook, the staff of the U.S. Nuclear Regulatory Commission describes (1) background information regarding the licensing and history of independent spent fuel storage installations (ISFSIs), (2) a discussion of the licensing process, (3) a description of all currently approved or certified models of dry cask storage systems (DCSSs), and (4) a description of sites currently storing spent fuel in an ISFSI. Storage of spent fuel at ISFSIs must be in accordance with the provisions of 10 CFR Part 72. The staff has provided this handbook for information purposes only. The accuracy of any information herein is not guaranteed. For verification or for more details, the reader should refer to the respective docket files for each DCSS and ISFSI site. The information in this handbook is current as of September 1, 1996.

Raddatz, M.G.; Waters, M.D.

1996-12-01T23:59:59.000Z

105

Combined thermal storage pond and dry cooling tower waste heat rejection system for solar-thermal steam-electric power plants. Final report  

DOE Green Energy (OSTI)

The thermal performance and economics of the combined thermal storage pond and dry cooling tower waste heat rejection system concept for solar-thermal steam-electric plants have been evaluated. Based on the computer simulation of the operation of southwest-sited solar-thermal plants, it has been determined that the combined pond-tower concept has significant cost and performance advantages over conventional dry cooling systems. Use of a thermal storage pond as a component of the dry cooling system allows a significant reduction in the required dry cooling heat exchange capacity and the associated parasitic power consumption. Importantly, it has been concluded that the combined pond-tower dry cooling system concept can be employed to economically maintain steam condensing temperatures at levels normally achieved with conventional evaporative cooling systems. An evaluation of alternative thermal storage pond design concepts has revealed that a stratified vertical-flow cut-and-fill reservoir with conventional membrane lining and covering would yield the best overall system performance at the least cost.

Guyer, E.C.; Bourne, J.G.; Brownell, D.L.; Rose, R.M.

1979-02-28T23:59:59.000Z

106

Evaluation of concepts for monitored retrievable storage of spent nuclear fuel and high-level radioactive waste  

SciTech Connect

The primary mission selected by DOE for the monitored retrieval storage (MRS) system is to provide an alternative means of storage in the event that the repository program is delayed. The MRS concepts considered were the eight concepts included in the MRS Research and Development Report to Congress (DOE 1983). These concepts are: metal cask (stationary and transportable); concrete cask (sealed storage cask); concrete cask-in-trench; field drywell; tunnel drywell; open cycle vault; closed cycle vault; and tunnel rack vault. Conceptual design analyses were performed for the candidate concepts using a common set of design requirements specified in consideration of the MRS mission.

Triplett, M.B.; Smith, R.I.

1984-04-01T23:59:59.000Z

107

Interim Storage of Used or Spent Nuclear Fuel Position Statement  

E-Print Network (OSTI)

The American Nuclear Society (ANS) supports the safe, controlled, licensed, and regulated interim storage of used nuclear fuel (UNF) (irradiated, spent fuel from a nuclear power reactor) until disposition can be determined and completed. ANS supports the U.S. Nuclear Regulatory Commission’s (NRC’s) determination that “spent fuel generated in any reactor can be stored safely and without significant environmental impacts for at least 30 years beyond the licensed life for operation. ” 1 Current operational and decommissioned nuclear power plants in the United States were licensed with the expectation that the UNF would be stored at the nuclear power plant site until shipment to an interim storage facility, reprocessing plant, or permanent storage. Because of delays in Federal programs and policy issues, utilities have been forced to store UNF. Current means of interim storage of UNF at nuclear power plant sites include storage of discharged fuel in a water-filled pool or in a sealed dry cask, both under safe, controlled, and monitored conditions. This UNF interim storage is designed, managed, and controlled to minimize or preclude potential radiological hazards or material releases. At nuclear power plant sites in the United States and internationally, this interim storage is regulated under site license requirements and technical specifications imposed by the national or state regulator. In the United States, NRC is the licensing and regulatory authority. ANS believes that UNF interim storage

unknown authors

2008-01-01T23:59:59.000Z

108

PRESERVATION OF H2 PRODUCTION ACTIVITY IN NANOPOROUS LATEX COATINGS OF RHODOPSEUDOMONAS PALUSTRIS CGA009 DURING DRY STORAGE AT AMBIENT TEMPERATURES  

Science Conference Proceedings (OSTI)

To assess the applicability of latex cell coatings as an "off-the-shelf' biocatalyst, the effect of osmoprotectants, temperature, humidity and O{sub 2} on preservation of H{sub 2} production in Rhodopseudomonas palustris coatings was evaluated. Immediately following latex coating coalescence (24 h) and for up to 2 weeks of dry storage, rehydrated coatings containing different osmoprotectants displayed similar rates of H{sub 2} production. Beyond 2 weeks of storage, sorbitol- treated coatings lost all H{sub 2} production activity, whereas considerable H{sub 2} production was still detected in sucrose- and trehalose-stabilized coatings. The relative humidity level at which the coatings were stored had a significant impact on the recovery and subsequent rates of H{sub 2} production. After 4 weeks storage under air at 60% humidity, coatings produced only trace amounts of H{sub 2} (0-0.1% headspace accumulation), whereas those stored at production activity after 8 weeks of storage. When stored in argon at production activity for 3 months, implicating oxidative damage as a key factor limiting coating storage. Overall, the results demonstrate that biocatalytic latex coatings are an attractive cell immobilization platform for preservation of bioactivity in the dry state.

Milliken, C.; Piskorska, M.; Soule, T.; Gosse, J.; Flickinger, M.; Smith, G.; Yeager, C.

2012-08-27T23:59:59.000Z

109

PRESERVATION OF H2 PRODUCTION ACTIVITY IN NANOPOROUS LATEX COATINGS OF RHODOPSEUDOMONAS PALUSTRIS CGA009 DURING DRY STORAGE AT AMBIENT TEMPERATURES  

SciTech Connect

To assess the applicability of latex cell coatings as an "off-the-shelf' biocatalyst, the effect of osmoprotectants, temperature, humidity and O{sub 2} on preservation of H{sub 2} production in Rhodopseudomonas palustris coatings was evaluated. Immediately following latex coating coalescence (24 h) and for up to 2 weeks of dry storage, rehydrated coatings containing different osmoprotectants displayed similar rates of H{sub 2} production. Beyond 2 weeks of storage, sorbitol- treated coatings lost all H{sub 2} production activity, whereas considerable H{sub 2} production was still detected in sucrose- and trehalose-stabilized coatings. The relative humidity level at which the coatings were stored had a significant impact on the recovery and subsequent rates of H{sub 2} production. After 4 weeks storage under air at 60% humidity, coatings produced only trace amounts of H{sub 2} (0-0.1% headspace accumulation), whereas those stored at <5% humidity retained 27-53% of their H{sub 2} production activity after 8 weeks of storage. When stored in argon at <5% humidity and room temperature, R. palustris coatings retained full H{sub 2} production activity for 3 months, implicating oxidative damage as a key factor limiting coating storage. Overall, the results demonstrate that biocatalytic latex coatings are an attractive cell immobilization platform for preservation of bioactivity in the dry state.

Milliken, C.; Piskorska, M.; Soule, T.; Gosse, J.; Flickinger, M.; Smith, G.; Yeager, C.

2012-08-27T23:59:59.000Z

110

Design of Transport Casks with Depleted Uranium Gamma Shield and Advanced Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

Transport Casks with Depleted Uranium Gamma Shield and Advanced Safety Transport Casks with Depleted Uranium Gamma Shield and Advanced Safety Matveev V.Z., Morenko A.I., Shapovalov V.I. Russian Federal Nuclear Center - All-Russian Research Institute of Experimental Physics (RFNC-VNIIEF) 37 Mira Prospect, Sarov, Russia, 607190, matveev@vniief.ru Maslov A.A., Orlov V.K., Semenov A.G., Sergeev V.M., Yuferov O.I., Visik A.M. Bochvar Institute of Inorganic Materials (VNIINM) 5-A Rogova street, p.b. 369, Moscow, Russia, 123060, majul2000@mail.ru Abstract - The report is dedicated to a problem of creation of a new generation of dual-purpose transport packing complete sets (TPCS) 1 with advanced safety. These sets are intended for transportation and storage of spent nuclear fuel assemblies (SNFA) 2 of VVER reactors and spent spark elements (SSE)

111

TRANSPORTATION CASK RECEIPT/RETURN FACILITY CRITICALITY SAFETY EVALUATIONS  

SciTech Connect

The purpose of this design calculation is to demonstrate that the handling operations of transportation casks performed in the Transportation Cask Receipt and Return Facility (TCRRF) and Buffer Area meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC [Bechtel SAIC Company] 2004 [DIRS 171599], Section 4.9.2.2), and the functional nuclear criticality safety requirement described in the ''Transportation Cask Receipt/Return Facility Description Document'' (BSC 2004 [DIRS 170217], Section 3.2.3). Specific scope of work contained in this activity consists of the following items: (1) Evaluate criticality effects for both dry and fully flooded conditions pertaining to TCRRF and Buffer Area operations for defense in depth. (2) Evaluate Category 1 and 2 event sequences for the TCRRF as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2004 [DIRS 167268], Section 7). This evaluation includes credible fuel reconfiguration conditions. In addition to the scope of work listed above, an evaluation was also performed of modeling assumptions for commercial spent nuclear fuel (CSNF) regarding inclusion of plenum and end regions of the active fuel. This calculation is limited to CSNF and US Department of Energy (DOE) SNF. it should be mentioned that the latter waste form is evaluated more in depth in the ''Canister Handling Facility Criticality Safety Calculations (BSC 2004 [DIRS 167614]). Further, the design and safety analyses of the naval SNF canisters are the responsibility of the US Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. In addition, this calculation is valid for the current design of the TCRRF and Buffer Area and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will have little or no impact on the criticality results and/or conclusions presented in this document. This calculation is subject to the ''Quality Assurance Requirements and Description'' (DOE 2004 [DIRS 171539]) because the TCRRF is included in the Q-List (BSC 2004 [DIRS 168361], p. A-3) as an item important to safety. This calculation is prepared in accordance with AP-3.12Q, ''Design Calculations and Analyses'' [DIRS 168413].

C.E. Sanders

2005-04-26T23:59:59.000Z

112

Alternative Cask Maintenance Facility concepts, an update and reassessment  

SciTech Connect

The results of three trade-off studies of alternative concepts for performing cask maintenance for Civilian Radioactive Waste Management System casks are presented. An earlier study resulted in a recommendation that a submerged pool concept for cask internal component removal be used in the design of a Cask Maintenance Facility. The first trade-off study resulted in confirming the previous recommendation that a submerged pool concept be used rather than an isolation cell; the basis for this continued recommendation is discussed. The second study provides an evaluation of the previously proposed facility for the capability of handling an increased quantity of OCRWM casks. This third study provides a preliminary concept for adding the capability to repaint the exterior cylindrical portions of casks.

Attaway, C.R.; Medley, L.B.; Williamson, A.; Pope, R.B.; Shappert, L.B.

1992-01-01T23:59:59.000Z

113

Business Case Slide 18: High-Volume: Casks - Issues  

NLE Websites -- All DOE Office Websites (Extended Search)

High-Volume: Casks - Issues Issues Low-cost manufacturing techniques for large shapes DUAGG(tm) Achieving a homogenous distribution in cement matrix Ensuring adequate strength...

114

Functions of the cask maintenance facility: A white paper  

SciTech Connect

The shipping cask systems are the mobile components of the transportation system, designed to safely transport spent nuclear fuel between different facilities under both normal and accident conditions. The cask system will consist of the heavily shielded cask, the cask transport vehicle (truck trailer or railcar), and any associated ancillary equipment (covers, impact limiters, lifting devices, etc.). The cask and certain parts of the cask system must be operated within the limits imposed by a certificate of compliance (COC) granted by the Nuclear Regulatory Commission (NRC). Each cask system must transport spent fuel safely during the life of the system. To maintain the operational effectiveness and safety of the cask systems, a cask maintenance facility (CMF) will be included as an integral part of the transportation system. The planning activity of the transportation system and the design effort of the CMF require that the functions to be performed by the CMF be explicitly defined. The purpose of this paper is to (1) define the potential transportation system functions to be performed at the CMF; (2) examine the impact of this functional definition on the overall transportation system; (3) identify any unresolved issues concerning the interaction of the CMF with other elements of the transportation system; and (4) make recommendations to resolve any unresolved issues so that decisions can be made early in the transportation system planning process.

1987-07-21T23:59:59.000Z

115

Interim Storage of Hanford Spent Fuel & Associated Sludge  

SciTech Connect

The Hanford site is currently dealing with a number of types of Spent Nuclear Fuel. The route to interim dry storage for the various fuel types branches along two different paths. Fuel types such as metallic N reactor fuel and Shippingport Core 2 Blanket assemblies are being placed in approximately 4 m long canisters which are then stored in tubes below grade in a new canister storage building. Other fuels such as TRIGA{trademark} and Light Water Reactor fuel will be relocated and stored in stand-alone casks on a concrete pad. Varying degrees of sophistication are being applied with respect to the drying and/or evacuation of the fuel interim storage canisters depending on the reactivity of the fuel, the degree of damaged fuel and the previous storage environment. The characterization of sludge from the Hanford K Basins is nearly complete and canisters are being designed to store the sludge (including uranium particles from fuel element cleaning) on an interim basis.

MAKENAS, B.J.

2002-07-01T23:59:59.000Z

116

Use of burnup credit for transportation and storage  

SciTech Connect

Burnup credit is the application of the effects of fuel burnup to nuclear criticality design. When burnup credit is considered in the design of storage facilities and transportation casks for spent fuel, the objectives are to reduce the requirements for storage space and to increase the payload of casks with acceptable nuclear criticality safety margins. The spent-fuel carrying capacities of previous-generation transport casks have been limited primarily by requirements to remove heat and/or to provide shielding. Shielding and heat transfer requirements for casks designed to transport older spent fuel with longer decay times are reduced significantly. Thus a considerable weight margin is available to the designer for increasing the payload capacity. One method to achieve an increase in capacity is to reduce fuel assembly spacing. The amount of reduction in assembly spacing is limited by criticality and fuel support structural concerns. The optimum fuel assembly spacing provides the maximum cask loading within a basket that has adequate criticality control and sufficient structural integrity for regulatory accident scenarios. The incorporation of burnup credit in cask designs could result in considerable benefits in the transport of spent fuel. The acceptance of burnup credit for the design of transport casks depends on the resolution of system safety issues and the uncertainties that affect the determination of criticality safety margins. The remainder of this report will examine these issues and the integrated approach under way to resolve them. 20 refs., 2 figs.

Sanders, T.L.; Ewing, R.I. (Sandia National Labs., Albuquerque, NM (USA)); Lake, W.H. (USDOE Office of Civilian Radioactive Waste Management, Washington, DC (USA))

1991-01-01T23:59:59.000Z

117

Conceptual design of the Clinch River Breeder Reactor spent-fuel shipping cask  

Science Conference Proceedings (OSTI)

Details of a baseline conceptual design of a spent fuel shipping cask for the Clinch River Breeder Reactor (CRBR) are presented including an assessment of shielding, structural, thermal, fabrication and cask/plant interfacing problems. A basis for continued cask development and for new technological development is established. Alternates to the baseline design are briefly presented. Estimates of development schedules, cask utilization and cost schedules, and of personnel dose commitments during CRBR in-plant handling of the cask are also presented.

Pope, R.B.; Diggs, J.M. (eds.)

1982-04-01T23:59:59.000Z

118

Criticality Safety Evaluation Report CSER-96-019 for Spent Nuclear Fuel (SNF) Processing and Storage Facilities Multi Canister Overpack (MCO)  

Science Conference Proceedings (OSTI)

This criticality evaluation is for Spent N Reactor fuel unloaded from the existing canisters in both KE and KW Basins, and loaded into multiple canister overpack (MCO) containers with specially built baskets containing a maximum of either 54 Mark IV or 48 Mark IA fuel assemblies. The criticality evaluations include loading baskets into the cask-MCO, operation at the Cold Vacuum Drying Facility,a nd storage in the Canister Storage Building. Many conservatisms have been built into this analysis, the primary one being the selection of the K{sub eff} = 0.95 criticality safety limit. This revision incorporates the analyses for the sampling/weld station in the Canister Storage Building and additional analysis of the MCO during the draining at CVDF. Additional discussion of the scrap basket model was added to show why the addition of copper divider plates was not included in the models.

KESSLER, S.F.

1999-10-20T23:59:59.000Z

119

Business Case Slide 17: High-Volume: Casks - Potential Benefits  

NLE Websites -- All DOE Office Websites (Extended Search)

Casks - Potential Benefits Potential benefits EM Use most or all of the DU inventory which could avoid transportation and disposal cost OCRWM Plans to acquire use of a fleet of...

120

Business Case Slide 13: High-Volume: Casks - DUCRETE  

NLE Websites -- All DOE Office Websites (Extended Search)

Previous Slide Next Slide Table of Contents High-Volume: Casks - DUCRETE(tm) DUAGG Briquettes DUAGG briquettes are made by a liquid-phase-sintering process and crushed and...

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


121

Radioactive-materials shipping-cask anticontamination enclosure  

DOE Patents (OSTI)

An anticontamination device for use in storing shipping casks for radioactive materials comprises (1) a seal plate assembly; (2) a double-layer plastic bag; and (3) a water management system or means for water management.

Belmonte, M.S.; Davis, J.H.; Williams, D.A.

1981-08-18T23:59:59.000Z

122

Conception of Universal Cask Based on Cermet for SNF Transportation...  

NLE Websites -- All DOE Office Websites (Extended Search)

low. These reasons cause high cost of SNF transportations. Most of the casks refer to package type B(M) according to IAEA classification, which can not be operated in the...

123

ALARA studies on spent fuel and waste casks  

SciTech Connect

In this report, some implications of applying the ALARA concept to cask designs for transporting spent fuel, high-level commercial and defense waste, and remote-handled transuranic waste are investigated. The XSDRNPM, one-dimensional radiation transport code, was used to obtain potential shield designs that would yield total dose rates at 1.8 m from the cask surface of 10, 5, and 2 mrem/h. Gamma shields of depleted uranium, lead, and steel were studied. The capacity of the casks was assumed to be 1, 4, or 7 elements or canisters, and the wastes were 1, 3, 5, and 10 years old. Depending on the dose rate, the cask empty weights and lifetime transportation costs were estimated.

Sutherland, S.H.

1980-04-01T23:59:59.000Z

124

Feasibility study for a transportation operations system cask maintenance facility  

SciTech Connect

The US Department of Energy (DOE), Office of Civilian Radioactive Waste Management (OCRWM) is responsible for the development of a waste management program for the disposition of spent nuclear fuel (SNF) and high-level waste (HLW). The program will include a transportation system for moving the nuclear waste from the sources to a geologic repository for permanent disposal. Specially designed casks will be used to safely transport the waste. The cask systems must be operated within limits imposed by DOE, the Nuclear Regulatory Commission (NRC), and the Department of Transportation (DOT). A dedicated facility for inspecting, testing, and maintaining the cask systems was recommended by the General Accounting Office (in 1979) as the best means of assuring their operational effectiveness and safety, as well as regulatory compliance. In November of 1987, OCRWM requested a feasibility study be made of a Cask Maintenance Facility (CMF) that would perform the required functions. 46 refs., 16 figs., 13 tabs.

Rennich, M.J.; Medley, L.G.; Attaway, C.R.

1991-01-01T23:59:59.000Z

125

High temperature post-irradiation performance of spent pressurized-water-reactor fuel rods under dry-storage conditions  

Science Conference Proceedings (OSTI)

Post-irradiation studies on failure mechanisms of well characterized PWR rods were conducted for up to a year at 482, 510 and 571/sup 0/C in unlimited air and inert gas atmospheres. No cladding breaches occurred even though the tests operated many orders of magnitude longer in time than the lifetime predicted by Blackburn's analyses. The extended lifetime is due to significant creep strain of the Zircaloy cladding which decreases the internal rod pressures. The cladding creep also contributes to radial cracks, through the external oxide and internal FCCI layers, which propagated into and arrested in an oxygen stabilized ..cap alpha..-Zircaloy layer. There were no signs of either additional cladding hydriding, stress-corrosion cracking or fuel pellet degradation. Using the Larson-Miller formulization, a conservative maximum storage temperature of 400/sup 0/C is recommended to ensure a 1000-year cladding lifetime. This accounts for crack propagation and assumes annealing of the irradiation-hardened cladding.

Einziger, R.E.; Atkin, S.D.; Stellrecht, D.E.; Pasupathi, V.

1981-06-01T23:59:59.000Z

126

Experience with certifying borated stainless steel as a shipping cask basket material  

SciTech Connect

The original cask designs for a cask demonstration project featured fuel baskets constructed of borated stainless steel (bss) as a structural material. The project is intended to demonstrate casks that can be used for both shipping and storing spent nuclear fuel assemblies. The baskets were intended to maintain the fuel assemblies in a subcritical array for both normal and accident conditions. The Nuclear Regulatory Commission, however, judged bss to be unacceptable as a structural material. The cask designs were subsequently modified. The knowledge gained during this cask demonstration project may be applicable to development of bss as a basket material in future cask design. 6 refs., 2 figs., 2 tabs.

Abbott, D.G. (EG and G Idaho, Inc., Idaho Falls, ID (USA)); Nickell, R.E. (Applied Science and Technology, Inc., Poway, CA (USA))

1990-01-01T23:59:59.000Z

127

TRANSPORTATION CASK RECEIPT AND RETURN FACILITY WORKER DOSE ASSESSMENT  

Science Conference Proceedings (OSTI)

The purpose of this design calculation is to estimate radiation doses received by personnel working in the Transportation Cask Receipt and Return Facility (TCRRF) of the repository including the personnel at the security gate and cask staging areas. This calculation is required to support the preclosure safety analysis (PCSA) to ensure that the predicted doses are within the regulatory limits prescribed by the U.S. Nuclear Regulatory Commission (NRC). The Cask Receipt and Return Facility receives NRC licensed transportation casks loaded with spent nuclear fuel (SNF) and high-level radioactive waste (HLW). The TCRRF operation starts with the receipt, inspection, and survey of the casks at the security gate and the staging areas, and proceeds to the process facilities. The transportation casks arrive at the site via rail cars or trucks under the guidance of the national transportation system. This calculation was developed by the Environmental and Nuclear Engineering organization and is intended solely for the use of Design and Engineering in work regarding facility design. Environmental and Nuclear Engineering personnel should be consulted before using this calculation for purposes other than those stated herein or for use by individuals other than authorized personnel in the Environmental and Nuclear Engineering organization.

V. Arakali

2005-02-24T23:59:59.000Z

128

Nuclear Fuels Storage & Transportation Planning Project | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Nuclear Fuels Storage & Nuclear Fuels Storage & Transportation Planning Project Nuclear Fuels Storage & Transportation Planning Project Independent Spent Fuel Storage Installation (ISFSI) at the shutdown Connecticut Yankee site. The ISFSI includes 40 multi-purpose canisters, within vertical concrete storage casks, containing 1019 used nuclear fuel assemblies [412.3 metric ton heavy metal (MTHM)] and 3 canisters of greater-than-class-C (GTCC) low-level radioactive waste. Photo courtesy of Connecticut Yankee (http://www.connyankee.com/html/fuel_storage.html). Independent Spent Fuel Storage Installation (ISFSI) at the shutdown Connecticut Yankee site. The ISFSI includes 40 multi-purpose canisters, within vertical concrete storage casks, containing 1019 used nuclear fuel

129

Equipment concepts for dry intercask transfer of spent fuel  

SciTech Connect

This report documents the results of a study of preconceptual design and analysis of four intercask transfer concepts. The four concepts are: a large shielded cylindrical turntable that contains an integral fuel handling machine (turntable concept); a shielded fuel handling machine under which shipping and storage casks are moved horizontally (shuttle concept); a small hot cell containing equipment for transferring fuel between shipping and storage casks (that enter and leave the cell on carts) in a bifurcated trench (trench concept); and a large hot cell, shielded by an earthen berm, that houses equipment for handling fuel between casks that enter and leave the cell on a single cart (igloo concept). The casks considered in this study are most of the transport casks currently operable in the USA, and the storage casks designated REA-2023 and GNS Castor-V. Exclusive of basic services assumed to be provided at the host site, the design and capital costs are estimated to range from $9 to $13 million. The portion of capital costs for portable equipment (for potential later use at another site) was estimated to range from 70% to 98%, depending on the concept. Increasing portability from a range of 70 to 90% to 98% adds $2 to 4 million to the capital costs. Operating costs are estimated at about $2 million/year for all concepts. Implementation times range from about 18 months for the more conventional systems to 40 months for the more unique systems. Times and costs for relocation to another site are 10 to 14 months and about $1 million, plus shipping costs and costs of new construction at the new site. All concepts have estimated capacities for fuel transfer at least equal to the criterion set for this study. Only the hot cell concepts have capability for recanning or repair of canisters. Some development is believed to be required for the turntable and shuttle concepts, but none for the other two concepts.

Schneider, K.J.

1983-07-01T23:59:59.000Z

130

Vestibule and Cask Preparation Mechanical Handling Calculation  

SciTech Connect

The scope of this document is to develop the size, operational envelopes, and major requirements of the equipment to be used in the vestibule, cask preparation area, and the crane maintenance area of the Fuel Handling Facility. This calculation is intended to support the License Application (LA) submittal of December 2004, in accordance with the directive given by DOE correspondence received on the 27th of January 2004 entitled: ''Authorization for Bechtel SAIC Company L.L.C. to Include a Bare Fuel Handling Facility and Increased Aging Capacity in the License Application, Contract Number DE-AC28-01R W12101'' (Ref. 167124). This correspondence was appended by further correspondence received on the 19th of February 2004 entitled: ''Technical Direction to Bechtel SAIC Company L.L. C. for Surface Facility Improvements, Contract Number DE-AC28-01R W12101; TDL No. 04-024'' (Ref. 16875 1). These documents give the authorization for a Fuel Handling Facility to be included in the baseline. The limitations of this preliminary calculation lie within the assumptions of section 5 , as this calculation is part of an evolutionary design process.

N. Ambre

2004-05-26T23:59:59.000Z

131

2013 Reporting Unit Codes | Department of Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

- September 2009 DOE Strategic Human Capital Plan (FY 2011 - 2015) Managing Aging Effects on Dry Cask Storage Systems for Extended Long Term Storage and Transportation...

132

Structural analysis of closure bolts for shipping casks  

Science Conference Proceedings (OSTI)

This paper identifies the active forces and moments in a closure bolt of a shipping cask. It examines the interactions of these forces/moments and suggest simplified methods for their analysis. The paper also evaluates the role that the forces and moments play in the structure integrity of the closure bolt and recommends stress limits and desirable practices to ensure its integrity.

Mok, G.C.; Fischer, L.E.

1993-04-01T23:59:59.000Z

133

Separator assembly for use in spent nuclear fuel shipping cask  

DOE Patents (OSTI)

A separator assembly for use in a spent nuclear fuel shipping cask has a honeycomb-type wall structure defining parallel cavities for holding nuclear fuel assemblies. Tubes formed of an effective neutron-absorbing material are embedded in the wall structure around each of the cavities and provide neutron flux traps when filled with water.

Bucholz, James A. (Oak Ridge, TN)

1983-01-01T23:59:59.000Z

134

Finding of No Significant Impact for the Storage of Tritium-Producing Burnable Absorber Rods in K-Area Transfer Bay at the Savannah River Site (DOE/EA-1528) (06/01/05)  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

the the Storage of Tritium-Producing Burnable Absorber Rods in K-Area Transfer Bay at the Savannah River Site Agency: U.S. Department of Energy (DOE) Action: Finding of No Significant Impact Summary: The DOE Savannah River Operations Office (SR) and the National Nuclear Security Administration (NNSA) Savannah River Site Office (SRSO) have prepared an environmental assessment (EA), DOE/EA-1528, to evaluate the potential environmental impacts of the temporary dry storage of a cask containing Tritium- Producing Burnable Absorber Rods (TPBARs) in the Transfer Bay in K Area at the Savannah River Site (SRS). Based on the analyses in the EA, DOE has determined that the proposed action is not a major Federal action significantly affecting the quality of the

135

Software requirements definition Shipping Cask Analysis System (SCANS)  

SciTech Connect

The US Nuclear Regulatory Commission (NRC) staff reviews the technical adequacy of applications for certification of designs of shipping casks for spent nuclear fuel. In order to confirm an acceptable design, the NRC staff may perform independent calculations. The current NRC procedure for confirming cask design analyses is laborious and tedious. Most of the work is currently done by hand or through the use of a remote computer network. The time required to certify a cask can be long. The review process may vary somewhat with the engineer doing the reviewing. Similarly, the documentation on the results of the review can also vary with the reviewer. To increase the efficiency of this certification process, LLNL was requested to design and write an integrated set of user-oriented, interactive computer programs for a personal microcomputer. The system is known as the NRC Shipping Cask Analysis System (SCANS). The computer codes and the software system supporting these codes are being developed and maintained for the NRC by LLNL. The objective of this system is generally to lessen the time and effort needed to review an application. Additionally, an objective of the system is to assure standardized methods and documentation of the confirmatory analyses used in the review of these cask designs. A software system should be designed based on NRC-defined requirements contained in a requirements document. The requirements document is a statement of a project's wants and needs as the users and implementers jointly understand them. The requirements document states the desired end products (i.e. WHAT's) of the project, not HOW the project provides them. This document describes the wants and needs for the SCANS system. 1 fig., 3 tabs.

Johnson, G.L.; Serbin, R.

1985-07-21T23:59:59.000Z

136

Accidental Drop of a Carbon Steel/Lead Shipping Cask (HFEF 14) at Low Temperatures  

Science Conference Proceedings (OSTI)

A shielded cask is used to transport radioactive materials between facilities at the Idaho National Laboratory. The cask was fabricated with an outer and inner shell of A36 carbon steel with lead poured in the annular space between the shells to provide radiation shielding. Carbon steel is known to be susceptible to low-temperature brittle fracture under impact loading. This paper will present the analysis results representing postulated transportation accidents during on-site transfers of the cask at subzero temperatures. The accident scenarios were based on a series of cask drops onto a rigid surface from a height of 1.83m (6 ft.) Finite element models of the cask and its contents were solved and post processed using the ABAQUS software. Each model was examined for failure to contain radioactive materials and/or significant loss of radiation shielding. Results of these analyses show that the body of the cask exhibits considerable ruggedness and will remain largely intact after the impact. There will be deformation of the main cask body with localized brittle failure of the cask outer shell and door structure. The cask payload outer waste can remains in the cask but will experience some permanent plastic deformation in each drop. It will not be deformed to the point where it will rupture, thus maintaining confinement of the can contents.

Brian D. Hawkes; Michael E. Nitzel

2007-08-01T23:59:59.000Z

137

Business Case Slide 15: High-Volume: Casks - DU/Steel Cermet  

NLE Websites -- All DOE Office Websites (Extended Search)

DUSteel Cermet Previous Slide Next Slide Table of Contents High-Volume: Casks - DUSteel Cermet Functions Radiation Shielding Gamma: High-Density DUO2Other Neutron Moderation...

138

Evaluation of the Cask Transportation Facility Modifications (CTFM) compliance to DOE order 6430.1A  

SciTech Connect

This report was prepared to evaluate the compliance of Cask Transportation Facility Modifications (CTFM) to DOE Order 6430.1A.

ARD, K.E.

1999-07-14T23:59:59.000Z

139

CLASSIFICATION OF THE MGR CARRIER/CASK TRANSPORT SYSTEM  

SciTech Connect

The purpose of this analysis is to document the Quality Assurance (QA) classification of the Monitored Geologic Repository (MGR) carrier/cask transport system structures, systems and components (SSCs) performed by the MGR Safety Assurance Department. This analysis also provides the basis for revision of YMP/90-55Q, Q-List (YMP 1998). The Q-List identifies those MGR SSCs subject to the requirements of DOE/RW-0333P, ''Quality Assurance Requirements and Description'' (QARD) (DOE 1998).

S.E. Salzman

1999-08-30T23:59:59.000Z

140

Cold vacuum drying system conceptual design report  

SciTech Connect

This document summarizes the activities involved in the removal of the SNF from the leaking basins and to place it in stable dry storage.

Bradshaw, F.W.

1996-05-01T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


141

THERMAL ANALYSIS OF A PROPOSED TRANSPORT CASK FOR THREE ADVANCED BURNER REACTOR USED FUEL ASSEMBLIES  

SciTech Connect

Preliminary studies of used fuel generated in the US Department of Energy’s Advanced Fuel Cycle Initiative have indicated that current used fuel transport casks may be insufficient for the transportation of said fuel. This work considers transport of three 5-year-cooled oxide Advanced Burner Reactor used fuel assemblies with a burn-up of 160 MWD/kg. A transport cask designed to carry these assemblies is proposed. This design employs a 7-cm-thick lead gamma shield and a 20-cm-thick NS-4-FR composite neutron shield. The temperature profile within the cask, from its center to its exterior surface, is determined by two dimensional computational fluid dynamics simulations of conduction, convection, and radiation within the cask. Simulations are performed for a cask with a smooth external surface and various neutron shield thicknesses. Separate simulations are performed for a cask with a corrugated external surface and a neutron shield thickness that satisfies shielding constraints. Resulting temperature profiles indicate that a three-assembly cask with a smooth external surface will meet fuel cladding temperature requirements but will cause outer surface temperatures to exceed the regulatory limit. A cask with a corrugated external surface will not exceed the limits for both the fuel cladding and outer surface temperatures.

T. Bullard; M. Greiner; M. Dennis; S. Bays; R. Weiner

2010-09-01T23:59:59.000Z

142

Optimization of Trajectories for the Cask and Plug Remote Handling System in Tokamak  

E-Print Network (OSTI)

May 2011 Optimization of Trajectories for the Cask and Plug Remote Handling System in Tokamak Building and Hot Cell Fusion for Energy Grant: F4E-GRT-276-01 (MS-RH) | April.2011-Oct.2011 o Partners| Project IST (F4E ­ ITER) #12;May 2011 Optimization of Trajectories for the Cask and Plug Remote Handling

Ribeiro,Isabel

143

DESIGN OF MTR FUEL-ELEMENT-SOURCE SHIPPING CASK FOR RAILWAY MOBILE IRRADIATION FACILITY. Progress Report  

SciTech Connect

The gamma -radiation field from a battery of 10 MTR spent fuel elements was calculated and a special shipping cask designed to contain the 10 elements. An internal watercooled tank in the cask holds the 10 elements in the vertical position. Two external air-cooled, finned-tube heat exchangers control the water temperature. The sides of the cask open to convert the cask to a radiation source without changing the position of the elements. A unique feature of the design is a device for closing the sides of the cask by gravity in the event of accident or power failure. This provides a ''fail-safe'' safety feature. (auth)

Brownell, L.E.; Patterson, J.; Purohit, S.N.

1957-09-01T23:59:59.000Z

144

Microsoft Word - DOE-ID-13-061 South Carolina EC B3-6.doc  

NLE Websites -- All DOE Office Websites (Extended Search)

system based on in-situ sensing technologies that monitors material degradation and aging for nuclear spent fuel dry cask storage system (DCSS) and similar structures. Work...

145

Certification challenges in the development of an innovative high payload capacity spent fuel transportation cask  

SciTech Connect

The design approach and certification strategy used in the development of an innovative transportation cask for legal weight truck shipments of spent nuclear fuel is presented. The proposed approach represents a significant departure from conventional cask designs in that it uses titanium alloy, a material with a high strength-to-weight ratio which has no precedent in transportation cask certification. The significant increase in payload obtainable with the proposed approach, and the associated benefits such as reduced life cycle costs, lower personnel exposure, and lower transportation accident risks are discussed. 8 refs., 3 figs., 1 tab.

Mair, B.R.; Severson, M.J.; Ciez, A.P. (Westinghouse Electric Corp., Pittsburgh, PA (USA))

1990-01-01T23:59:59.000Z

146

A method for determining the spent-fuel contribution to transport cask containment requirements  

Science Conference Proceedings (OSTI)

This report examines containment requirements for spent-fuel transport containers that are transported under normal and hypothetical accident conditions. A methodology is described that estimates the probability of rod failure and the quantity of radioactive material released from breached rods. This methodology characterizes the dynamic environment of the cask and its contents and deterministically models the peak stresses that are induced in spent-fuel cladding by the mechanical and thermal dynamic environments. The peak stresses are evaluated in relation to probabilistic failure criteria for generated or preexisting ductile tearing and material fractures at cracks partially through the wall in fuel rods. Activity concentrations in the cask cavity are predicted from estimates of the fraction of gases, volatiles, and fuel fines that are released when the rod cladding is breached. Containment requirements based on the source term are calculated in terms of maximum permissible volumetric leak rates from the cask. Calculations are included for representative cask designs.

Sanders, T.L.; Seager, K.D. [Sandia National Labs., Albuquerque, NM (United States); Rashid, Y.R.; Barrett, P.R. [ANATECH Research Corp., La Jolla, CA (United States); Malinauskas, A.P. [Oak Ridge National Lab., TN (United States); Einziger, R.E. [Pacific Northwest Lab., Richland, WA (United States); Jordan, H. [EG and G Rocky Flats, Inc., Golden, CO (United States). Rocky Flats Plant; Duffey, T.A.; Sutherland, S.H. [APTEK, Inc., Colorado Springs, CO (United States); Reardon, P.C. [GRAM, Inc., Albuquerque, NM (United States)

1992-11-01T23:59:59.000Z

147

Tandem SAM Domain Structure of Human Caskin1: A Presynaptic, Self-Assembling Scaffold for CASK  

Science Conference Proceedings (OSTI)

The synaptic scaffolding proteins CASK and Caskin1 are part of the fibrous mesh of proteins that organize the active zones of neural synapses. CASK binds to a region of Caskin1 called the CASK interaction domain (CID). Adjacent to the CID, Caskin1 contains two tandem sterile a motif (SAM) domains. Many SAM domains form polymers so they are good candidates for forming the fibrous structures seen in the active zone. We show here that the SAM domains of Caskin1 form a new type of SAM helical polymer. The Caskin1 polymer interface exhibits a remarkable segregation of charged residues, resulting in a high sensitivity to ionic strength in vitro. The Caskin1 polymers can be decorated with CASK proteins, illustrating how these proteins may work together to organize the cytomatrix in active zones.

Stafford, Ryan L.; Hinde, Elizabeth; Knight, Mary Jane; Pennella, Mario A.; Ear, Jason; Digman, Michelle A.; Gratton, Enrico; Bowie, James U. (UCI); (UCLA)

2012-02-07T23:59:59.000Z

148

Maintenance manual for the Beneficial Uses Shipping System cask. Revision 1  

Science Conference Proceedings (OSTI)

This document is the Maintenance Manual for the Beneficial Uses Shipping System (BUSS) cask. These instructions address requirements for maintenance, inspection, testing, and repair, supplementing general information found in the BUSS Safety Analysis Report for Packaging (SARP), SAND 83-0698. Use of the BUSS cask is authorized by the Department of Energy (DOE) and the Nuclear Regulatory Commission (NRC) for the shipment of special form cesium chloride or strontium flouride capsules.

Bronowski, D.R.; Yoshimura, H.R.

1993-05-01T23:59:59.000Z

149

SCANS (Shipping Cask ANalysis System) a microcomputer-based analysis system for shipping cask design review: User`s manual to Version 3a. Volume 1, Revision 2  

SciTech Connect

SCANS (Shipping Cask ANalysis System) is a microcomputer-based system of computer programs and databases developed at the Lawrence Livermore National Laboratory (LLNL) for evaluating safety analysis reports on spent fuel shipping casks. SCANS is an easy-to-use system that calculates the global response to impact loads, pressure loads and thermal conditions, providing reviewers with an independent check on analyses submitted by licensees. SCANS is based on microcomputers compatible with the IBM-PC family of computers. The system is composed of a series of menus, input programs, cask analysis programs, and output display programs. All data is entered through fill-in-the-blank input screens that contain descriptive data requests. Analysis options are based on regulatory cases described in the Code of Federal Regulations 10 CFR 71 and Regulatory Guides published by the US Nuclear Regulatory Commission in 1977 and 1978.

Mok, G.C.; Thomas, G.R.; Gerhard, M.A.; Trummer, D.J.; Johnson, G.L. [Lawrence Livermore National Lab., CA (United States)

1998-03-01T23:59:59.000Z

150

SPENT FUEL TRANSFER, STORAGE AND SHIPMENT FOR PL-3  

SciTech Connect

In refueling development studies performed on PL-3 Phase I design, several methods of fuel transfer, storage, and shipment were investigated. An evaluation of the relative merits of the systems and designs under study, as applied to either the BWR or PWR concepts, is made and optimum designs are selected. An analysis of spent fuel shipping cask shielding requirements is presented, along with recommendations for future study in this area. (auth)

Hauenstein, G.C.; Pomeroy, D.L.

1962-03-01T23:59:59.000Z

151

Transportation Storage Interface  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

and Transportation: Technical Needs 13 * High priority degradation areas: * Stress corrosion cracking of stainless steel canister body and welds * Degradation of cask bolts *...

152

Design Calculations for Gas Flow & Diffusion Behavior in the large Diameter Container & Cask  

DOE Green Energy (OSTI)

This report describes the calculations for the gas behavior in the void volumes or gas spaces of the sludge Large Diameter Container (LDC) and Cask. The objective is to prevent flammable gas conditions in the LDC and Cask gas spaces. This is achieved by the Active Inert Ventilation System (AIVS), which uses argon gas for dilution purposes. With AIVS, the oxygen content is kept below 5 vol% in the LDC, and the hydrogen content is kept below 4 vol% in the Cask before its purge at the KE Basin. After the Cask sweep-through purge with argon at the KE Basin, oxygen is kept below 5% in both the Cask and the LDC. The analysis here assumes that any oxygen generated in the sludge is consumed by the uranium and uranium dioxide (SNF-18133, ''Gas Behavior in Large Diameter Containers (LDCs) During and Following Loading with 105K East Sludge''). Thus, oxygen production from radiolysis is intentionally not included in this report, but hydrogen from radiolysis and from chemical reactions between uranium and water are considered, depending on the scenario being analyzed. The analysis starts immediately after the final decant at K Basin, when argon is assumed to be the only gas in the LDC gas space, except for the normal water vapor. The oxygen ingress is calculated during the disconnecting of the lines hoses from the LDC, during the time that air is surrounding the LDC with two NucFil-type filters in place after the disconnect, before the Cask is sealed, and, finally, during the sweep-through Cask purge. Dissolution of oxygen from water due to increasing sludge temperatures (mainly during hot transport to the T Plant) is also included.

PIEPHO, M.G.

2003-10-21T23:59:59.000Z

153

Assessment of Reactivity Margins and Loading Curves for PWR Burnup Credit Cask Designs  

SciTech Connect

This report presents studies to assess reactivity margins and loading curves for pressurized water reactor (PWR) burnup-credit criticality safety evaluations. The studies are based on a generic high-density 32-assembly cask and systematically vary individual calculational (depletion and criticality) assumptions to demonstrate the impact on the predicted effective neutron multiplication factor, k{sub eff}, and burnup-credit loading curves. The purpose of this report is to provide a greater understanding of the importance of input parameter variations and quantify the impact of calculational assumptions on the outcome of a burnup-credit evaluation. This study should provide guidance to regulators and industry on the technical areas where improved information will most enhance the estimation of accurate subcritical margins. Based on these studies, areas where future work may provide the most benefit are identified. The report also includes an evaluation of the degree of burnup credit needed for high-density casks to transport the current spent nuclear fuel inventory. By comparing PWR discharge data to actinide-only based loading curves and determining the number of assemblies that meet the loading criteria, this evaluation finds that additional negative reactivity (through either increased credit for fuel burnup or cask design/utilization modifications) is necessary to accommodate the majority of current spent fuel assemblies in high-capacity casks. Assemblies that are not acceptable for loading in the prototypic high-capacity cask may be stored or transported by other means (e.g., lower capacity casks that utilize flux traps and/or increased fixed poison concentrations or high-capacity casks with design/utilization modifications).

Wagner, J.C.

2002-12-17T23:59:59.000Z

154

Recommendations for cask features for robotic handling from the Advanced Handling Technology Project  

SciTech Connect

This report describes the current status and recent progress in the Advanced Handling Technology Project (AHTP) initiated to explore the use of advanced robotic systems and handling technologies to perform automated cask handling operations at radioactive waste handling facilities, and to provide guidance to cask designers on the impact of robotic handling on cask design. Current AHTP tasks have developed system mock-ups to investigate robotic manipulation of impact limiters and cask tiedowns. In addition, cask uprighting and transport, using computer control of a bridge crane and robot, were performed to demonstrate the high speed cask transport operation possible under computer control. All of the current AHTP tasks involving manipulation of impact limiters and tiedowns require robotic operations using a torque wrench. To perform these operations, a pneumatic torque wrench and control system were integrated into the tool suite and control architecture of the gantry robot. The use of captured fasteners is briefly discussed as an area where alternative cask design preferences have resulted from the influence of guidance for robotic handling vs traditional operations experience. Specific robotic handling experiences with these system mock-ups highlight a number of continually recurring design principles: (1) robotic handling feasibility is improved by mechanical designs which emphasize operation with limited dexterity in constrained workspaces; (2) clearances, tolerances, and chamfers must allow for operations under actual conditions with consideration for misalignment and imprecise fixturing; (3) successful robotic handling is enhanced by including design detail in representations for model-based control; (4) robotic handling and overall quality assurance are improved by designs which eliminate the use of loose, disassembled parts. 8 refs., 15 figs.

Drotning, W.

1991-02-01T23:59:59.000Z

155

STP-ECRTS - THERMAL AND GAS ANALYSES FOR SLUDGE TRANSPORT AND STORAGE CONTAINER (STSC) STORAGE AT T PLANT  

DOE Green Energy (OSTI)

The Sludge Treatment Project (STP) is responsible for the disposition of sludge contained in the six engineered containers and Settler tank within the 105-K West (KW) Basin. The STP is retrieving and transferring sludge from the Settler tank into engineered container SCS-CON-230. Then, the STP will retrieve and transfer sludge from the six engineered containers in the KW Basin directly into a Sludge Transport and Storage Containers (STSC) contained in a Sludge Transport System (STS) cask. The STSC/STS cask will be transported to T Plant for interim storage of the STSC. The STS cask will be loaded with an empty STSC and returned to the KW Basin for loading of additional sludge for transportation and interim storage at T Plant. CH2MHILL Plateau Remediation Company (CHPRC) contracted with Fauske & Associates, LLC (FAI) to perform thermal and gas generation analyses for interim storage of STP sludge in the Sludge Transport and Storage Container (STSCs) at T Plant. The sludge types considered are settler sludge and sludge originating from the floor of the KW Basin and stored in containers 210 and 220, which are bounding compositions. The conditions specified by CHPRC for analysis are provided in Section 5. The FAI report (FAI/10-83, Thermal and Gas Analyses for a Sludge Transport and Storage Container (STSC) at T Plant) (refer to Attachment 1) documents the analyses. The process considered was passive, interim storage of sludge in various cells at T Plant. The FATE{trademark} code is used for the calculation. The results are shown in terms of the peak sludge temperature and hydrogen concentrations in the STSC and the T Plant cell. In particular, the concerns addressed were the thermal stability of the sludge and the potential for flammable gas mixtures. This work was performed with preliminary design information and a preliminary software configuration.

CROWE RD; APTHORPE R; LEE SJ; PLYS MG

2010-04-29T23:59:59.000Z

156

Spent-fuel-storage alternatives  

Science Conference Proceedings (OSTI)

The Spent Fuel Storage Alternatives meeting was a technical forum in which 37 experts from 12 states discussed storage alternatives that are available or are under development. The subject matter was divided into the following five areas: techniques for increasing fuel storage density; dry storage of spent fuel; fuel characterization and conditioning; fuel storage operating experience; and storage and transport economics. Nineteen of the 21 papers which were presented at this meeting are included in this Proceedings. These have been abstracted and indexed. (ATT)

Not Available

1980-01-01T23:59:59.000Z

157

Conceptual Design Report Cask Loadout Sys and Cask Drop Redesign for the Immersion Pail Support Structure and Operator Interface Platform at 105 K West  

SciTech Connect

This conceptual design report documents the redesign of the IPSS and the OIP in the 105 KW Basin south loadout pit due to a postulated cask drop accident, as part of Project A.5/A.6, Canister Transfer Facility Modifications. Project A.5/A.6 involves facility modifications needed to transfer fuel from the basin into the cask-MCO. The function of the IPSS is to suspend, guide, and position the immersion pail. The immersion pail protects the cask-MCO from contamination by basin water and acts as a lifting device for the cask-MCO. The OIP provides operator access to the south loadout pit. Previous analyses studied the effects of a cask-MCO drop on the south loadout pit concrete structure and on the IPSS. The most recent analysis considered the resulting loads at the pit slab/wall joint (Kanjilal, 1999). This area had not been modeled previously, and the analysis results indicate that the demand capacity exceeds the allowable at the slab/wall joint. The energy induced on the south loadout pit must be limited such that the safety class function of the basin is maintained. The solution presented in this CDR redesigns the IPSS and the OIP to include impact-absorbing features that will reduce the induced energy. The impact absorbing features of the new design include: Impact-absorbing material at the IPSS base and at the upper portion of the IPSS legs. A sleeve which provides a hydraulic means of absorbing energy. Designing the OIP to act as an impact absorber. The existing IPSS structure in 105 KW will be removed. This conceptual design considers only loads resulting from drops directly over the IPSS and south loadout pit area. Drops in other areas of the basin are not considered, and will be covered as part of a future revision to this CDR.

LANGEVIN, A.S.

1999-07-12T23:59:59.000Z

158

Safety analysis report vitrified high level waste type B shipping cask  

Science Conference Proceedings (OSTI)

This Safety Analysis Report describes the design, analyses, and principle features of the Vitrified High Level Waste (VHLW) Cask. In preparing this report a detailed evaluation of the design has been performed to ensure that all safety, licensing, and operational goals for the cask and its associated Department of Energy program can be met. The functions of this report are: (1) to fully document that all functional and regulatory requirements of 10CFR71 can be met by the package; and (2) to document the design and analyses of the cask for review by the Nuclear Regulatory Commission. The VHLW Cask is the reusable shipping package designed by GNSI under Department of Energy contract DE-AC04-89AL53-689 for transportation of Vitrified High Level Waste, and to meet the requirements for certification under 10CFR71 for a Type B(U) package. The VHLW cask has been designed as packaging for transport of canisters of Vitrified High Level Waste solidified at Department of Energy facilities.

NONE

1995-03-01T23:59:59.000Z

159

Spent fuel drying system test results (second dry-run)  

DOE Green Energy (OSTI)

The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks have been detected in the basins and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 7.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the second dry-run test, which was conducted without a fuel element. With the concurrence of project management, the test protocol for this run, and subsequent drying test runs, was modified. These modifications were made to allow for improved data correlation with drying procedures proposed under the IPS. Details of these modifications are discussed in Section 3.0.

Klinger, G.S.; Oliver, B.M.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J.; Ritter, G.A.

1998-07-01T23:59:59.000Z

160

Referenced-site environmental document for a Monitored Retrievable Storage facility: backup waste management option for handling 1800 MTU per year  

SciTech Connect

This environmental document includes a discussion of the purpose of a monitored retrievable storage facility, a description of two facility design concepts (sealed storage cask and field drywell), a description of three reference sites (arid, warm-wet, and cold-wet), and a discussion and comparison of the impacts associated with each of the six site/concept combinations. This analysis is based on a 15,000-MTU storage capacity and a throughput rate of up to 1800 MTU per year.

Silviera, D.J.; Aaberg, R.L.; Cushing, C.E.; Marshall, A.; Scott, M.J.; Sewart, G.H.; Strenge, D.L.

1985-06-01T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


161

Cold vacuum drying facility 90% design review  

Science Conference Proceedings (OSTI)

This document contains review comment records for the CVDF 90% design review. Spent fuels retrieved from the K Basins will be dried at the CVDF. It has also been recommended that the Multi-Conister Overpacks be welded, inspected, and repaired at the CVD Facility before transport to dry storage.

O`Neill, C.T.

1997-05-02T23:59:59.000Z

162

A methodology for estimating the residual contamination contribution to the source term in a spent-fuel transport cask  

Science Conference Proceedings (OSTI)

This report describes the ranges of the residual contamination that may build up in spent-fuel transport casks. These contamination ranges are calculated based on data taken from published reports and from previously unpublished data supplied by cask transporters. The data involve dose rate measurements, interior smear surveys, and analyses of water flushed out of cask cavities during decontamination operations. A methodology has been developed to estimate the effect of residual contamination on spent-fuel cask containment requirements. Factors in estimating the maximum permissible leak rates include the form of the residual contamination; possible release modes; internal gas-borne depletion; and the temperature, pressure, and vibration characteristics of the cask during transport under normal and accident conditions. 12 refs., 9 figs., 4 tabs.

Sanders, T.L. (Sandia National Labs., Albuquerque, NM (United States)); Jordan, H. (EG and G Rocky Flats, Inc., Golden, CO (United States). Rocky Flats Plant); Pasupathi, V. (Battelle, Columbus, OH (United States)); Mings, W.J. (USDOE Idaho Field Office, Idaho Falls, ID (United States)); Reardon, P.C. (GRAM, Inc., Albuquerque, NM (United States))

1991-09-01T23:59:59.000Z

163

TN-68 Spent Fuel Transport Cask Analytical Evaluation for Drop Events  

SciTech Connect

The U.S. Nuclear Regulatory Commission (NRC) is responsible for licensing commercial spent nuclear fuel transported in casks certified by NRC under the Code of Federal Regulations (10 CFR), Title 10, Part 71 [1]. Both the International Atomic Energy Agency regulations for transporting radioactive materials [2, paragraph 727], and 10 CFR 71.73 require casks to be evaluated for hypothetical accident conditions, which includes a 9-meter (m) (30-ft) drop-impact event onto a flat, essentially unyielding, horizontal surface, in the most damaging orientation. This paper examines the behavior of one of the NRC certified transportation casks, the TN-68 [3], for drop-impact events. The specific area examined is the behavior of the bolted connections in the cask body and the closure lid, which are significantly loaded during the hypothetical drop-impact event. Analytical work to evaluate the NRC-certified TN-68 spent fuel transport cask [3] for a 9-m (30-ft) drop-impact event on a flat, unyielding, horizontal surface, was performed using the ANSYS® [4] and LS DYNA™ [5] finite-element analysis codes. The models were sufficiently detailed, in the areas of bolt closure interfaces and containment boundaries, to evaluate the structural integrity of the bolted connections under 9-m (30-ft) free-drop hypothetical accident conditions, as specified in 10 CFR 71.73. Evaluation of the cask for puncture, caused by a free drop through a distance of 1-m (40-in.) onto a mild steel bar mounted on a flat, essentially unyielding, horizontal surface, required by 10 CFR 71.73, was not included in the current work, and will have to be addressed in the future. Based on the analyses performed to date, it is concluded that, even though brief separation of the flange and the lid surfaces may occur under some conditions, the seals would close at the end of the drop events, because the materials remain elastic during the duration of the event.

Shah, M. J.; Klymyshyn, Nicholas A.; Adkins, Harold E.; Koeppel, Brian J.

2007-03-30T23:59:59.000Z

164

Trojan Spent Fuel Pool Chemistry Control During Fuel Transfer to Storage Cask  

Science Conference Proceedings (OSTI)

The decommissioning staff at Trojan Nuclear Power Plant faced a difficult carbon steel fuel basket corrosion problem resulting from decreased pH in their fuel pool. This report provides the details of the technical solution proposed by the EPRI investigative team. They based the solution upon sound chemical principles backed up with laboratory experimental data and a literature review.

2001-02-23T23:59:59.000Z

165

Seismic and cask drop excitation evaluation of the tower shielding reactor  

SciTech Connect

During the current shutdown of the Tower Shielding Reactor II (TSR-II), analyses were performed to determine the effect of nearby cask drops on the structural and mechanical integrity of the reactor. This evaluation was then extended to include the effects of earthquakes. Several analytic models were developed to simulate the effects of earthquake and cask drop excitation. A coupled soil-structure model was developed. As a result of the analyses, several hardware modifications and enhancements were implemented to ensure reactor integrity during future operations. 6 figs.

Harris, S.P.; Stover, R.L.; Johnson, J.J.; Sumodobila, B.N. (EQE, Inc., San Francisco, CA (USA); Oak Ridge National Lab., TN (USA); EQE, Inc., San Francisco, CA (USA))

1989-01-01T23:59:59.000Z

166

Annotated Bibliography for Drying Nuclear Fuel  

Science Conference Proceedings (OSTI)

Internationally, the nuclear industry is represented by both commercial utilities and research institutions. Over the past two decades many of these entities have had to relocate inventories of spent nuclear fuel from underwater storage to dry storage. These efforts were primarily prompted by two factors: insufficient storage capacity (potentially precipitated by an open-ended nuclear fuel cycle) or deteriorating quality of existing underwater facilities. The intent of developing this bibliography is to assess what issues associated with fuel drying have been identified, to consider where concerns have been satisfactorily addressed, and to recommend where additional research would offer the most value to the commercial industry and the U. S. Department of Energy.

Rebecca E. Smith

2011-09-01T23:59:59.000Z

167

Demonstration of a transportable storage system for spent nuclear fuel  

Science Conference Proceedings (OSTI)

The purpose of this paper is to discuss the joint demonstration project between the Sacramento Municipal Utility District (SMUD) and the US Department of Energy (DOE) regarding the use of a transportable storage system for the long-term storage and subsequent transport of spent nuclear fuel. SMUD's Rancho Seco nuclear generating station was shut down permanently in June 1989. After the shutdown, SMUD began planning the decommissioning process, including the disposition of the spent nuclear fuel. Concurrently, Congress had directed the Secretary of Energy to develop a plan for the use of dual-purpose casks. Licensing and demonstrating a dual-purpose cask, or transportable storage system, would be a step toward achieving Congress's goal of demonstrating a technology that can be used to minimize the handling of spent nuclear fuel from the time the fuel is permanently removed from the reactor through to its ultimate disposal at a DOE facility. For SMUD, using a transportable storage system at the Rancho Seco Independent Spent-Fuel Storage Installation supports the goal of abandoning Rancho Seco's spent-fuel pool as decommissioning proceeds.

Shetler, J.R.; Miller, K.R.; Jones, R.E. (Sacramento Municipal Utility District, Herald, CA (United States))

1993-01-01T23:59:59.000Z

168

Hydrogen Storage  

Science Conference Proceedings (OSTI)

Oct 10, 2012 ... Energy Storage: Materials, Systems and Applications: Hydrogen Storage Program Organizers: Zhenguo "Gary" Yang, Pacific Northwest ...

169

Separator assembly for use in spent-nuclear-fuel shipping cask. [Patent application  

DOE Patents (OSTI)

A separator assembly for use in a spent-nuclear-fuel shipping cask has a honeycomb-type wall structure defining parallel cavities for holding nuclear fuel assemblies. Tubes formed of an effective neutron-absorbing material are embedded in the wall structure around each of the cavities and provide neutron flux traps when filled with water.

Bucholz, J.A.

1981-04-24T23:59:59.000Z

170

Second Annual Maintenance, Inspection, and Test Report for PAS-1 Cask Certification for Shipping Payload B  

Science Conference Proceedings (OSTI)

The Nuclear Packaging, Inc. (NuPac), PAS-1 cask is required to undergo annual maintenance and inspections to retain certification in accordance with U.S. Department of Energy (DOE) Certificate of Compliance USA/9184B(U) (Appendix A). The packaging configuration being tested and maintained is the NuPac PAS-1 cask for Payload B. The intent of the maintenance and inspections is to ensure the packaging remains in unimpaired physical condition. Two casks, serial numbers 2162-026 and 2162-027, were maintained, inspected, and tested at the 306E Development, Fabrication, and Test Laboratory, located at the Hanford Site's 300 Area. Waste Management Federal Services, Inc. (WMFS), a subsidiary of GTS Duratek, was in charge of the maintenance and testing. Cogema Engineering Corporation (Cogema) directed the operations in the test facility. The maintenance, testing, and inspections were conducted successfully with both PAS-1 casks. The work conducted on the overpacks included weighing, gasket replacement, and plastic pipe plug and foam inspections. The work conducted on the secondary containment vessel (SCV) consisted of visual inspection of the vessel and threaded parts (i.e., fasteners), visual inspection of sealing surfaces, replacement of O-ring seals, and a helium leak test. The work conducted on the primary containment vessel (PCV) consisted of visual inspection of the vessel and threaded parts (i.e., fasteners), visual inspection of sealing surfaces, replacement of O-ring seals, dimensional inspection of the vessel bottom, a helium leak test, and dye penetrant inspection of the welds. The vermiculite material used in the cask rack assembly was replaced.

KELLY, D.J.

2000-10-09T23:59:59.000Z

171

Base Natural Gas in Underground Storage (Summary)  

U.S. Energy Information Administration (EIA) Indexed Site

Citygate Price Residential Price Commercial Price Industrial Price Electric Power Price Gross Withdrawals Gross Withdrawals From Gas Wells Gross Withdrawals From Oil Wells Gross Withdrawals From Shale Gas Wells Gross Withdrawals From Coalbed Wells Repressuring Nonhydrocarbon Gases Removed Vented and Flared Marketed Production NGPL Production, Gaseous Equivalent Dry Production Imports By Pipeline LNG Imports Exports Exports By Pipeline LNG Exports Underground Storage Capacity Gas in Underground Storage Base Gas in Underground Storage Working Gas in Underground Storage Underground Storage Injections Underground Storage Withdrawals Underground Storage Net Withdrawals Total Consumption Lease and Plant Fuel Consumption Pipeline & Distribution Use Delivered to Consumers Residential Commercial Industrial Vehicle Fuel Electric Power Period:

172

Preliminary analysis of the postulated changes needed to achieve rail cask handling capabilities at selected light water reactors  

SciTech Connect

Reactor-specific railroad and crane information for all LWRs in the US was extracted from current sources of information. Based on this information, reactors were separated into two basic groups consisting of reactors with existing, usable rail cask capabilities and those without these capabilities. The latter group is the main focus of this study. The group of reactors without present rail cask handling capabilities was further separated into two subgroups consisting of reactors considered essentially incapable of handling a large rail cask of about 100 tons and reactors where postulated facility changes could result in rail cask handling capabilities. Based on a selected population of 127 reactors, the results of this assessment indicate that usable rail cask capabilities exist at 83 (65%) of the reactors. Twelve (27%) of the remaining 44 reactors are deemed incapable of handling a large rail cask without major changes, and 32 reactors are considered likely candidates for potentially achieving rail cask handling capabilities. In the latter group, facility changes were postulated that would conceptually enable these reactors to handle large rail casks. The estimated cost per plant of required facility changes varied widely from a high of about $35 million to a low of <$0.3 million. Only 11 of the 32 plants would require crane upgrades. Spur track and right-of-way costs would apparently vary widely among sites. These results are based on preliminary analyses using available generic cost data. They represent lower bound values that are useful for developing an initial assessment of the viability of the postulated changes on a system-wide basis, but are not intended to be absolute values for specific reactors or sites.

Konzek, G.J.

1986-02-01T23:59:59.000Z

173

SENSIBLE HEAT STORAGE FOR A SOLAR THERMAL POWER PLANT  

E-Print Network (OSTI)

Natural-Draft Dry-Cooling Tower • Power-Generation SubsystemSubsystem Costs Cost a, b, Dry-Cooling Tower Costs c, II.Steam Wet-Cooling Tower Costs Turbine~Generator STORAGE UNIT

Baldwin, Thomas F.

2011-01-01T23:59:59.000Z

174

Criticality safety and shielding design issues in the development of a high-capacity cask for truck transport  

SciTech Connect

General Atomics (GA) will be submitting an application for certification to the US Nuclear Regulatory Commission (NRC) for the GA-4 and GA-9 Casks In 1992. The GA-4 and GA-9 Casks are high-capacity legal weight truck casks designed to transport light water reactor spent fuel assemblies. To maintain a capacity of four pressurized-water-reactor (PWR) spent fuel assemblies, the GA-4 Cask uses burnup credit as part of the criticality control for initial enrichments over 3.0 wt% U-235. Using the US Department of Energy (DOE) Burnup Credit Program as a basis, GA has performed burnup credit analysis which is included in the Safety Analysis Report for Packaging (SARP). The GA-9 Cask can meet the criticality safety requirements using the ``fresh fuel`` assumption. Our approach to shielding design is to optimize the GA-4 and GA-9 Cask shielding configurations for minimum weights and maximum payloads. This optimization involves the use of the most effective shielding material, square cross-section geometry with rounded corners and tapered neutron shielding sections in the non-fuel regions.

Boshoven, J.K.

1992-08-01T23:59:59.000Z

175

Criticality safety and shielding design issues in the development of a high-capacity cask for truck transport  

Science Conference Proceedings (OSTI)

General Atomics (GA) will be submitting an application for certification to the US Nuclear Regulatory Commission (NRC) for the GA-4 and GA-9 Casks In 1992. The GA-4 and GA-9 Casks are high-capacity legal weight truck casks designed to transport light water reactor spent fuel assemblies. To maintain a capacity of four pressurized-water-reactor (PWR) spent fuel assemblies, the GA-4 Cask uses burnup credit as part of the criticality control for initial enrichments over 3.0 wt% U-235. Using the US Department of Energy (DOE) Burnup Credit Program as a basis, GA has performed burnup credit analysis which is included in the Safety Analysis Report for Packaging (SARP). The GA-9 Cask can meet the criticality safety requirements using the fresh fuel'' assumption. Our approach to shielding design is to optimize the GA-4 and GA-9 Cask shielding configurations for minimum weights and maximum payloads. This optimization involves the use of the most effective shielding material, square cross-section geometry with rounded corners and tapered neutron shielding sections in the non-fuel regions.

Boshoven, J.K.

1992-01-01T23:59:59.000Z

176

A comparison of spent fuel shipping cask response to 10 CFR 71 normal conditions and realistic hot day extremes  

SciTech Connect

The structural properties of spent nuclear fuel shipping containers vary as a function of the cask wall temperature. An analysis is performed to determine the effect of a realistic, though bounding, hot day environment on the thermal behavior of spent fuel shipping casks. These results are compared to those which develop under a steady-state application of the prescribed normal thermal conditions of 10CFR71. The completed analysis revealed that the majority of wall temperatures, for a wide variety of spent fuel shipping cask configurations, fall well below those predicted by using the steady-state application of the regulatory boundary conditions. It was found that maximum temperatures at the cask surface occasionally lie above temperatures predicted under the regulatory condition. This is due to the conservative assumptions present in the ambient conditions used. The analysis demonstrates that diurnal temperature variations which penetrate the cask wall have maxima substantially less than the corresponding temperatures obtained when applying the steady-state regulatory boundary conditions. Therefore, it is certain that vital cask components and the spent fuel itself will not exceed the temperatures calculated by use of the steady-state interpretation of the 10CFR71 normal conditions.

Manson, S.J. [Texas Univ., Austin, TX (United States). Coll. of Engineering; Gianoulakis, S.E. [Sandia National Labs., Albuquerque, NM (United States)

1994-02-01T23:59:59.000Z

177

HI-STAR 100 Spent Fuel Transport Cask Analytical Evaluation for Drop Events  

Science Conference Proceedings (OSTI)

The U.S. Nuclear Regulatory Commission (NRC) is responsible for licensing commercial spent nuclear fuel transported in casks certified by NRC under the Code of Federal Regulations (CFR), Title 10, Part 71 [1]. Both the International Atomic Energy Agency (IAEA) regulations for transporting radioactive materials [2, paragraph 727], and 10 CFR 71.73 require casks to be evaluated for hypothetical accident conditions, which includes a 9-meter (m) (30-ft) drop impact event on a flat, essentially unyielding, horizontal surface, in the most damaging orientation. This paper examines the behavior of one of the NRC-certified transportation casks, the HI-STAR 100 [3], for drop impact events. The specific area examined is the behavior of the bolted connections in the “overpack” top flange and the closure plate, which are significantly loaded during the hypothetical drop impact event. The term “overpack” refers to the cask that receives and contains a sealed multi-purpose canister (MPC) containing spent nuclear fuel. The analytical work to evaluate the NRC-certified HI-STAR 100 spent fuel transport cask [3] for a 9-m (30-ft) drop impact event on a flat, unyielding, horizontal surface, was performed using the ANSYS® [4] and LS DYNA™ [5] finite-element analysis codes. The models were sufficiently detailed, in the areas of bolt closure interfaces and containment boundaries, to evaluate the structural integrity of the bolted connections under 9-m (30-ft) free-drop hypothetical accident conditions, as specified in 10 CFR 71.73. Evaluation of the cask for puncture, caused by a free-drop through a distance of 1-m (40-in.) onto a mild steel bar mounted on a flat, essentially unyielding, horizontal surface, required by 10 CFR 71.73, was not included in the current work, and will have to be addressed in the future. Based on the analyses performed to date, it is concluded that, even though brief separation of the flange and the closure plate surfaces may occur, the seals would close at the end of the drop events, because the materials remain elastic during the duration of the event.

Shah, M. J.; Klymyshyn, Nicholas A.; Adkins, Harold E.; Koeppel, Brian J.

2007-03-30T23:59:59.000Z

178

WIPP Remote Handled Waste Facility: Performance Dry Run Operations  

SciTech Connect

The Remote Handled (RH) TRU Waste Handling Facility at the Waste Isolation Pilot Plant (WIPP) was recently upgraded and modified in preparation for handling and disposal of RH Transuranic (TRU) waste. This modification will allow processing of RH-TRU waste arriving at the WIPP site in two different types of shielded road casks, the RH-TRU 72B and the CNS 10-160B. Washington TRU Solutions (WTS), the WIPP Management and Operation Contractor (MOC), conducted a performance dry run (PDR), beginning August 19, 2002 and successfully completed it on August 24, 2002. The PDR demonstrated that the RHTRU waste handling system works as designed and demonstrated the handling process for each cask, including underground disposal. The purpose of the PDR was to develop and implement a plan that would define in general terms how the WIPP RH-TRU waste handling process would be conducted and evaluated. The PDR demonstrated WIPP operations and support activities required to dispose of RH-TRU waste in the WIPP underground.

Burrington, T. P.; Britain, R. M.; Cassingham, S. T.

2003-02-24T23:59:59.000Z

179

Spent fuel drying system test results (first dry-run)  

DOE Green Energy (OSTI)

The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site. Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 7.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the first dry-run test, which was conducted without a fuel element. The empty test apparatus was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The data from this dry-run test can serve as a baseline for the first two fuel element tests, 1990 (Run 1) and 3128W (Run 2). The purpose of this dry-run was to establish the background levels of hydrogen in the system, and the hydrogen generation and release characteristics attributable to the test system without a fuel element present. This test also serves to establish the background levels of water in the system and the water release characteristics. The system used for the drying test series was the Whole Element Furnace Testing System, described in Section 2.0, which is located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodology are given in section 3.0, and the experimental results provided in Section 4.0. These results are further discussed in Section 5.0.

Klinger, G.S.; Oliver, B.M.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J.; Ritter, G.A.

1998-07-01T23:59:59.000Z

180

Carlsbad Area Office unveils full-scale model of new WIPP waste transportation cask  

NLE Websites -- All DOE Office Websites (Extended Search)

Carlsbad Area Office Unveils Full-Scale Model Carlsbad Area Office Unveils Full-Scale Model Of New WIPP Waste Transportation Cask CARLSBAD, N.M., February 23, 2000 - The U.S. Department of Energy's (DOE) Carlsbad Area Office today unveiled a full-scale model of its newest waste transportation cask, the RH-72B, during a ceremony at the local DOE offices. "This is another milestone for the Department of Energy," said Dr. Inés Triay, Manager of the Carlsbad Area Office, describing the importance of the new container for those attending the ceremony. "After we receive approval from the U.S. Nuclear Regulatory Commission (NRC), we plan to add the RH-72B to our fleet, which will help the Department meet its continuing mission to remove transuranic waste from the accessible environment and

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


181

Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters |  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Data Report on Corrosion Testing of Stainless Steel SNF Storage Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters Data Report on Corrosion Testing of Stainless Steel SNF Storage Canisters The report assesses the localized corrosion performance of container/cask materials used in the interim storage of used nuclear fuel. A detailed evaluation of the storage system environment, including uncertainties in temperature, humidity, and sea and continental salt occurrence is provided, and the potential impacts on corrosion are discussed. Initial results from a sampling program of in situ dust deposits on in-service storage canisters are provided. The results of dust deliquescence testing, to evaluate potential stifling of corrosion due the limited mass of the deposited salts, are presented. CorrosionTestStainlessSteelSNFStorContainer.pdf

182

STRUCTURAL ANALYSES OF FUEL CASKS SUBJECTED TO BOLT PRELOAD, INTERNAL PRESSURE AND SEQUENTIAL DYNAMIC IMPACTS  

Science Conference Proceedings (OSTI)

Large fuel casks subjected to the combined loads of closure bolt tightening, internal pressure and sequential dynamic impacts present challenges when evaluating their performance in the Hypothetical Accident Conditions (HAC) specified in the Code of Federal Regulations Title 10 Part 71 (10CFR71). Testing is often limited by cost, difficulty in preparing test units and the limited availability of facilities which can carry out such tests. In the past, many casks were evaluated without testing by using simplified analytical methods. In addition, there are no realistic analyses of closure bolt stresses for HAC conditions reported in the open literature. This paper presents a numerical technique for analyzing the accumulated damages of a large fuel cask caused by the sequential loads of the closure bolt tightening and the internal pressure as well as the drop and crash dynamic loads. The bolt preload and the internal pressure are treated as quasi-static loads so that the finite element method with explicit numerical integration scheme based on the theory of wave propagation can be applied. The dynamic impacts with short durations such as the 30-foot drop and the 40-inch puncture for the hypothetical accident conditions specified in 10CFR71 are also analyzed by using the finite-element method with explicit numerical integration scheme.

Wu, T

2009-06-25T23:59:59.000Z

183

Fire tests and analyses of a rail cask-sized calorimeter.  

Science Conference Proceedings (OSTI)

Three large open pool fire experiments involving a calorimeter the size of a spent fuel rail cask were conducted at Sandia National Laboratories Lurance Canyon Burn Site. These experiments were performed to study the heat transfer between a very large fire and a large cask-like object. In all of the tests, the calorimeter was located at the center of a 7.93-meter diameter fuel pan, elevated 1 meter above the fuel pool. The relative pool size and positioning of the calorimeter conformed to the required positioning of a package undergoing certification fire testing. Approximately 2000 gallons of JP-8 aviation fuel were used in each test. The first two tests had relatively light winds and lasted 40 minutes, while the third had stronger winds and consumed the fuel in 25 minutes. Wind speed and direction, calorimeter temperature, fire envelop temperature, vertical gas plume speed, and radiant heat flux near the calorimeter were measured at several locations in all tests. Fuel regression rate data was also acquired. The experimental setup and certain fire characteristics that were observed during the test are described in this paper. Results from three-dimensional fire simulations performed with the Cask Analysis Fire Environment (CAFE) fire code are also presented. Comparisons of the thermal response of the calorimeter as measured in each test to the results obtained from the CAFE simulations are presented and discussed.

Figueroa, Victor G.; Lopez, Carlos; Suo-Anttila, Ahti Jorma (Computational Engineering Analysis LLC, Albuquerque, NM); Greiner, Miles (University of Nevada, Reno, Reno, NV)

2010-10-01T23:59:59.000Z

184

A comparison of spent fuel shipping cask response to 10 CFR 71 normal conditions and realistic hot day extremes  

SciTech Connect

An examination of the effect of a realistic (though conservative) hot day environment on the thermal transient behavior of spent fuel shipping casks is made. These results are compared to those that develop under the prescribed normal thermal condition of 10 CFR 71. Of specific concern are the characteristics of propagating thermal waves, which are set up by diurnal variations of temperature and insolation in the outdoor environment. In order to arrive at a realistic approximation of these variations on a conservative hot day, actual temperature and insolation measurements have been obtained from the National Climatic Data Center (NCDC) for representatively hot and high heat flux days. Thus, the use of authentic meteorological data ensures the realistic approach sought. Further supporting the desired realism of the modeling effort is the use of realistic cask configurations in which multiple laminations of structural, shielding, and other materials are expected to attenuate the propagating thermal waves. The completed analysis revealed that the majority of wall temperatures, for a wide variety of spent fuel shipping cask configurations, fall well below those predicted by enforcement of the regulatory environmental conditions of 10 CFR 71. It was found that maximum temperatures at the cask surface occasionally lie above temperatures predicted under the prescribed regulatory conditions. However, the temperature differences are small enough that the normal conservative assumptions that are made in the course of typical cask evaluations should correct for any potential violations. The analysis demonstrates that diurnal temperature variations that penetrate the cask wall all have maxima substantially less than the corresponding regulatory solutions. Therefore it is certain that vital cask components and the spent fuel itself will not exceed the temperatures calculated by use of the conditions of 10 CFR 71.

Manson, S.J.; Gianoulakis, S.E. [Sandia National Labs., Albuquerque, NM (United States). Transportation Systems Development Dept.

1994-04-01T23:59:59.000Z

185

Glossary Term - Dry Ice  

NLE Websites -- All DOE Office Websites (Extended Search)

Deuteron Previous Term (Deuteron) Glossary Main Index Next Term (Electron) Electron Dry Ice A block of dry ice sublimating on a table. Dry ice is the solid form of carbon dioxide...

186

Cold Vacuum Drying (CVD) Facility General Service Helium System Design Description  

DOE Green Energy (OSTI)

This document describes the Cold Vacuum Drying Facility general service helium system (GSHe). The GSHe is a general service facility process support system, but does include safety-class systems, structures and components providing protection to the offsite public. The GSHe also performs safety-significant functions that provide protection to onsite workers. The GSHe essential function is to provide helium to support process functions during all phases of facility operations. GSHe helium is used to purge the cask and the MCO in order to maintain their internal atmospheres below hydrogen flammability concentrations. The GSHe also supplies helium to purge the PWC lines and components and the VPS vacuum pump.

FARWICK, C.C.

1999-07-06T23:59:59.000Z

187

NRC ISSUES REPORT FOR COMMENT ON SPENT NUCLEAR FUEL TRANSPORTATION CASK RESPONSE TO CALDECOTT TUNNEL FIRE SCENARIO  

E-Print Network (OSTI)

The Nuclear Regulatory Commission is seeking public comment on a study of how a truck cask for transporting spent nuclear fuel might perform in a severe tunnel fire. The report models the performance of the NAC International Model LWT (NAC) spent fuel cask under the conditions of the April 1982 fire in the Caldecott highway tunnel near Oakland, Calif., when a gasoline tanker carrying 8,800 gallons of gasoline overturned and caught fire. Severe, intense fires such as the Caldecott fire are extremely rare. However, they provide an opportunity to study how transportation packages might perform under very severe accident conditions. The results of this study strongly indicate that any radioactive release from the NAC model or a similar spent fuel shipping cask involved in a severe tunnel fire such as that of the Caldecott highway tunnel accident would be within regulatory limits. The peak internal temperatures predicted for the NAC cask in the analysis of the Caldecott fire scenario were not high enough to result in rupture of the fuel cladding (protective metal tubing around the fuel). Therefore, it would not be expected that any radioactive material (including spent nuclear fuel particles or fission products) would be released from the fuel rods. The maximum cask temperatures experienced around the lid, vent and drain ports exceeded the

unknown authors

2006-01-01T23:59:59.000Z

188

Flash drying protects standby plants  

Science Conference Proceedings (OSTI)

This article describes how special fast-drying technique provides effective corrosion protection for units that will be in standby for a short time. The Jacksonville Electric Authority (JEA) has developed a technique for rapidly drying out its boilers as an effective corrosion prevention measure, even for units which will be out of service for a short time. The JEA has several steam generating units that are not in continual service. These units, whether on standby or in extended cold storage, must be maintained if they are to operate reliably when they are needed. JEA uses dehumidification as the primary method to reduce corrosion in these standby units. Engineers at JEA believe it is better to reduce the amount of water retained in standby boilers than to add inhibiting chemicals to retained water for corrosion protection.

Mallard, R.E.

1996-08-01T23:59:59.000Z

189

Spent Nuclear Fuel (SNF) Project Cask and MCO Helium Purge System Design Review Completion Report Project A.5 and A.6  

SciTech Connect

This report documents the results of the design verification performed on the Cask and Multiple Canister Over-pack (MCO) Helium Purge System. The helium purge system is part of the Spent Nuclear Fuel (SNF) Project Cask Loadout System (CLS) at 100K area. The design verification employed the ''Independent Review Method'' in accordance with Administrative Procedure (AP) EN-6-027-01.

ARD, K.E.

2000-04-19T23:59:59.000Z

190

Hydrogen Storage  

Science Conference Proceedings (OSTI)

Applied Neutron Scattering in Engineering and Materials Science Research: Hydrogen Storage Sponsored by: Metallurgical Society of the Canadian Institute of ...

191

Industry Spent Fuel Storage Handbook  

Science Conference Proceedings (OSTI)

The Industry Spent Fuel Storage Handbook (8220the Handbook8221) addresses the relevant aspects of at-reactor spent (or used) nuclear fuel (SNF) storage in the United States. With the prospect of SNF being stored at reactor sites for the foreseeable future, it is expected that all U.S. nuclear power plants will have to implement at-reactor dry storage by 2025 or shortly thereafter. The Handbook provides a broad overview of recent developments for storing SNF at U.S. reactor sites, focusing primarily on at...

2010-07-29T23:59:59.000Z

192

Stacker-reclaimer scheduling in a dry bulk terminal  

Science Conference Proceedings (OSTI)

A dry bulk terminal acts as a multi-modal interface for transhipping iron ores. Stacker-reclaimers are the dedicated equipments in storage yard for iron ore handling. Both unloading and loading processes are supported by stacker-reclaimers in most cases. ... Keywords: dry bulk terminal, genetic algorithm, lower bound, stacker-reclaimer scheduling

Dayong Hu; Zhenqiang Yao

2012-11-01T23:59:59.000Z

193

Advances in solar assisted drying systems for agricultural produce  

Science Conference Proceedings (OSTI)

The technical directions in the development of solar assisted drying systems system for agricultural produce are compact collector design, high efficiency, integrated storage, and long-life drying system. Air based solar collectors are not the only available ... Keywords: V-groove solar collector, double-pass solar collector, photovoltaic thermal collectors, solar assisted chemical heat pump system, solar dehumidification system

Kamaruzzaman Sopian; Mohd Yusof Sulaiman; Mohd Yusof Othman; Sohif Mat; Muhamad Yahya; Mohamad A. Alghoul; Baharudin Ali; Lim Chin Haw; Mohd Hafidz Ruslan; Azami Zaharim

2009-02-01T23:59:59.000Z

194

Modified horizontal solar collector for low temperature grain drying  

DOE Green Energy (OSTI)

The project consisted of constructing a horizontal solar collector with a small amount of rock storage integrated into the collector air stream. The collected energy was used to dry corn in a 6000 bushel low-temperature drying facility. The collector proved to be economically feasible to build and collected sufficient energy to show a reasonable return on the investment.

None

1980-01-27T23:59:59.000Z

195

NETL: Carbon Storage - Geologic Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Geologic Storage Geologic Storage Carbon Storage Geologic Storage Focus Area Geologiccarbon dioxide (CO2) storage involves the injection of supercritical CO2 into deep geologic formations (injection zones) overlain by competent sealing formations and geologic traps that will prevent the CO2 from escaping. Current research and field studies are focused on developing better understanding 11 major types of geologic storage reservoir classes, each having their own unique opportunities and challenges. Understanding these different storage classes provides insight into how the systems influence fluids flow within these systems today, and how CO2 in geologic storage would be anticipated to flow in the future. The different storage formation classes include: deltaic, coal/shale, fluvial, alluvial, strandplain, turbidite, eolian, lacustrine, clastic shelf, carbonate shallow shelf, and reef. Basaltic interflow zones are also being considered as potential reservoirs. These storage reservoirs contain fluids that may include natural gas, oil, or saline water; any of which may impact CO2 storage differently. The following summarizes the potential for storage and the challenges related to CO2 storage capability for fluids that may be present in more conventional clastic and carbonate reservoirs (saline water, and oil and gas), as well as unconventional reservoirs (unmineable coal seams, organic-rich shales, and basalts):

196

Baseline descriptions for LWR spent fuel storage, handling, and transportation  

SciTech Connect

Baseline descriptions for the storage, handling, and transportation of reactor spent fuel are provided. The storage modes described include light water reactor (LWR) pools, away-from-reactor basins, dry surface storage, reprocessing-facility interim storage pools, and deep geologic storage. Land and water transportation are also discussed. This work was sponsored by the Department of Energy/Office of Safeguards and Security as part of the Sandia Laboratories Fixed Facility Physical Protection Program. 45 figs, 4 tables.

Moyer, J.W.; Sonnier, C.S.

1978-04-01T23:59:59.000Z

197

Transfer Cask Assembly Onsite Transfer of K-Basin Fuel at Hanford  

DOE Green Energy (OSTI)

Packaging Technology, Inc. was awarded a contract for the design and fabrication of a unique 18.5-ton transportation system to be used on-site at Hanford, WA. Unique aspects include rectangular cask geometry, solid 7 inch-thick stainless steel construction, hinged lid with remotely operable quick release locking mechanism. The lid maintains shielding and material confinement integrity after hypothetical accident conditions, and is equipped with a hydrogen venting system. This paper presents how the project requirements were translated into a successful design, and includes a brief discussion of a confirmation test program.

BRUBAKER, M.L.

2002-07-01T23:59:59.000Z

198

Hot Dry Rock Geothermal Energy Development in the USA David Duchane and Donald Brown  

E-Print Network (OSTI)

utility options such as pumped storage or compressed air energy storage (CAES) is that the HDR power plant1 Hot Dry Rock Geothermal Energy Development in the USA by David Duchane and Donald Brown Los energy resources lies right beneath our feet in the form of hot dry rock (HDR), the common geologic

199

Testing of ethylene propylene seals for the GA-4/GA-9 casks  

SciTech Connect

The primary O-ring seal of the GA-4 and GA-9 casks was tested for leakage with a full-scale mockup of the cask lid and flange. Tests were performed at temperatures of ambient, {minus}41{degrees}, 121{degrees}, and 193{degrees}C. Shim plates between the lid and flange simulated gaps caused by thermal distortion. The testing used a helium mass spectrometer leak detector (MSLD). Results showed that the primary seal was leaktight for all test conditions. Helium permeation through the seal began in 13--23 minutes for the ambient tests and in 1--2 minutes for the tests at elevated temperatures. After each test several hours of the pumping were typically required to reduce the MSLD background reading to an acceptable level for the next test, indicating that the seal had become saturated with helium. To verify that the test results showed permeation and not real leakage, several response checks were conducted in which a calibrated leak source was inserted in the detector line near the seal. When the leak source was activated the detector responded within seconds.

Boonstra, R.H.

1993-08-01T23:59:59.000Z

200

Natural Gas Withdrawals from Underground Storage (Annual Supply &  

U.S. Energy Information Administration (EIA) Indexed Site

Citygate Price Residential Price Commercial Price Industrial Price Electric Power Price Gross Withdrawals Gross Withdrawals From Gas Wells Gross Withdrawals From Oil Wells Gross Withdrawals From Shale Gas Wells Gross Withdrawals From Coalbed Wells Repressuring Nonhydrocarbon Gases Removed Vented and Flared Marketed Production NGPL Production, Gaseous Equivalent Dry Production Imports By Pipeline LNG Imports Exports Exports By Pipeline LNG Exports Underground Storage Capacity Gas in Underground Storage Base Gas in Underground Storage Working Gas in Underground Storage Underground Storage Injections Underground Storage Withdrawals Underground Storage Net Withdrawals Total Consumption Lease and Plant Fuel Consumption Pipeline & Distribution Use Delivered to Consumers Residential Commercial Industrial Vehicle Fuel Electric Power Period: Monthly Annual

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


201

Injections of Natural Gas into Storage (Annual Supply & Disposition)  

U.S. Energy Information Administration (EIA) Indexed Site

Citygate Price Residential Price Commercial Price Industrial Price Electric Power Price Gross Withdrawals Gross Withdrawals From Gas Wells Gross Withdrawals From Oil Wells Gross Withdrawals From Shale Gas Wells Gross Withdrawals From Coalbed Wells Repressuring Nonhydrocarbon Gases Removed Vented and Flared Marketed Production NGPL Production, Gaseous Equivalent Dry Production Imports By Pipeline LNG Imports Exports Exports By Pipeline LNG Exports Underground Storage Capacity Gas in Underground Storage Base Gas in Underground Storage Working Gas in Underground Storage Underground Storage Injections Underground Storage Withdrawals Underground Storage Net Withdrawals Total Consumption Lease and Plant Fuel Consumption Pipeline & Distribution Use Delivered to Consumers Residential Commercial Industrial Vehicle Fuel Electric Power Period: Monthly Annual

202

Energy Storage  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

National Laboratories September 27, 2007 San Francisco, CA PEER REVIEW 2007 DOE(SNL)CEC Energy Storage Program FYO7 Projects Sandia is a multiprogram laboratory operated by...

203

Actinide partitioning-transmutation program. V. Preconceptual designs and costs of partitioning facilities and shipping casks, Appendix 4. Final report  

SciTech Connect

This Appendix contains cost estimate documents for the Fuels Fabrication Plant Waste Treatment Facility. Plant costs are summarized by Code of Accounts and by Process Function. Costs contributing to each account are detailed. Process equipment costs are detailed for each Waste Treatment Process. Service utility costs are also summarized and detailed. Shipping cask costs are provided.

Not Available

1980-06-01T23:59:59.000Z

204

NGLW RCRA Storage Study  

Science Conference Proceedings (OSTI)

The Idaho Nuclear Technology and Engineering Center (INTEC) at the Idaho National Engineering and Environmental Laboratory contains radioactive liquid waste in underground storage tanks at the INTEC Tank Farm Facility (TFF). INTEC is currently treating the waste by evaporation to reduce the liquid volume for continued storage, and by calcination to reduce and convert the liquid to a dry waste form for long-term storage in calcine bins. Both treatment methods and activities in support of those treatment operations result in Newly Generated Liquid Waste (NGLW) being sent to TFF. The storage tanks in the TFF are underground, contained in concrete vaults with instrumentation, piping, transfer jets, and managed sumps in case of any liquid accumulation in the vault. The configuration of these tanks is such that Resource Conservation and Recovery Act (RCRA) regulations apply. The TFF tanks were assessed several years ago with respect to the RCRA regulations and they were found to be deficient. This study considers the configuration of the current tanks and the RCRA deficiencies identified for each. The study identifies four potential methods and proposes a means of correcting the deficiencies. The cost estimates included in the study account for construction cost; construction methods to minimize work exposure to chemical hazards, radioactive contamination, and ionizing radiation hazards; project logistics; and project schedule. The study also estimates the tank volumes benefit associated with each corrective action to support TFF liquid waste management planning.

R. J. Waters; R. Ochoa; K. D. Fritz; D. W. Craig

2000-06-01T23:59:59.000Z

205

Experimental and theoretical performances of a solar assisted dehumidification system for drying centella asiatica L  

Science Conference Proceedings (OSTI)

A solar assisted dehumidification system has been designed, fabricated, and evaluated. The main components of the drying system consist of a solar collector, an energy storage tank, an auxiliary heater, two blowers, two adsorber columns, two water-air ... Keywords: dehumidification, drying of centella asiatica L, performance of the drying system

M. Yahya; K. Sopian; W. R. W. Daud; M. Y. Othman; B. Yatim; M. A. Alghoul; A. Zaharim

2008-11-01T23:59:59.000Z

206

EVALUATION OF A SULFUR OXIDE CHEMICAL HEAT STORAGE PROCESS FOR A STEAM SOLAR ELECTRIC PLANT  

E-Print Network (OSTI)

10. The Parallel Power Plant. III. NIGHTTIME OPERATION: A.~. W. , "Dry Cooling Tower Power Plant Design SpecificationsSUMMARY OF COSTS 1. Entire Power Plant--Storage System. · ·

Dayan, J.

2011-01-01T23:59:59.000Z

207

Shielding analysis of the TRUPACT-series casks for transportation of Hanford HLW  

SciTech Connect

In this paper, the authors propose the possibility of utilizing the TRUPACT-series casks for the transportation of high-level waste (HLW) from the Hanford reservation. The configurations of the TRUPACT series are a rectangular parallelepiped and a right circular cylinder, which are the TRUPACT-1 and -11, respectively. The TRUPACT series was designed as a type B contact-handled transuranic (CH-TRU) waste transportation system for use in Waste Isolation Pilot Plant-related operations and was subjected to type B container accident tests, which it successfully passed. Thus from a safety standpoint, the TRUPACT series is provided with double containment, impact limitation, and fire-retardant capabilities. However, the shielding analysis has shown the major modifications are required to allow for the transport of even a reasonable fraction of Hanford HLW.

Banjac, V.; Sanchez, P.E.; Hills, C.R.; Heger, A.S. (Univ. of New Mexico, Albuquerque, NM (United States))

1993-01-01T23:59:59.000Z

208

Cooperative Project on Burnup Credit--Data and Analysis for Spent Nuclear Fuel Transport and Storage in Burnup Credit Casks  

Science Conference Proceedings (OSTI)

A key part of EPRI's research is directed towards assuring efficient and effective management of spent nuclear fuel (SNF) from commercial nuclear power plants. A summary of the 2005 burnup-credit-related activities jointly sponsored by the U.S. Department of Energy Office of National Transportation, the U.S. Nuclear Regulatory Commission, and the Electric Power Research Institute (EPRI) is presented. A simple, but straightforward, approach for quantifying the benefits of PWR fission product burnup credit...

2005-12-22T23:59:59.000Z

209

Silo Storage Preconceptual Design  

Science Conference Proceedings (OSTI)

The National Nuclear Security Administration (NNSA) has a need to develop and field a low-cost option for the long-term storage of a variety of radiological material. The storage option’s primary requirement is to provide both environmental and physical protection of the materials. Design criteria for this effort require a low initial cost and minimum maintenance over a 50-year design life. In 1999, Argonne National Laboratory-West was tasked with developing a dry silo storage option for the BN-350 Spent Fuel in Aktau Kazakhstan. Argon’s design consisted of a carbon steel cylinder approximately 16 ft long, 18 in. outside diameter and 0.375 in. wall thickness. The carbon steel silo was protected from corrosion by a duplex coating system consisting of zinc and epoxy. Although the study indicated that the duplex coating design would provide a design life well in excess of the required 50 years, the review board was concerned because of the novelty of the design and the lack of historical use. In 2012, NNSA tasked Idaho National Laboratory (INL) with reinvestigating the silo storage concept and development of alternative corrosion protection strategies. The 2012 study, “Silo Storage Concepts, Cathodic Protection Options Study” (INL/EST-12-26627), concludes that the option which best fits the design criterion is a passive cathotic protection scheme, consisting of a carbon steel tube coated with zinc or a zinc-aluminum alloy encapsulated in either concrete or a cement grout. The hot dipped zinc coating option was considered most efficient, but the flame-sprayed option could be used if a thicker zinc coating was determined to be necessary.

Stephanie L. Austad; Patrick W. Bragassa; Kevin M Croft; David S Ferguson; Scott C Gladson; Annette L Shafer; John H Weathersby

2012-09-01T23:59:59.000Z

210

Hydrogen Storage  

Fuel Cell Technologies Publication and Product Library (EERE)

This 2-page fact sheet provides a brief introduction to hydrogen storage technologies. Intended for a non-technical audience, it explains the different ways in which hydrogen can be stored, as well a

211

Energy Storage  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Advanced Development Concept Nitrogen-Air Battery F.M. Delnick, D. Ingersoll, K.Waldrip Sandia National Laboratories Albuquerque, NM presented to U.S. DOE Energy Storage Systems...

212

Permitting plan for the high-level waste interim storage  

SciTech Connect

This document addresses the environmental permitting requirements for the transportation and interim storage of solidified high-level waste (HLW) produced during Phase 1 of the Hanford Site privatization effort. Solidified HLW consists of canisters containing vitrified HLW (glass) and containers that hold cesium separated during low-level waste pretreatment. The glass canisters and cesium containers will be transported to the Canister Storage Building (CSB) in a U.S. Department of Energy (DOE)-provided transportation cask via diesel-powered tractor trailer. Tri-Party Agreement (TPA) Milestone M-90 establishes a new major milestone, and associated interim milestones and target dates, governing acquisition and/or modification of facilities necessary for: (1) interim storage of Tank Waste Remediation Systems (TWRS) immobilized HLW (IHLW) and other canistered high-level waste forms; and (2) interim storage and disposal of TWRS immobilized low-activity tank waste (ILAW). An environmental requirements checklist and narrative was developed to identify the permitting path forward for the HLW interim storage (HLWIS) project (See Appendix B). This permitting plan will follow the permitting logic developed in that checklist.

Deffenbaugh, M.L.

1997-04-23T23:59:59.000Z

213

Transporting Dry Ice  

NLE Websites -- All DOE Office Websites (Extended Search)

Requirements for Shipping Dry Ice IATA PI 904 Source: Reg of the Day from ERCweb 2006 Environmental Resource Center | 919-469-1585 | webmaster@ercweb.com http:...

214

SRTC criticality safety technical review: Phase 1 criticality analysis for the 9972-9975 family of shipping casks: (SRT-CMA-940003)  

SciTech Connect

Review of SRT-CMA-940003, ``Phase I Criticality Analysis For The 9972-9975 Family Of Shipping Casks (U). (SRT-CMA-940003).`` January 22, 1994, has been performed by the SRTC Applied Physics Group. The NCSE is a criticality assessment of the 9972-9975 family of shipping casks. This work is a follow-on of a previous criticality safety evaluation, with the differences between this and the previous evaluation are that now wall tolerances are modeled and more sophisticated analytical methods are applied. The NCSE under review concludes that, with one exception, the previously specified plutonium and uranium mass limits for 9972-9975 family of shipping casks do ensure that WSRC Nuclear Criticality Safety Manual requirements (ref. 1) are satisfied. The one exception is that the plutonium mass limit for the 9974 cask had to be reduced from 4.4 to 4.3 kg. In contrast, the 7.5 kg uranium mass limit for the 9974 cask was raised to 14.5 kg, making the uranium mass identical for all casks in this family. This technical review consisted of an independent check of the methods and models employed, application of ANSI/ANS 8.1 and 8.15, and verification of WSRC Nuclear Criticality Safety Manual procedures.

Rathbun, R.

1994-03-02T23:59:59.000Z

215

DUF6 Storage Safety  

NLE Websites -- All DOE Office Websites (Extended Search)

Storage Safety Depleted UF6 Storage line line How DUF6 is Stored Where DUF6 is Stored DUF6 Storage Safety Cylinder Leakage Depleted UF6 Storage Safety Continued cylinder storage is...

216

DRY TRANSFER FACILITY CRITICALITY SAFETY CALCULATIONS  

SciTech Connect

This design calculation updates the previous criticality evaluation for the fuel handling, transfer, and staging operations to be performed in the Dry Transfer Facility (DTF) including the remediation area. The purpose of the calculation is to demonstrate that operations performed in the DTF and RF meet the nuclear criticality safety design criteria specified in the ''Project Design Criteria (PDC) Document'' (BSC 2004 [DIRS 171599], Section 4.9.2.2), the nuclear facility safety requirement in ''Project Requirements Document'' (Canori and Leitner 2003 [DIRS 166275], p. 4-206), the functional/operational nuclear safety requirement in the ''Project Functional and Operational Requirements'' document (Curry 2004 [DIRS 170557], p. 75), and the functional nuclear criticality safety requirements described in the ''Dry Transfer Facility Description Document'' (BSC 2005 [DIRS 173737], p. 3-8). A description of the changes is as follows: (1) Update the supporting calculations for the various Category 1 and 2 event sequences as identified in the ''Categorization of Event Sequences for License Application'' (BSC 2005 [DIRS 171429], Section 7). (2) Update the criticality safety calculations for the DTF staging racks and the remediation pool to reflect the current design. This design calculation focuses on commercial spent nuclear fuel (SNF) assemblies, i.e., pressurized water reactor (PWR) and boiling water reactor (BWR) SNF. U.S. Department of Energy (DOE) Environmental Management (EM) owned SNF is evaluated in depth in the ''Canister Handling Facility Criticality Safety Calculations'' (BSC 2005 [DIRS 173284]) and is also applicable to DTF operations. Further, the design and safety analyses of the naval SNF canisters are the responsibility of the U.S. Department of the Navy (Naval Nuclear Propulsion Program) and will not be included in this document. Also, note that the results for the Monitored Geologic Repository (MGR) Site specific Cask (MSC) calculations are limited to the specific design chosen (see Assumption 3.4). A more current design will be included in the next revision of the criticality calculations for the Aging Facility. In addition, this calculation is valid for the current design as provided in Attachment III of the DTF and may not reflect the ongoing design evolution of the facility. However, it is anticipated that design changes to the facility layout will have little or no impact on the criticality results and/or conclusions presented in this document.

C.E. Sanders

2005-05-17T23:59:59.000Z

217

Hydrogen Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Objectives - Develop and verify: On-board hydrogen storage systems achieving: 1.5 kWhkg (4.5 wt%), 1.2 kWhL, and 6kWh by 2005 2 kWhkg (6 wt%), 1.5 kWhL, and 4kWh by...

218

SUPERCONDUCTING MAGNETIC ENERGY STORAGE  

E-Print Network (OSTI)

Scale Superconducting Magnetic Energy Storage Plant", IEEEfor SlIperconducting Magnetic Energy Storage Unit", inSuperconducting Magnetic Energy Storage Plant, Advances in

Hassenzahl, W.

2011-01-01T23:59:59.000Z

219

SUPERCONDUCTING MAGNETIC ENERGY STORAGE  

E-Print Network (OSTI)

Superconducting 30-MJ Energy Storage Coil", Proc. 19 80 ASC,Superconducting Magnetic Energy Storage Plant", IEEE Trans.SlIperconducting Magnetic Energy Storage Unit", in Advances

Hassenzahl, W.

2011-01-01T23:59:59.000Z

220

AQUIFER THERMAL ENERGY STORAGE  

E-Print Network (OSTI)

aquifers for thermal energy storage. Problems outlined aboveModeling of Thermal Energy Storage in Aquifers," Proceed-ings of Aquifer Thermal Energy Storage Workshop, Lawrence

Tsang, C.-F.

2011-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


221

Storage | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Usage Storage Storage Energy storage isnt just for AA batteries. Thanks to investments from the Energy Department's Advanced Research...

222

AQUIFER THERMAL ENERGY STORAGE  

E-Print Network (OSTI)

using aquifers for thermal energy storage. Problems outlinedmatical Modeling of Thermal Energy Storage in Aquifers,"Proceed- ings of Aquifer Thermal Energy Storage Workshop,

Tsang, C.-F.

2011-01-01T23:59:59.000Z

223

FCT Hydrogen Storage: Contacts  

NLE Websites -- All DOE Office Websites (Extended Search)

Contacts to someone by E-mail Share FCT Hydrogen Storage: Contacts on Facebook Tweet about FCT Hydrogen Storage: Contacts on Twitter Bookmark FCT Hydrogen Storage: Contacts on...

224

Freeze drying method  

DOE Patents (OSTI)

The present invention provides methods and apparatus for freeze drying in which a solution, which can be a radioactive salt dissolved within an acid, is frozen into a solid on vertical plates provided within a freeze drying chamber. The solid is sublimated into vapor and condensed in a cold condenser positioned above the freeze drying chamber and connected thereto by a conduit. The vertical positioning of the cold condenser relative to the freeze dryer helps to help prevent substances such as radioactive materials separated from the solution from contaminating the cold condenser. Additionally, the system can be charged with an inert gas to produce a down rush of gas into the freeze drying chamber to also help prevent such substances from contaminating the cold condenser.

Coppa, Nicholas V. (Malvern, PA); Stewart, Paul (Youngstown, NY); Renzi, Ernesto (Youngstown, NY)

1999-01-01T23:59:59.000Z

225

Freeze drying apparatus  

Science Conference Proceedings (OSTI)

The present invention provides methods and apparatus for freeze drying in which a solution, which can be a radioactive salt dissolved within an acid, is frozen into a solid on vertical plates provided within a freeze drying chamber. The solid is sublimated into vapor and condensed in a cold condenser positioned above the freeze drying chamber and connected thereto by a conduit. The vertical positioning of the cold condenser relative to the freeze dryer helps to help prevent substances such as radioactive materials separated from the solution from contaminating the cold condenser. Additionally, the system can be charged with an inert gas to produce a down rush of gas into the freeze drying chamber to also help prevent such substances from contaminating the cold condenser.

Coppa, Nicholas V. (Malvern, PA); Stewart, Paul (Youngstown, NY); Renzi, Ernesto (Youngstown, NY)

2001-01-01T23:59:59.000Z

226

A validated methodology for evaluating burnup credit in spent fuel casks  

SciTech Connect

The concept of allowing reactivity credit for the transmuted state of spent fuel offers both economic and risk incentives. This paper presents a general overview of the technical work being performed in support of the US Department of Energy (DOE) program to resolve issues related to the implementation of burnup credit. An analysis methodology is presented along with information representing the validation of the method against available experimental data. The experimental data that are applicable to burnup credit include chemical assay data for the validation of the isotopic prediction models, fresh fuel critical experiments for the validation of criticality calculations for various cask geometries, and reactor restart critical data to validate criticality calculations with spent fuel. The methodology has been specifically developed to be simple and generally applicable, therefore giving rise to uncertainties or sensitivities which are identified and quantified in terms of a percent bias in k{sub eff}. Implementation issues affecting licensing requirements and operational procedures are discussed briefly. 24 refs., 3 tabs.

Brady, M.C. (Oak Ridge National Lab., TN (USA)); Sanders, T.L. (Sandia National Labs., Albuquerque, NM (USA))

1991-01-01T23:59:59.000Z

227

Energy Storage  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Daniel R. Borneo, PE Daniel R. Borneo, PE Sandia National Laboratories September 27, 2007 San Francisco, CA PEER REVIEW 2007 DOE(SNL)/CEC Energy Storage Program FYO7 Projects Sandia is a multiprogram laboratory operated by Sandia Corporation, a Lockheed Martin Company, for the United States Department of Energy under contract DE-AC04-94AL85000. 2 Presentation Outline * DOE(SNL)/CEC Collaboration - Background of DOE(SNL)/CEC Collaboration - FY07 Project Review * Zinc Bromine Battery (ZBB) Demonstration * Palmdale Super capacitor Demonstration * Sacramento Municipal Utility District (SMUD) Regional Transit (RT) Super capacitor demonstration * Beacon Flywheel Energy Storage System (FESS) 3 Background of DOE(SNL)/CEC Collaboration * Memorandum of Understanding Between CEC and DOE (SNL). - In Place since 2004

228

Energy Storage  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Development Concept Development Concept Nitrogen-Air Battery F.M. Delnick, D. Ingersoll, K.Waldrip Sandia National Laboratories Albuquerque, NM presented to U.S. DOE Energy Storage Systems Research Program Washington, DC November 2-4, 2010 Sandia National Laboratories is a multi-program laboratory operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin company, for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-AC04-94AL85000. Funded by the Energy Storage Systems Program of the U.S. Department Of Energy through Sandia National Laboratories Full Air Breathing Battery Concept * Concept is to use O 2 and N 2 as the electrodes in a battery * Novel because N 2 is considered inert * Our group routinely reacts N 2 electrochemically

229

NETL: Carbon Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Carbon Sequestration Partnerships Regional Carbon Sequestration Partnership (RCSP) Programmatic Points of Contact Carbon Storage Program Infrastructure Coordinator Carbon Storage...

230

Application-storage discovery  

Science Conference Proceedings (OSTI)

Discovering application dependency on data and storage is a key prerequisite for many storage optimization tasks such as data assignment to storage tiers, storage consolidation, virtualization, and handling unused data. However, in the real world these ... Keywords: enterprise storage, experimental evaluation, storage discovery

Nikolai Joukov; Birgit Pfitzmann; HariGovind V. Ramasamy; Murthy V. Devarakonda

2010-05-01T23:59:59.000Z

231

Dries Kimpe | Argonne National Laboratory  

NLE Websites -- All DOE Office Websites (Extended Search)

Publications View Publications Projects IOFSL: IO Forwarding Scalability Layer NoLoSS: Enabling Exascale Science through Node Local Storage Systems Novel Storage Architectures...

232

McGuire Dry Storage Bid Evaluation Status  

National Nuclear Security Administration (NNSA)

3 Motivation for Reviewing Data Motivation for Reviewing Data Internal Review of SNM Inventory of Record. Internal Review of SNM Inventory of Record. Complete QA validation of all...

233

Used Fuel and High-Level Radioactive Waste Extended Storage Collaboration Program  

Science Conference Proceedings (OSTI)

The Electric Power Research Institute (EPRI) convened a workshop of over 40 representatives of the nuclear industry, federal government, national laboratories, and suppliers of used-fuel dry-storage systems to discuss the potential issues associated with extended dry storage of used fuel, that is, storage considerably beyond the term of current and recently proposed U.S. Nuclear Regulatory Commission (NRC) regulations. The workshop was held November 18-19, 2009, at EPRI's offices in Washington, DC.

2010-03-02T23:59:59.000Z

234

Occupational dose estimates for a monitored retrievable storage facility  

SciTech Connect

Occupational doses were estimated for radiation workers at the monitored retrievable storage (MRS) facility. This study provides an estimate of the occupational dose based on the current MRS facility design, examines the extent that various design parameters and assumptions affect the dose estimates, and identifies the areas and activities where exposures can be reduced most effectively. Occupational doses were estimated for both the primary storage concept and the alternate storage concept. The dose estimates indicate the annual dose to all radiation workers will be below the 5 rem/yr federal dose equivalent limit. However, the estimated dose to most of the receiving and storage crew (the workers responsible for the receipt, storage, and surveillance of the spent fuel and its subsequent retrieval), to the crane maintenance technicians, and to the cold and remote maintenance technicians is above the design objective of 1 rem/yr. The highest annual dose is received by the riggers (4.7 rem) in the receiving and storage crew. An indication of the extent to which various design parameters and assumptions affect the dose estimates was obtained by changing various design-based assumptions such as work procedures, background dose rates in radiation zones, and the amount of fuel received and stored annually. The study indicated that a combination of remote operations, increased shielding, and additional personnel (for specific jobs) or changes in operating procedures will be necessary to reduce worker doses below 1.0 rem/yr. Operations that could be made at least partially remote include the removal and replacement of the tiedowns, impact limiters, and personnel barriers from the shipping casks and the removal or installation of the inner closure bolts. Reductions of the background dose rates in the receiving/shipping and the transfer/discharge areas may be accomplished with additional shielding.

Harty, R.; Stoetzel, G.A.

1986-06-01T23:59:59.000Z

235

CAPSIZE: A personal computer program and cross-section library for determining the shielding requirements, size, and capacity of shipping casks subject to various proposed objectives  

SciTech Connect

A new interactive program called CAPSIZE has been written for the IBM-PC to rapidly determine the likely impact that proposed design objectives might have on the size and capacity of spent fuel shipping casks designed to meet those objectives. Given the burnup of the spent fuel, its cooling time, the thickness of the internal basket walls, the desired external dose rate, and the nominal weight limit of the loaded cask, the CAPSIZE program will determine the maximum number of PWR fuel assemblies that may be shipped in a lead-, steel-, or uranium-shielded cask meeting those objectives. The necessary neutron and gamma shield thicknesses are determined by the program in such a way as to meet the specified external dose rate while simultaneously minimizing the overall weight of the loaded cask. The one-group cross-section library used in the CAPSIZE program has been distilled from the intermediate results of several hundred 1-D multigroaup discrete ordinates calculations for different types of casks. Neutron and gamma source terms, as well as the decay heat terms, are based on ORIGEN-S analyses of PWR fuel assemblies having exposures of 10, 20, 30, 40, 50, and 60 gigawatt days per metric tonne of initial heavy metal (GWD/MTIHM). In each case, values have been tabulated at 17 different decay times between 120 days and 25 years. Other features of the CAPSIZE program include a steady-state heat transfer calculation which will minimize the size and weight of external cooling fins, if and when such fins are required. Comparisons with previously reported results show that the CAPSIZE program can generally estimate the necessary neutron and gamma shield thicknesses to within 0.16 in. and 0.08 in., respectively. The corresponding cask weights have generally been found to be within 1000 lbs of previously reported results. 13 refs., 20 figs., 54 tabs.

Bucholz, J.A.

1987-05-01T23:59:59.000Z

236

Gas storage materials, including hydrogen storage materials  

DOE Patents (OSTI)

A material for the storage and release of gases comprises a plurality of hollow elements, each hollow element comprising a porous wall enclosing an interior cavity, the interior cavity including structures of a solid-state storage material. In particular examples, the storage material is a hydrogen storage material such as a solid state hydride. An improved method for forming such materials includes the solution diffusion of a storage material solution through a porous wall of a hollow element into an interior cavity.

Mohtadi, Rana F; Wicks, George G; Heung, Leung K; Nakamura, Kenji

2013-02-19T23:59:59.000Z

237

Dry piston coal feeder  

SciTech Connect

This invention provides a solids feeder for feeding dry coal to a pressurized gasifier at elevated temperatures substantially without losing gas from the gasifier by providing a lock having a double-acting piston that feeds the coals into the gasifier, traps the gas from escaping, and expels the trapped gas back into the gasifier.

Hathaway, Thomas J. (Belle Meade, NJ); Bell, Jr., Harold S. (Madison, NJ)

1979-01-01T23:59:59.000Z

238

Recycle Experience of Dismantled Cask Handling Crane by Surface Removal Sampling at Kori Unit No.1  

SciTech Connect

The Kori No.1, which began operation in 1978, replaced its cask handling crane in 2000. To prove the safety of recycling and reuse of crane scrap, a particular calculation method for surface contamination was used. Because surface radioactive contamination of steel is limited to a few-microns-thick layer, we can calculate the total(removable and fixed contamination) activity of the sample conservatively by this surface removal sampling means. If we multiply the ratio of total surface and the area of the selected surface by its activity, total activity of the scrap can be estimated. Conservatively, the sampled portion can be used as a representative sample of the scrap. Both the inner and outer part of the scrap was sampled separately, and gamma spectra were analyzed to check whether activation had occurred. Before sampling, the entire surface of the steel is scan surveyed by several kinds of GM and GP detectors. Contaminated parts were segregated, or decontaminated to the background. Almost one sample per one ton of steel was collected. Gamma spectra of 62 samples were analyzed by 100% efficiency HP Ge detector. Only 60Co was detected, and its highest activity was 0.01 Bq/g,. This level of activity is much lower than the ''clearance levels'' outlined in IAEA TecDoc-855.(4). The total alpha and total beta for 6 samples were measured in the laboratory by low background alpha, using a beta gas proportional counter. Activities were much lower than 0.005 Bq/g. A representative sample was taken from the complete mixture of 62 samples. Gamma activities of nuclides were measured to estimate the dose to the public. This study revealed that activities of nuclides were lower than 'clearance levels' if decontaminated until the lower limit of detection level of the portable field instrument. New surface removal sampling method was tested. This method allows us to easily calculate the specific activity for the solid material.

Kim, K. D.; Baeg, C. Y.; Son, J. K.; Kim, H. S.; Ha, J. A.; Song, M. J.

2002-02-25T23:59:59.000Z

239

Spent Fuel Drying System Test Results (Dry-Run in Preparation for Run 8)  

Science Conference Proceedings (OSTI)

The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 7.0) have been conducted by Pacific Northwest National Laboratory (PNNL)(a)on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of a test ''dry-run'' conducted prior to the eighth and last of those tests, which was conducted on an N-Reactor outer fuel element removed from K-West canister6513U. The system used for the dry-run test was the Whole Element Furnace Testing System, described in Section 2.0, located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodologies are given in Section 3.0. The experimental results are provided in Section 4.0 and discussed Section 5.0.

BM Oliver; GS Klinger; J Abrefah; SC Marschman; PJ MacFarlan; GA Ritter

1999-08-11T23:59:59.000Z

240

Microwavable thermal energy storage material  

DOE Patents (OSTI)

A microwavable thermal energy storage material is provided which includes a mixture of a phase change material and silica, and a carbon black additive in the form of a conformable dry powder of phase change material/silica/carbon black, or solid pellets, films, fibers, moldings or strands of phase change material/high density polyethylene/ethylene-vinyl acetate/silica/carbon black which allows the phase change material to be rapidly heated in a microwave oven. The carbon black additive, which is preferably an electrically conductive carbon black, may be added in low concentrations of from 0.5 to 15% by weight, and may be used to tailor the heating times of the phase change material as desired. The microwavable thermal energy storage material can be used in food serving applications such as tableware items or pizza warmers, and in medical wraps and garments.

Salyer, Ival O. (Dayton, OH)

1998-09-08T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


241

Microwavable thermal energy storage material  

DOE Patents (OSTI)

A microwavable thermal energy storage material is provided which includes a mixture of a phase change material and silica, and a carbon black additive in the form of a conformable dry powder of phase change material/silica/carbon black, or solid pellets, films, fibers, moldings or strands of phase change material/high density polyethylene/ethylene vinyl acetate/silica/carbon black which allows the phase change material to be rapidly heated in a microwave oven. The carbon black additive, which is preferably an electrically conductive carbon black, may be added in low concentrations of from 0.5 to 15% by weight, and may be used to tailor the heating times of the phase change material as desired. The microwavable thermal energy storage material can be used in food serving applications such as tableware items or pizza warmers, and in medical wraps and garments. 3 figs.

Salyer, I.O.

1998-09-08T23:59:59.000Z

242

FCT Hydrogen Storage: The 'National Hydrogen Storage Project...  

NLE Websites -- All DOE Office Websites (Extended Search)

The 'National Hydrogen Storage Project' to someone by E-mail Share FCT Hydrogen Storage: The 'National Hydrogen Storage Project' on Facebook Tweet about FCT Hydrogen Storage: The...

243

Review of Used Nuclear Fuel Storage and Transportation Technical Gap  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Analysis Analysis Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analysis While both wet and dry storage have been shown to be safe options for storing used nuclear fuel (UNF), the focus of the program is on dry storage of commercial UNF at reactor or centralized locations. This report focuses on the knowledge gaps concerning extended storage identified in numerous domestic and international investigations and provides the Used Fuel Disposition Campaign"s (UFDC) gap description, any alternate gap descriptions, the rankings by the various organizations, evaluation of the priority assignment, and UFDC-recommended action based on the comparison. Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analysis More Documents & Publications

244

Net Withdrawals of Natural Gas from Underground Storage (Summary)  

U.S. Energy Information Administration (EIA) Indexed Site

Pipeline and Distribution Use Price Citygate Price Residential Price Commercial Price Industrial Price Vehicle Fuel Price Electric Power Price Proved Reserves as of 12/31 Reserves Adjustments Reserves Revision Increases Reserves Revision Decreases Reserves Sales Reserves Acquisitions Reserves Extensions Reserves New Field Discoveries New Reservoir Discoveries in Old Fields Estimated Production Number of Producing Gas Wells Gross Withdrawals Gross Withdrawals From Gas Wells Gross Withdrawals From Oil Wells Gross Withdrawals From Shale Gas Wells Gross Withdrawals From Coalbed Wells Repressuring Nonhydrocarbon Gases Removed Vented and Flared Marketed Production Natural Gas Processed NGPL Production, Gaseous Equivalent Dry Production Imports By Pipeline LNG Imports Exports Exports By Pipeline LNG Exports Underground Storage Capacity Underground Storage Injections Underground Storage Withdrawals Underground Storage Net Withdrawals LNG Storage Additions LNG Storage Withdrawals LNG Storage Net Withdrawals Total Consumption Lease and Plant Fuel Consumption Lease Fuel Plant Fuel Pipeline & Distribution Use Delivered to Consumers Residential Commercial Industrial Vehicle Fuel Electric Power Period: Monthly Annual

245

Session: Hot Dry Rock  

DOE Green Energy (OSTI)

This session at the Geothermal Energy Program Review X: Geothermal Energy and the Utility Market consisted of four presentations: ''Hot Dry Rock - Summary'' by George P. Tennyson, Jr.; ''HDR Opportunities and Challenges Beyond the Long Term Flow Test'' by David V. Duchane; ''Start-Up Operations at the Fenton Hill HDR Pilot Plant'' by Raymond F. Ponden; and ''Update on the Long-Term Flow Testing Program'' by Donald W. Brown.

Tennyson, George P. Jr.; Duchane, David V.; Ponden, Raymond F.; Brown, Donald W.

1992-01-01T23:59:59.000Z

246

Drying of fiber webs  

DOE Patents (OSTI)

A process and an apparatus for high-intensity drying of fiber webs or sheets, such as newsprint, printing and writing papers, packaging paper, and paperboard or linerboard, as they are formed on a paper machine. The invention uses direct contact between the wet fiber web or sheet and various molten heat transfer fluids, such as liquified eutectic metal alloys, to impart heat at high rates over prolonged durations, in order to achieve ambient boiling of moisture contained within the web. The molten fluid contact process causes steam vapor to emanate from the web surface, without dilution by ambient air; and it is differentiated from the evaporative drying techniques of the prior industrial art, which depend on the uses of steam-heated cylinders to supply heat to the paper web surface, and ambient air to carry away moisture, which is evaporated from the web surface. Contact between the wet fiber web and the molten fluid can be accomplished either by submersing the web within a molten bath or by coating the surface of the web with the molten media. Because of the high interfacial surface tension between the molten media and the cellulose fiber comprising the paper web, the molten media does not appreciately stick to the paper after it is dried. Steam generated from the paper web is collected and condensed without dilution by ambient air to allow heat recovery at significantly higher temperature levels than attainable in evaporative dryers.

Warren, David W. (9253 Glenoaks Blvd., Sun Valley, CA 91352)

1997-01-01T23:59:59.000Z

247

Drying of fiber webs  

DOE Patents (OSTI)

A process and an apparatus are disclosed for high-intensity drying of fiber webs or sheets, such as newsprint, printing and writing papers, packaging paper, and paperboard or linerboard, as they are formed on a paper machine. The invention uses direct contact between the wet fiber web or sheet and various molten heat transfer fluids, such as liquefied eutectic metal alloys, to impart heat at high rates over prolonged durations, in order to achieve ambient boiling of moisture contained within the web. The molten fluid contact process causes steam vapor to emanate from the web surface, without dilution by ambient air; and it is differentiated from the evaporative drying techniques of the prior industrial art, which depend on the uses of steam-heated cylinders to supply heat to the paper web surface, and ambient air to carry away moisture, which is evaporated from the web surface. Contact between the wet fiber web and the molten fluid can be accomplished either by submersing the web within a molten bath or by coating the surface of the web with the molten media. Because of the high interfacial surface tension between the molten media and the cellulose fiber comprising the paper web, the molten media does not appreciatively stick to the paper after it is dried. Steam generated from the paper web is collected and condensed without dilution by ambient air to allow heat recovery at significantly higher temperature levels than attainable in evaporative dryers. 6 figs.

Warren, D.W.

1997-04-15T23:59:59.000Z

248

Occult Trucking and Storage  

E-Print Network (OSTI)

At least we used to. We are Occult Trucking and Storage andNOTHING. FLASHBACK -- OCCULT TRUCKING AND STORAGE DEPOT --I saw him. FLASHBACK - OCCULT TRUCKING AND STORAGE DEPOT -

Eyres, Jeffrey Paul

2011-01-01T23:59:59.000Z

249

Sorption Storage Technology Summary  

NLE Websites -- All DOE Office Websites (Extended Search)

Storage Technology Summary DOE H2 Storage Workshop, Feb 14-15, 2011, Washington, DC 1 Compressed & Cryo-Compressed Hydrogen Storage Workshop February 14 - 15, 2011, Washington, DC...

250

Seasonal thermal energy storage  

DOE Green Energy (OSTI)

This report describes the following: (1) the US Department of Energy Seasonal Thermal Energy Storage Program, (2) aquifer thermal energy storage technology, (3) alternative STES technology, (4) foreign studies in seasonal thermal energy storage, and (5) economic assessment.

Allen, R.D.; Kannberg, L.D.; Raymond, J.R.

1984-05-01T23:59:59.000Z

251

SUPERCONDUCTING MAGNETIC ENERGY STORAGE  

E-Print Network (OSTI)

Adki ns, "Raccoon Mountain Pumped-Storage Plant- Ten Years2J O. D. Johnson, "Worldwide Pumped-Storage Projects", PowerUnderground Pumped Hydro Storage", Proc. 1976 Eng.

Hassenzahl, W.

2011-01-01T23:59:59.000Z

252

FCT Hydrogen Storage: Basics  

NLE Websites -- All DOE Office Websites (Extended Search)

Basics to someone by E-mail Share FCT Hydrogen Storage: Basics on Facebook Tweet about FCT Hydrogen Storage: Basics on Twitter Bookmark FCT Hydrogen Storage: Basics on Google...

253

Subsea Pumped Hydro Storage.  

E-Print Network (OSTI)

??A new technology for energy storage called Subsea Pumped Hydro Storage (SPHS) has been evaluated from a techno-economical point of view. Intermittent renewable energy sources… (more)

Erik, Almen John

2013-01-01T23:59:59.000Z

254

Energy Storage Testing  

NLE Websites -- All DOE Office Websites (Extended Search)

Energy Storage Testing The Advanced Vehicle Testing Activity is tasked by the U.S. Department of Energys Vehicle Technology Program to conduct various types of energy storage...

255

NERSC HPSS Storage Statistics  

NLE Websites -- All DOE Office Websites (Extended Search)

Storage Trends and Summaries Storage by Scientific Discipline Troubleshooting Optimizing IO performance on the Lustre file system IO Formats Sharing Data Transferring Data Unix...

256

Underground Natural Gas Storage  

U.S. Energy Information Administration (EIA)

Underground Natural Gas Storage. Measured By. Disseminated Through. Monthly Survey of Storage Field Operators -- asking injections, withdrawals, base gas, working gas.

257

Method of drying articles  

DOE Patents (OSTI)

A method of drying a green particulate article includes the steps of: (a) Providing a green article which includes a particulate material and a pore phase material, the pore phase material including a solvent; and (b) contacting the green article with a liquid desiccant for a period of time sufficient to remove at least a portion of the solvent from the green article, the pore phase material acting as a semipermeable barrier to allow the solvent to be sorbed into the liquid desiccant, the pore phase material substantially preventing the liquid desiccant from entering the pores. 3 figs.

Janney, M.A.; Kiggans, J.O. Jr.

1999-03-23T23:59:59.000Z

258

Method of drying articles  

DOE Patents (OSTI)

A method of drying a green particulate article includes the steps of: a. Providing a green article which includes a particulate material and a pore phase material, the pore phase material including a solvent; and b. contacting the green article with a liquid desiccant for a period of time sufficient to remove at least a portion of the solvent from the green article, the pore phase material acting as a semipermeable barrier to allow the solvent to be sorbed into the liquid desiccant, the pore phase material substantially preventing the liquid desiccant from entering the pores.

Janney, Mark A. (Knoxville, TN); Kiggans, Jr., James O. (Oak Ridge, TN)

1999-01-01T23:59:59.000Z

259

Session: Hot Dry Rock  

SciTech Connect

This session at the Geothermal Energy Program Review X: Geothermal Energy and the Utility Market consisted of four presentations: ''Hot Dry Rock - Summary'' by George P. Tennyson, Jr.; ''HDR Opportunities and Challenges Beyond the Long Term Flow Test'' by David V. Duchane; ''Start-Up Operations at the Fenton Hill HDR Pilot Plant'' by Raymond F. Ponden; and ''Update on the Long-Term Flow Testing Program'' by Donald W. Brown.

Tennyson, George P. Jr.; Duchane, David V.; Ponden, Raymond F.; Brown, Donald W.

1992-01-01T23:59:59.000Z

260

Storage | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Storage Storage Storage Energy storage isn’t just for AA batteries. Thanks to investments from the Energy Department's Advanced Research Projects Agency-Energy (ARPA-E), energy storage may soon play a bigger part in our electricity grid, making it possible to generate more renewable electricity. Learn more. Energy storage isn't just for AA batteries. Thanks to investments from the Energy Department's Advanced Research Projects Agency-Energy (ARPA-E), energy storage may soon play a bigger part in our electricity grid, making it possible to generate more renewable electricity. Learn more.

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


261

Bases for extrapolating materials durability in fuel storage pools  

SciTech Connect

A major body of evidence indicates that zirconium alloys have the most consistent and reliable durability in wet storage, justifying projections of safe wet storage greater than 50 y. Aluminum alloys have the widest range of durabilities in wet storage; systematic control and monitoring of water chemistry have resulted in low corrosion rates for more than two decades on some fuels and components. However, cladding failures have occurred in a few months when important parameters were not controlled. Stainless steel is extremely durable when stress, metallurgical and water chemistry factors are controlled. LWR SS cladding has survived for 25 y in wet storage. However, sensitized, stressed SS fuels and components have seriously degraded in fuel storage pools (FSPs) at {approximately} 30 C. Satisfactory durability of fuel assembly and FSP component materials in extended wet storage requires investments in water quality management and surveillance, including chemical and biological factors. The key aspect of the study is to provide storage facility operators and other decision makers a basis to judge the durability of a given fuel type in wet storage as a prelude to basing other fuel management plans (e.g. dry storage) if wet storage will not be satisfactory through the expected period of interim storage.

Johnson, A.B. Jr.

1994-12-01T23:59:59.000Z

262

Foreign programs for the storage of spent nuclear power plant fuels, high-level waste canisters and transuranic wastes  

SciTech Connect

The various national programs for developing and applying technology for the interim storage of spent fuel, high-level radioactive waste, and TRU wastes are summarized. Primary emphasis of the report is on dry storage techniques for uranium dioxide fuels, but data are also provided concerning pool storage.

Harmon, K.M.; Johnson, A.B. Jr.

1984-04-01T23:59:59.000Z

263

Transportation Storage Interface | Department of Energy  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Storage Interface Transportation Storage Interface Regulation of Future Extended Storage and Transportation. Transportation Storage Interface More Documents & Publications Status...

264

Control of Dry Season Evapotranspiration over the Amazonian Forest as Inferred from Observations at a Southern Amazon Forest Site  

Science Conference Proceedings (OSTI)

The extent to which soil water storage can support an average dry season evapotranspiration (ET) is investigated using observations from the Rebio Jarú site for the period of 2000 to 2002. During the dry season, when total rainfall is less than ...

Robinson I. Negrón Juárez; Martin G. Hodnett; Rong Fu; Michael L. Goulden; Celso von Randow

2007-06-01T23:59:59.000Z

265

Technical Assessment Guide (TAG) - Power Generation and Storage Technology Options  

Science Conference Proceedings (OSTI)

The EPRI Technical Assessment Guide (TAG)Power Generation and Storage Technology Options helps energy company decision makers optimize capital investments in power generation and energy storage infrastructure. The 2009 TAG has been significantly enhanced. The following topics are among those that are new or enhanced: several options on CO2 capture controls and costs for existing retrofits and for new Pulverized Coal and Combustion Turbine Combined Cycle plants; several options on hybrid and dry cooling f...

2009-12-11T23:59:59.000Z

266

Spent nuclear fuel Canister Storage Building CDR Review Committee report  

SciTech Connect

The Canister Storage Building (CSB) is a subproject under the Spent Nuclear Fuels Major System Acquisition. This subproject is necessary to design and construct a facility capable of providing dry storage of repackaged spent fuels received from K Basins. The CSB project completed a Conceptual Design Report (CDR) implementing current project requirements. A Design Review Committee was established to review the CDR. This document is the final report summarizing that review

Dana, W.P.

1995-12-01T23:59:59.000Z

267

Energy from hot dry rock  

DOE Green Energy (OSTI)

The Hot Dry Rock Geothermal Energy Program is described. The system, operation, results, development program, environmental implications, resource, economics, and future plans are discussed. (MHR)

Hendron, R.H.

1979-01-01T23:59:59.000Z

268

LEVERAGING AGING MATERIALS DATA TO SUPPORT EXTENSION OF TRANSPORTATION SHIPPING PACKAGES SERVICE LIFE  

SciTech Connect

Nuclear material inventories are increasingly being transferred to interim storage locations where they may reside for extended periods of time. Use of a shipping package to store nuclear materials after the transfer has become more common for a variety of reasons. Shipping packages are robust and have a qualified pedigree for performance in normal operation and accident conditions but are only certified over an approved transportation window. The continued use of shipping packages to contain nuclear material during interim storage will result in reduced overall costs and reduced exposure to workers. However, the shipping package materials of construction must maintain integrity as specified by the safety basis of the storage facility throughout the storage period, which is typically well beyond the certified transportation window. In many ways, the certification processes required for interim storage of nuclear materials in shipping packages is similar to life extension programs required for dry cask storage systems for commercial nuclear fuels. The storage of spent nuclear fuel in dry cask storage systems is federally-regulated, and over 1500 individual dry casks have been in successful service up to 20 years in the US. The uncertainty in final disposition will likely require extended storage of this fuel well beyond initial license periods and perhaps multiple re-licenses may be needed. Thus, both the shipping packages and the dry cask storage systems require materials integrity assessments and assurance of continued satisfactory materials performance over times not considered in the original evaluation processes. Test programs for the shipping packages have been established to obtain aging data on materials of construction to demonstrate continued system integrity. The collective data may be coupled with similar data for the dry cask storage systems and used to support extending the service life of shipping packages in both transportation and storage.

Dunn, K. [Savannah River National Laboratory; Bellamy, S. [Savannah River National Laboratory; Daugherty, W. [Savannah River National Laboratory; Sindelar, R. [Savannah River National Laboratory; Skidmore, E. [Savannah River National Laboratory

2013-08-18T23:59:59.000Z

269

Upcoming Natural Gas Storage Facilities.  

U.S. Energy Information Administration (EIA)

Kentucky Energy Hub Project Orbit Gas Storage Inc KY Leader One Gas Storage Project Peregrine Midstream Partners WY Tricor Ten Section Storage Project

270

Vehicle Technologies Office: Energy Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Energy Storage to someone by E-mail Share Vehicle Technologies Office: Energy Storage on Facebook Tweet about Vehicle Technologies Office: Energy Storage on Twitter Bookmark...

271

Carbon Storage Review 2012  

NLE Websites -- All DOE Office Websites (Extended Search)

of Energy National Energy Technology Laboratory Carbon Storage R&D Project Review Meeting Developing the Technologies and Building the Infrastructure for CO 2 Storage August 21-23,...

272

NREL: Energy Storage - News  

NLE Websites -- All DOE Office Websites (Extended Search)

Energy Storage News Below are news stories related to NREL's energy storage research. August 28, 2013 NREL Battery Calorimeters Win R&D 100 Award The award-wining Isothermal...

273

NETL: Carbon Storage Archive  

NLE Websites -- All DOE Office Websites (Extended Search)

2013 Carbon Storage Newsletter PDF-571KB has been posted. 08.27.2013 Publications August 2013 Carbon Storage Newsletter PDF-1.1MB has been posted. 08.15.2013 News Ancient...

274

SUPERCONDUCTING MAGNETIC ENERGY STORAGE  

E-Print Network (OSTI)

pumped hydro, compressed air, and battery energy storage areto other energy storage sys tem s suc h as pumped hydro andenergy would be $50/MJ whereas the cost of the pumped hydro

Hassenzahl, W.

2011-01-01T23:59:59.000Z

275

Sechage solaire des aliments (solar food drying and conservation of food for year-round consumption)  

Science Conference Proceedings (OSTI)

This report is an introduction to food drying as a measure to avoid the loss of agricultural surpluses, and conserve food for year-round consumption. It discusses the basic rules of food drying and gives an overview of various methods and appropriate dryer constructions. It also provides detailed explanations on how to process vegetables, fruits, and meats and gives advice on storage and cooking.

Not Available

1985-09-01T23:59:59.000Z

276

Effects of a potential drop of a shipping cask, a waste container, and a bare fuel assembly during waste-handling operations; Yucca Mountain Site Characterization Project  

Science Conference Proceedings (OSTI)

This study investigates the effects of potential drops of a typical shipping cask, waste container, and bare fuel assembly during waste-handling operations at the prospective Yucca Mountain Repository. The waste-handling process (one stage, no consolidation configuration) is examined to estimate the maximum loads imposed on typical casks and containers as they are handled by various pieces of equipment during waste-handling operations. Maximum potential drop heights for casks and containers are also evaluated for different operations. A nonlinear finite-element model is employed to represent a hybrid spent fuel container subject to drop heights of up to 30 ft onto a reinforced concrete floor. The impact stress, strain, and deformation are calculated, and compared to the failure criteria to estimate the limiting (maximum permissible) drop height for the waste container. A typical Westinghouse 17 {times} 17 PWR fuel assembly is analyzed by a simplified model to estimate the energy absorption by various parts of the fuel assembly during a 30 ft drop, and to determine the amount of kinetic energy in a fuel pin at impact. A nonlinear finite-element analysis of an individual fuel pin is also performed to estimate the amount of fuel pellet fracture due to impact. This work was completed on May 1990.

Wu, C.L.; Lee, J.; Lu, D.L.; Jardine, L.J. [Bechtel National, Inc., San Francisco, CA (United States)

1991-12-01T23:59:59.000Z

277

Energy Storage & Delivery  

Science Conference Proceedings (OSTI)

Energy Storage & Delivery. Summary: Schematic of Membrane Molecular Structure The goal of the project is to develop ...

2013-07-23T23:59:59.000Z

278

Conventional Storage Water Heaters  

Energy.gov (U.S. Department of Energy (DOE))

Conventional storage water heaters remain the most popular type of water heating system for homes and buildings.

279

Process, Techniques, and Successes in Welding the Dry Shielded Canister Welds of the TMI-2 Reactor Core Debris  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL) is operated by Bechtel-BWXT Idaho LLC (BBWI), which recently completed a very successful $100 million Three-Mile Island-2 (TMI-2) program for the Department of Energy (DOE). This complex and challenging program used an integrated multidisciplinary team approach that loaded, welded, and transported an unprecedented 25 dry shielded canisters (DSC) in seven months, and did so ahead of schedule. The program moved over 340 canisters of TMI-2 core debris that had been in wet storage into a dry storage facility at the INEEL. The main thrust of this paper is relating the innovations, techniques, approaches, and lessons learned associated to welding of the DSC's. This paper shows the synergism of elements to meet program success and shares these lessons learned that will facilitate success with welding of dry shielded canisters in other DOE complex dry storage programs.

Zirker, Laurence R; Rankin, Richard Allen; Ferrell, Larry Joseph

2002-02-01T23:59:59.000Z

280

Processes, Techniques, and Successes in Welding the Dry Shielded Canisters of the TMI-2 Reactor Core Debris  

SciTech Connect

The Idaho National Engineering and Environmental Laboratory (INEEL) is operated by Bechtel-BWXT Idaho LLC (BBWI), which recently completed a very successful $100 million Three-Mile Island-2 (TMI-2) program for the Department of Energy (DOE). This complex and challenging program used an integrated multidisciplinary team approach that loaded, welded, and transported an unprecedented 25 dry shielded canisters (DSC) in seven months, and did so ahead of schedule. The program moved over 340 canisters of TMI-2 core debris that had been in wet storage into a dry storage facility at the INEEL. The main thrust of this paper is relating the innovations, techniques, approaches, and lessons learned associated to welding of the DSC's. This paper shows the synergism of elements to meet program success and shares these lessons learned that will facilitate success with welding of dry shielded canisters in other DOE complex dry storage programs.

Zirker, L.R.; Rankin, R.A.; Ferrell, L.J.

2002-01-29T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


281

Dry Ice vs. Pipette Experiment Description  

E-Print Network (OSTI)

Dry Ice vs. Pipette Experiment Description Dry ice (solid) is put into the bulb of a pipette, plastic pipette 1 ice cube sized piece of dry ice Butter knife (or some object to break dry ice) Gloves (surgical gloves will not work, they must protect hands from dry ice) Safety glasses for demonstrator

282

Storage Sub-committee  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Storage Sub-committee Storage Sub-committee 2012 Work Plan Confidential 1 2012 Storage Subcommittee Work Plan * Report to Congress. (legislative requirement) - Review existing and projected research and funding - Review existing DOE, Arpa-e projects and the OE 5 year plan - Identify gaps and recommend additional topics - Outline distributed (review as group) * Develop and analysis of the need for large scale storage deployment (outline distributed again) * Develop analysis on regulatory issues especially valuation and cost recovery Confidential 2 Large Scale Storage * Problem Statement * Situation Today * Benefits Analysis * Policy Issues * Technology Gaps * Recommendations * Renewables Variability - Reserves and capacity requirements - Financial impacts - IRC Response to FERC NOI and update

283

Textile Drying Via Wood Gasification  

E-Print Network (OSTI)

This project was carried out to investigate the possibility of using wood gas as a direct replacement for natural gas in textile drying. The Georgia Tech updraft gasifier was used for the experimental program. During preliminary tests, the 1 million Btu/hr pilot plant produced clean burning gas which appeared viable for drying textiles. The gasifier was coupled to a modified textile drying oven and a series of tests were carried out to assess product degradation of white, colored, and chemically treated fabrics.

McGowan, T. F.; Jape, A. D.

1983-01-01T23:59:59.000Z

284

FCT Hydrogen Storage: Hydrogen Storage R&D Activities  

NLE Websites -- All DOE Office Websites (Extended Search)

Hydrogen Storage R&D Activities Hydrogen Storage R&D Activities to someone by E-mail Share FCT Hydrogen Storage: Hydrogen Storage R&D Activities on Facebook Tweet about FCT Hydrogen Storage: Hydrogen Storage R&D Activities on Twitter Bookmark FCT Hydrogen Storage: Hydrogen Storage R&D Activities on Google Bookmark FCT Hydrogen Storage: Hydrogen Storage R&D Activities on Delicious Rank FCT Hydrogen Storage: Hydrogen Storage R&D Activities on Digg Find More places to share FCT Hydrogen Storage: Hydrogen Storage R&D Activities on AddThis.com... Home Basics Current Technology DOE R&D Activities National Hydrogen Storage Compressed/Liquid Hydrogen Tanks Testing and Analysis Quick Links Hydrogen Production Hydrogen Delivery Fuel Cells Technology Validation Manufacturing Codes & Standards

285

Safety-Basis Thermal Analysis for KE Basin Sludge Transport and Storage  

DOE Green Energy (OSTI)

A series of safety-basis thermal and gas generation analyses were completed and independently reviewed to assess the thermal performance of a large diameter container (LDC) containing KE Basin sludge. The results demonstrate: (1) the sludge transport system (STS) containing a LDC can safely transport a KE basin sludge payload up to 2.0 m{sup 3} and, (2) large diameter containers with sludge payloads up to 2.0 m{sup 3} can be safely stored in a process cell at T Plant. The transport and storage analyses are based on a conservative set of assumptions, including limiting environmental conditions. Conclusions drawn from the transport and storage results were not impacted by changes in the radial gap between the cask and LDC, purge gas (i.e., either helium or nitrogen), sludge porosity, or thermal conductivity. The design of the transport cask and large diameter container can accommodate reasonable changes in these values. Both transport from KE Basin and long-term storage at T Plant are addressed for sludge payloads up to 2.0 m{sup 3}. Additional analyses determined the expected range of T Plant environmental temperatures, the hydrogen and oxygen generation rate due to the radiolysis of water, and the maximum hydrogen concentration within a process cell due to chemical reactions and the radiolysis of water. All sludge temperature and hydrogen concentration criteria for transport and storage are met. The analyses assumed a safety-basis sludge mixture defined as 60% by volume floor and 40% by volume canister sludge with 35% retained gas, and a conservative segregated (axial) distribution of metallic uranium (resulting from particulate settling) with associated safety-basis properties. The analyses recognized that the retrieval process would produce non-uniform sludge distributions. Four batch process loadings of 0.5m{sup 3} each are assumed. Each process batch loading will settle and segregate (separate) into two layers: an active layer containing all the metallic uranium which is chemically active, and a non-active layer containing uranium oxide, non-uranium material, and no metallic uranium. This is a conservative representation of operational controls designed to limit the metallic uranium concentration. The sludge layers are assumed to remain intact during transport and storage.

HEARD, F.J.; SATHYANARAYANA, J.J.

2002-09-30T23:59:59.000Z

286

Hot Dry Rock - Summary  

SciTech Connect

Hot Dry Rock adds a new flexibility to the utilization of geothermal energy. Almost always the approach has been to limit that utilization to places where there is a natural source of water associated with a source of heat. Actually, the result was that steam was mined. Clearly there are much larger heat resources available which lack natural water to transport that energy to the surface. Also, as is found in hydrothermal fields being mined for steam, the water supply finally gets used up. There is a strong motive in the existing capital investment to revitalize those resources. Techniques for introducing, recovering and utilizing the water necessary to recover the heat from below the surface of the earth is the subject of this session. Implicit in that utilization is the ability to forecast with reasonable accuracy the busbar cost of that energy to the utility industry. The added element of supplying the water introduces costs which must be recovered while still supplying energy which is competitive. Hot Dry Rock technology can supply energy. That has been proved long since. The basic barrier to its use by the utility industry has been and remains proof to the financial interests that the long term cost is competitive enough to warrant investment in a technology that is new to utility on-grid operations. As the opening speaker for this session states, the test that is underway will ''simulate the operations of a commercial facility in some ways, but it will not show that energy from HDR can be produced at a variety of locations with different geological settings''. Further, the Fenton Hill system is a research facility not designed for commercial production purposes, but it can give indications of how the system must be changed to provide economic HDR operations. And so it is that we must look beyond the long term flow test, at the opportunities and challenges. Proving that the huge HDR resources can be accessed on a worldwide scale must involve the construction of additional sites, preferably to the specifications of the now Federal geothermal community. These facilities will have to be engineered to produce and market energy at competitive prices. At the same time, we must not rest on our technological laurels, though they be many. Design and operational techniques have been conceived which could lead to improved economics and operations for HDR. These must be pursued and where merit is found, vigorously pursued. Accelerated research and development ought to include revolutionary drilling techniques, reservoir interrogation, and system modeling to assure the competitiveness and geographical diversity of applications of HDR. Much of this work will be applicable to the geothermal industry in general. More advanced research ought to include such innovations as the utilization of other operating fluids. Supercritical carbon dioxide and the ammonia/water (Kalina) cycle have been mentioned. But even as the near and more distant outlook is examined, today's work was reported in the HDR session. The start-up operations for the current test series at the Fenton Hill HDR Pilot Plant were described. The surface plant is complete and initial operations have begun. While some minor modifications to the system have been required, nothing of consequence has been found to impede operations. Reliability, together with the flexibility and control required for a research system were shown in the system design, and demonstrated by the preliminary results of the plant operations and equipment performance. Fundamental to the overall success of the HDR energy resource utilization is the ability to optimize the pressure/flow impedance/time relationships as the reservoir is worked. Significant new insights are still being developed out of the data which will substantially affect the operational techniques applied to new systems. However, again, these will have to be proved to be general and not solely specific to the Fenton Hill site. Nevertheless, high efficiency use of the reservoir without unintended reservoir grow

Tennyson, George P. Jr.

1992-03-24T23:59:59.000Z

287

NETL: Carbon Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Storage Storage Technologies Carbon Storage (formerly referred to as the "Carbon Sequestration Program") Program Overview For quick navigation of NETL's Carbon Storage Program website, please click on the image. NETL's Carbon Storage Program Fossil fuels are considered the most dependable, cost-effective energy source in the world. The availability of these fuels to provide clean, affordable energy is essential for domestic and global prosperity and security well into the 21st century. However, a balance is needed between energy security and concerns over the impacts of concentrations of greenhouse gases (GHGs) in the atmosphere - particularly carbon dioxide (CO2). NETL's Carbon Storage Program is developing a technology portfolio of safe, cost-effective, commercial-scale CO2 capture, storage, and mitigation

288

Chemical Storage-Overview  

NLE Websites -- All DOE Office Websites (Extended Search)

Storage - Storage - Overview Ali T-Raissi, FSEC Hydrogen Storage Workshop Argonne National Laboratory, Argonne, Illinois August 14-15, 2002 Hydrogen Fuel - Attributes * H 2 +½ O 2 → H 2 O (1.23 V) * High gravimetric energy density: 27.1 Ah/g, based on LHV of 119.93 kJ/g * 1 wt % = 189.6 Wh/kg (0.7 V; i.e. η FC = 57%) * Li ion cells: 130-150 Wh/kg Chemical Hydrides - Definition * They are considered secondary storage methods in which the storage medium is expended - primary storage methods include reversible systems (e.g. MHs & C-nanostructures), GH 2 & LH 2 storage Chemical Hydrides - Definition (cont.) * The usual chemical hydride system is reaction of a reactant containing H in the "-1" oxidation state (hydride) with a reactant containing H in the "+1" oxidation

289

UFD Storage and Transportation - Transportation Working Group Report  

DOE Green Energy (OSTI)

The Used Fuel Disposition (UFD) Transportation Task commenced in October 2010. As its first task, Pacific Northwest National Laboratory (PNNL) compiled a list of structures, systems, and components (SSCs) of transportation systems and their possible degradation mechanisms during extended storage. The list of SSCs and the associated degradation mechanisms [known as features, events, and processes (FEPs)] were based on the list of used nuclear fuel (UNF) storage system SSCs and degradation mechanisms developed by the UFD Storage Task (Hanson et al. 2011). Other sources of information surveyed to develop the list of SSCs and their degradation mechanisms included references such as Evaluation of the Technical Basis for Extended Dry Storage and Transportation of Used Nuclear Fuel (NWTRB 2010), Transportation, Aging and Disposal Canister System Performance Specification, Revision 1 (OCRWM 2008), Data Needs for Long-Term Storage of LWR Fuel (EPRI 1998), Technical Bases for Extended Dry Storage of Spent Nuclear Fuel (EPRI 2002), Used Fuel and High-Level Radioactive Waste Extended Storage Collaboration Program (EPRI 2010a), Industry Spent Fuel Storage Handbook (EPRI 2010b), and Transportation of Commercial Spent Nuclear Fuel, Issues Resolution (EPRI 2010c). SSCs include items such as the fuel, cladding, fuel baskets, neutron poisons, metal canisters, etc. Potential degradation mechanisms (FEPs) included mechanical, thermal, radiation and chemical stressors, such as fuel fragmentation, embrittlement of cladding by hydrogen, oxidation of cladding, metal fatigue, corrosion, etc. These degradation mechanisms are discussed in Section 2 of this report. The degradation mechanisms have been evaluated to determine if they would be influenced by extended storage or high burnup, the need for additional data, and their importance to transportation. These categories were used to identify the most significant transportation degradation mechanisms. As expected, for the most part, the transportation importance was mirrored by the importance assigned by the UFD Storage Task. A few of the more significant differences are described in Section 3 of this report

Maheras, Steven J.; Ross, Steven B.

2011-08-01T23:59:59.000Z

290

NEWTON: Preventing Tire Dry Rot  

NLE Websites -- All DOE Office Websites (Extended Search)

Preventing Tire Dry Rot Preventing Tire Dry Rot Name: Millard Status: student Grade: 9-12 Location: MD Country: USA Date: Spring 2013 Question: My dad has a classic car, and because it gets driven very little each year, the tires dry rot before he can get much tread wear on them. What could be used to protect the tires from dry rot and cracking? Replies: Hi Millard, Thanks for the question. I would recommend keeping the car on blocks so that there is no weight on the tires. Additionally, I would recommend that no electrical equipment (motors, switches, and other things that spark) be used around the car. The sparks generate ozone and ozone can cause rubber items such as tires, belts, and hoses to crack. I hope this helps. Please let me know if you have more questions. Thanks Jeff Grell

291

DRI Companies | Open Energy Information  

Open Energy Info (EERE)

DRI Companies DRI Companies Jump to: navigation, search Name DRI Companies Place Irvine, California Zip 92614 Sector Solar Product US-based residential and commercial installer of turnkey solar systems, through subsidiary iDRI Energy. Coordinates 41.837752°, -79.268594° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":41.837752,"lon":-79.268594,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

292

Abrasives for Dry Blast Cleaning  

Science Conference Proceedings (OSTI)

...The materials used in dry abrasive blast cleaning can be categorized as metallic grit, metallic shot, sand, glass, and miscellaneous. Hardness, density, size, and shape are important considerations in choosing an abrasive for a specific

293

Report on Biomass Drying Technology  

DOE Green Energy (OSTI)

Using dry fuel provides significant benefits to combustion boilers, mainly increased boiler efficiency, lower air emissions, and improved boiler operation. The three main choices for drying biomass are rotary dryers, flash dryers, and superheated steam dryers. Which dryer is chosen for a particular application depends very much on the material characteristics of the biomass, the opportunities for integrating the process and dryer, and the environmental controls needed or already available.

Amos, W. A.

1999-01-12T23:59:59.000Z

294

Treatment, packaging, and storage of bundle scrap hardware  

SciTech Connect

A study was performed to identify and evaluate the various technical options for treatment, packaging and storing the bundle scrap hardware that results from rod consolidation. The three general scenarios addressed were keeping the treated scrap in the pool, moving it to on-site dry storage, or immediate disposal. The study concluded that practical alternatives existed for all three cases. Use of novel scrap packaging techniques achieved an overall net consolidation ratio of two. The most economical concept was found to be using advanced technology in the pool storage scenario with dry storage schemes a close second. The project also provides information on scrap characterization and provides tools to assist in classifying the scrap hardware.

Fuierer, A. (Rochester Gas and Electric Corp., NY (United States)); Dabolt, R. (Chem-Nuclear Systems, Inc., Columbia, SC (United States))

1991-09-01T23:59:59.000Z

295

Heat storage duration  

DOE Green Energy (OSTI)

Both the amount and duration of heat storage in massive elements of a passive building are investigated. Data taken for one full winter in the Balcomb solar home are analyzed with the aid of sub-system simulation models. Heat storage duration is tallied into one-day intervals. Heat storage location is discussed and related to overall energy flows. The results are interpreted and conclusions drawn.

Balcomb, J.D.

1981-01-01T23:59:59.000Z

296

Energy Storage Systems 2007 Peer Review - International Energy Storage  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

International Energy International Energy Storage Program Presentations Energy Storage Systems 2007 Peer Review - International Energy Storage Program Presentations The U.S. DOE Energy Storage Systems Program (ESS) held an annual peer review on September 27, 2007 in San Francisco, CA. Eighteen presentations were divided into categories; those related to international energy storage programs are below. Other presentation categories were: Economics - Benefit Studies and Environment Benefit Studies Utility & Commercial Applications of Advanced Energy Storage Systems Power Electronics Innovations in Energy Storage Systems ESS 2007 Peer Review - DOE-CEC Energy Storage Program FY07 Projects - Daniel Borneo, SNL.pdf ESS 2007 Peer Review - Joint NYSERDA-DOE Energy Storage Initiative Projects

297

NETL: Gasification Systems - Evaluation of the Benefits of Advanced Dry  

NLE Websites -- All DOE Office Websites (Extended Search)

Feed Systems Feed Systems Evaluation of the Benefits of Advanced Dry Feed System for Low Rank Coal Project Number: DE-FE0007902 General Electric Company (GE) is evaluating and demonstrating the benefits of novel dry feed technologies to effectively, reliably, and economically provide feeding of low-cost, low-rank coals into commercial Integrated Gasification Combined Cycle (IGCC) systems. GE is completing comparative techno-economic studies of two IGCC power plant cases, one without and one with advanced dry feed technologies. A common basis of design is being developed so that overall assumptions and methodologies are common in the two cases for both technical and economic areas. The baseline case, without advanced dry feed technologies, will use operational data from the Eastman Chemical Company Kingsport gasification facility in combination with DOE/NETL's Cost and Performance Baseline Low-Rank Coal to Electricity IGCC study for both cost and performance comparisons. Advanced dry feed technologies, based upon the Posimetric® pump currently under development by GE, will be developed to match the proposed plant conditions and configuration, and will be analyzed to provide comparative performance and cost information to the baseline plant case. The scope of this analysis will cover the feed system from the raw coal silo up to, and including, the gasifier injector. Test data from previous and current testing will be summarized in a report to support the assumptions used to evaluate the advanced technologies and the potential value for future applications. This study focuses primarily on IGCC systems with 90 percent carbon capture, utilization, and storage (CCUS), but the dry feed system will be applicable to all IGCC power generating plants, as well as other industries requiring pressurized syngas.

298

NETL: Carbon Storage - Infrastructure  

NLE Websites -- All DOE Office Websites (Extended Search)

Infrastructure Infrastructure Carbon Storage Infrastructure The Infrastructure Element of DOE's Carbon Storage Program is focused on research and development (R&D) initiatives to advance geologic CO2 storage toward commercialization. DOE determined early in the program's development that addressing CO2 mitigation on a regional level is the most effective way to address differences in geology, climate, population density, infrastructure, and socioeconomic development. This element includes the following efforts designed to support the development of regional infrastructure for carbon capture and storage (CCS). Click on Image to Navigate Infrastructure Content on this page requires a newer version of Adobe Flash Player. Get Adobe Flash player Regional Carbon Sequestration Partnerships (RCSP) - This

299

Other Innovative Storage Systems  

Science Conference Proceedings (OSTI)

High Efficiency Electrical Energy Storage Using Reversible Solid Oxide Cells: Scott Barnett1; Gareth Hughes1; Kyle Yakal-Kremski1; Zhan Gao1; 1 Northwestern ...

300

NREL: Energy Storage - Webmaster  

NLE Websites -- All DOE Office Websites (Extended Search)

to reply. Your name: Your email address: Your message: Send Message Printable Version Energy Storage Home About the Project Technology Basics Research & Development Awards &...

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


301

NREL: Energy Storage - Resources  

NLE Websites -- All DOE Office Websites (Extended Search)

Resources The National Renewable Energy Laboratory's (NREL) Energy Storage team and partners work within a variety of programs that have created test manuals to establish standard...

302

Advanced Energy Storage Publications  

NLE Websites -- All DOE Office Websites (Extended Search)

Advanced Energy Storage Publications Reports: Advanced Technology Development Program For Lithium-Ion Batteries: Gen 2 Performance Evaluation Final Report Advanced Technology...

303

Storage Sub-committee  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Gaps - Existing R&D and pilot programs - CAES - Controllable pumping - Off shore (energy island, etc) - Gravity systems - Thermal storage Confidential 3 Report to DOE ...

304

Carbon Storage Program  

NLE Websites -- All DOE Office Websites (Extended Search)

fuel power plants as viable, clean sources of electric power. The program is focused on developing technologies that can achieve 99 percent of carbon dioxide (CO 2 ) storage...

305

HEATS: Thermal Energy Storage  

SciTech Connect

HEATS Project: The 15 projects that make up ARPA-E’s HEATS program, short for “High Energy Advanced Thermal Storage,” seek to develop revolutionary, cost-effective ways to store thermal energy. HEATS focuses on 3 specific areas: 1) developing high-temperature solar thermal energy storage capable of cost-effectively delivering electricity around the clock and thermal energy storage for nuclear power plants capable of cost-effectively meeting peak demand, 2) creating synthetic fuel efficiently from sunlight by converting sunlight into heat, and 3) using thermal energy storage to improve the driving range of electric vehicles (EVs) and also enable thermal management of internal combustion engine vehicles.

None

2012-01-01T23:59:59.000Z

306

H 2 Storage Projects  

Science Conference Proceedings (OSTI)

... 10. Titanium-decorated carbon nanotubes: a potential high-capacity hydrogen storage madium. ... 3. Exohydrogenated single-wall carbon nanotubes. ...

307

Natural Gas Storage Valuation .  

E-Print Network (OSTI)

??In this thesis, one methodology for natural gas storage valuation is developed and two methodologies are improved. Then all of the three methodologies are applied… (more)

Li, Yun

2007-01-01T23:59:59.000Z

308

NETL: Carbon Storage FAQs  

NLE Websites -- All DOE Office Websites (Extended Search)

Does CCS really make a difference for the environment? Carbon capture and storage (CCS) is one of several options, including the use of renewables, nuclear energy, alternative...

309

Cold Vacuum Drying (CVD) Facility General Service Helium System Design Description  

DOE Green Energy (OSTI)

The purpose of this System Design Description (SDD) is to describe the characteristics of the Cold Vacuum Drying (CVD) Facility general service helium system. The general service helium system is a general service facility process support system, but does include safety-class structures, systems and components (SSCs) providing protection to the offsite public. The general service helium system also performs safety-significant functions that provide protection to onsite workers. The general helium system essential function is to provide helium (He) to support process functions during all phases of facility operations. General service helium is used to purge the cask and the MCO in order to maintain their internal atmospheres below hydrogen flammability concentrations. The general service helium system also supplies helium to purge the process water conditioning (PWC) lines and components and the vacuum purge system (VPS) vacuum pump. The general service helium system, if available following an Safety Class Instrument and Control System (SCIC) Isolation and Purge (IS0 and PURGE) Trip, can provide an alternate general service helium system source to supply the Safety-Class Helium (SCHe) System.

SHAPLEY, B.J.

2000-04-20T23:59:59.000Z

310

NETL: Carbon Storage - Reference Shelf  

NLE Websites -- All DOE Office Websites (Extended Search)

Carbon Storage > Reference Shelf Carbon Storage > Reference Shelf Carbon Storage Reference Shelf Below are links to Carbon Storage Program documents and reference materials. Each of the 10 categories has a variety of documents posted for easy access to current information - just click on the category link to view all related materials. RSS Icon Subscribe to the Carbon Storage RSS Feed. Carbon Storage Collage 2012 Carbon Utilization and Storage Atlas IV Carbon Sequestration Project Portfolio DOE/NETL Carbon Dioxide Capture and Storage RD&D Roadmap Public Outreach and Education for Carbon Storage Projects Carbon Storage Technology Program Plan Carbon Storage Newsletter Archive Impact of the Marcellus Shale Gas Play on Current and Future CCS Activities Site Screening, Selection, and Initial Characterization for Storage of CO2 in Deep Geologic Formations Carbon Storage Systems and Well Management Activities Monitoring, Verification, and Accounting of CO2 Stored in Deep Geologic Formations

311

Dry cleaning of Turkish coal  

Science Conference Proceedings (OSTI)

This study dealt with the upgrading of two different type of Turkish coal by a dry cleaning method using a modified air table. The industrial size air table used in this study is a device for removing stones from agricultural products. This study investigates the technical and economical feasibility of the dry cleaning method which has never been applied before on coals in Turkey. The application of a dry cleaning method on Turkish coals designated for power generation without generating environmental pollution and ensuring a stable coal quality are the main objectives of this study. The size fractions of 5-8, 3-5, and 1-3 mm of the investigated coals were used in the upgrading experiments. Satisfactory results were achieved with coal from the Soma region, whereas the upgrading results of Hsamlar coal were objectionable for the coarser size fractions. However, acceptable results were obtained for the size fraction 1-3 mm of Hsamlar coal.

Cicek, T. [Dokuz Eylul University, Izmir (Turkey). Faculty of Engineering

2008-07-01T23:59:59.000Z

312

Cool Storage Technology Guide  

Science Conference Proceedings (OSTI)

It is a fact that avoiding load growth is cheaper than constructing new power plants. Cool storage technologies offer one method for strategically stemming the impact of future peak demand growth. This guide provides a comprehensive resource for understanding and evaluating cool storage technologies.

2000-08-14T23:59:59.000Z

313

Energy storage capacitors  

DOE Green Energy (OSTI)

The properties of capacitors are reviewed in general, including dielectrics, induced polarization, and permanent polarization. Then capacitance characteristics are discussed and modelled. These include temperature range, voltage, equivalent series resistance, capacitive reactance, impedance, dissipation factor, humidity and frequency effects, storage temperature and time, and lifetime. Applications of energy storage capacitors are then discussed. (LEW)

Sarjeant, W.J.

1984-01-01T23:59:59.000Z

314

Warehouse and Storage Buildings  

U.S. Energy Information Administration (EIA) Indexed Site

Warehouse and Storage Warehouse and Storage Characteristics by Activity... Warehouse and Storage Warehouse and storage buildings are those used to store goods, manufactured products, merchandise, raw materials, or personal belongings. Basic Characteristics [ See also: Equipment | Activity Subcategories | Energy Use ] Warehouse and Storage Buildings... While the idea of a warehouse may bring to mind a large building, in reality most warehouses were relatively small. Forty-four percent were between 1,001 and 5,000 square feet, and seventy percent were less than 10,000 square feet. Many warehouses were newer buildings. Twenty-five percent were built in the 1990s and almost fifty percent were constructed since 1980. Tables: Buildings and Size Data by Basic Characteristics Establishment, Employment, and Age Data by Characteristics

315

Hydrogen-based electrochemical energy storage - Energy ...  

An energy storage device (100) providing high storage densities via hydrogen storage. The device (100) includes a counter electrode (110), a storage ...

316

1986 Federal Interim Storage fee study: a technical and economic analysis  

SciTech Connect

JAI examined alternative methods for structuring charges for federal interim storage (FIS) services and concluded that the combined interests of the Department and the users would be best served, and costs most appropriately recovered, by a two-part fee involving an Initial Payment upon execution of a contract for FIS services followed by a Final Payment upon delivery of the spent fuel to the Department. The Initial Payment would be an advance payment covering the pro rata share of preoperational costs, including (1) the capital costs of the required transfer facilities and storage area, (2) development costs, (3) government administrative costs including storage fund management, (4) impact aid payments made in accordance with Section 136(e) of the Act, and (5) module costs (i.e., storage casks, drywells or silos). The Final Payment would be made at the time of delivery of the spent fuel to the Department and would be calculated to cover the sum of the following: (1) any under- or over-estimation in the costs used to calculate the Initial Payment of the fee (including savings due to rod consolidation), and (2) the total estimated cost of operation and decommissioning of the FIS facilities (including government administrative costs, storage fund management and impact aid). The module costs were included in the Initial Payment to preclude the possible need to obtain appropriations for federal funds to support the purchase of the modules in advance of receipt of the Final Payment. Charges for the transport of spent fuel from the reactor site to FIS facilities would be separately assessed at actual cost since these will be specific to each reactor site and destination.

1986-09-01T23:59:59.000Z

317

,"Underground Natural Gas Storage by Storage Type"  

U.S. Energy Information Administration (EIA) Indexed Site

Sourcekey","N5030US2","N5010US2","N5020US2","N5070US2","N5050US2","N5060US2" "Date","U.S. Natural Gas Underground Storage Volume (MMcf)","U.S. Total Natural Gas in Underground...

318

Underground Natural Gas Storage by Storage Type  

U.S. Energy Information Administration (EIA) Indexed Site

Feb-13 Mar-13 Apr-13 May-13 Jun-13 Jul-13 View History All Operators Natural Gas in Storage 6,482,603 6,102,063 6,235,751 6,653,184 7,027,708 7,302,556 1973-2013 Base Gas 4,379,494...

319

EFFECT OF MECHANICAL CONDITIONING ON THIN-LAYER DRYING OF ENERGY SORGHUM (Sorghum bicolor (L.) Moench)  

SciTech Connect

Cellulosic energy varieties of Sorghum bicolor (L.) Moench show promise as a bioenergy feedstock, however, high moisture content at the time of harvest results in unacceptable levels of degradation when stored in aerobic conditions. To safely store sorghum biomass for extended periods in baled format, the material must be dried to inhibit microbial growth. One possible solution is allowing the material to dry under natural in-field conditions. This study examines the differences in thin-layer drying rates of intact and conditioned sorghum under laboratory-controlled temperatures and relative humidity levels (20 degrees C and 30 degrees C from 40% to 85% relative humidity), and models experimental data using the Page’s Modified equation. The results demonstrate that conditioning drastically accelerates drying times. Relative humidity had a large impact on the time required to reach a safe storage moisture content for intact material (approximately 200 hours at 30 degrees C and 40% relative humidity and 400 hours at 30 degrees C and 70% relative humidity), but little to no impact on the thin-layer drying times of conditioned material (approximately 50 hours for all humidity levels < 70% at 30 degrees C). The drying equation parameters were influenced by temperature, relative humidity, initial moisture content, and material damage, allowing drying curves to be empirically predicted. The results of this study provide valuable information applicable to the agricultural community and to future research on drying simulation and management of energy sorghum.

Ian J. Bonner; Kevin L. Kenney

2012-10-01T23:59:59.000Z

320

Ultrafine hydrogen storage powders  

DOE Patents (OSTI)

A method of making hydrogen storage powder resistant to fracture in service involves forming a melt having the appropriate composition for the hydrogen storage material, such, for example, LaNi.sub.5 and other AB.sub.5 type materials and AB.sub.5+x materials, where x is from about -2.5 to about +2.5, including x=0, and the melt is gas atomized under conditions of melt temperature and atomizing gas pressure to form generally spherical powder particles. The hydrogen storage powder exhibits improved chemcial homogeneity as a result of rapid solidfication from the melt and small particle size that is more resistant to microcracking during hydrogen absorption/desorption cycling. A hydrogen storage component, such as an electrode for a battery or electrochemical fuel cell, made from the gas atomized hydrogen storage material is resistant to hydrogen degradation upon hydrogen absorption/desorption that occurs for example, during charging/discharging of a battery. Such hydrogen storage components can be made by consolidating and optionally sintering the gas atomized hydrogen storage powder or alternately by shaping the gas atomized powder and a suitable binder to a desired configuration in a mold or die.

Anderson, Iver E. (Ames, IA); Ellis, Timothy W. (Doylestown, PA); Pecharsky, Vitalij K. (Ames, IA); Ting, Jason (Ames, IA); Terpstra, Robert (Ames, IA); Bowman, Robert C. (La Mesa, CA); Witham, Charles K. (Pasadena, CA); Fultz, Brent T. (Pasadena, CA); Bugga, Ratnakumar V. (Arcadia, CA)

2000-06-13T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


321

SERI Solar Energy Storage Program  

DOE Green Energy (OSTI)

The SERI Solar Energy Storage Program provides research on advanced technologies, system analyses, and assessments of thermal energy storage for solar applications in support of the Thermal and Chemical Energy Storage Program of the DOE Division of Energy Storage Systems. Currently, research is in progress on direct contact latent heat storage and thermochemical energy storage and transport. Systems analyses are being performed of thermal energy storage for solar thermal applications, and surveys and assessments are being prepared of thermal energy storage in solar applications.

Copeland, R. J.; Wright, J. D.; Wyman, C. E.

1980-02-01T23:59:59.000Z

322

NREL: Energy Storage - Industry Participants  

NLE Websites -- All DOE Office Websites (Extended Search)

Industry Participants NREL's energy storage project is funded by the DOE's Vehicle Technologies Office. We work closely with automobile manufacturers, energy storage developers,...

323

Gas Storage Technology Consortium  

Science Conference Proceedings (OSTI)

Gas storage is a critical element in the natural gas industry. Producers, transmission and distribution companies, marketers, and end users all benefit directly from the load balancing function of storage. The unbundling process has fundamentally changed the way storage is used and valued. As an unbundled service, the value of storage is being recovered at rates that reflect its value. Moreover, the marketplace has differentiated between various types of storage services, and has increasingly rewarded flexibility, safety, and reliability. The size of the natural gas market has increased and is projected to continue to increase towards 30 trillion cubic feet (TCF) over the next 10 to 15 years. Much of this increase is projected to come from electric generation, particularly peaking units. Gas storage, particularly the flexible services that are most suited to electric loads, is critical in meeting the needs of these new markets. In order to address the gas storage needs of the natural gas industry, an industry-driven consortium was created--the Gas Storage Technology Consortium (GSTC). The objective of the GSTC is to provide a means to accomplish industry-driven research and development designed to enhance operational flexibility and deliverability of the Nation's gas storage system, and provide a cost effective, safe, and reliable supply of natural gas to meet domestic demand. This report addresses the activities for the quarterly period of January 1, 2006 through March 31, 2006. Activities during this time period were: (1) Organize and host the 2006 Spring Meeting in San Diego, CA on February 21-22, 2006; (2) Award 8 projects for co-funding by GSTC for 2006; (3) New members recruitment; and (4) Improving communications.

Joel L. Morrison; Sharon L. Elder

2006-05-10T23:59:59.000Z

324

Gas Storage Technology Consortium  

SciTech Connect

Gas storage is a critical element in the natural gas industry. Producers, transmission and distribution companies, marketers, and end users all benefit directly from the load balancing function of storage. The unbundling process has fundamentally changed the way storage is used and valued. As an unbundled service, the value of storage is being recovered at rates that reflect its value. Moreover, the marketplace has differentiated between various types of storage services and has increasingly rewarded flexibility, safety, and reliability. The size of the natural gas market has increased and is projected to continue to increase towards 30 trillion cubic feet over the next 10 to 15 years. Much of this increase is projected to come from electric generation, particularly peaking units. Gas storage, particularly the flexible services that are most suited to electric loads, is crucial in meeting the needs of these new markets. To address the gas storage needs of the natural gas industry, an industry-driven consortium was created--the Gas Storage Technology Consortium (GSTC). The objective of the GSTC is to provide a means to accomplish industry-driven research and development designed to enhance the operational flexibility and deliverability of the nation's gas storage system, and provide a cost-effective, safe, and reliable supply of natural gas to meet domestic demand. This report addresses the activities for the quarterly period of April 1, 2007 through June 30, 2007. Key activities during this time period included: (1) Organizing and hosting the 2007 GSTC Spring Meeting; (2) Identifying the 2007 GSTC projects, issuing award or declination letters, and begin drafting subcontracts; (3) 2007 project mentoring teams identified; (4) New NETL Project Manager; (5) Preliminary planning for the 2007 GSTC Fall Meeting; (6) Collecting and compiling the 2005 GSTC project final reports; and (7) Outreach and communications.

Joel L. Morrison; Sharon L. Elder

2007-06-30T23:59:59.000Z

325

Gas Storage Technology Consortium  

Science Conference Proceedings (OSTI)

Gas storage is a critical element in the natural gas industry. Producers, transmission and distribution companies, marketers, and end users all benefit directly from the load balancing function of storage. The unbundling process has fundamentally changed the way storage is used and valued. As an unbundled service, the value of storage is being recovered at rates that reflect its value. Moreover, the marketplace has differentiated between various types of storage services, and has increasingly rewarded flexibility, safety, and reliability. The size of the natural gas market has increased and is projected to continue to increase towards 30 trillion cubic feet (TCF) over the next 10 to 15 years. Much of this increase is projected to come from electric generation, particularly peaking units. Gas storage, particularly the flexible services that are most suited to electric loads, is critical in meeting the needs of these new markets. In order to address the gas storage needs of the natural gas industry, an industry driven consortium was created--the Gas Storage Technology Consortium (GSTC). The objective of the GSTC is to provide a means to accomplish industry-driven research and development designed to enhance operational flexibility and deliverability of the Nation's gas storage system, and provide a cost effective, safe, and reliable supply of natural gas to meet domestic demand. This report addresses the activities for the quarterly period of April 1, 2005 through June 30, 2005. During this time period efforts were directed toward (1) GSTC administration changes, (2) participating in the American Gas Association Operations Conference and Biennial Exhibition, (3) issuing a Request for Proposals (RFP) for proposal solicitation for funding, and (4) organizing the proposal selection meeting.

Joel Morrison

2005-09-14T23:59:59.000Z

326

Gas Storage Technology Consortium  

Science Conference Proceedings (OSTI)

Gas storage is a critical element in the natural gas industry. Producers, transmission and distribution companies, marketers, and end users all benefit directly from the load balancing function of storage. The unbundling process has fundamentally changed the way storage is used and valued. As an unbundled service, the value of storage is being recovered at rates that reflect its value. Moreover, the marketplace has differentiated between various types of storage services and has increasingly rewarded flexibility, safety, and reliability. The size of the natural gas market has increased and is projected to continue to increase towards 30 trillion cubic feet (TCF) over the next 10 to 15 years. Much of this increase is projected to come from electric generation, particularly peaking units. Gas storage, particularly the flexible services that are most suited to electric loads, is crucial in meeting the needs of these new markets. To address the gas storage needs of the natural gas industry, an industry-driven consortium was created - the Gas Storage Technology Consortium (GSTC). The objective of the GSTC is to provide a means to accomplish industry-driven research and development designed to enhance the operational flexibility and deliverability of the nation's gas storage system, and provide a cost-effective, safe, and reliable supply of natural gas to meet domestic demand. This report addresses the activities for the quarterly period of January1, 2007 through March 31, 2007. Key activities during this time period included: {lg_bullet} Drafting and distributing the 2007 RFP; {lg_bullet} Identifying and securing a meeting site for the GSTC 2007 Spring Proposal Meeting; {lg_bullet} Scheduling and participating in two (2) project mentoring conference calls; {lg_bullet} Conducting elections for four Executive Council seats; {lg_bullet} Collecting and compiling the 2005 GSTC Final Project Reports; and {lg_bullet} Outreach and communications.

Joel L. Morrison; Sharon L. Elder

2007-03-31T23:59:59.000Z

327

Cooling thermal storage  

Science Conference Proceedings (OSTI)

This article gives some overall guidelines for successful operation of cooling thermal storage installations. Electric utilities use rates and other incentives to encourage thermal storage, which not only reduces their system peaks but also transfers a portion of their load from expensive daytime inefficient peaking plants to less expensive nighttime base load high efficiency coal and nuclear plants. There are hundreds of thermal storage installations around the country. Some of these are very successful; others have failed to achieve all of their predicted benefits because application considerations were not properly addressed.

Gatley, D.P.

1987-04-01T23:59:59.000Z

328

Collector: storage wall systems  

SciTech Connect

Passive Trombe wall systems require massive masonry walls to minimize large temperature swings and movable night insulation to prevent excessive night heat losses. As a solar energy collection system, Trombe wall systems have low efficiencies because of the nature of the wall and, if auxiliary heat is needed, because of absorption of this heat. Separation of collector and storage functions markedly improves the efficiency. A simple fiberglass absorber can provide high efficiency while phase change storage provides a compact storage unit. The need for movable insulation is obviated.

Boardman, H.

1980-01-01T23:59:59.000Z

329

Guides and Case Studies for Hot-Dry and Mixed-Dry Climates | Department of  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Dry and Mixed-Dry Climates Dry and Mixed-Dry Climates Guides and Case Studies for Hot-Dry and Mixed-Dry Climates Map of the Hot-Dry and Mixed-Dry Zone of the United States. The zone contains the eastern side of California and follows the US border to cover the western half of Texas. The Department of Energy (DOE) has developed a series of best practices and case studies to help builders improve whole-house energy performance in buildings found in hot-dry and mixed-dry climates. Best Practice Guides New Construction Case Studies Improvements to Existing Homes Case Studies Best Practice Guides 40% Whole-House Energy Savings in Hot-Dry and Mixed-Dry Climates - Volume 9 New Construction Case Studies Arizona Project: Gordon Estates - Phoenix Builder: Mandalay Homes Profile: Fourteen homes in this subdivision achieved Challenge Home

330

Hydrogen Storage- Overview  

NLE Websites -- All DOE Office Websites (Extended Search)

- - Overview George Thomas, Hydrogen Consultant to SNL * and Jay Keller, Hydrogen Program Manager Sandia National Laboratories H 2 Delivery and Infrastructure Workshop May 7-8, 2003 * Most of this presentation has been extracted from George Thomas' invited BES Hydrogen Workshop presentation (May 13-14, 2003) Sandia National Laboratories 4/14/03 2 Sandia National Laboratories From George Thomas, BES workshop 5/13/03 H 2 storage is a critical enabling technology for H 2 use as an energy carrier The low volumetric density of gaseous fuels requires a storage method which compacts the fuel. Hence, hydrogen storage systems are inherently more complex than liquid fuels. Storage technologies are needed in all aspects of hydrogen utilization. production distribution utilization

331

NETL: Carbon Storage FAQs  

NLE Websites -- All DOE Office Websites (Extended Search)

Where is CO2 storage happening today? Where is CO2 storage happening today? Sleipner Project (Norway) Sleipner Project (Norway) Carbon dioxide (CO2) storage is currently happening across the United States and around the world. Large, commercial-scale projects, like the Sleipner CO2 Storage Site in Norway, the Weyburn-Midale CO2 Project in Canada, and the In Salah project in Algeria, have been injecting CO2 for many years. Each of these projects stores more than 1 million tons of CO2 per year. Large-scale efforts are currently underway in Africa, China, Australia, and Europe, too. These commercial-scale projects are demonstrating that large volumes of CO2 can be safely and permanently stored. Additionally, a multitude of pilot efforts are underway in different parts of the world to determine suitable locations and technologies for future

332

storage technology barriers. The...  

NLE Websites -- All DOE Office Websites (Extended Search)

Summit Power to build a 400-megawatt (MW) coal-fired power plant with carbon capture and storage (CCS) in Britain. The companies will submit the Caledonia Clean Energy Project to...

333

Flywheel Energy Storage Module  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

kWh100 kW Flywheel Energy Storage Module * 100KWh - 18 cost KWh vs. current State of the Art * Bonded Magnetic Bearings on Rim ID * No Shaft Hub (which limits surface speed)...

334

DUF6 Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

of depleted UF6 is stored in steel cylinders at three sites in the U.S. Depleted UF6 Inventory and Storage Locations U.S. DOE's inventory of depleted UF6 consists of approximately...

335

Storage Ring Parameters  

NLE Websites -- All DOE Office Websites (Extended Search)

Photon Source Parameters Storage Ring Parameters Print General Parameters Parameter Value Beam particle electron Beam energy 1.9 GeV (1.0-1.9 GeV possible) Injection energy 1.9 GeV...

336

Hydrogen storage composition and method  

DOE Patents (OSTI)

A hydrogen storage composition based on a metal hydride dispersed in an aerogel prepared by a sol-gel process. The starting material for the aerogel is an organometallic compound, including the alkoxysilanes, organometals of the form M(OR){sub X} where R is an organic ligand of the form C{sub n}H{sub 2n+1}, and organometals of the form MO{sub x}Ry where R is an alkyl group, where M is an oxide-forming metal, n, x and y are integers and y is two less than the valence of M. A sol is prepared by combining the starting material, alcohol, water, and an acid. The sol is conditioned to the proper viscosity and a hydride in the form of a fine powder is added. The mixture is polymerized and dried under supercritical conditions. The final product is a composition having a hydride uniformly dispersed throughout an inert, stable and highly porous matrix. It is capable of absorbing up to 30 motes of hydrogen per kilogram at room temperature and pressure, rapidly and reversibly. Hydrogen absorbed by the composition can be readily be recovered by heat or evacuation.

Wicks, G.G.; Heung, L.K.

1994-01-01T23:59:59.000Z

337

Thermal Energy Storage  

Science Conference Proceedings (OSTI)

The Ice Bear30 Hybrid Air Conditionerthermal energy storage system150uses smart integrated controls, ice storage, and a dedicated compressor for cooling. The system is designed to provide cooling to interior spaces by circulating refrigerant within an additional evaporator coil added to a standard unitary air conditioner. The Ice Bear 30 is a relatively small size (5 ton), intended for use in residential and light commercial applications. This report describes EPRI tests of the Ice Bear 30, which is manu...

2009-12-14T23:59:59.000Z

338

Analog storage integrated circuit  

DOE Patents (OSTI)

A high speed data storage array is defined utilizing a unique cell design for high speed sampling of a rapidly changing signal. Each cell of the array includes two input gates between the signal input and a storage capacitor. The gates are controlled by a high speed row clock and low speed column clock so that the instantaneous analog value of the signal is only sampled and stored by each cell on coincidence of the two clocks.

Walker, J. T. (Palo Alto, CA); Larsen, R. S. (Menlo Park, CA); Shapiro, S. L. (Palo Alto, CA)

1989-01-01T23:59:59.000Z

339

Thermal Energy Storage  

Science Conference Proceedings (OSTI)

This Technology Brief provides an update on the current state of cool thermal energy storage systems (TES) for end-use applications. Because of its ability to shape energy use, TES is strategic technology that allows end-users to reduce their energy costs while simultaneously providing benefits for electric utilities through persistent peak demand reduction and peak shifting. In addition to discussing the concepts of thermal energy storage, the Brief discusses the current state of TES technologies and dr...

2008-12-16T23:59:59.000Z

340

Analog storage integrated circuit  

DOE Patents (OSTI)

A high speed data storage array is defined utilizing a unique cell design for high speed sampling of a rapidly changing signal. Each cell of the array includes two input gates between the signal input and a storage capacitor. The gates are controlled by a high speed row clock and low speed column clock so that the instantaneous analog value of the signal is only sampled and stored by each cell on coincidence of the two clocks. 6 figs.

Walker, J.T.; Larsen, R.S.; Shapiro, S.L.

1989-03-07T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


341

NETL: Carbon Storage FAQs  

NLE Websites -- All DOE Office Websites (Extended Search)

different options for CO2 storage? different options for CO2 storage? Oil and gas reservoirs, many containing carbon dioxide (CO2), as well as natural deposits of almost pure CO2, can be found in many places in the United States and around the world. These are examples of long-term storage of CO2 by nature, where "long term" means millions of years. Their existence demonstrates that naturally occurring geologic formations and structures of various kinds are capable of securely storing CO2 deep in the subsurface for very long periods of time. Because of the economic importance of oil and gas, scientists and engineers have studied these natural deposits for many decades in order to understand the physical and chemical processes which led to their formation. There are also many decades of engineering experience in subsurface operations similar to those needed for CO2 storage. The most directly applicable experience comes from the oil industry, which, for 40 years, has injected CO2 in depleted oil reservoirs for the recovery of additional product through enhanced oil recovery (EOR). Additional experience comes from natural gas storage operations, which have utilized depleted gas reservoirs, as well as reservoirs containing only water. Scientists and engineers are now combining the knowledge obtained from study of natural deposits with experience from analogous operations as a basis for studying the potential for large-scale storage of CO2 in the deep subsurface.

342

Combined Corex/DRI technology  

Science Conference Proceedings (OSTI)

A feasible steelmaking alternative, the Corex/direct reduction/electric arc furnace combination, provides an economic route for the production of high quality steel products. This combination is a major step into a new generation of iron and steel mills. These mills are based on the production of liquid steel using noncoking coal and comply with the increasing demands of environmental protection. The favorable production costs are based on: Utilization of Corex and DRI/HBI plants; Production of hot metal equal to blast furnace quality; Use of low cost raw materials such as noncoking coal and lump ore; Use of process gas as reducing agent for DRI/HBI production; and Use of electric arc furnace with high hot metal input as the steelmaking process. The high flexibility of the process permits the adjustment of production in accordance with the strategy of the steel mills. New but proven technologies and applications of the latest state of art steelmaking process, e.g., Corex, in conjunction with DRI production as basic raw material for an electric arc furnace, will insure high quality, high availability, optimized energy generation at high efficiency rates, and high product quality for steelmaking.

Flickenschild, A.J.; Reufer, F. [Deutsche Voest-Alpine Industrieanlagenbau GmbH, Dusseldorf (Germany); Eberle, A.; Siuka, D. [Voest-Alpine Industrieanlagenbau, Linz (Austria)

1996-08-01T23:59:59.000Z

343

Energy Conversion, Storage, and Transport News  

Science Conference Proceedings (OSTI)

NIST Home > Energy Conversion, Storage, and Transport News. Energy Conversion, Storage, and Transport News. (showing ...

2010-10-26T23:59:59.000Z

344

Energy Conversion, Storage, and Transport Portal  

Science Conference Proceedings (OSTI)

NIST Home > Energy Conversion, Storage, and Transport Portal. Energy Conversion, Storage, and Transport Portal. Programs ...

2013-04-08T23:59:59.000Z

345

Measurements for Hydrogen Storage Materials  

Science Conference Proceedings (OSTI)

Measurements for Hydrogen Storage Materials. Summary: ... Hydrogen is promoted as petroleum replacement in the Hydrogen Economy. ...

2013-07-02T23:59:59.000Z

346

GAS STORAGE TECHNOLOGY CONSORTIUM  

Science Conference Proceedings (OSTI)

Gas storage is a critical element in the natural gas industry. Producers, transmission and distribution companies, marketers, and end users all benefit directly from the load balancing function of storage. The unbundling process has fundamentally changed the way storage is used and valued. As an unbundled service, the value of storage is being recovered at rates that reflect its value. Moreover, the marketplace has differentiated between various types of storage services, and has increasingly rewarded flexibility, safety, and reliability. The size of the natural gas market has increased and is projected to continue to increase towards 30 trillion cubic feet (TCF) over the next 10 to 15 years. Much of this increase is projected to come from electric generation, particularly peaking units. Gas storage, particularly the flexible services that are most suited to electric loads, is critical in meeting the needs of these new markets. In order to address the gas storage needs of the natural gas industry, an industry-driven consortium was created--the Gas Storage Technology Consortium (GSTC). The objective of the GSTC is to provide a means to accomplish industry-driven research and development designed to enhance operational flexibility and deliverability of the Nation's gas storage system, and provide a cost effective, safe, and reliable supply of natural gas to meet domestic demand. To accomplish this objective, the project is divided into three phases that are managed and directed by the GSTC Coordinator. Base funding for the consortium is provided by the U.S. Department of Energy (DOE). In addition, funding is anticipated from the Gas Technology Institute (GTI). The first phase, Phase 1A, was initiated on September 30, 2003, and is scheduled for completion on March 31, 2004. Phase 1A of the project includes the creation of the GSTC structure, development of constitution (by-laws) for the consortium, and development and refinement of a technical approach (work plan) for deliverability enhancement and reservoir management. This report deals with the second 3-months of the project and encompasses the period December 31, 2003, through March 31, 2003. During this 3-month, the dialogue of individuals representing the storage industry, universities and the Department of energy was continued and resulted in a constitution for the operation of the consortium and a draft of the initial Request for Proposals (RFP).

Robert W. Watson

2004-04-17T23:59:59.000Z

347

Gas Storage Technology Consortium  

Science Conference Proceedings (OSTI)

Gas storage is a critical element in the natural gas industry. Producers, transmission and distribution companies, marketers, and end users all benefit directly from the load balancing function of storage. The unbundling process has fundamentally changed the way storage is used and valued. As an unbundled service, the value of storage is being recovered at rates that reflect its value. Moreover, the marketplace has differentiated between various types of storage services, and has increasingly rewarded flexibility, safety, and reliability. The size of the natural gas market has increased and is projected to continue to increase towards 30 trillion cubic feet (TCF) over the next 10 to 15 years. Much of this increase is projected to come from electric generation, particularly peaking units. Gas storage, particularly the flexible services that are most suited to electric loads, is critical in meeting the needs of these new markets. In order to address the gas storage needs of the natural gas industry, an industry-driven consortium was created-the Gas Storage Technology Consortium (GSTC). The objective of the GSTC is to provide a means to accomplish industry-driven research and development designed to enhance operational flexibility and deliverability of the Nation's gas storage system, and provide a cost effective, safe, and reliable supply of natural gas to meet domestic demand. This report addresses the activities for the quarterly period of July 1, 2006 to September 30, 2006. Key activities during this time period include: {lg_bullet} Subaward contracts for all 2006 GSTC projects completed; {lg_bullet} Implement a formal project mentoring process by a mentor team; {lg_bullet} Upcoming Technology Transfer meetings: {sm_bullet} Finalize agenda for the American Gas Association Fall Underground Storage Committee/GSTC Technology Transfer Meeting in San Francisco, CA. on October 4, 2006; {sm_bullet} Identify projects and finalize agenda for the Fall GSTC Technology Transfer Meeting, Pittsburgh, PA on November 8, 2006; {lg_bullet} Draft and compile an electronic newsletter, the GSTC Insider; and {lg_bullet} New members update.

Joel L. Morrison; Sharon L. Elder

2006-09-30T23:59:59.000Z

348

1985 Federal Interim Storage Fee Study: a technical and economic analysis  

SciTech Connect

JAI examined alternative methods for structuring charges for FIS services and concluded that the combined interests of the Deaprtment and the users would be best served, and costs most appropriately recovered, by a two-part fee involving an Initial Payment upon execution of a contract for FIS services followed by a Final Payment upon delivery of the spent fuel to the Department. The Initial Payment would be an advance payment covering the pro rata share of preoperational costs, including (1) the capital costs of the required transfer facilities and storage area, (2) development costs, (3) government administrative costs including storage fund management, (4) impact aid payments made in accordance with section 136(e) of the Act, and (5) module costs (i.e., storage casks, drywells or silos). The Final Payment would be made at the time of delivery of the spent fuel to the Department and would be calculated to cover the sum of the following: (1) any under-or over-estimation in the costs used to calculate the Initial Payment of the fee (including savings due to rod consolidation), and (2) the total estimated cost of operation and decommissioning of the FIS facilities (including government administrative costs, storage fund management and impact aid). The module costs were included in the Initial Payment to preclude the possible need to obtain appropriations for federal funds to support the purchase of the modules in advance of receipt of the Final Payment. Charges for the transport of spent fuel from the reactor site to FIS facilities would be separately assessed at actual cost since these will be specific to each reactor site and destination.

1985-09-01T23:59:59.000Z

349

ARM - Campaign Instrument - dri-air  

NLE Websites -- All DOE Office Websites (Extended Search)

Send Campaign Instrument : Desert Research Institute Airborne Aerosol Instruments (DRI-AIR) Instrument Categories Aerosols, Airborne Observations Campaigns Aerosol IOP ...

350

FCT Hydrogen Storage: Current Technology  

NLE Websites -- All DOE Office Websites (Extended Search)

Current Technology to someone Current Technology to someone by E-mail Share FCT Hydrogen Storage: Current Technology on Facebook Tweet about FCT Hydrogen Storage: Current Technology on Twitter Bookmark FCT Hydrogen Storage: Current Technology on Google Bookmark FCT Hydrogen Storage: Current Technology on Delicious Rank FCT Hydrogen Storage: Current Technology on Digg Find More places to share FCT Hydrogen Storage: Current Technology on AddThis.com... Home Basics Current Technology Gaseous and Liquid Hydrogen Storage Materials-Based Hydrogen Storage Hydrogen Storage Challenges Status of Hydrogen Storage Technologies DOE R&D Activities Quick Links Hydrogen Production Hydrogen Delivery Fuel Cells Technology Validation Manufacturing Codes & Standards Education Systems Analysis Contacts Current Technology

351

Method of preparing nuclear wastes for tansportation and interim storage  

SciTech Connect

Nuclear waste is formed into a substantially water-insoluble solid for temporary storage and transportation by mixing the calcined waste with at least 10 weight percent powdered anhydrous sodium silicate to form a mixture and subjecting the mixture to a high humidity environment for a period of time sufficient to form cementitious bonds by chemical reaction. The method is suitable for preparing an interim waste form from dried high level radioactive wastes.

Bandyopadhyay, Gautam (Naperville, IL); Galvin, Thomas M. (Darien, IL)

1984-01-01T23:59:59.000Z

352

Mathematical modelling of brown seaweed drying curves  

Science Conference Proceedings (OSTI)

Simple solution on one-term exponential models is used in the analysis of raw data obtained from the drying experiment. The values of the parameters a, n and the constant k for the models are determined using a plot of curve drying models. Three different ... Keywords: brown seaweed, drying curves, mathematical models

Ahmad Fudholi; Mohd Hafidz Ruslan; Lim Chin Haw; Sohif Mat; Mohd Yusof Othman; Azami Zaharim; Kamaruzzaman Sopian

2012-01-01T23:59:59.000Z

353

Dry Cooling: Perspectives on Future Needs  

Science Conference Proceedings (OSTI)

The total number of dry-cooled power plants in the United States has increased significantly in recent years. This is because nonutility generators are using dry-cooling systems to meet environmental protection and water conservation requirements. A survey shows that utility planners expect that dry cooling could become an important cooling-system option for new utility plants.

1991-08-19T23:59:59.000Z

354

GAS STORAGE TECHNOLOGY CONSORTIUM  

SciTech Connect

Gas storage is a critical element in the natural gas industry. Producers, transmission and distribution companies, marketers, and end users all benefit directly from the load balancing function of storage. The unbundling process has fundamentally changed the way storage is used and valued. As an unbundled service, the value of storage is being recovered at rates that reflect its value. Moreover, the marketplace has differentiated between various types of storage services, and has increasingly rewarded flexibility, safety, and reliability. The size of the natural gas market has increased and is projected to continue to increase towards 30 trillion cubic feet (TCF) over the next 10 to 15 years. Much of this increase is projected to come from electric generation, particularly peaking units. Gas storage, particularly the flexible services that are most suited to electric loads, is critical in meeting the needs of these new markets. In order to address the gas storage needs of the natural gas industry, an industry-driven consortium was created--the Gas Storage Technology Consortium (GSTC). The objective of the GSTC is to provide a means to accomplish industry-driven research and development designed to enhance operational flexibility and deliverability of the Nation's gas storage system, and provide a cost effective, safe, and reliable supply of natural gas to meet domestic demand. To accomplish this objective, the project is divided into three phases that are managed and directed by the GSTC Coordinator. Base funding for the consortium is provided by the U.S. Department of Energy (DOE). In addition, funding is anticipated from the Gas Technology Institute (GTI). The first phase, Phase 1A, was initiated on September 30, 2003, and was completed on March 31, 2004. Phase 1A of the project included the creation of the GSTC structure, development and refinement of a technical approach (work plan) for deliverability enhancement and reservoir management. This report deals with Phase 1B and encompasses the period April 1, 2004, through June 30, 2004. During this 3-month period, a Request for Proposals (RFP) was made. A total of 17 proposals were submitted to the GSTC. A proposal selection meeting was held June 9-10, 2004 in Morgantown, West Virginia. Of the 17 proposals, 6 were selected for funding.

Robert W. Watson

2004-07-15T23:59:59.000Z

355

Radioactive waste storage issues  

SciTech Connect

In the United States we generate greater than 500 million tons of toxic waste per year which pose a threat to human health and the environment. Some of the most toxic of these wastes are those that are radioactively contaminated. This thesis explores the need for permanent disposal facilities to isolate radioactive waste materials that are being stored temporarily, and therefore potentially unsafely, at generating facilities. Because of current controversies involving the interstate transfer of toxic waste, more states are restricting the flow of wastes into - their borders with the resultant outcome of requiring the management (storage and disposal) of wastes generated solely within a state`s boundary to remain there. The purpose of this project is to study nuclear waste storage issues and public perceptions of this important matter. Temporary storage at generating facilities is a cause for safety concerns and underscores, the need for the opening of permanent disposal sites. Political controversies and public concern are forcing states to look within their own borders to find solutions to this difficult problem. Permanent disposal or retrievable storage for radioactive waste may become a necessity in the near future in Colorado. Suitable areas that could support - a nuclear storage/disposal site need to be explored to make certain the health, safety and environment of our citizens now, and that of future generations, will be protected.

Kunz, D.E.

1994-08-15T23:59:59.000Z

356

Superconducting magnetic energy storage  

DOE Green Energy (OSTI)

Long-time varying-daily, weekly, and seasonal-power demands require the electric utility industry to have installed generating capacity in excess of the average load. Energy storage can reduce the requirement for less efficient excess generating capacity used to meet peak load demands. Short-time fluctuations in electric power can occur as negatively damped oscillations in complex power systems with generators connected by long transmission lines. Superconducting inductors with their associated converter systems are under development for both load leveling and transmission line stabilization in electric utility systems. Superconducting magnetic energy storage (SMES) is based upon the phenomenon of the nearly lossless behavior of superconductors. Application is, in principal, efficient since the electromagnetic energy can be transferred to and from the storage coils without any intermediate conversion to other energy forms. Results from a reference design for a 10-GWh SMES unit for load leveling are presented. The conceptual engineering design of a 30-MJ, 10-MW energy storage coil is discussed with regard to system stabilization, and tests of a small scale, 100-KJ SMES system are presented. Some results of experiments are provided from a related technology based program which uses superconducting inductive energy storage to drive fusion plasmas.

Rogers, J.D.; Boenig, H.J.; Hassenzahl, W.V.; Schermer, R.I.

1978-01-01T23:59:59.000Z

357

Underground Natural Gas Storage by Storage Type  

U.S. Energy Information Administration (EIA) Indexed Site

2007 2008 2009 2010 2011 2012 View 2007 2008 2009 2010 2011 2012 View History All Operators Net Withdrawals 192,093 33,973 -348,719 -17,009 -347,562 -7,279 1967-2012 Injections 3,132,920 3,340,365 3,314,990 3,291,395 3,421,813 2,825,427 1935-2012 Withdrawals 3,325,013 3,374,338 2,966,180 3,274,385 3,074,251 2,818,148 1944-2012 Salt Cavern Storage Fields Net Withdrawals 20,001 -42,044 -56,010 -58,295 -92,413 -19,528 1994-2012 Injections 400,244 440,262 459,330 510,691 532,893 465,005 1994-2012 Withdrawals 420,245 398,217 403,321 452,396 440,480 445,477 1994-2012 Nonsalt Cavern Storage Net Withdrawals 172,092 76,017 -292,710 41,286 -255,148 12,249 1994-2012 Injections 2,732,676 2,900,103 2,855,667 2,780,703 2,888,920 2,360,422 1994-2012 Withdrawals

358

Underground Natural Gas Storage by Storage Type  

Gasoline and Diesel Fuel Update (EIA)

2007 2008 2009 2010 2011 2012 View 2007 2008 2009 2010 2011 2012 View History All Operators Net Withdrawals 192,093 33,973 -348,719 -17,009 -347,562 -7,279 1967-2012 Injections 3,132,920 3,340,365 3,314,990 3,291,395 3,421,813 2,825,427 1935-2012 Withdrawals 3,325,013 3,374,338 2,966,180 3,274,385 3,074,251 2,818,148 1944-2012 Salt Cavern Storage Fields Net Withdrawals 20,001 -42,044 -56,010 -58,295 -92,413 -19,528 1994-2012 Injections 400,244 440,262 459,330 510,691 532,893 465,005 1994-2012 Withdrawals 420,245 398,217 403,321 452,396 440,480 445,477 1994-2012 Nonsalt Cavern Storage Net Withdrawals 172,092 76,017 -292,710 41,286 -255,148 12,249 1994-2012 Injections 2,732,676 2,900,103 2,855,667 2,780,703 2,888,920 2,360,422 1994-2012 Withdrawals

359

Structural Integrity of Advanced Claddings During Spent Nuclear Fuel Transportation and Storage  

Science Conference Proceedings (OSTI)

Thermal creep is the dominant deformation mechanism of fuel cladding during transportation and dry storage of spent nuclear fuel. Thermal creep data and creep models of Westinghouse ZIRLO and LK3 cladding tubes were generated for use in spent-fuel storage and transportation applications. The final report consists of two volumes. This document (Volume 1) provides the project results obtained on non-irradiated and irradiated standard ZIRLO and non-irradiated optimized ZIRLO claddings.

2011-06-28T23:59:59.000Z

360

NREL: Learning - Hydrogen Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Hydrogen Storage Hydrogen Storage On the one hand, hydrogen's great asset as a renewable energy carrier is that it is storable and transportable. On the other hand, its very low natural density requires storage volumes that are impractical for vehicles and many other uses. Current practice is to compress the gas in pressurized tanks, but this still provides only limited driving range for vehicles and is bulkier than desirable for other uses as well. Liquefying the hydrogen more than doubles the fuel density, but uses up substantial amounts of energy to lower the temperature sufficiently (-253°C at atmospheric pressure), requires expensive insulated tanks to maintain that temperature, and still falls short of desired driving range. One possible way to store hydrogen at higher density is in the spaces within the crystalline

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


361

Storage Ring Operation Modes  

NLE Websites -- All DOE Office Websites (Extended Search)

Longitudinal bunch profile and Up: APS Storage Ring Parameters Longitudinal bunch profile and Up: APS Storage Ring Parameters Previous: Source Parameter Table Storage Ring Operation Modes Standard Operating Mode, top-up Fill pattern: 102 mA in 24 singlets (single bunches) with a nominal current of 4.25 mA and a spacing of 153 nanoseconds between singlets. Lattice configuration: Low emittance lattice with effective emittance of 3.1 nm-rad and coupling of 1%. Bunch length (rms): 33.5 ps. Refill schedule: Continuous top-up with single injection pulses occurring at a minimum of two minute intervals, or a multiple of two minute intervals. Special Operating Mode - 324 bunches, non top-up Fill pattern: 102 mA in 324 uniformly spaced singlets with a nominal single bunch current of 0.31 mA and a spacing of 11.37 nanoseconds between singlets.

362

Flywheel Energy Storage Module  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

kWh/100 kW kWh/100 kW Flywheel Energy Storage Module * 100KWh - 1/8 cost / KWh vs. current State of the Art * Bonded Magnetic Bearings on Rim ID * No Shaft / Hub (which limits surface speed) * Flexible Motor Magnets on Rim ID * Develop Touch-down System for Earthquake Flying Rim Eliminate Shaft and Hub Levitate on Passive Magnetic Bearings Increase Rim Tip Speed Larger Diameter Thinner Rim Stores More Energy 4 X increase in Stored Energy with only 60% Increase in Weight Development of a 100 kWh/100 kW Flywheel Energy Storage Module High Speed, Low Cost, Composite Ring with Bore-Mounted Magnetics Current State of the Art Flywheel Limitations of Existing Flywheel * 15 Minutes of storage * Limited to Frequency Regulation Application * Rim Speed (Stored Energy) Limited by Hub Strain and Shaft Dynamics

363

Inertial energy storage device  

DOE Patents (OSTI)

The inertial energy storage device of the present invention comprises a composite ring formed of circumferentially wound resin-impregnated filament material, a flanged hollow metal hub concentrically disposed in the ring, and a plurality of discrete filament bandsets coupling the hub to the ring. Each bandset is formed of a pair of parallel bands affixed to the hub in a spaced apart relationship with the axis of rotation of the hub being disposed between the bands and with each band being in the configuration of a hoop extending about the ring along a chordal plane thereof. The bandsets are disposed in an angular relationship with one another so as to encircle the ring at spaced-apart circumferential locations while being disposed in an overlapping relationship on the flanges of the hub. The energy storage device of the present invention has the capability of substantial energy storage due to the relationship of the filament bands to the ring and the flanged hub.

Knight, Jr., Charles E. (Knoxville, TN); Kelly, James J. (Oak Ridge, TN); Pollard, Roy E. (Powell, TN)

1978-01-01T23:59:59.000Z

364

Thermal energy storage material  

DOE Patents (OSTI)

A thermal energy storage material which is stable at atmospheric temperature and pressure and has a melting point higher than 32.degree.F. is prepared by dissolving a specific class of clathrate forming compounds, such as tetra n-propyl or tetra n-butyl ammonium fluoride, in water to form a substantially solid clathrate. The resultant thermal energy storage material is capable of absorbing heat from or releasing heat to a given region as it transforms between solid and liquid states in response to temperature changes in the region above and below its melting point.

Leifer, Leslie (Hancock, MI)

1976-01-01T23:59:59.000Z

365

Storage Business Model White Paper  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Storage Business Model White Paper Storage Business Model White Paper Summary June 11 2013 Storage Business Model White Paper - Purpose  Identify existing business models for investors/operators, utilities, end users  Discuss alignment of storage "value proposition" with existing market designs and regulatory paradigms  Difficulties in realizing wholesale market product revenue streams for distributed storage - the "bundled applications" problem  Discuss risks/barriers to storage adoption and where existing risk mitigation measures fall down  Recommendations for policy/research steps - Alternative business models - Accelerated research into life span and failure modes

366

Electrical Energy Storage  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Electrochemical Flow Storage System Typical Cell Power Density (Wcm 2 ) 0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1 UTRC Conventional Conventional flow battery cell UTRC flow battery...

367

Flash Storage Today  

Science Conference Proceedings (OSTI)

Can flash memory become the foundation for a new tier in the storage hierarchy? The past few years have been an exciting time for flash memory. The cost has fallen dramatically as fabrication has become more efficient and the market has grown; the density ...

Adam Leventhal

2008-07-01T23:59:59.000Z

368

Alkaline storage battery  

Science Conference Proceedings (OSTI)

An alkaline storage battery having located in a battery container a battery element comprising a positive electrode, a negative electrode, a separator and a gas ionizing auxiliary electrode, in which the gas ionizing electrode is contained in a bag of microporous film, is described.

Suzuki, S.

1984-02-28T23:59:59.000Z

369

Flywheel Energy Storage  

Science Conference Proceedings (OSTI)

Flywheels are under consideration as an alternative for electrochemical batteries in a variety of applications This summary report provides a discussion of the mechanics of flywheels and magnetic bearings, the general characteristics of inertial energy storage systems, design considerations for flywheel systems, materials for advanced flywheels, and cost considerations.

1997-09-03T23:59:59.000Z

370

Underground pumped hydroelectric storage  

DOE Green Energy (OSTI)

Underground pumped hydroelectric energy storage was conceived as a modification of surface pumped storage to eliminate dependence upon fortuitous topography, provide higher hydraulic heads, and reduce environmental concerns. A UPHS plant offers substantial savings in investment cost over coal-fired cycling plants and savings in system production costs over gas turbines. Potential location near load centers lowers transmission costs and line losses. Environmental impact is less than that for a coal-fired cycling plant. The inherent benefits include those of all pumped storage (i.e., rapid load response, emergency capacity, improvement in efficiency as pumps improve, and capacity for voltage regulation). A UPHS plant would be powered by either a coal-fired or nuclear baseload plant. The economic capacity of a UPHS plant would be in the range of 1000 to 3000 MW. This storage level is compatible with the load-leveling requirements of a greater metropolitan area with population of 1 million or more. The technical feasibility of UPHS depends upon excavation of a subterranean powerhouse cavern and reservoir caverns within a competent, impervious rock formation, and upon selection of reliable and efficient turbomachinery - pump-turbines and motor-generators - all remotely operable.

Allen, R.D.; Doherty, T.J.; Kannberg, L.D.

1984-07-01T23:59:59.000Z

371

Cryptographic cloud storage  

Science Conference Proceedings (OSTI)

We consider the problem of building a secure cloud storage service on top of a public cloud infrastructure where the service provider is not completely trusted by the customer. We describe, at a high level, several architectures that combine recent and ...

Seny Kamara; Kristin Lauter

2010-01-01T23:59:59.000Z

372

Pneumatic energy storage  

DOE Green Energy (OSTI)

An essential component to hybrid electric and electric vehicles is energy storage. A power assist device could also be important to many vehicle applications. This discussion focuses on the use of compressed gas as a system for energy storage and power in vehicle systems. Three possible vehicular applications for which these system could be used are discussed in this paper. These applications are pneumatically driven vehicles, series hybrid electric vehicles, and power boost for electric and conventional vehicles. One option for a compressed gas system is as a long duration power output device for purely pneumatic and hybrid cars. This system must provide enough power and energy to drive under normal conditions for a specified time or distance. The energy storage system for this use has the requirement that it will be highly efficient, compact, and have low mass. Use of a compressed gas energy storage as a short duration, high power output system for conventional motor vehicles could reduce engine size or reduce transient emissions. For electric vehicles this kind of system could lengthen battery life by providing battery load leveling during accelerations. The system requirements for this application are that it be compact and have low mass. The efficiency of the system is a secondary consideration in this application.

Flowers, D.

1995-09-19T23:59:59.000Z

373

NV Energy Electricity Storage Valuation  

SciTech Connect

This study examines how grid-level electricity storage may benet the operations of NV Energy in 2020, and assesses whether those benets justify the cost of the storage system. In order to determine how grid-level storage might impact NV Energy, an hourly production cost model of the Nevada Balancing Authority (\\BA") as projected for 2020 was built and used for the study. Storage facilities were found to add value primarily by providing reserve. Value provided by the provision of time-of-day shifting was found to be limited. If regulating reserve from storage is valued the same as that from slower ramp rate resources, then it appears that a reciprocating engine generator could provide additional capacity at a lower cost than a pumped storage hydro plant or large storage capacity battery system. In addition, a 25-MW battery storage facility would need to cost $650/kW or less in order to produce a positive Net Present Value (NPV). However, if regulating reserve provided by storage is considered to be more useful to the grid than that from slower ramp rate resources, then a grid-level storage facility may have a positive NPV even at today's storage system capital costs. The value of having storage provide services beyond reserve and time-of-day shifting was not assessed in this study, and was therefore not included in storage cost-benefit calculations.

Ellison, James F.; Bhatnagar, Dhruv; Samaan, Nader A.; Jin, Chunlian

2013-06-30T23:59:59.000Z

374

Carbon-based Materials for Energy Storage  

E-Print Network (OSTI)

Flexible, lightweight energy-storage devices are of greatstrategy to fabricate flexible energy-storage devices.Flexible, lightweight energy-storage devices (batteries and

Rice, Lynn Margaret

2012-01-01T23:59:59.000Z

375

AQUIFER THERMAL ENERGY STORAGE-A SURVEY  

E-Print Network (OSTI)

High temperature underground thermal energy storage, inProceedings, Thermal Energy Storage in Aquifers Workshop:underground thermal energy storage, in ATES newsletter:

Tsang, Chin Fu

2012-01-01T23:59:59.000Z

376

Storage/Handling | Department of Energy  

NLE Websites -- All DOE Office Websites (Extended Search)

StorageHandling StorageHandling Records Management Procedures for Storage, Transfer & Retrieval of Records from the Washington National Records Center (WNRC) or Legacy Management...

377

Nanostructured Materials for Energy Generation and Storage  

E-Print Network (OSTI)

for Electrochemical Energy Storage Nanostructured Electrodesof Electrode Design for Energy Storage and Generation .batteries and their energy storage efficiency. vii Contents

Khan, Javed Miller

2012-01-01T23:59:59.000Z

378

Energy Storage Demonstration Project Locations | Department of...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Energy Storage Demonstration Project Locations Energy Storage Demonstration Project Locations Map of the United States showing the location of Energy Storage Demonstration projects...

379

THERMAL ENERGY STORAGE IN AQUIFERS WORKSHOP  

E-Print Network (OSTI)

Survey of Thermal Energy Storage in Aquifers Coupled withGeneration and Energy Storage," presented at Frontiers ofStudy of Underground Energy Storage Using High-Pressure,

Authors, Various

2011-01-01T23:59:59.000Z

380

AQUIFER THERMAL ENERGY STORAGE-A SURVEY  

E-Print Network (OSTI)

1978, High temperature underground thermal energy storage,in Proceedings, Thermal Energy Storage in Aquifers Workshop:High temperature underground thermal energy storage, in ATES

Tsang, Chin Fu

2012-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


381

THERMAL ENERGY STORAGE IN AQUIFERS WORKSHOP  

E-Print Network (OSTI)

B. Quale. Seasonal storage of thermal energy in water in theand J. Schwarz, Survey of Thermal Energy Storage in AquifersSecond Annual Thermal Energy Storage Contractors'

Authors, Various

2011-01-01T23:59:59.000Z

382

Nuclear Fuels Storage & Transportation Planning Project | Department...  

NLE Websites -- All DOE Office Websites (Extended Search)

Nuclear Fuels Storage & Transportation Planning Project Nuclear Fuels Storage & Transportation Planning Project Independent Spent Fuel Storage Installation (ISFSI) at the shutdown...

383

Fuel Cell Technologies Office: Hydrogen Storage  

Office of Energy Efficiency and Renewable Energy (EERE) Indexed Site

| Consumer Information Hydrogen Storage Search Search Help Hydrogen Storage EERE Fuel Cell Technologies Office Hydrogen Storage Printable Version Share this resource Send...

384

Distributed Generation with Heat Recovery and Storage  

E-Print Network (OSTI)

of electricity and natural gas DER No Heat Storage: therecovery and storage) utility electricity and natural gasbut no heat storage, a 200 kW natural gas reciprocating

Siddiqui, Afzal S.; Marnay, Chris; Firestone, Ryan M.; Zhou, Nan

2008-01-01T23:59:59.000Z

385

Natural Gas Underground Storage Capacity (Summary)  

Gasoline and Diesel Fuel Update (EIA)

Salt Caverns Storage Capacity Aquifers Storage Capacity Depleted Fields Storage Capacity Total Working Gas Capacity Working Gas Capacity of Salt Caverns Working Gas Capacity of...

386

Storage Ring | Advanced Photon Source  

NLE Websites -- All DOE Office Websites (Extended Search)

The Electron Storage Ring The 7-GeV electrons are injected into the 1104-m-circumference storage ring, a circle of more than 1,000 electromagnets and associated equipment, located...

387

Hydrogen Storage Technologies Hydrogen Delivery  

E-Print Network (OSTI)

Hydrogen Storage Technologies Roadmap Hydrogen Delivery Technical Team Roadmap June 2013 #12;This.................................................................................. 13 6. Hydrogen Storage and Innovation for Vehicle efficiency and Energy sustainability) is a voluntary, nonbinding, and nonlegal

388

Thermal energy storage application areas  

DOE Green Energy (OSTI)

The use of thermal energy storage in the areas of building heating and cooling, recovery of industrial process and waste heat, solar power generation, and off-peak energy storage and load management in electric utilities is reviewed. (TFD)

Not Available

1979-03-01T23:59:59.000Z

389

Part II Energy Storage Technologies  

NLE Websites -- All DOE Office Websites (Extended Search)

II. Energy Storage Technology Overview * Instructor - Haresh Kamath, EPRI PEAC * Short term - Flywheels, Cranking Batteries, Electrochemical Capacitors, SMES * Long term -...

390

Wet/dry cooling tower and method  

DOE Patents (OSTI)

A wet/dry cooling tower wherein a liquid to-be-cooled is flowed along channels of a corrugated open surface or the like, which surface is swept by cooling air. The amount of the surface covered by the liquid is kept small compared to the dry part thereof so that said dry part acts as a fin for the wet part for heat dissipation.

Glicksman, Leon R. (Lynnfield, MA); Rohsenow, Warren R. (Waban, MA)

1981-01-01T23:59:59.000Z

391

Normal matter storage of antiprotons  

SciTech Connect

Various simple issues connected with the possible storage of anti p in relative proximity to normal matter are discussed. Although equilibrium storage looks to be impossible, condensed matter systems are sufficiently rich and controllable that nonequilibrium storage is well worth pursuing. Experiments to elucidate the anti p interactions with normal matter are suggested. 32 refs.

Campbell, L.J.

1987-01-01T23:59:59.000Z

392

Transportable Energy Storage Systems Project  

Science Conference Proceedings (OSTI)

This project will define the requirements and specification for a transportable energy storage system and then screen various energy storage options and assess their capability to meet that specification. The application will be designed to meet peak electrical loads (3-4 hours of storage) on the electrical distribution system.

2009-10-23T23:59:59.000Z

393

COSBench: cloud object storage benchmark  

Science Conference Proceedings (OSTI)

With object storage systems being increasingly recognized as a preferred way to expose one's storage infrastructure to the web, the past few years have witnessed an explosion in the acceptance of these systems. Unfortunately, the proliferation of available ... Keywords: benchmark tool, object storage

Qing Zheng; Haopeng Chen; Yaguang Wang; Jian Zhang; Jiangang Duan

2013-04-01T23:59:59.000Z

394

Hybrid electrical energy storage systems  

Science Conference Proceedings (OSTI)

Electrical energy is a high quality form of energy that can be easily converted to other forms of energy with high efficiency and, even more importantly, it can be used to control lower grades of energy quality with ease. However, building a cost-effective ... Keywords: charge, electrical storage, energy, energy storage, hybrid storage, management

Massoud Pedram; Naehyuck Chang; Younghyun Kim; Yanzhi Wang

2010-08-01T23:59:59.000Z

395

Cold vacuum drying facility design requirements  

SciTech Connect

This document provides the detailed design requirements for the Spent Nuclear Fuel Project Cold Vacuum Drying Facility. Process, safety, and quality assurance requirements and interfaces are specified.

IRWIN, J.J.

1999-07-01T23:59:59.000Z

396

Liquid Desiccant Drying of Thermoreversibly Gelcast Bodies  

Science Conference Proceedings (OSTI)

Presentation Title, Liquid Desiccant Drying of Thermoreversibly Gelcast Bodies. Author(s), Noah O Shanti, Katherine T Faber. On-Site Speaker (Planned), Noah ...

397

,"Utah Dry Natural Gas Proved Reserves"  

U.S. Energy Information Administration (EIA) Indexed Site

,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Utah Dry Natural Gas Proved Reserves",10,"Annual",2011,"6301977" ,"Release Date:","81...

398

ARM - Campaign Instrument - dri-gnd  

NLE Websites -- All DOE Office Websites (Extended Search)

Send Campaign Instrument : Desert Research Institute Ground-Based Aerosol Instruments (DRI-GND) Instrument Categories Aerosols Campaigns Aerosol IOP Download Data Southern...

399

Integrated Ingredients Dehydrated Agricultural Drying Low Temperature...  

Open Energy Info (EERE)

Login | Sign Up Search Page Edit with form History Facebook icon Twitter icon Integrated Ingredients Dehydrated Agricultural Drying Low Temperature Geothermal Facility Jump...

400

Dry Barrier Mix in Reduction Cell Cathodes  

Science Conference Proceedings (OSTI)

Presentation Title, Dry Barrier Mix in Reduction Cell Cathodes ... successfully tested as a replacement for barrier bricks in several reduction cell technology types ...

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


401

Natural Gas Dry Production (Annual Supply & Disposition)  

U.S. Energy Information Administration (EIA) Indexed Site

Repressuring Nonhydrocarbon Gases Removed Vented and Flared Marketed Production Natural Gas Processed NGPL Production, Gaseous Equivalent Dry Production Imports By Pipeline LNG...

402

,"Pennsylvania Dry Natural Gas Reserves Estimated Production...  

U.S. Energy Information Administration (EIA) Indexed Site

Of Series","Frequency","Latest Data for" ,"Data 1","Pennsylvania Dry Natural Gas Reserves Estimated Production (Billion Cubic Feet)",1,"Annual",2011 ,"Release...

403

,"Mississippi Dry Natural Gas Reserves Estimated Production ...  

U.S. Energy Information Administration (EIA) Indexed Site

Of Series","Frequency","Latest Data for" ,"Data 1","Mississippi Dry Natural Gas Reserves Estimated Production (Billion Cubic Feet)",1,"Annual",2011 ,"Release...

404

,"Dry Natural Gas Reserves Estimated Production "  

U.S. Energy Information Administration (EIA) Indexed Site

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Dry Natural Gas Reserves Estimated Production ",52,"Annual",2011,"6301977" ,"Release Date:","81...

405

Geothermal Food Processors Agricultural Drying Low Temperature...  

Open Energy Info (EERE)

Login | Sign Up Search Page Edit with form History Facebook icon Twitter icon Geothermal Food Processors Agricultural Drying Low Temperature Geothermal Facility Jump to:...

406

,"Ohio Dry Natural Gas Proved Reserves"  

U.S. Energy Information Administration (EIA) Indexed Site

,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Ohio Dry Natural Gas Proved Reserves",10,"Annual",2011,"6301977" ,"Release Date:","81...

407

,"California Dry Natural Gas Proved Reserves"  

U.S. Energy Information Administration (EIA) Indexed Site

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","California Dry Natural Gas Proved Reserves",10,"Annual",2011,"6301977" ,"Release Date:","81...

408

FINAL REPORT: Transformational electrode drying process  

SciTech Connect

This report includes major findings and outlook from the transformational electrode drying project performance period from January 6, 2012 to August 1, 2012. Electrode drying before cell assembly is an operational bottleneck in battery manufacturing due to long drying times and batch processing. Water taken up during shipment and other manufacturing steps needs to be removed before final battery assembly. Conventional vacuum ovens are limited in drying speed due to a temperature threshold needed to avoid damaging polymer components in the composite electrode. Roll to roll operation and alternative treatments can increase the water desorption and removal rate without overheating and damaging other components in the composite electrode, thus considerably reducing drying time and energy use. The objective of this project was the development of an electrode drying procedure, and the demonstration of processes with no decrease in battery performance. The benchmark for all drying data was an 80°C vacuum furnace treatment with a residence time of 18 – 22 hours. This report demonstrates an alternative roll to roll drying process with a 500-fold improvement in drying time down to 2 minutes and consumption of only 30% of the energy compared to vacuum furnace treatment.

Claus Daniel, C.; Wixom, M. (A123 Systems, Inc.)

2013-12-19T23:59:59.000Z

409

Propane earth materials drying techniques and technologies.  

E-Print Network (OSTI)

??A feasibility study for the use of propane as a subbase drying technique. Michael Blahut (1) Dr. Vernon Schaefer (2) Dr. Chris Williams (3) The… (more)

Blahut, Michael Edward

2010-01-01T23:59:59.000Z

410

,"Texas Dry Natural Gas Proved Reserves"  

U.S. Energy Information Administration (EIA) Indexed Site

,"Worksheet Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","Texas Dry Natural Gas Proved Reserves",10,"Annual",2011,"6301981" ,"Release Date:","81...

411

,"New Mexico Dry Natural Gas Proved Reserves"  

U.S. Energy Information Administration (EIA) Indexed Site

Name","Description"," Of Series","Frequency","Latest Data for" ,"Data 1","New Mexico Dry Natural Gas Proved Reserves",10,"Annual",2011,"6301977" ,"Release Date:","81...

412

Energy Storage & Power Electronics 2008 Peer Review - Energy Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

& Power Electronics 2008 Peer Review - Energy & Power Electronics 2008 Peer Review - Energy Storage Systems (ESS) Presentations Energy Storage & Power Electronics 2008 Peer Review - Energy Storage Systems (ESS) Presentations The 2008 Peer Review Meeting for the DOE Energy Storage and Power Electronics Program (ESPE) was held in Washington DC on Sept. 29-30, 2008. Current and completed program projects were presented and reviewed by a group of industry professionals. The 2008 agenda was composed of 28 projects that covered a broad range of new and ongoing, state-of-the-art, energy storage and power electronics technologies, including updates on the collaborations among DOE/ESPE, CEC in California, and NYSERDA in New York. Energy Storage Systems (ESS) presentations are available below. ESPE 2008 Peer Review - EAC Energy Storage Subcommittee - Brad Roberts, S&C

413

NATURAL GAS STORAGE ENGINEERING Kashy Aminian  

E-Print Network (OSTI)

NATURAL GAS STORAGE ENGINEERING Kashy Aminian Petroleum & Natural Gas Engineering, West Virginia University, Morgantown, WV, USA. Keywords: Gas Storage, Natural Gas, Storage, Deliverability, Inventory Chapters Glossary Bibliography Biographical Sketch Summary Underground storage of natural gas

Mohaghegh, Shahab

414

FAQs about Storage Capacity  

Gasoline and Diesel Fuel Update (EIA)

about Storage Capacity about Storage Capacity How do I determine if my tanks are in operation or idle or non-reportable? Refer to the following flowchart. Should idle capacity be included with working capacity? No, only report working capacity of tanks and caverns in operation, but not for idle tanks and caverns. Should working capacity match net available shell in operation/total net available shell capacity? Working capacity should be less than net available shell capacity because working capacity excludes contingency space and tank bottoms. What is the difference between net available shell capacity in operation and total net available shell capacity? Net available shell capacity in operation excludes capacity of idle tanks and caverns. What do you mean by transshipment tanks?

415

gas cylinder storage guidelines  

NLE Websites -- All DOE Office Websites (Extended Search)

Compressed Gas Cylinder Storage Guidelines Compressed Gas Cylinder Storage Guidelines All cylinders must be stored vertical, top up across the upper half the cylinder but below the shoulder. Small cylinder stands or other methods may be appropriate to ensure that the cylinders are secured from movement. Boxes, cartons, and other items used to support small cylinders must not allow water to accumulate and possible cause corrosion. Avoid corrosive chemicals including salt and fumes - keep away from direct sunlight and keep objects away that could fall on them. Use Gas pressure regulators that have been inspected in the last 5 years. Cylinders that contain fuel gases whether full or empty must be stored away from oxidizer cylinders at a minimum of 20 feet. In the event they are stored together, they must be separated by a wall 5 feet high with

416

Carbon Storage Review 2012  

NLE Websites -- All DOE Office Websites (Extended Search)

Sequestration Options in the Illinois Basin - Phase III DE-FC26-05NT42588 Robert J. Finley and the MGSC Project Team Illinois State Geological Survey (University of Illinois) and Schlumberger Carbon Services U.S. Department of Energy National Energy Technology Laboratory Carbon Storage R&D Project Review Meeting Developing the Technologies and Building the Infrastructure for CO 2 Storage August 21-23, 2012 * The Midwest Geological Sequestration Consortium is funded by the U.S. Department of Energy through the National Energy Technology Laboratory (NETL) via the Regional Carbon Sequestration Partnership Program (contract number DE-FC26-05NT42588) and by a cost share agreement with the Illinois Department of Commerce and Economic Opportunity, Office of Coal Development through the Illinois Clean Coal

417

NSLS VUV Storage Ring  

NLE Websites -- All DOE Office Websites (Extended Search)

VUV Storage Ring VUV Storage Ring VUV Normal Operations Operating Parameters (pdf) Insertion Devices Flux & Brightness Orbit Stability Lattice Information (pdf) Lattice : MAD Dataset Mechanical Drawing (pdf) VUV Operating Schedule Introduction & History The VUV Ring at the National Synchrotron Light Source was one of the first of the 2nd generation light sources to operate in the world. Initially designed in 1976 the final lattice design was completed in 1978 shortly after funding was approved. Construction started at the beginning of FY 1979 and installation of the magnets was well underway by the end of FY 1980. The first stored beam was achieved in December of 1981 at 600 MeV and the first photons were delivered to beamlines in May 1982, with routine beam line operations underway by the start of FY 1983. The number of beam

418

Solar panel with storage  

SciTech Connect

A self contained, fully automatic, vertical wall panel, solar energy system characterized by having no moving parts in the panel. The panel is substantially a shallow rectangular box having a closed perimeter, an outer insulating chamber which is substantially a double glazed window, and an inner energy storage chamber which is provided with containers of phase change materials. The energy storage chamber is provided with air entrance and exit passages which communicate with the space to be heated. Thermostatically controlled blowers serve to move air from the space to be heated across the containers of phase change material and back to the space to be heated. Thermostatically controlled blowers also serve to move insulating material into and out of the insulating chamber at appropriate times.

Zilisch, K.P.

1984-05-08T23:59:59.000Z

419

Superconducting magnetic energy storage  

SciTech Connect

Recent programmatic developments in Superconducting Magnetic Energy Storage (SMES) have prompted renewed and widespread interest in this field. In mid 1987 the Defense Nuclear Agency, acting for the Strategic Defense Initiative Office, issued a request for proposals for the design and construction of SMES Engineering Test Model (ETM). Two teams, one led by Bechtel and the other by Ebasco, are now engaged in the first phase of the development of a 10 to 20 MWhr ETM. This report presents the rationale for energy storage on utility systems, describes the general technology of SMES, and explains the chronological development of the technology. The present ETM program is outlined; details of the two projects for ETM development are described in other papers in these proceedings. The impact of high T/sub c/ materials on SMES is discussed. 69 refs., 3 figs., 3 tabs.

Hassenzahl, W.

1988-08-01T23:59:59.000Z

420

Superconducting magnetic energy storage  

DOE Green Energy (OSTI)

Fusion power production requires energy storage and transfer on short time scales to create confining magnetic fields and for heating plasmas. The theta-pinch Scyllac Fusion Test Reactor (SFTR) requires 480 MJ of energy to drive the 5-T compression field with a 0.7-ms rise time. Tokamak Experimental Power Reactors (EPR) require 1 to 2 GJ of energy with a 1 to 2-s rise time for plasma ohmic heating. The design, development, and testing of four 300-kJ energy storage coils to satisfy the SFTR needs are described. Potential rotating machinery and homopolar energy systems for both the Reference Theta-Pinch Reactor (RTPR) and tokamak ohmic-heating are presented.

Rogers, J.D.

1976-01-01T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
to obtain the most current and comprehensive results.


421

Fact Sheet: Energy Storage Technology Advancement Partnership...  

Energy.gov (U.S. Department of Energy (DOE)) Indexed Site

Fact Sheet: Energy Storage Technology Advancement Partnership (October 2012) More Documents & Publications Webinar Presentation: Energy Storage Solutions for Microgrids (November...

422

Energy Storage Technologies Available for Licensing ...  

Energy Storage Technologies Available for Licensing U.S. Department of Energy laboratories and participating research institutions have energy storage ...

423

Maui energy storage study.  

SciTech Connect

This report investigates strategies to mitigate anticipated wind energy curtailment on Maui, with a focus on grid-level energy storage technology. The study team developed an hourly production cost model of the Maui Electric Company (MECO) system, with an expected 72 MW of wind generation and 15 MW of distributed photovoltaic (PV) generation in 2015, and used this model to investigate strategies that mitigate wind energy curtailment. It was found that storage projects can reduce both wind curtailment and the annual cost of producing power, and can do so in a cost-effective manner. Most of the savings achieved in these scenarios are not from replacing constant-cost diesel-fired generation with wind generation. Instead, the savings are achieved by the more efficient operation of the conventional units of the system. Using additional storage for spinning reserve enables the system to decrease the amount of spinning reserve provided by single-cycle units. This decreases the amount of generation from these units, which are often operated at their least efficient point (at minimum load). At the same time, the amount of spinning reserve from the efficient combined-cycle units also decreases, allowing these units to operate at higher, more efficient levels.

Ellison, James; Bhatnagar, Dhruv; Karlson, Benjamin

2012-12-01T23:59:59.000Z

424

Management of spent nuclear fuel on the Oak Ridge Reservation, Oak Ridge, Tennessee: Environmental assessment  

SciTech Connect

On June 1, 1995, DOE issued a Record of Decision [60 Federal Register 28680] for the Department-wide management of spent nuclear fuel (SNF); regionalized storage of SNF by fuel type was selected as the preferred alternative. The proposed action evaluated in this environmental assessment is the management of SNF on the Oak Ridge Reservation (ORR) to implement this preferred alternative of regional storage. SNF would be retrieved from storage, transferred to a hot cell if segregation by fuel type and/or repackaging is required, loaded into casks, and shipped to off-site storage. The proposed action would also include construction and operation of a dry cask SNF storage facility on ORR, in case of inadequate SNF storage. Action is needed to enable DOE to continue operation of the High Flux Isotope Reactor, which generates SNF. This report addresses environmental impacts.

1996-02-01T23:59:59.000Z

425

Energy Storage | Open Energy Information  

Open Energy Info (EERE)

Storage Storage Jump to: navigation, search TODO: Source information Contents 1 Introduction 2 Benefits 3 Technologies 4 References Introduction Energy storage is a tool that can be used by grid operators to help regulate the electrical grid and help meet demand. In its most basic form, energy storage "stores" excess energy that would otherwise be wasted so that it can be used later when demand is higher. Energy Storage can be used to balance microgrids, perform frequency regulation, and provide more reliable power for high tech industrial facilities.[1] Energy storage will also allow for the expansion of intermittent renewable energy, like wind and solar, to provide electricity around the clock. Some of the major issues concerning energy storage include cost, efficiency, and size.

426

Grid Applications for Energy Storage  

NLE Websites -- All DOE Office Websites (Extended Search)

Applications for Energy Storage Applications for Energy Storage Flow Cells for Energy Storage Workshop Washington DC 7-8 March 2012 Joe Eto jheto@lbl.gov (510) 486-7284 Referencing a Recent Sandia Study,* This Talk Will: Describe and illustrate selected grid applications for energy storage Time-of-use energy cost management Demand charge management Load following Area Regulation Renewables energy time shift Renewables capacity firming Compare Sandia's estimates of the economic value of these applications to the Electricity Storage Association's estimates of the capital costs of energy storage technologies *Eyer, J. and G. Corey. Energy Storage for the Electricity Grid: Benefits and Market Potential Assessment Guide. February 2010. SAND2010-0815 A Recent Sandia Study Estimates the Economic

427

Preservation of Laboratory Instruments in Static Storage  

SciTech Connect

It is desirable to place laboratory instruments in static storage so that they may be put into operation with only normal servicing. Such instruments may be subject to many forms of deterioration. There may be deterioration of metal parts due to chemical and electrolytic corrosion and the effects of moisture, excessive dryness, and microorganisms, i.e., mildew on organic parts. To preserve such instruments without disassembly or troublesome surface coatings, requires methods that will remove the major cause of deterioration - that is, excessive humidity, by reducing and maintaining the relative humidity of the air surrounding the item at 30 per cent or less. It is also necessary to eliminate or separate hygroscopic materials from the item since they will cause corrosion, by surface adsorption and condensation, even though a dry atmosphere is maintained. The methods and materials used must not only be efficient and economical but also require a minimun of maintenance, Protection against physical damage and temperature extremes is dependent upon the storage site and is not considered in this report.

Gregg, J. L.; Shackelford, M. A.

1950-02-22T23:59:59.000Z

428

DOE hot dry rock program  

DOE Green Energy (OSTI)

Hydraulic fracturing has been used to create and subsequently to enlarge the first hot dry rock heat-extraction loop at Fenton Hill, New Mexico. Encouraging results prompted the DOE to expand this project into a program of national scope. The elements of that Program and their present status are discussed. Emphasis is given the ongoing Fenton Hill Project where techniques and information developed in the existing research system will soon be used to produce a multiply-fractured engineering system in hotter rock at the same site. Recent results from research loop operation and progress in constructing the engineering system are reported. Although acoustic mapping and system geometry indicate that the primary hydraulic fractures are essentially vertical, relatively low fracturing pressure and absence of a sharp breakdown suggest that at Fenton Hill fracture initiation occurs by reopening of old natural fractures rather than by initiation of new ones. Flow patterns and temperature behavior suggest opening of additional old fractures as the loop is operated. Except where the hot fluid leaves the crack system to enter the production well, flow impedances are very low without either artificial propping or inflation by pressurization.

Nunz, G.J.

1980-01-01T23:59:59.000Z

429

The hot dry rock geothermal energy program  

DOE Green Energy (OSTI)

The paper presents a simplified description of the Department of Energy's Hot-Dry-Rock program conducted at Fenton Hill, New Mexico. What a hot-dry-rock resource is and what the magnitude of the resource is are also described.

Smith, M.C.

1987-09-01T23:59:59.000Z

430

FINAL REPORT: Transformational electrode drying process  

DOE Green Energy (OSTI)

Electrode drying before cell assembly is an operational bottleneck in battery manufacturing due to long drying times and batch processing. Water taken up during shipment and other manufacturing steps needs to be removed before final battery assembly. Conventional vacuum ovens are limited in drying speed due to a temperature threshold needed to avoid damaging polymer components in the composite electrode. Roll to roll operation and alternative treatments can increase the water desorption and removal rate without overheating and damaging other components in the composite electrode, thus considerably reducing drying time and energy use. The objective of this project was the development of an electrode drying procedure, and the demonstration of processes with no decrease in battery performance. The benchmark for all drying data was an 80°C vacuum furnace treatment with a residence time of 18 – 22 hours. This report demonstrates an alternative roll to roll drying process with a 500-fold improvement in drying time down to 2 minutes and consumption of only 30% of the energy compared to vacuum furnace treatment.

Claus Daniel, C.; Wixom, M. (A123 Systems, Inc.)

2013-12-19T23:59:59.000Z

431

EIA - Natural Gas Storage Data & Analysis  

Gasoline and Diesel Fuel Update (EIA)

Storage Storage Weekly Working Gas in Underground Storage U.S. Natural gas inventories held in underground storage facilities by East, West, and Producing regions (weekly). Underground Storage - All Operators Total storage by base gas and working gas, and storage activity by State (monthly, annual). Underground Storage by Type U.S. storage and storage activity by all operators, salt cavern fields and nonsalt cavern (monthly, annual). Underground Storage Capacity Storage capacity, working gas capacity, and number of active fields for salt caverns, aquifers, and depleted fields by State (monthly, annual). Liquefied Natural Gas Additions to and Withdrawals from Storage By State (annual). Weekly Natural Gas Storage Report Estimates of natural gas in underground storage for the U.S. and three regions of the U.S.

432

NETL: Carbon Storage - NETL Carbon Capture and Storage Database  

NLE Websites -- All DOE Office Websites (Extended Search)

CCS Database CCS Database Carbon Storage NETL's Carbon Capture, Utilization, and Storage Database - Version 4 Welcome to NETL's Carbon Capture, Utilization, and Storage (CCUS) Database. The database includes active, proposed, canceled, and terminated CCUS projects worldwide. Information in the database regarding technologies being developed for capture, evaluation of sites for carbon dioxide (CO2) storage, estimation of project costs, and anticipated dates of completion is sourced from publically available information. The CCUS Database provides the public with information regarding efforts by various industries, public groups, and governments towards development and eventual deployment of CCUS technology. As of November 2012, the database contained 268 CCUS projects worldwide. The 268 projects include 68 capture, 61 storage, and 139 for capture and storage in more than 30 countries across 6 continents. While most of the projects are still in the planning and development stage, or have recently been proposed, 37 are actively capturing and injecting CO2

433

Hot Dry Rock; Geothermal Energy  

SciTech Connect

The commercial utilization of geothermal energy forms the basis of the largest renewable energy industry in the world. More than 5000 Mw of electrical power are currently in production from approximately 210 plants and 10 000 Mw thermal are used in direct use processes. The majority of these systems are located in the well defined geothermal generally associated with crustal plate boundaries or hot spots. The essential requirements of high subsurface temperature with huge volumes of exploitable fluids, coupled to environmental and market factors, limit the choice of suitable sites significantly. The Hot Dry Rock (HDR) concept at any depth originally offered a dream of unlimited expansion for the geothermal industry by relaxing the location constraints by drilling deep enough to reach adequate temperatures. Now, after 20 years intensive work by international teams and expenditures of more than $250 million, it is vital to review the position of HDR in relation to the established geothermal industry. The HDR resource is merely a body of rock at elevated temperatures with insufficient fluids in place to enable the heat to be extracted without the need for injection wells. All of the major field experiments in HDR have shown that the natural fracture systems form the heat transfer surfaces and that it is these fractures that must be for geothermal systems producing from naturally fractured formations provide a basis for directing the forthcoming but, equally, they require accepting significant location constraints on HDR for the time being. This paper presents a model HDR system designed for commercial operations in the UK and uses production data from hydrothermal systems in Japan and the USA to demonstrate the reservoir performance requirements for viable operations. It is shown that these characteristics are not likely to be achieved in host rocks without stimulation processes. However, the long term goal of artificial geothermal systems developed by systematic engineering procedures at depth may still be attained if high temperature sites with extensive fracturing are developed or exploited. [DJE -2005

1990-01-01T23:59:59.000Z

434

Interim storage study report  

SciTech Connect

High-level radioactive waste (HLW) stored at the Idaho Chemical Processing Plant (ICPP) in the form of calcine and liquid and liquid sodium-bearing waste (SBW) will be processed to provide a stable waste form and prepare the waste to be transported to a permanent repository. Because a permanent repository will not be available when the waste is processed, the waste must be stored at ICPP in an Interim Storage Facility (ISF). This report documents consideration of an ISF for each of the waste processing options under consideration.

Rawlins, J.K.

1998-02-01T23:59:59.000Z

435

Gas Storage Technology Consortium  

Science Conference Proceedings (OSTI)

The EMS Energy Institute at The Pennsylvania State University (Penn State) has managed the Gas Storage Technology Consortium (GSTC) since its inception in 2003. The GSTC infrastructure provided a means to accomplish industry-driven research and development designed to enhance the operational flexibility and deliverability of the nation's gas storage system, and provide a cost-effective, safe, and reliable supply of natural gas to meet domestic demand. The GSTC received base funding from the U.S. Department of Energy's (DOE) National Energy Technology Laboratory (NETL) Oil & Natural Gas Supply Program. The GSTC base funds were highly leveraged with industry funding for individual projects. Since its inception, the GSTC has engaged 67 members. The GSTC membership base was diverse, coming from 19 states, the District of Columbia, and Canada. The membership was comprised of natural gas storage field operators, service companies, industry consultants, industry trade organizations, and academia. The GSTC organized and hosted a total of 18 meetings since 2003. Of these, 8 meetings were held to review, discuss, and select proposals submitted for funding consideration. The GSTC reviewed a total of 75 proposals and committed co-funding to support 31 industry-driven projects. The GSTC committed co-funding to 41.3% of the proposals that it received and reviewed. The 31 projects had a total project value of $6,203,071 of which the GSTC committed $3,205,978 in co-funding. The committed GSTC project funding represented an average program cost share of 51.7%. Project applicants provided an average program cost share of 48.3%. In addition to the GSTC co-funding, the consortium provided the domestic natural gas storage industry with a technology transfer and outreach infrastructure. The technology transfer and outreach were conducted by having project mentoring teams and a GSTC website, and by working closely with the Pipeline Research Council International (PRCI) to jointly host technology transfer meetings and occasional field excursions. A total of 15 technology transfer/strategic planning workshops were held.

Joel Morrison; Elizabeth Wood; Barbara Robuck

2010-09-30T23:59:59.000Z

436

Acoustically enhanced heat exchange and drying apparatus  

DOE Patents (OSTI)

A heat transfer drying apparatus includes an acoustically augmented heat transfer chamber for receiving material to be dried. The chamber includes a first heat transfer gas inlet, a second heat transfer gas inlet, a material inlet, and a gas outlet which also serves as a dried material and gas outlet. A non-pulsing first heat transfer gas source provides a first drying gas to the acoustically augmented heat transfer chamber through the first heat transfer gas inlet. A valveless, continuous second heat transfer gas source provides a second drying gas to the acoustically augmented heat transfer chamber through the second heat transfer gas inlet. The second drying gas also generates acoustic waves which bring about acoustical coupling with the gases in the acoustically augmented heat transfer chamber. The second drying gas itself oscillates at an acoustic frequency of approximately 180 Hz due to fluid mechanical motion in the gas. The oscillations of the second heat transfer gas coupled to the first heat transfer gas in the acoustically augmented heat transfer chamber enhance heat and mass transfer by convection within the chamber. 3 figs.

Bramlette, T.T.; Keller, J.O.

1987-07-10T23:59:59.000Z

437

Hydrogen Storage Materials Database Demonstration  

NLE Websites -- All DOE Office Websites (Extended Search)

| Fuel Cell Technologies Program Source: US DOE 4/25/2011 eere.energy.gov | Fuel Cell Technologies Program Source: US DOE 4/25/2011 eere.energy.gov Hydrogen Storage Materials Database Demonstration FUEL CELL TECHNOLOGIES PROGRAM Ned Stetson Storage Tech Team Lead Fuel Cell Technologies Program U.S. Department of Energy 12/13/2011 Hydrogen Storage Materials Database Marni Lenahan December 13, 2011 Database Background * The Hydrogen Storage Materials Database was built to retain information from DOE Hydrogen Storage funded research and make these data more accessible. * Data includes properties of hydrogen storage materials investigated such as synthesis conditions, sorption and release conditions, capacities, thermodynamics, etc. http://hydrogenmaterialssearch.govtools.us Current Status * Data continues to be collected from DOE funded research.

438

Enabling Utility-Scale Electrical Energy Storage through Underground Hydrogen-Natural Gas Co-Storage.  

E-Print Network (OSTI)

??Energy storage technology is needed for the storage of surplus baseload generation and the storage of intermittent wind power, because it can increase the flexibility… (more)

Peng, Dan

2013-01-01T23:59:59.000Z

439

Gas hydrate cool storage system  

DOE Patents (OSTI)

The invention presented relates to the development of a process utilizing a gas hydrate as a cool storage medium for alleviating electric load demands during peak usage periods. Several objectives of the invention are mentioned concerning the formation of the gas hydrate as storage material in a thermal energy storage system within a heat pump cycle system. The gas hydrate was formed using a refrigerant in water and an example with R-12 refrigerant is included. (BCS)

Ternes, M.P.; Kedl, R.J.

1984-09-12T23:59:59.000Z

440

Article for thermal energy storage  

DOE Patents (OSTI)

A thermal energy storage composition is provided which is in the form of a gel. The composition includes a phase change material and silica particles, where the phase change material may comprise a linear alkyl hydrocarbon, water/urea, or water. The thermal energy storage composition has a high thermal conductivity, high thermal energy storage, and may be used in a variety of applications such as in thermal shipping containers and gel packs.

Salyer, Ival O. (Dayton, OH)

2000-06-27T23:59:59.000Z

Note: This page contains sample records for the topic "dry cask storage" from the National Library of EnergyBeta (NLEBeta).
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441

Electric storage cell or battery  

SciTech Connect

A lead storage cell comprises a storage jar, an electrolyte contained in the storage jar, negative and positive electrodes within the electrolyte and respectively having a negative electrode metal or active material and a positive electrode active material which are placed in contact with each other preferably a large-meshed woven or non-woven fabric having resistance to the electrolyte and inserted between the negative and positive electrodes.

Kosuga, J.

1981-11-17T23:59:59.000Z

442

Electricity Energy Storage Technology Options  

Science Conference Proceedings (OSTI)

A confluence of industry drivers8212including increased deployment of renewable generation, the high capital cost of managing grid peak demands, and large capital investments in grid infrastructure for reliability8212is creating new interest in electric energy storage systems. New EPRI research offers a current snapshot of the storage landscape and an analytical framework for estimating the benefits of applications and life-cycle costs of energy storage systems. This paper describes in detail 10 key appl...

2010-12-23T23:59:59.000Z

443

Magnetic energy storage  

DOE Green Energy (OSTI)

The fusion program embraces low loss superconductor strand development with integration into cables capable of carrying 50 kA in pulsed mode at high fields. This evolvement has been paralleled with pulsed energy storage coil development and testing from tens of kJ at low fields to a 20 MJ prototype tokamak induction coil at 7.5 T. Energy transfer times have ranged from 0.7 ms to several seconds. Electric utility magnetic storage for prospective application is for diurnal load leveling with massive systems to store 10 GWh at 1.8 K in a dewar structure supported on bedrock underground. An immediate utility application is a 30 MJ system to be used to damp power oscillations on the Bonneville Power Administration electric transmission lines. An off-shoot of this last work is a new program for electric utility VAR control with the potential for use to suppress subsynchronous resonance. This paper presents work in progress, work planned, and recently completed unusual work.

Rogers, J.D.

1980-01-01T23:59:59.000Z

444

Flywheel energy storage workshop  

DOE Green Energy (OSTI)

Since the November 1993 Flywheel Workshop, there has been a major surge of interest in Flywheel Energy Storage. Numerous flywheel programs have been funded by the Advanced Research Projects Agency (ARPA), by the Department of Energy (DOE) through the Hybrid Vehicle Program, and by private investment. Several new prototype systems have been built and are being tested. The operational performance characteristics of flywheel energy storage are being recognized as attractive for a number of potential applications. Programs are underway to develop flywheels for cars, buses, boats, trains, satellites, and for electric utility applications such as power quality, uninterruptible power supplies, and load leveling. With the tremendous amount of flywheel activity during the last two years, this workshop should again provide an excellent opportunity for presentation of new information. This workshop is jointly sponsored by ARPA and DOE to provide a review of the status of current flywheel programs and to provide a forum for presentation of new flywheel technology. Technology areas of interest include flywheel applications, flywheel systems, design, materials, fabrication, assembly, safety & containment, ball bearings, magnetic bearings, motor/generators, power electronics, mounting systems, test procedures, and systems integration. Information from the workshop will help guide ARPA & DOE planning for future flywheel programs. This document is comprised of detailed viewgraphs.

O`Kain, D.; Carmack, J. [comps.

1995-12-31T23:59:59.000Z

445

Drying Results of K-Basin Fuel Element 6513U (Run 8)  

Science Conference Proceedings (OSTI)

The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 8.0) have been conducted by Pacific Northwest National Laboratory (PNNL)on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the eighth of those tests, which was conducted on an N-Reactor outer fuel element removed from K-West canister 6513U. This element (referred to as Element 6513U) was stored underwater in the K-West Basin from 1983 until 1996. Element 6513U was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The system used for the drying test was the Whole Element Furnace Testing System, described in Section 2.0, located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodologies are given in Section 3.0. Inspections of the fuel element before and after the test are provided in Section 4.0. The experimental results are provided in Section 5.0 and discussed in Section 6.0.

BM Oliver; GS Klinger; J Abrefah; SC Marschman; PJ MacFarlan; GA Ritter

1999-08-11T23:59:59.000Z

446

Drying results of K-Basin fuel element 1164M (run 6)  

Science Conference Proceedings (OSTI)

The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basin have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford site (WHC 1995). Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 8.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the sixth of those tests, which was conducted on an N-Reactor outer fuel element removed from K-West canister 1164 M. This element (referred to as Element 1164M) was stored underwater in the K-West Basin from 1983 until 1996. Element 1164M was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The system used for the drying test was the Whole Element Furnace Testing System, described in Section 2.0, located in the Postirradiation Testing laboratory (PTL, 327 Building). The test conditions and methodologies are given in Section 3.0. Inspections of the fuel element before and after the test are provided in Section 4.0. The experimental results are provided in Section 5.0, and discussed in Section 6.0.

Oliver, B.M.; Klinger, G.S.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J.; Ritter, G.A.

1998-08-01T23:59:59.000Z

447

Drying results of K-Basin fuel element 5744U (Run 4)  

Science Conference Proceedings (OSTI)

The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. Because some leaks in the basins have been detected and some of the fuel is breached due to handling damage and corrosion, efforts are underway to remove the fuel elements from wet storage. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium fuel elements in an interim storage facility on the Hanford Site. Information required to support the development of the drying processes, and the required safety analyses, is being obtained from characterization tests conducted on fuel elements removed from the K-Basins. A series of whole element drying tests (reported in separate documents, see Section 8.0) have been conducted by Pacific Northwest National Laboratory (PNNL) on several intact and damaged fuel elements recovered from both the K-East and K-West Basins. This report documents the results of the fourth of those tests, which was conducted on an N-Reactor outer fuel element removed from K-West canister 5744U. This element (referred to as Element 5744U) was stored underwater in the K-West Basin from 1983 until 1996. Element 5744U was subjected to a combination of low- and high-temperature vacuum drying treatments that were intended to mimic, wherever possible, the fuel treatment strategies of the IPS. The system used for the drying test was the Whole Element Furnace Testing System, described in Section 2.0, located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodologies are given in Section 3.0. Inspections of the fuel element before and after the test are provided in Section 4.0. The experimental results are provided in Section 5.0, and discussed in Section 6.0.

Klinger, G.S.; Oliver, B.M.; Abrefah, J.; Marschman, S.C.; MacFarlan, P.J.; Ritter, G.A.

1998-07-01