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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

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

3

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

4

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

5

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

6

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

7

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

8

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

9

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

10

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

11

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

12

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 countryís 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

13

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

14

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

15

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

16

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

17

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

18

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

19

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

20

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

Note: This page contains sample records for the topic "fuel dry 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

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

22

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...

23

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

24

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

25

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

26

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

27

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

28

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

29

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

30

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

31

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

32

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

33

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 ...

34

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

35

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

36

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

37

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

38

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

39

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

40

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

Note: This page contains sample records for the topic "fuel dry 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

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...

43

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

44

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

45

Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Promulgation of Promulgation of Renewable Fuel Storage Tank Regulations to someone by E-mail Share Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank Regulations on Facebook Tweet about Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank Regulations on Twitter Bookmark Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank Regulations on Google Bookmark Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank Regulations on Delicious Rank Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank Regulations on Digg Find More places to share Alternative Fuels Data Center: Promulgation of Renewable Fuel Storage Tank Regulations on AddThis.com... More in this section... Federal

46

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 INLís 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

47

Status report on the Spent-Fuel Test-Climax, Nevada Test Site: a test of dry storage of spent fuel in a deep granite location  

SciTech Connect

The Spent Fuel Test-Climax (SFT-C) is located at a depth of 420 m in the Climax granite at the Nevada Test Site. The test array contains 11 canistered PWR fuel assemblies, plus associated electrical simulators and electrical heaters. There are nearly 900 channels of thermal, radiation, stress, displacement, and test control instrumentation. This paper is a general status report on the test, which started in May 1980.

Ramspott, L.D.; Ballou, L.B.; Patrick, W.C.

1982-03-01T23:59:59.000Z

48

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

49

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

50

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

51

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

52

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

53

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...

54

HTGR spent fuel storage study  

SciTech Connect

This report documents a study of alternate methods of storing high-temperature gas-cooled reactor (HTGR) spent fuel. General requirements and design considerations are defined for a storage facility integral to a fuel recycle plant. Requirements for stand-alone storage are briefly considered. Three alternate water-cooled storage conceptual designs (plug well, portable well, and monolith) are considered and compared to a previous air-cooled design. A concept using portable storage wells in racks appears to be the most favorable, subject to seismic analysis and economic evaluation verification.

Burgoyne, R.M.; Holder, N.D.

1979-04-01T23:59:59.000Z

55

Alternative Fuels Data Center: Biodiesel Fuel Storage Grants  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Biodiesel Fuel Storage Biodiesel Fuel Storage Grants to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Fuel Storage Grants on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Fuel Storage Grants on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Fuel Storage Grants on Google Bookmark Alternative Fuels Data Center: Biodiesel Fuel Storage Grants on Delicious Rank Alternative Fuels Data Center: Biodiesel Fuel Storage Grants on Digg Find More places to share Alternative Fuels Data Center: Biodiesel Fuel Storage Grants on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biodiesel Fuel Storage Grants The Alabama Biodiesel Incentive Program, administered by the Alabama Department of Economic and Community Affairs (ADECA) Energy Division,

56

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

57

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

58

Dry Processing of Used Nuclear Fuel  

SciTech Connect

Dry (non-aqueous) separations technologies have been used for treatment of used nuclear fuel since the 1960s, and they are still being developed and demonstrated in many countries. Dry technologies offer potential advantages compared to traditional aqueous separations including: compactness, resistance to radiation effects, criticality control benefits, compatibility with advanced fuel types, and ability to produce low purity products. Within the Department of Energyís Advanced Fuel Cycle Initiative, an electrochemical process employing molten salts is being developed for recycle of fast reactor fuel and treatment of light water reactor oxide fuel to produce a feed for fast reactors. Much of the development of this technology is based on treatment of used Experimental Breeder Reactor II (EBR-II) fuel, which is metallic. Electrochemical treatment of the EBR-II fuel has been ongoing in the Fuel Conditioning Facility, located at the Materials and Fuel Complex of Idaho National Laboratory since 1996. More than 3.8 metric tons of heavy metal of metallic fast reactor fuel have been treated using this technology. This paper will summarize the status of electrochemical development and demonstration activities with used nuclear fuel, including high-level waste work. A historic perspective on the background of dry processing will also be provided.

K. M. Goff; M. F. Simpson

2009-09-01T23:59:59.000Z

59

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

60

Fuel Cell Technologies Office: Hydrogen Storage  

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

Fuel Cell Technologies Office: Hydrogen Storage to Fuel Cell Technologies Office: Hydrogen Storage to someone by E-mail Share Fuel Cell Technologies Office: Hydrogen Storage on Facebook Tweet about Fuel Cell Technologies Office: Hydrogen Storage on Twitter Bookmark Fuel Cell Technologies Office: Hydrogen Storage on Google Bookmark Fuel Cell Technologies Office: Hydrogen Storage on Delicious Rank Fuel Cell Technologies Office: Hydrogen Storage on Digg Find More places to share Fuel Cell Technologies Office: Hydrogen Storage on AddThis.com... Home Basics Current Technology DOE R&D Activities Quick Links Hydrogen Production Hydrogen Delivery Fuel Cells Technology Validation Manufacturing Codes & Standards Education Systems Analysis Contacts On-board hydrogen storage for transportation applications continues to be

Note: This page contains sample records for the topic "fuel dry 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.


61

Fuel Cell Technologies Office: Hydrogen Compression, Storage...  

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

Hydrogen Compression, Storage, and Dispensing Cost Reduction Workshop to someone by E-mail Share Fuel Cell Technologies Office: Hydrogen Compression, Storage, and Dispensing Cost...

62

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

63

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

64

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

65

Alternative Fuels Data Center: Biodiesel Storage Regulations  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Biodiesel Storage Biodiesel Storage Regulations to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Storage Regulations on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Storage Regulations on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Storage Regulations on Google Bookmark Alternative Fuels Data Center: Biodiesel Storage Regulations on Delicious Rank Alternative Fuels Data Center: Biodiesel Storage Regulations on Digg Find More places to share Alternative Fuels Data Center: Biodiesel Storage Regulations on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biodiesel Storage Regulations Underground storage tank regulations apply to all biodiesel blends with the exception of 100% biodiesel (B100). An owner changing the use of an

66

Regenerative Fuel Cells for Energy Storage  

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

11 1 Regenerative Fuel Cells for Energy Storage April 2011 Corky Mittelsteadt April 2011 2 Outline 1. Regenerative Fuel Cells at Giner 2. Regenerative Systems for Energy Storage 1....

67

Fuel Cells, Hydrogen Storage, Ferroelectrics, Wind Energy  

Science Conference Proceedings (OSTI)

Mar 15, 2012 ... Energy Nanomaterials: Fuel Cells, Hydrogen Storage, Ferroelectrics, Wind Energy Sponsored by: The Minerals, Metals and Materials Society,†...

68

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

69

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

70

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 fŁr 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 Dominionís (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

71

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

72

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

Researchers at ORNL have developed an integrated system that reduces the total life-cycle cost of used fuel storage while improving overall safety. This multicanister ...

73

Hydrogen & Fuel Cells - Hydrogen - Hydrogen Storage  

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

University of Chicago team. On-board hydrogen storage is critical to the development of future high energy efficiency transportation technologies, such as hydrogen-powered fuel...

74

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 Commissionís (NRCís) determination that ďspent 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. Ē 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

75

Final safety analysis report for the irradiated fuels storage facility  

SciTech Connect

A fuel storage facility has been constructed at the Idaho Chemical Processing Plant to provide safe storage for spent fuel from two commercial HTGR's, Fort St. Vrain and Peach Bottom, and from the Rover nuclear rocket program. The new facility was built as an addition to the existing fuel storage basin building to make maximum use of existing facilities and equipment. The completed facility provides dry storage for one core of Peach Bottom fuel (804 elements), 1$sup 1$/$sub 2$ cores of Fort St. Vrain fuel (2200 elements), and the irradiated fuel from the 20 reactors in the Rover program. The facility is designed to permit future expansion at a minimum cost should additional storage space for graphite-type fuels be required. A thorough study of the potential hazards associated with the Irradiated Fuels Storage Facility has been completed, indicating that the facility is capable of withstanding all credible combinations of internal accidents and pertinent natural forces, including design basis natural phenomena of a 10,000 year flood, a 175-mph tornado, or an earthquake having a bedrock acceleration of 0.33 g and an amplification factor of 1.3, without a loss of integrity or a significant release of radioactive materials. The design basis accident (DBA) postulated for the facility is a complete loss of cooling air, even though the occurrence of this situation is extremely remote, considering the availability of backup and spare fans and emergency power. The occurrence of the DBA presents neither a radiation nor an activity release hazard. A loss of coolant has no effect upon the fuel or the facility other than resulting in a gradual and constant temperature increase of the stored fuel. The temperature increase is gradual enough that ample time (28 hours minimum) is available for corrective action before an arbitrarily imposed maximum fuel centerline temperature of 1100$sup 0$F is reached. (LK)

Bingham, G.E.; Evans, T.K.

1976-01-01T23:59:59.000Z

76

Characteristics of fuel crud and its impact on storage, handling, and shipment of spent fuel. [Fuel crud  

Science Conference Proceedings (OSTI)

Corrosion products, called ''crud,'' form on out-of-reactor surfaces of nuclear reactor systems and are transported by reactor coolant to the core, where they deposit on external fuel-rod cladding surfaces and are activated by nuclear reactions. After discharge of spent fuel from a reactor, spallation of radioactive crud from the fuel rods could impact wet or dry storage operations, handling (including rod consolidation), and shipping. It is the purpose of this report to review earlier (1970s) and more recent (1980s) literature relating to crud, its characteristics, and any impact it has had on actual operations. Crud characteristics vary from reactor type to reactor type, reactor to reactor, fuel assembly to fuel assembly in a reactor, circumferentially and axially in an assembly, and from cycle to cycle for a specific facility. To characterize crud of pressurized-water (PWRs) and boiling-water reactors (BWRs), published information was reviewed on appearance, chemical composition, areal density and thickness, structure, adhesive strength, particle size, and radioactivity. Information was also collected on experience with crud during spent fuel wet storage, rod consolidation, transportation, and dry storage. From experience with wet storage, rod consolidation, transportation, and dry storage, it appears crud spallation can be managed effectively, posing no significant radiological problems. 44 refs., 11 figs.

Hazelton, R.F.

1987-09-01T23:59:59.000Z

77

Hydrogen Storage Requirements for Fuel Cell Vehicles  

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

GENERAL MOTORS GENERAL MOTORS HYDROGEN STORAGE REQUIREMENTS FOR FUEL CELL VEHICLES Brian G. Wicke GM R&D and Planning DOE Hydrogen Storage Workshop August 14-15, 2002 Argonne National Laboratory General Motors Fuel Cell Vehicles * GM fuel cell vehicle Goal - be the first to profitably sell one million fuel cell vehicles * Fuel cell powerplant must be suitable for a broad range of light-duty vehicles (not just niche) * UNCOMPROMISED performance & reliability are REQUIRED * SAFETY IS A GIVEN * Evolutionary and Revolutionary vehicle designs are included-GM AUTONOMY-as long as the customer is (more than) satisfied GENERAL MOTORS AUTONOMY GENERAL MOTORS AUTONOMY General Motors Fuel Cell Vehicles * Focus on PEM fuel cell technology * Must consider entire hydrogen storage & (unique) fuel delivery systems,

78

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

79

Metal hydride fuel storage and method thereof  

DOE Patents (OSTI)

Disclosed herein is a metal hydride fuel storage cartridge having integrated resistive heaters that can be used in conjunction with fuel cells such as MEMS-based fuel cells. The cartridge is fabricated using micromachining methods and thin/thick film materials synthesis techniques.

Morse, Jeffrey D. (Martinez, CA); Jankowski, Alan F. (Livermore, CA); Yu, Conrad (Antioch, CA)

2006-10-17T23:59:59.000Z

80

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

Note: This page contains sample records for the topic "fuel dry 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.


81

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

82

Hydrogen storage and integrated fuel cell assembly  

DOE Patents (OSTI)

Hydrogen is stored in materials that absorb and desorb hydrogen with temperature dependent rates. A housing is provided that allows for the storage of one or more types of hydrogen-storage materials in close thermal proximity to a fuel cell stack. This arrangement, which includes alternating fuel cell stack and hydrogen-storage units, allows for close thermal matching of the hydrogen storage material and the fuel cell stack. Also, the present invention allows for tailoring of the hydrogen delivery by mixing different materials in one unit. Thermal insulation alternatively allows for a highly efficient unit. Individual power modules including one fuel cell stack surrounded by a pair of hydrogen-storage units allows for distribution of power throughout a vehicle or other electric power consuming devices.

Gross, Karl J. (Fremont, CA)

2010-08-24T23:59:59.000Z

83

DOE Hydrogen and Fuel Cells Program: Hydrogen Storage  

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

Energy Search help Home > Hydrogen Storage Printable Version Hydrogen Storage Hydrogen storage is a key enabling technology for the advancement of hydrogen and fuel cell power...

84

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

85

Safeguards and nonproliferation aspects of a dry fuel recycling technology  

Science Conference Proceedings (OSTI)

Los Alamos National Laboratory undertook an independent assessment of the proliferation potentials and safeguardability of a dry fuel recycling technology, whereby spent pressurized-water reactor (PWR) fuels are used to fuel canadian deuterium uranium (CANDU) reactors. Objectives of this study included (1) the evaluation of presently available technologies that may be useful to safeguard technology options for dry fuel recycling (2) and identification of near-term and long-term research needs to develop process-specific safeguards requirements. The primary conclusion of this assessment is that like all other fuel cycle alternatives proposed in the past, the dry fuel recycle entails prolfferation risks and that there are no absolute technical fixes to eliminate such risks. This study further concludes that the proliferation risks of dry fuel recycling options are relatively minimal and presently known safeguards systems and technologies can be modified and/or adapted to meet the requirements of safeguarding such fuel recycle facilities.

Pillay, K.K.S.

1993-05-01T23:59:59.000Z

86

Small Fuel Cell Systems with Hydrogen Storage  

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

eere.energy.gov H 2 and FC Technologies Manufacturing R&D Workshop Renaissance Hotel, Washington, DC August 11-12, 2011 Small Fuel Cell Systems with Hydrogen Storage Ned T....

87

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

88

Metal hydride fuel storage and method thereof - Energy ...  

Disclosed herein is a metal hydride fuel storage cartridge having integrated resistive heaters that can be used in conjunction with fuel cells such as MEMS-based fuel ...

89

Corrosion in ICPP fuel storage basins  

SciTech Connect

The Idaho Chemical Processing Plant currently stores irradiated nuclear fuel in fuel storage basins. Historically, fuel has been stored for over 30 years. During the 1970`s, an algae problem occurred which required higher levels of chemical treatment of the basin water to maintain visibility for fuel storage operations. This treatment led to higher levels of chlorides than seen previously which cause increased corrosion of aluminum and carbon steel, but has had little effect on the stainless steel in the basin. Corrosion measurements of select aluminum fuel storage cans, aluminum fuel storage buckets, and operational support equipment have been completed. Aluminum has exhibited good general corrosion rates, but has shown accelerated preferential attack in the form of pitting. Hot dipped zinc coated carbon steel, which has been in the basin for approximately 40 years, has shown a general corrosion rate of 4 mpy, and there is evidence of large shallow pits on the surface. A welded Type 304 stainless steel corrosion coupon has shown no attack after 13 years exposure. Galvanic couples between carbon steel welded to Type 304 stainless steel occur in fuel storage yokes exposed to the basin water. These welded couples have shown galvanic attack as well as hot weld cracking and intergranular cracking. The intergranular stress corrosion cracking is attributed to crevices formed during fabrication which allowed chlorides to concentrate.

Dirk, W.J.

1993-09-01T23:59:59.000Z

90

Fuel Cell Technologies Office: Onboard Storage Tank Workshop  

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

Onboard Storage Tank Onboard Storage Tank Workshop to someone by E-mail Share Fuel Cell Technologies Office: Onboard Storage Tank Workshop on Facebook Tweet about Fuel Cell Technologies Office: Onboard Storage Tank Workshop on Twitter Bookmark Fuel Cell Technologies Office: Onboard Storage Tank Workshop on Google Bookmark Fuel Cell Technologies Office: Onboard Storage Tank Workshop on Delicious Rank Fuel Cell Technologies Office: Onboard Storage Tank Workshop on Digg Find More places to share Fuel Cell Technologies Office: Onboard Storage Tank Workshop on AddThis.com... Publications Program Publications Technical Publications Educational Publications Newsletter Program Presentations Multimedia Conferences & Meetings Annual Merit Review Proceedings Workshop & Meeting Proceedings

91

Fuel Cell Technologies Office: Hydrogen Storage (Text Alternative Version)  

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

Storage (Text Storage (Text Alternative Version) to someone by E-mail Share Fuel Cell Technologies Office: Hydrogen Storage (Text Alternative Version) on Facebook Tweet about Fuel Cell Technologies Office: Hydrogen Storage (Text Alternative Version) on Twitter Bookmark Fuel Cell Technologies Office: Hydrogen Storage (Text Alternative Version) on Google Bookmark Fuel Cell Technologies Office: Hydrogen Storage (Text Alternative Version) on Delicious Rank Fuel Cell Technologies Office: Hydrogen Storage (Text Alternative Version) on Digg Find More places to share Fuel Cell Technologies Office: Hydrogen Storage (Text Alternative Version) on AddThis.com... Publications Program Publications Technical Publications Educational Publications Newsletter Program Presentations Multimedia Conferences & Meetings

92

Alternative Fuels Data Center: Biodiesel Retail and Storage Requirements  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Biodiesel Retail and Biodiesel Retail and Storage Requirements to someone by E-mail Share Alternative Fuels Data Center: Biodiesel Retail and Storage Requirements on Facebook Tweet about Alternative Fuels Data Center: Biodiesel Retail and Storage Requirements on Twitter Bookmark Alternative Fuels Data Center: Biodiesel Retail and Storage Requirements on Google Bookmark Alternative Fuels Data Center: Biodiesel Retail and Storage Requirements on Delicious Rank Alternative Fuels Data Center: Biodiesel Retail and Storage Requirements on Digg Find More places to share Alternative Fuels Data Center: Biodiesel Retail and Storage Requirements on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Biodiesel Retail and Storage Requirements

93

Storage of burned PWR and BWR fuel  

SciTech Connect

In the last few years, credit for fuel burnup has been allowed in the design and criticality safety analysis of high-density spent-fuel storage racks. Design and operating philosophies, however, differ significantly between pressurized water reactor (PWR)- and boiling water reactor (BWR)-type plants because: (1) PWR storage pools generally use soluble boron, which provides backup criticality control under accident conditions; and (2) BWR fuel generally contains gadolinium burnable poison, which results in a characteristically peaked burnup-dependent reactivity variation. In PWR systems, the reactivity decreases monotonically with burnup in a nearly linear fashion (excluding xenon effects), and a two-region concept is feasible. In BWR systems, the reactivity is initially low, increases as fuel burnup progresses, and reaches a maximum at a burnup where the gadolinium is nearly depleted. In any spent-fuel storage rack design, uncertainties due to manufacturing tolerances and in calculational methods must be included to assure that the highest reactivity (k/sub eff/) is less than the 0.95 US Nuclear Regulatory Commission limit. In the absence of definitive critical experiment data with spent fuel, the uncertainty due to depletion calculations must be assumed on the basis of judgment. High-density spent-fuel storage racks may be designed for both PWR and BWR plants with credit for burnup. However, the design must be tailored to each plant with appropriate consideration of the preferences/specifications of the utility operating staff.

Turner, S.E.

1987-01-01T23:59:59.000Z

94

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

95

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

96

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.

1998-07-01T23:59:59.000Z

97

Drying Results of K-Basin Fuel Element 2660M (Run 7)  

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 seventh of those tests, which was conducted on an N-Reactor outer fuel element removed from K-West canister 2660M. This element (referred to as Element 2660M) was stored underwater in the K-West Basin from 1983 until 1996. Element 2660M 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.

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

1999-07-26T23:59:59.000Z

98

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):

99

Energy Storage Fuel Cell Vehicle Analysis: Preprint  

DOE Green Energy (OSTI)

In recent years, hydrogen fuel cell (FC) vehicle technology has received considerable attention as a strategy to decrease oil consumption and reduce harmful emissions. However, the cost, transient response, and cold performance of FC systems may present significant challenges to widespread adoption of the technology for transportation in the next 15 years. The objectives of this effort were to perform energy storage modeling with fuel cell vehicle simulations to quantify the benefits of hybridization and to identify a process for setting the requirements of ES for hydrogen-powered FC vehicles for U.S. Department of Energy's Energy Storage Program.

Markel, T.; Pesaran, A.; Zolot, M.; Sprik, S.; Tataria, H.; Duong, T.

2005-04-01T23:59:59.000Z

100

Energy Storage Fuel Cell Vehicle Analysis  

DOE Green Energy (OSTI)

In recent years, hydrogen fuel cell (FC) vehicle technology has received considerable attention as a strategy to decrease oil consumption and reduce harmful emissions. However, the cost, transient response, and cold performance of FC systems may present significant challenges to widespread adoption of the technology for transportation in the next 15 years. The objectives of this effort were to perform energy storage modeling with fuel cell vehicle simulations to quantify the benefits of hybridization and to identify a process for setting the requirements of ES for hydrogen-powered FC vehicles for U.S. Department of Energy?s Energy Storage Program.

Pesaran, A.; Markel, T.; Zolot, M.; Sprik, S.; Tataria, H.; Duong, T.

2005-08-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel dry 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

President Reagan Calls for a National Spent Fuel Storage Facility...  

National Nuclear Security Administration (NNSA)

for a National Spent Fuel Storage Facility The Reagan Administration announces a nuclear energy policy that anticipates the establishment of a facility for the storage of...

102

Fuel Cell Technologies Office: Hydrogen Storage  

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

Storage Storage On-board hydrogen storage for transportation applications continues to be one of the most technically challenging barriers to the widespread commercialization of hydrogen-fueled vehicles. The EERE hydrogen storage activity focuses primarily on the applied research and development (R&D) of low-pressure, materials-based technologies to allow for a driving range of more than 300 miles (500 km) while meeting packaging, cost, safety, and performance requirements to be competitive with current vehicles. While automakers have recently demonstrated progress with some prototype vehicles traveling more than 300 miles on a single fill, this driving range must be achievable across different vehicle models and without compromising space, performance, or cost. In addition, hydrogen storage will be needed for both other niche vehicular applications and off-board uses such as for stationary power generation and for hydrogen delivery and refueling infrastructure.

103

NREL: Vehicles and Fuels Research - Energy Storage  

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

Research Research Search More Search Options Site Map NREL's Energy Storage Project is leading the charge on battery thermal management, modeling, and systems solutions to enhance the performance of fuel cell, hybrid electric, and electric vehicles (FCVs, HEVs, and EVs) for a cleaner, more secure transportation future. NREL's experts work closely with the U.S. Department of Energy (DOE), industry, and automotive manufacturers to improve energy storage devices, such as battery modules and ultracapacitors, by enhancing their thermal performance and life-cycle cost. Activities also involve modeling and simulation to evaluate technical targets and energy storage parameters, and investigating combinations of energy storage systems to increase vehicle efficiency. Much of this research is conducted at our state-of-the-art energy storage

104

Hydrogen & Fuel Cells - Hydrogen - Hydrogen Storage  

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

Hydrogen Storage Systems Modeling and Analysis Hydrogen Storage Systems Modeling and Analysis Several different approaches are being pursued to develop on-board hydrogen storage systems for light-duty vehicle applications. The different approaches have different characteristics, such as: the thermal energy and temperature of charge and discharge kinetics of the physical and chemical process steps involved requirements for the materials and energy interfaces between the storage system and the fuel supply system on one hand, and the fuel user on the other Other storage system design and operating parameters influence the projected system costs as well. Argonne researchers are developing thermodynamic, kinetic, and engineering models of the various hydrogen storage systems to understand the characteristics of storage systems based on these approaches and to evaluate their potential to meet the DOE targets for on-board applications. The DOE targets for 2015 include a system gravimetric capacity of 1.8 kWh/kg (5.5 wt%) and a system volumetric capacity of 1.3 kWh/L (40 g/L). We then use these models to identify significant component and performance issues, and evaluate alternative system configurations and design and operating parameters.

105

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

106

Drying results of K-Basin fuel element 1990 (Run 1)  

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 fuels 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 first of those tests (Run 1), which was conducted on an N-Reactor inner fuel element (1990) that had been stored underwater in the K-West Basin (see Section 2.0). This fuel element 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 testing was conducted in the Whole Element Furnace Testing System, described in Section 3.0, located in the Postirradiation Testing Laboratory (PTL, 327 Building). The test conditions and methodology are given in Section 4.0, and the experimental results provided in Section 5.0. These results are further discussed in Section 6.0.

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

1998-06-01T23:59:59.000Z

107

Fuel Cell Technologies Office: Hydrogen Storage Materials Requirements...  

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

(Text Version) to someone by E-mail Share Fuel Cell Technologies Office: Hydrogen Storage Materials Requirements (Text Version) on Facebook Tweet about Fuel Cell Technologies...

108

Fuel Cell Technologies Office: Hydrogen Storage Workshop Proceedings  

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

Proceedings to someone by E-mail Share Fuel Cell Technologies Office: Hydrogen Storage Workshop Proceedings on Facebook Tweet about Fuel Cell Technologies Office: Hydrogen...

109

Fuel Cell Technologies Office: Hydrogen Storage Materials Database...  

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

(Text Version) to someone by E-mail Share Fuel Cell Technologies Office: Hydrogen Storage Materials Database Demonstration Webinar (Text Version) on Facebook Tweet about Fuel...

110

Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements  

SciTech Connect

In 1998, a major change in the technical strategy for managing Multi Canister Overpacks (MCO) while stored within the Canister Storage Building (CSB) occurred. The technical strategy is documented in Baseline Change Request (BCR) No. SNF-98-006, Simplified SNF Project Baseline (MCO Sealing) (FDH 1998). This BCR deleted the hot conditioning process initially adopted for the Spent Nuclear Fuel Project (SNF Project) as documented in WHC-SD-SNF-SP-005, Integrated Process Strategy for K Basins Spent Nuclear Fuel (WHC 199.5). In summary, MCOs containing Spent Nuclear Fuel (SNF) from K Basins would be placed in interim storage following processing through the Cold Vacuum Drying (CVD) facility. With this change, the needs for the Hot Conditioning System (HCS) and inerting/pressure retaining capabilities of the CSB storage tubes and the MCO Handling Machine (MHM) were eliminated. Mechanical seals will be used on the MCOs prior to transport to the CSB. Covers will be welded on the MCOs for the final seal at the CSB. Approval of BCR No. SNF-98-006, imposed the need to review and update the CSB functions and requirements baseline documented herein including changing the document title to ''Spent Nuclear Fuel Project Canister Storage Building Functions and Requirements.'' This revision aligns the functions and requirements baseline with the CSB Simplified SNF Project Baseline (MCO Sealing). This document represents the Canister Storage Building (CSB) Subproject technical baseline. It establishes the functions and requirements baseline for the implementation of the CSB Subproject. The document is organized in eight sections. Sections 1.0 Introduction and 2.0 Overview provide brief introductions to the document and the CSB Subproject. Sections 3.0 Functions, 4.0 Requirements, 5.0 Architecture, and 6.0 Interfaces provide the data described by their titles. Section 7.0 Glossary lists the acronyms and defines the terms used in this document. Section 8.0 References lists the references used for this document.

KLEM, M.J.

2000-10-18T23:59:59.000Z

111

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

112

Report on interim storage of spent nuclear fuel  

SciTech Connect

The report on interim storage of spent nuclear fuel discusses the technical, regulatory, and economic aspects of spent-fuel storage at nuclear reactors. The report is intended to provide legislators state officials and citizens in the Midwest with information on spent-fuel inventories, current and projected additional storage requirements, licensing, storage technologies, and actions taken by various utilities in the Midwest to augment their capacity to store spent nuclear fuel on site.

1993-04-01T23:59:59.000Z

113

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

114

Drying Results of K-Basin Fuel Element 6603M (Rune 5)  

SciTech Connect

The water-filled K-Basins in the Hanford 100 Area have been used to store N-Reactor spent nuclear fuel (SNF) since the 1970s. An Integrated Process Strategy (IPS) has been developed to package, dry, transport, and store these metallic uranium spent nuclear fuels 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 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 fifth of those tests conducted on an N-Reactor outer fuel element (6603M) which had been stored underwater in the Hanford 100 Area K-West basin from 1983 until 1996. This fuel element was subjected to a combination of low- and high-temperature vacuum drying treatments which 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. The test conditions and methodologies are given in Section 3.0. Inspections on the fuel element before and after the test are provided in Section 4.0. The experimental results are provided in Section 5.0. Discussion of the results is given in Section 6.0.

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

1999-09-24T23:59:59.000Z

115

Summary engineering description of underwater fuel storage facility for foreign research reactor spent nuclear fuel  

SciTech Connect

This document is a summary description for an Underwater Fuel Storage Facility (UFSF) for foreign research reactor (FRR) spent nuclear fuel (SNF). A FRR SNF environmental Impact Statement (EIS) is being prepared and will include both wet and dry storage facilities as storage alternatives. For the UFSF presented in this document, a specific site is not chosen. This facility can be sited at any one of the five locations under consideration in the EIS. These locations are the Idaho National Engineering Laboratory, Savannah River Site, Hanford, Oak Ridge National Laboratory, and Nevada Test Site. Generic facility environmental impacts and emissions are provided in this report. A baseline fuel element is defined in Section 2.2, and the results of a fission product analysis are presented. Requirements for a storage facility have been researched and are summarized in Section 3. Section 4 describes three facility options: (1) the Centralized-UFSF, which would store the entire fuel element quantity in a single facility at a single location, (2) the Regionalized Large-UFSF, which would store 75% of the fuel element quantity in some region of the country, and (3) the Regionalized Small-UFSF, which would store 25% of the fuel element quantity, with the possibility of a number of these facilities in various regions throughout the country. The operational philosophy is presented in Section 5, and Section 6 contains a description of the equipment. Section 7 defines the utilities required for the facility. Cost estimates are discussed in Section 8, and detailed cost estimates are included. Impacts to worker safety, public safety, and the environment are discussed in Section 9. Accidental releases are presented in Section 10. Standard Environmental Impact Forms are included in Section 11.

Dahlke, H.J.; Johnson, D.A.; Rawlins, J.K.; Searle, D.K.; Wachs, G.W.

1994-10-01T23:59:59.000Z

116

Nuclear Fuels Storage & Transportation Planning Project Documents |  

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

Fuel Cycle Technologies ¬Ľ Nuclear Fuels Storage & Fuel Cycle Technologies ¬Ľ Nuclear Fuels Storage & Transportation Planning Project ¬Ľ Nuclear Fuels Storage & Transportation Planning Project Documents Nuclear Fuels Storage & Transportation Planning Project Documents September 30, 2013 Preliminary Evaluation of Removing Used Nuclear Fuel From Shutdown Sites In January 2013, the Department of Energy issued the Strategy for the Management and Disposal of Used Nuclear Fuel and High-Level Radioactive Waste. Among the elements contained in this strategy is an initial focus on accepting used nuclear fuel from shutdown reactor sites. February 22, 2013 Public Preferences Related to Consent-Based Siting of Radioactive Waste Management Facilities for Storage and Disposal This report provides findings from a set of social science studies

117

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

118

Fuel Cell Technologies Office: Flow Cells for Energy Storage Workshop  

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

Flow Cells for Energy Flow Cells for Energy Storage Workshop to someone by E-mail Share Fuel Cell Technologies Office: Flow Cells for Energy Storage Workshop on Facebook Tweet about Fuel Cell Technologies Office: Flow Cells for Energy Storage Workshop on Twitter Bookmark Fuel Cell Technologies Office: Flow Cells for Energy Storage Workshop on Google Bookmark Fuel Cell Technologies Office: Flow Cells for Energy Storage Workshop on Delicious Rank Fuel Cell Technologies Office: Flow Cells for Energy Storage Workshop on Digg Find More places to share Fuel Cell Technologies Office: Flow Cells for Energy Storage Workshop on AddThis.com... Publications Program Publications Technical Publications Educational Publications Newsletter Program Presentations Multimedia Conferences & Meetings Annual Merit Review Proceedings

119

Design and Operation of Equipment to Detect and Remove Water within Used Nuclear Fuel Storage Bottles  

SciTech Connect

Inspection and drying equipment has been implemented in a hot cell to address the inadvertent ingress of water into used nuclear fuel storage bottles. Operated with telemanipulators, the system holds up to two fuel bottles and allows their threaded openings to be connected to pressure transducers and a vacuum pump. A prescribed pressure rebound test is used to diagnose the presence of moisture. Bottles found to contain moisture are dried by vaporization. The drying process is accelerated by the application of heat and vacuum. These techniques detect and remove virtually all free water (even water contained in a debris bed) while leaving behind most, if not all, particulates. The extracted water vapour passes through a thermoelectric cooler where it is condensed back to the liquid phase for collection. Fuel bottles are verified to be dry by passing the pressure rebound test.

C.C. Baker; T.M. Pfeiffer; J.C. Price

2013-09-01T23:59:59.000Z

120

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

ORNL 2011-G00239/jcn UUT-B ID 201102603 09.2011 Integrated Used Nuclear Fuel Storage, Transportation, and Disposal Canister System Technology Summary

Note: This page contains sample records for the topic "fuel dry 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

Virtual Screening of Materials for Gaseous Fuel Storage  

Science Conference Proceedings (OSTI)

Presentation Title, Virtual Screening of Materials for Gaseous Fuel Storage .... Numerical Study on Behavior of Top-Blown Supersonic Jets and Their Interaction †...

122

Review of Used Nuclear Fuel Storage and Transportation Technical Gap  

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

Analyses Analyses Review of Used Nuclear Fuel Storage and Transportation Technical Gap Analyses The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology, has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development activities related to storage, transportation, and disposal of used nuclear fuel and high-level radioactive waste. The mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation, and disposal of used nuclear fuel (UNF) and wastes generated by existing and future nuclear fuel cycles. The Storage and Transportation activities within the UFDC are being developed to address issues regarding the extended storage of UNF and its subsequent

123

Testing of the CANDU Spent Fuel Storage Basket Package  

SciTech Connect

The paper described the results of testing for a CANDU Spent Fuel Storage Basket Package Prototype intended to be used for transport and storage of the CANDU spent fuel bundles within NPP CANDU Cernavoda, Romania. The results obtained proved that the objectives of those tests were achieved

Vieru, G.

2002-02-28T23:59:59.000Z

124

Drying results of K-Basin fuel element 3128W (run 2)  

Science Conference Proceedings (OSTI)

An N-Reactor outer fuel element that had been stored underwater in the Hanford 100 Area K-East Basin was subjected to a combination of low- and high-temperature vacuum drying treatments. These studies are part of a series of tests being conducted by Pacific Northwest National Laboratory on the drying behavior of N-Reactor spent nuclear fuel elements removed from both the K-West and K-East Basins. The drying test series was designed to test fuel elements that ranged from intact to severely damaged. The fuel element discussed in this report was removed from an open K-East canister (3128W) during the first fuel selection campaign conducted in 1995, and has remained in wet storage in the Postirradiation Testing Laboratory (PTL, 327 Building) since that time. Although it was judged to be breached during in-basin (i.e., K-Basin) examinations, visual inspection of this fuel element in the hot cell indicated that it was likely intact. Some scratches on the coating covering the cladding were identified before the furnace test. The drying test was conducted in the Whole Element Furnace Testing System located in G-Cell within the PTL. This test system is composed of three basic systems: the in-cell furnace equipment, the system gas loop, and the analytical instrument package. Element 3128W was subjected to the drying processes based on those proposed under the Integrated Process Strategy, which included a hot drying step. Results of the Pressure Rise and Gas Evolution Tests suggest that most of the free water in the system was released during the extended CVD cycle (68 hr versus 8 hr for the first run). An additional {approximately}0.34 g of water was released during the subsequent HVD phase, characterized by multiple water release peaks, with a principle peak at {approximately}180 C. This additional water is attributed to decomposition of a uranium hydrate (UO{sub 4}{center_dot}4H{sub 2}O/UO{sub 4}{center_dot}2H{sub 2}O) coating that was observed to be covering the surface of the fuel element to a thickness of {approximately}1.6 mg/cm{sup 2}. A limited quantity of hydrogen ({approximately}9 mg) was also released during HVD, mainly at temperatures above 300 C, likely from hydride decomposition.

Abrefah, J.; Klinger, G.S.; Oliver, B.M.; Marshman, S.C.; MacFarlan, P.J.; Ritter, G.A. [Pacific Northwest National Lab., Richland, WA (United States); Flament, T.A. [Numatec Hanford Corp., Richland, WA (United States)

1998-07-01T23:59:59.000Z

125

Hydrogen and Fuel Cell Technologies Program: Storage Fact Sheet  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

FUEL CELL TECHNOLOGIES PROGRAM FUEL CELL TECHNOLOGIES PROGRAM Hydrogen and Fuel Cell Technologies Program: Storage Hydrogen Storage Developing safe, reliable, compact, and cost-effective hydrogen storage tech- nologies is one of the most technically challenging barriers to the widespread use of hydrogen as a form of energy. To be competitive with conventional vehicles, hydrogen-powered cars must be able to travel more than 300 mi between fills. This is a challenging goal because hydrogen has physical characteristics that make it difficult to store in large quantities without taking up a significant amount of space. Where and How Will Hydrogen be Stored? Hydrogen storage will be required

126

Hydrogen fuel closer to reality because of storage advances  

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

Hydrogen fuel closer to reality because of storage advances Hydrogen fuel closer to reality because of storage advances Hydrogen fuel closer to reality because of storage advances Advances made in rechargeable solid hydrogen fuel storage tanks. March 21, 2012 Field experiments on the Alamosa Canyon How best to achieve the benchmark of 300 miles of travel without refueling? It may be to use the lightweight compound ammonia-borane to carry the hydrogen. With hydrogen accounting for almost 20 percent of its weight, this stable, non-flammable compound is one of the highest-capacity materials for storing hydrogen. In a car, the introduction of a chemical catalyst would release the hydrogen as needed, thus avoiding on-board storage of large quantities of flammable hydrogen gas. When the ammonia-borane fuel is depleted of hydrogen, it would be regenerated at a

127

Hydrogen fuel closer to reality because of storage advances  

E-Print Network (OSTI)

.S. Department of Energy's Chemical Hydrogen Storage Center of Excellence describe a significant advance- 1 - Hydrogen fuel closer to reality because of storage advances March 21, 2012 Drive toward hydrogen vehicles just got shorter A significant advance in hydrogen storage could make hydrogen a more

Kurien, Susan

128

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

129

Arrival condition of spent fuel after storage, handling, and transportation  

Science Conference Proceedings (OSTI)

This report presents the results of a study conducted to determine the probable arrival condition of spent light-water reactor (LWR) fuel after handling and interim storage in spent fuel storage pools and subsequent handling and accident-free transport operations under normal or slightly abnormal conditions. The objective of this study was to provide information on the expected condition of spent LWR fuel upon arrival at interim storage or fuel reprocessing facilities or at disposal facilities if the fuel is declared a waste. Results of a literature survey and data evaluation effort are discussed. Preliminary threshold limits for storing, handling, and transporting unconsolidated spent LWR fuel are presented. The difficulty in trying to anticipate the amount of corrosion products (crud) that may be on spent fuel in future shipments is also discussed, and potential areas for future work are listed. 95 references, 3 figures, 17 tables.

Bailey, W.J.; Pankaskie, P.J.; Langstaff, D.C.; Gilbert, E.R.; Rising, K.H.; Schreiber, R.E.

1982-11-01T23:59:59.000Z

130

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

131

The Impact of Microbially Influenced Corrosion on Spent Nuclear Fuel and Storage Life  

SciTech Connect

A study was performed to evaluate if microbial activity could be considered a threat to spent nuclear fuel integrity. The existing data regarding the impact of microbial influenced corrosion (MIC) on spent nuclear fuel storage does not allow a clear assessment to be made. In order to identify what further data are needed, a literature survey on MIC was accomplished with emphasis on materials used in nuclear fuel fabrication, e.g., A1, 304 SS, and zirconium. In addition, a survey was done at Savannah River, Oak Ridge, Hanford, and the INEL on the condition of their wet storage facilities. The topics discussed were the SNF path forward, the types of fuel, ramifications of damaged fuel, involvement of microbial processes, dry storage scenarios, ability to identify microbial activity, definitions of water quality, and the use of biocides. Information was also obtained at international meetings in the area of biological mediated problems in spent fuel and high level wastes. Topics dis cussed included receiving foreign reactor research fuels into existing pools, synergism between different microbes and other forms of corrosion, and cross contamination.

J. H. Wolfram; R. E. Mizia; R. Jex; L. Nelson; K. M. Garcia

1996-10-01T23:59:59.000Z

132

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

133

Hydrogen Storage Sub-Program Overview - DOE Hydrogen and Fuel...  

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

FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program IntroductIon The Hydrogen Storage sub-program supports research and development (R&D) of materials and...

134

Fuel cell systems for first lunar outpost -- Reactant storage options  

DOE Green Energy (OSTI)

A Lunar Surface Power Working Group was formed to review candidate systems for providing power to the First Lunar Outpost habitat. The working group met for five days in the fall of 1992 and concluded that the most attractive candidate included a photovoltaic unit, a fuel cell, a regenerator to recycle the reactants, and storage of oxygen and hydrogen gases. Most of the volume (97%) and weight (64%) are taken up by the reactants and their storage tanks. The large volume is difficult to accommodate, and therefore, the working group explored ways of reducing the volume. An alternative approach to providing separate high pressure storage tanks is to use two of the descent stage propellant storage tanks, which would have to be wrapped with graphite fibers to increase their pressure capability. This saves 90% of the volume required for storage of fuel cell reactants. Another approach is to use the descent storage propellant tanks for storage of the fuel cell reactants as cryogenic liquids, but this requires a gas liquefaction system, increases the solar array by 40%, and increases the heat rejection rate by 170% compared with storage of reactants as high pressure gases. For a high power system (>20 kW) the larger energy storage requirement would probably favor the cryogenic storage option.

Nelson, P.A. [Argonne National Lab., IL (United States). Chemical Technology Div.

1995-06-01T23:59:59.000Z

135

Dry oxidation and fracture of LWR spent fuels  

SciTech Connect

This report evaluates the characteristics of oxidation and fracture of light-water reactor (LWR) spent fuel in dry air. It also discusses their effects on radionuclide releases in the anticipated high-level waste repository environment. A sphere model may describe diffusion-limited formation of lower oxides, such as U{sub 4}O{sub 9}, in the oxidation of the spent fuel (SF) matrix. Detrimental higher oxides, such as U{sub 3}O{sub 8}, may not form at temperatures below a threshold temperature. The nucleation process suggests that a threshold temperature exists. The calculated results regarding fracture properties of the SF matrix agree with experimental observations. Oxidation and fracture of Zircaloy may not be significant under anticipated conditions. Under saturated or unsaturated aqueous conditions, oxidation of the SF matrix is believed to increase the releases of Pu-(239+240), Am-(241+243), C-14, Tc-99, I-129, and Cs-135. Under dry conditions, I-129 releases are likely to be small, unlike C-14, in lower oxides; Cl-36, Tc-99, I-129, and Cs-135 may be released fast in higher oxides. 79 refs.

Ahn, T.M.

1996-11-01T23:59:59.000Z

136

Degradation of EBR-II driver fuel during wet storage  

DOE Green Energy (OSTI)

Characterization data are reported for sodium bonded EBR-II reactor fuel which had been stored underwater in containers since the 1981--1982 timeframe. Ten stainless steel storage containers, which had leaked water during storage due to improper sealing, were retrieved from the ICPP-603 storage basin at the Idaho National Engineering and Environmental Laboratory (INEEL) in Idaho. In the container chosen for detailed destructive analysis, the stainless steel cladding on the uranium alloy fuel had ruptured and fuel oxide sludge filled the bottom of the container. Headspace gas sampling determined that greater than 99% hydrogen was present. Cesium 137, which had leached out of the fuel during the aqueous corrosion process, dominated the radionuclide source term of the water. The metallic sodium from the fuel element bond had reacted with the water, forming a concentrated caustic solution of NaOH.

Pahl, R. G.

2000-03-09T23:59:59.000Z

137

A Preliminary Evaluation of Using Fill Materials to Stabilize Used Nuclear Fuel During Storage and Transportation  

Science Conference Proceedings (OSTI)

This report contains a preliminary evaluation of potential fill materials that could be used to fill void spaces in and around used nuclear fuel contained in dry storage canisters in order to stabilize the geometry and mechanical structure of the used nuclear fuel during extended storage and transportation after extended storage. Previous work is summarized, conceptual descriptions of how canisters might be filled were developed, and requirements for potential fill materials were developed. Elements of the requirements included criticality avoidance, heat transfer or thermodynamic properties, homogeneity and rheological properties, retrievability, material availability and cost, weight and radiation shielding, and operational considerations. Potential fill materials were grouped into 5 categories and their properties, advantages, disadvantages, and requirements for future testing were discussed. The categories were molten materials, which included molten metals and paraffin; particulates and beads; resins; foams; and grout. Based on this analysis, further development of fill materials to stabilize used nuclear fuel during storage and transportation is not recommended unless options such as showing that the fuel remains intact or canning of used nuclear fuel do not prove to be feasible.

Maheras, Steven J.; Best, Ralph; Ross, Steven B.; Lahti, Erik A.; Richmond, David J.

2012-08-01T23:59:59.000Z

138

Analysis of Fuel Cell Vehicle Hybridization and Implications for Energy Storage Devices: June 2004  

DOE Green Energy (OSTI)

This paper addresses the impact of fuel efficiency characteristics on vehicle system efficiency, fuel economy from downsizing different fuel cells, as well as the energy storage system.

Zolot, M.; Markel, T.; Pesaran, A.

2007-01-01T23:59:59.000Z

139

Analysis of Fuel Cell Vehicles Hybridization and Implications for Energy Storage Devices (Presentation)  

DOE Green Energy (OSTI)

Presents an analysis of hybridization and implications energy storage devices concerning fuel cell vehicles.

Zolot, M.; Markel, T.; Pesaran, A.

2004-06-01T23:59:59.000Z

140

Fuel Cell Technologies Office: Hydrogen Compression, Storage...  

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

of Energy's (DOE's) Argonne National Laboratory (ANL) held a Hydrogen Compression, Storage, and Dispensing Cost Reduction Workshop on March 20-21, 2013, in Argonne, Illinois....

Note: This page contains sample records for the topic "fuel dry 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

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

142

Fuel Cell Technologies Office: Onboard Storage Tank Workshop  

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

Onboard Storage Tank Workshop Onboard Storage Tank Workshop The U.S. Department of Energy (DOE) and Sandia National Laboratories co-hosted the Onboard Storage Tank Workshop on April 29th, 2010. Onboard storage tank experts gathered to share lessons learned about research and development (R&D) needs; regulations, codes and standards (RCS); and a path forward to enable the successful deployment of hydrogen storage tanks in early market fuel cell applications. The workshop also included initial follow up to the DOE and Department of Transportation (DOT) International Workshop on Compressed Natural Gas and Hydrogen Fuels held on December 10-11, 2009. Here you will find information about Workshop proceedings including all presentations. Agenda and Notes The following agenda and notes provide summary information about the workshop.

143

Fuel Cell Technologies Office: Hydrogen Storage  

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

Current Technology DOE R&D Activities Quick Links Hydrogen Production Hydrogen Delivery Fuel Cells Technology Validation Manufacturing Codes & Standards Education Systems...

144

Rapid determination of wood fuel moisture content using a microwave oven for drying  

SciTech Connect

A method of determining moisture content (MC) of wood fuel using a microwave oven for drying the wood was evaluated by drying paired samples of five different wood fuel types in a microwave oven and a conventional oven. When compared to the conventional oven drying method, the microwave technique produces consistently lower MC determinations, although the differences are less than 1 percent. The advantage of the microwave technique is the speed at which MC determinations can be determined (less than 15 minutes). Schedules for drying five wood fuel types are presented. (Refs. 7).

Harris, R.A.

1982-10-01T23:59:59.000Z

145

President Reagan Calls for a National Spent Fuel Storage Facility |  

National Nuclear Security Administration (NNSA)

Reagan Calls for a National Spent Fuel Storage Facility | Reagan Calls for a National Spent Fuel Storage Facility | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > President Reagan Calls for a National Spent ... President Reagan Calls for a National Spent Fuel Storage Facility October 08, 1981

146

Fuel Cell Technologies Office: Storage Systems Analysis Working Group  

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

Storage Systems Analysis Working Group Storage Systems Analysis Working Group The Storage Systems Analysis Working Group, launched in March 2005, provides a forum to facilitate research and communication of hydrogen storage-related analysis activities among researchers actively engaged in hydrogen storage systems analyses. The working group includes members from DOE, the national laboratories, industry, and academia. Description Technical Targets Meetings Contacts Description Hydrogen storage is a key enabling technology for the advancement of hydrogen and fuel cell power technologies in transportation, stationary, and portable power applications. One of the most challenging technical barriers known is how to efficiently store hydrogen on-board a vehicle to meet customer expectations of a driving range greater than 300 miles-as well as performance, safety, and cost-without impacting passenger or cargo space. The Department of Energy's hydrogen storage activity is coordinated through the "National Hydrogen Storage Project," with multiple university, industry, and federal laboratory partners focused on research and development of on-board vehicular hydrogen storage technologies. This research also has components applicable to off-board storage of hydrogen for refueling infrastructure and the off-board regeneration of chemical hydrogen carriers applicable to hydrogen delivery.

147

Test storage of spent reactor fuel in the Climax granite at the Nevada Test Site  

SciTech Connect

A test of retrievable dry geologic storage of spent fuel assemblies from an operating commercial nuclear reactor is underway at the Nevada Test Site. This generic test is located 420 m below the surface in the Climax granitic stock. Eleven canisters of spent fuel approximately 2.3 years out of reactor core (about 2 kW/canister thermal output) will be emplaced in a storage drift along with 6 electrical simulator canisters and their effects will be compared. Two adjacent drifts will contain electrical heaters, which will be operated to simulate within the test array the thermal field of a large repository. The test objectives, technical concepts and rationale, and details of the test are stated and discussed.

Ramspott, L.D.; Ballou, L.B.

1980-02-13T23:59:59.000Z

148

Hydrogen Storage Needs for Early Motive Fuel Cell Markets  

DOE Green Energy (OSTI)

The National Renewable Energy Laboratory's (NREL) objective for this project is to identify performance needs for onboard energy storage of early motive fuel cell markets by working with end users, manufacturers, and experts. The performance needs analysis is combined with a hydrogen storage technology gap analysis to provide the U.S. Department of Energy (DOE) Fuel Cell Technologies Program with information about the needs and gaps that can be used to focus research and development activities that are capable of supporting market growth.

Kurtz, J.; Ainscough, C.; Simpson, L.; Caton, M.

2012-11-01T23:59:59.000Z

149

Crude oil and finished fuel storage stability: An annotated review  

DOE Green Energy (OSTI)

A state-of-the-art review and assessment of storage effects on crude oil and product quality was undertaken through a literature search by computer accessing several data base sources. Pertinent citations from that literature search are tabulated for the years 1980 to the present. This 1990 revision supplements earlier reviews by Brinkman and others which covered stability publications through 1979 and an update in 1983 by Goetzinger and others that covered the period 1952--1982. For purposes of organization, citations are listed in the current revision chronologically starting with the earliest 1980 publications. The citations have also been divided according to primary subject matter. Consequently 11 sections appear including: alternate fuels, gasoline, distillate fuel, jet fuel, residual fuel, crude oil, biodegradation, analyses, reaction mechanisms, containment, and handling and storage. Each section contains a brief narrative followed by all the citations for that category.

Whisman, M.L.; Anderson, R.P.; Woodward, P.W.; Giles, H.N.

1991-01-01T23:59:59.000Z

150

Chemical Hydrides for Hydrogen Storage in Fuel Cell Applications  

Science Conference Proceedings (OSTI)

Due to its high hydrogen storage capacity (up to 19.6% by weight for the release of 2.5 molar equivalents of hydrogen gas) and its stability under typical ambient conditions, ammonia borane (AB) is a promising material for chemical hydrogen storage for fuel cell applications in transportation sector. Several systems models for chemical hydride materials such as solid AB, liquid AB and alane were developed and evaluated at PNNL to determine an optimal configuration that would meet the 2010 and future DOE targets for hydrogen storage. This paper presents an overview of those systems models and discusses the simulation results for various transient drive cycle scenarios.

Devarakonda, Maruthi N.; Brooks, Kriston P.; Ronnebro, Ewa; Rassat, Scot D.; Holladay, Jamelyn D.

2012-04-16T23:59:59.000Z

151

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

152

West Valley facility spent fuel handling, storage, and shipping experience  

Science Conference Proceedings (OSTI)

The result of a study on handling and shipping experience with spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory (PNL) and was jointly sponsored by the US Department of Energy (DOE) and the Electric Power Research Institute (EPRI). The purpose of the study was to document the experience with handling and shipping of relatively old light-water reactor (LWR) fuel that has been in pool storage at the West Valley facility, which is at the Western New York Nuclear Service Center at West Valley, New York and operated by DOE. A subject of particular interest in the study was the behavior of corrosion product deposits (i.e., crud) deposits on spent LWR fuel after long-term pool storage; some evidence of crud loosening has been observed with fuel that was stored for extended periods at the West Valley facility and at other sites. Conclusions associated with the experience to date with old spent fuel that has been stored at the West Valley facility are presented. The conclusions are drawn from these subject areas: a general overview of the West Valley experience, handling of spent fuel, storing of spent fuel, rod consolidation, shipping of spent fuel, crud loosening, and visual inspection. A list of recommendations is provided. 61 refs., 4 figs., 5 tabs.

Bailey, W.J.

1990-11-01T23:59:59.000Z

153

Ammonia as an Alternative Energy Storage Medium for Hydrogen Fuel Cells: Scientific and Technical Review for Near-Term Stationary Power Demonstration Projects, Final Report  

E-Print Network (OSTI)

Alternative Energy Storage Medium for Hydrogen Fuel Cells:Alternative Energy Storage Medium for Hydrogen Fuel Cells:based energy storage system to produce hydrogen for a fuel

Lipman, Tim; Shah, Nihar

2007-01-01T23:59:59.000Z

154

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

155

Storage of LWR spent fuel in air. Volume 3, Results from exposure of spent fuel to fluorine-contaminated air  

SciTech Connect

The Behavior of Spent Fuel in Storage (BSFS) Project has conducted research to develop data on spent nuclear fuel (irradiated U0{sub 2}) that could be used to support design, licensing, and operation of dry storage installations. Test Series B conducted by the BSFS Project was designed as a long-term study of the oxidation of spent fuel exposed to air. It was discovered after the exposures were completed in September 1990 that the test specimens had been exposed to an atmosphere of bottled air contaminated with an unknown quantity of fluorine. This exposure resulted in the test specimens reacting with both the oxygen and the fluorine in the oven atmospheres. The apparent source of the fluorine was gamma radiation-induced chemical decomposition of the fluoro-elastomer gaskets used to seal the oven doors. This chemical decomposition apparently released hydrofluoric acid (HF) vapor into the oven atmospheres. Because the Test Series B specimens were exposed to a fluorine-contaminated oven atmosphere and reacted with the fluorine, it is recommended that the Test Series B data not be used to develop time-temperature limits for exposure of spent nuclear fuel to air. This report has been prepared to document Test Series B and present the collected data and observations.

Cunningham, M.E.; Thomas, L.E.

1995-06-01T23:59:59.000Z

156

Perils of plutonium [spent nuclear fuel storage  

Science Conference Proceedings (OSTI)

This paper focuses on the security of the ponds at reactor sites where radioactive spent fuel are being stored. A recent report by a panel of the National Academy of Sciences in Washington, DC, said that attacks by knowledgeable terrorists with access ...

P. P. Predd

2005-07-01T23:59:59.000Z

157

Decontamination of FAST (CPP-666) fuel storage area stainless steel fuel storage racks  

SciTech Connect

The purpose of this report was to identify and evaluate alternatives for the decontamination of the RSM stainless steel that will be removed from the Idaho Chemical Processing plant (ICPP) fuel storage area (FSA) located in the FAST (CPP-666) building, and to recommend decontamination alternatives for treating this material. Upon the completion of a literature search, the review of the pertinent literature, and based on the review of a variety of chemical, mechanical, and compound (both chemical and mechanical) decontamination techniques, the preliminary results of analyses of FSA critically barrier contaminants, and the data collected during the FSA Reracking project, it was concluded that decontamination and beneficial recycle of the FSA stainless steel produced is technically feasible and likely to be cost effective as compared to burying the material at the RWMC. It is recommended that an organic acid, or commercial product containing an organic acid, be used to decontaminate the FSA stainless steel; however, it is also recommended that other surface decontamination methods be tested in the event that this method proves unsuitable. Among the techniques that should be investigated are mechanical techniques (CO{sub 2} pellet blasting and ultra-high pressure water blasting) and chemical techniques that are compatible with present ICPP waste streams.

Kessinger, G.F.

1993-10-01T23:59:59.000Z

158

Opportunities for Utility-Owned CHP at Dry-Mill Fuel Ethanol Plants  

Science Conference Proceedings (OSTI)

This report quantifies opportunities to co-locate natural-gas-fueled combined heat and power (CHP) facilities with corn dry-mill fuel ethanol plants in the upper Midwest. It also evaluates the opportunity to generate renewable power by fueling the CHP plants with biogas produced by anaerobic digestion of the byproducts of the corn wet-milling process.

2008-09-23T23:59:59.000Z

159

Hydrogen Storage Needs for Early Motive Fuel Cell Markets  

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

Storage Needs for Storage Needs for Early Motive Fuel Cell Markets J. Kurtz, C. Ainscough, L. Simpson, and M. Caton Technical Report NREL/TP-5600-52783 November 2012 NREL is a national laboratory of the U.S. Department of Energy, Office of Energy Efficiency & Renewable Energy, operated by the Alliance for Sustainable Energy, LLC. National Renewable Energy Laboratory 15013 Denver West Parkway Golden, Colorado 80401 303-275-3000 * www.nrel.gov Contract No. DE-AC36-08GO28308 Hydrogen Storage Needs for Early Motive Fuel Cell Markets J. Kurtz, C. Ainscough, L. Simpson, and M. Caton Prepared under Task No. H272.4410 Technical Report NREL/TP-5600-52783 November 2012 NOTICE This report was prepared as an account of work sponsored by an agency of the United States government.

160

Fuel Cycle Technologies Near Term Planning for Storage and Transportation of Used Nuclear Fuel  

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

Fuels Storage Fuels Storage and Transportation Planning Project (NFST) Program Status Jeff Williams Project Director National Transportation Stakeholders Forum Buffalo, New York May 2013 2 ÔĀģ "With the appropriate authorizations from Congress, the Administration currently plans to implement a program over the next 10 years that: Ôāß Sites, designs and licenses, constructs and begins operations of a pilot interim storage facility by 2021 with an initial focus on accepting used nuclear fuel from shut-down reactor sites; Ôāß Advances toward the siting and licensing of a larger interim storage facility to be available by 2025 that will have sufficient capacity to provide flexibility in the waste management system and allows for acceptance of enough used

Note: This page contains sample records for the topic "fuel dry 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

Fail-safe storage rack for irradiated fuel rod assemblies  

DOE Patents (OSTI)

A fail-safe storage rack is provided for interim storage of spent but radioactive nuclear fuel rod assemblies. The rack consists of a checkerboard array of substantially square, elongate receiving tubes fully enclosed by a double walled container, the outer wall of which is imperforate for liquid containment and the inner wall of which is provided with perforations for admitting moderator liquid flow to the elongate receiving tubes, the liquid serving to take up waste heat from the stored nuclear assemblies and dissipate same to the ambient liquid reservoir. A perforated cover sealing the rack facilitates cooling liquid entry and dissipation.

Lewis, D.R.

1993-03-23T23:59:59.000Z

162

Fail-safe storage rack for fuel rod assemblies  

DOE Patents (OSTI)

This report discusses a fail-safe storage rack which is provided for interim storage of spent but radioactive nuclear fuel rod assemblies. The rack consists of a checkerboard array of substantially square, elongate receiving tubes fully enclosed by a double walled container, the outer wall of which is imperforate for liquid containment and the inner wall of which is provided with perforations for admitting moderator liquid flow to the elongate receiving tubes, the liquid serving to take up waste heat from the stored nuclear assemblies and dissipate same to the ambient liquid reservoir. A perforated cover sealing the rack facilitates cooling liquid entry and dissipation.

Lewis, D.R.

1991-12-31T23:59:59.000Z

163

Hydrogen Fuel Cells and Storage Technology: Fundamental Research for Optimization of Hydrogen Storage and Utilization  

SciTech Connect

Design and development of improved low-cost hydrogen fuel cell catalytic materials and high-capacity hydrogenn storage media are paramount to enabling the hydrogen economy. Presently, effective and durable catalysts are mostly precious metals in pure or alloyed form and their high cost inhibits fuel cell applications. Similarly, materials that meet on-board hydrogen storage targets within total mass and volumetric constraints are yet to be found. Both hydrogen storage performance and cost-effective fuel cell designs are intimately linked to the electronic structure, morphology and cost of the chosen materials. The FCAST Project combined theoretical and experimental studies of electronic structure, chemical bonding, and hydrogen adsorption/desorption characteristics of a number of different nanomaterials and metal clusters to develop better fundamental understanding of hydrogen storage in solid state matrices. Additional experimental studies quantified the hydrogen storage properties of synthesized polyaniline(PANI)/Pd composites. Such conducting polymers are especially interesting because of their high intrinsic electron density and the ability to dope the materials with protons, anions, and metal species. Earlier work produced contradictory results: one study reported 7% to 8% hydrogen uptake while a second study reported zero hydrogen uptake. Cost and durability of fuel cell systems are crucial factors in their affordability. Limits on operating temperature, loss of catalytic reactivity and degradation of proton exchange membranes are factors that affect system durability and contribute to operational costs. More cost effective fuel cell components were sought through studies of the physical and chemical nature of catalyst performance, characterization of oxidation and reduction processes on system surfaces. Additional development effort resulted in a new hydrocarbon-based high-performance sulfonated proton exchange membrane (PEM) that can be manufactured at low cost and accompanied by improved mechanical and thermal stability.

Perret, Bob; Heske, Clemens; Nadavalath, Balakrishnan; Cornelius, Andrew; Hatchett, David; Bae, Chusung; Pang, Tao; Kim, Eunja; Hemmers, Oliver

2011-03-28T23:59:59.000Z

164

Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)  

SciTech Connect

The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. Because this sub-project is still in the construction/start-up phase, all verification activities have not yet been performed (e.g., canister cover cap and welding fixture system verification, MCO Internal Gas Sampling equipment verification, and As-built verification.). The verification activities identified in this report that still are to be performed will be added to the start-up punchlist and tracked to closure.

PICKETT, W.W.

2000-09-22T23:59:59.000Z

165

Spent nuclear fuel storage -- Performance tests and demonstrations  

SciTech Connect

This report summarizes the results of heat transfer and shielding performance tests and demonstrations conducted from 1983 through 1992 by or in cooperation with the US Department of Energy (DOE), Office of Commercial Radioactive Waste Management (OCRWM). The performance tests consisted of 6 to 14 runs involving one or two loadings, usually three backfill environments (helium, nitrogen, and vacuum backfills), and one or two storage system orientations. A description of the test plan, spent fuel load patterns, results from temperature and dose rate measurements, and fuel integrity evaluations are contained within the report.

McKinnon, M.A.; DeLoach, V.A.

1993-04-01T23:59:59.000Z

166

Vehicular hydrogen storage using lightweight tanks (regenerative fuel cell systems)  

DOE Green Energy (OSTI)

Energy storage systems with extremely high specific energy (>400 Wh/kg) have been designed that use lightweight tankage to contain the gases generated by reversible (unitized) regenerative fuel cells (URFCs). Lawrence Livermore National Laboratory (LLNL) will leverage work for aerospace applications supported by other sponsors (including BMDO, NASA, and USAF) to develop URFC systems for transportation and utility applications. Lightweight tankage is important for primary fuel cell powered vehicles that use on-board storage of hydrogen. Lightweight pressure vessels with state-of-the-art performance factors were designed, and prototypes are being fabricated to meet the DOE 2000 goals (4000 Wh/kg, 12% hydrogen by weight, 700 Wh/liter, and $20/kWh in high volume production). These pressure vessels use technologies that are easily adopted by industrial partners. Advanced liners provide permeation barriers for gas storage and are mandrels for composite overwrap. URFCs are important to the efficient use of hydrogen as a transportation fuel and enabler of renewable energy. H{sub 2}/halogen URFCs may be advantageous for stationary applications whereas H{sub 2}/O{sub 2} or H{sub 2}/air URFCs are advantageous for vehicular applications. URFC research and development is required to improve performance (efficiency), reduce catalyst loading, understand engineering operation, and integrate systems. LLNL has the experimental equipment and advanced URFC membrane electrode assemblies (some with reduced catalyst loading) for evaluating commercial hardware (not funded by DOE in FY1999).

Mitlitsky, F; Myers, B; Weisberg, A H

1999-06-01T23:59:59.000Z

167

Sensitivity analysis of a dry-processed Candu fuel pellet's design parameters  

SciTech Connect

Sensitivity analysis was carried out in order to investigate the effect of a fuel pellet's design parameters on the performance of a dry-processed Canada deuterium uranium (CANDU) fuel and to suggest the optimum design modifications. Under a normal operating condition, a dry-processed fuel has a higher internal pressure and plastic strain due to a higher fuel centerline temperature when compared with a standard natural uranium CANDU fuel. Under a condition that the fuel bundle dimensions do not change, sensitivity calculations were performed on a fuel's design parameters such as the axial gap, dish depth, gap clearance and plenum volume. The results showed that the internal pressure and plastic strain of the cladding were most effectively reduced if a fuel's element plenum volume was increased. More specifically, the internal pressure and plastic strain of the dry-processed fuel satisfied the design limits of a standard CANDU fuel when the plenum volume was increased by one half a pellet, 0.5 mm{sup 3}/K. (authors)

Choi, Hangbok; Ryu, Ho Jin [Korea Atomic Energy Research Institute 1045 Daedeok-daero, Yuseong-gu, Daejeon, 305-353 (Korea, Republic of)

2007-07-01T23:59:59.000Z

168

Gap Analysis to Support Extended Storage of Used Nuclear Fuel | Department  

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

Gap Analysis to Support Extended Storage of Used Nuclear Fuel Gap Analysis to Support Extended Storage of Used Nuclear Fuel Gap Analysis to Support Extended Storage of Used Nuclear Fuel The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology, has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development activities related to storage, transportation, and disposal of used nuclear fuel and high-level radioactive waste. The mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel (UNF) and wastes generated by existing and future nuclear fuel cycles. The Storage and Transportation staff within the UFDC are responsible for addressing issues regarding the

169

The effect of drying on the heating value of biomass fuels  

E-Print Network (OSTI)

There has been some speculation as to whether or not biomass fuels (such as feedlot manure) may lose volatile matter during the drying process. Since current standards state that heating value analysis may be performed before or after drying, and volatile matter analysis can only be performed after drying, and since many fuel suppliers are paid on a heating value basis of the fuel, there has been some controversy in this matter. Furthermore, it is known that if manure is left out at ambient temperatures over long periods of time, the heating value decreases as well. It is therefore the objective of this work to ascertain if in fact volatile matter is lost during the drying or aging process and, if so, to find an optimum aging and /or drying time and to model the loss of volatile matter. It has been found that, if indeed there is volatile matter loss over the drying process, then it is so small as to be negligible. Furthermore, no appreciable amount of volatile loss occurs even if the fuel is dried for extensive amounts of time as are generally needed to obtain constant weight in the fuel sample. It has also been found that heating value decreases with aging time (falling even after only one to two days at atmospheric conditions), yet the heating value of an initial (undried) fuel sample increases with aging time. This is because moisture is lost as well as combustibles so the heat produced by the fuel will increase with a decrease in moisture even though volatiles are lost.

Rodriguez, Pablo Gregorio

1994-01-01T23:59:59.000Z

170

Drying damaged K West fuel elements (Summary of whole element furnace runs 1 through 8)  

DOE Green Energy (OSTI)

N Reactor fuel elements stored in the Hanford K Basins were subjected to high temperatures and vacuum conditions to remove water. Results of the first series of whole element furnace tests i.e., Runs 1 through 8 were collected in this summary report. The report focuses on the six tests with breached fuel from the K West Basin which ranged from a simple fracture at the approximate mid-point to severe damage with cladding breaches at the top and bottom ends with axial breaches and fuel loss. Results of the tests are summarized and compared for moisture released during cold vacuum drying, moisture remaining after drying, effects of drying on the fuel element condition, and hydrogen and fission product release.

LAWRENCE, L.A.

1998-10-13T23:59:59.000Z

171

Spent nuclear fuel project cold vacuum drying facility operations manual  

SciTech Connect

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

IRWIN, J.J.

1999-05-12T23:59:59.000Z

172

Hydrogen Composite Tank Program Principal Investigator: Dr. Neel Sirosh, Director of Fuel Storage  

E-Print Network (OSTI)

Hydrogen Composite Tank Program Principal Investigator: Dr. Neel Sirosh, Director of Fuel Storage-effective and efficient high-pressure hydrogen storage systems. World's premier automotive OEMs developing fuel cell vehicles have demonstrated significant interest in compressed hydrogen storage systems developed

173

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

174

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 ó a spent fuel cask probabilistic risk assessment (PRA) (EPRI report 1002877) ó are designed to provide insights related to the risks associated with dry storage of spent fuel.

2004-11-30T23:59:59.000Z

175

Technical System Targets: Onboard Hydrogen Storage for Light-Duty Fuel Cell Vehicles  

E-Print Network (OSTI)

is to be determined. e Onboard efficiency is the energy efficiency for delivering hydrogen from the storage systemTechnical System Targets: Onboard Hydrogen Storage for Light-Duty Fuel Cell Vehicles a Storage to the powerplant divided by the total mass/volume of the complete storage system, including all stored hydrogen

176

Compact approach to monitored retrievable storage of spent fuel  

Science Conference Proceedings (OSTI)

Recent federal waste-management legislation has raised national interest in monitored retrievable storage (MRS) of unprocessed spent fuel from civilian nuclear power plants. We have reviewed the current MRS design approaches, and we have examined an alternative concept that is extremely compact in terms of total land use. This approach may offer substantial advantages in the areas of monitoring and in safeguards against theft, as well as in reducing the chances of groundwater contamination. Total facility costs are roughly estimated and found to be generally competitive with other MRS concepts. 4 references, 3 figures, 3 tables.

Muir, D.W.

1984-09-01T23:59:59.000Z

177

Examination of Spent CANDU (TM) Fuel Following 27 Years of Pool Storage  

Science Conference Proceedings (OSTI)

After 27 years in pool storage, the Zircaloy cladding of CANDU fuel showed no deterioration. Further, in deliberately defected fuel elements, uranium oxide surface oxidation appeared to have no impact on fuel-cladding integrity. These results increase utilities' confidence that the fuel can be stored in pools for periods of at least 50 years.

1992-05-01T23:59:59.000Z

178

Design Verification Report Spent Nuclear Fuel (SNF) Project Canister Storage Building (CSB)  

Science Conference Proceedings (OSTI)

The Sub-project W379, ''Spent Nuclear Fuel Canister Storage Building (CSB),'' was established as part of the Spent Nuclear Fuel (SNF) Project. The primary mission of the CSB is to safely store spent nuclear fuel removed from the K Basins in dry storage until such time that it can be transferred to the national geological repository at Yucca Mountain Nevada. This sub-project was initiated in late 1994 by a series of studies and conceptual designs. These studies determined that the partially constructed storage building, originally built as part of the Hanford Waste Vitrification Plant (HWVP) Project, could be redesigned to safely store the spent nuclear fuel. The scope of the CSB facility initially included a receiving station, a hot conditioning system, a storage vault, and a Multi-Canister Overpack (MCO) Handling Machine (MHM). Because of evolution of the project technical strategy, the hot conditioning system was deleted from the scope and MCO welding and sampling stations were added in its place. This report outlines the methods, procedures, and outputs developed by Project W379 to verify that the provided Structures, Systems, and Components (SSCs): satisfy the design requirements and acceptance criteria; perform their intended function; ensure that failure modes and hazards have been addressed in the design; and ensure that the SSCs as installed will not adversely impact other SSCs. The original version of this document was prepared by Vista Engineering for the SNF Project. The purpose of this revision is to document completion of verification actions that were pending at the time the initial report was prepared. Verification activities for the installed and operational SSCs have been completed. Verification of future additions to the CSB related to the canister cover cap and welding fixture system and MCO Internal Gas Sampling equipment will be completed as appropriate for those components. The open items related to verification of those requirements are noted in section 3.1.5 and will be tracked as part of the CSB Facility action tracking system.

BAZINET, G.D.

2000-11-03T23:59:59.000Z

179

Multi-fuel reformers for fuel cells used in transportation: Assessment of hydrogen storage technologies. Phase 1, Final report  

DOE Green Energy (OSTI)

This report documents a portion of the work performed Multi-fuel Reformers for Fuel Cells Used in Transportation. One objective for development is to develop advanced fuel processing systems to reform methanol, ethanol, natural gas, and other hydrocarbons into hydrogen for use in transportation fuel cell systems, while a second objective is to develop better systems for on-board hydrogen storage. This report examines techniques and technology available for storage of pure hydrogen on board a vehicle as pure hydrogen of hydrides. The report focuses separately on near- and far-term technologies, with particular emphasis on the former. Development of lighter, more compact near-term storage systems is recommended to enhance competitiveness and simplify fuel cell design. The far-term storage technologies require substantial applied research in order to become serious contenders.

Not Available

1994-03-01T23:59:59.000Z

180

Trojan Nuclear Plant Decommissioning: Final Survey for the Independent Spent Fuel Storage Installation Site  

Science Conference Proceedings (OSTI)

This report describes the final radiological survey for the area where Portland General Electric (PGE) will construct the Independent Spent Fuel Storage Installation (ISFSI) at Trojan nuclear power plant. The survey fulfills the requirements for release of this area from Trojan's 10 CFR 50 license before radiation levels increase with spent fuel storage in the ISFSI.

1998-05-13T23:59:59.000Z

Note: This page contains sample records for the topic "fuel dry 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

A FUEL?CELL DISTRIBUTED ENERGY RESOURCE WITH INTEGRATED ENERGY STORAGE  

Science Conference Proceedings (OSTI)

This paper presents a fuel?cell distributed energy resource with integrated energy storage. A compatible power electronic interface to couple the fuel?cell with the grid and/or a local load is introduced. Details of the energy storage module

Hassan Nikkhajoei

2009-01-01T23:59:59.000Z

182

ALARA Analysis for Shippingport Pressurized Water Reactor Core 2 Fuel Storage in the Canister Storage Building (CSB)  

E-Print Network (OSTI)

The addition of Shippingport Pressurized Water Reactor (PWR) Core 2 Blanket Fuel Assembly storage in the Canister Storage Building (CSB) will increase the total cumulative CSB personnel exposure from receipt and handling activities. The loaded Shippingport Spent Fuel Canisters (SSFCs) used for the Shippingport fuel have a higher external dose rate. Assuming an MCO handling rate of 170 per year (K East and K West concurrent operation), 24-hr CSB operation, and nominal SSFC loading, all work crew personnel will have a cumulative annual exposure of less than the 1,000 mrem limit.

Lewis, M E

2000-01-01T23:59:59.000Z

183

Modular Energy Storage System for Hydrogen Fuel Cell Vehicles  

SciTech Connect

The objective of the project is to develop technologies, specifically power electronics, energy storage electronics and controls that provide efficient and effective energy management between electrically powered devices in alternative energy vehicles ‚?? plug-in electric vehicles, hybrid vehicles, range extended vehicles, and hydrogen-based fuel cell vehicles. The in-depth research into the complex interactions between the lower and higher voltage systems from data obtained via modeling, bench testing and instrumented vehicle data will allow an optimum system to be developed from a performance, cost, weight and size perspective. The subsystems are designed for modularity so that they may be used with different propulsion and energy delivery systems. This approach will allow expansion into new alternative energy vehicle markets.

Janice Thomas

2010-05-31T23:59:59.000Z

184

Technical framework to facilitate foreign spent fuel storage and geologic disposal in Russia  

SciTech Connect

The option of storage and eventual geologic disposal in Russia of spent fuel of US origin used in Taiwan provides a unique opportunity that can benefit many parties. Taiwan has a near term need for a spent fuel storage and geologic disposal solution, available financial resources, but limited prospect for a timely domestic solution. Russia has significant spent fuel storage and transportation management experience, candidate storage and repository sites, but limited financial resources available for their development. The US has interest in Taiwan energy security, national security and nonproliferation interests in Russian spent fuel storage and disposal and interest in the US origin fuel. While it is understood that such a project includes complex policy and international political issues as well as technical issues, the goal of this paper is to begin the discussion by presenting a technical path forward to establish the feasibility of this concept for Russia.

Jardine, L J; Halsey, W G; Cmith, C F

2000-01-31T23:59:59.000Z

185

Hydrogen, Fuel Cells, and Infrastructure Technologies FY 2002 Progress Report Section III. Hydrogen Storage  

E-Print Network (OSTI)

. Hydrogen Storage #12;Hydrogen, Fuel Cells, and Infrastructure Technologies FY 2002 Progress Report 200 #12 square inch (psi) 7.5 wt % and 8.5 wt% Type IV composite hydrogen storage tanks of specified sizes for DOE Future Truck and Nevada hydrogen bus programs · Demonstrate 10,000 psi storage tanks Approach

186

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

187

Spent Nuclear Fuel (SNF) Cold Vacuum Drying (CVD) Facility Operations Manual  

SciTech Connect

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-553, Spent Nuclear Fuel Project Final Safety Analysis Report Annex B--Cold Vacuum Drying Facility. The HNF-SD-SNF-DRD-002, 1999, Cold Vacuum Drying Facility Design Requirements, Rev. 4, and the CVDF Final Design Report. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence and references to the CVDF System Design Descriptions (SDDs). This manual has been developed for the SNFP Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

IRWIN, J.J.

1999-07-02T23:59:59.000Z

188

Spent Nuclear Fuel (SNF) Project Cold Vacuum Drying (CVD) Facility Operations Manual  

Science Conference Proceedings (OSTI)

This document provides the Operations Manual for the Cold Vacuum Drying Facility (CVDF). The Manual was developed in conjunction with HNF-SD-SNF-SAR-002, Safety Analysis Report for the Cold Vacuum Drying Facility, Phase 2, Supporting Installation of the Processing Systems (Garvin 1998) and, the HNF-SD-SNF-DRD-002, 1997, Cold Vacuum Drying Facility Design Requirements, Rev. 3a. The Operations Manual contains general descriptions of all the process, safety and facility systems in the CVDF, a general CVD operations sequence, and has been developed for the spent nuclear fuel project (SNFP) Operations Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

IRWIN, J.J.

2000-02-03T23:59:59.000Z

189

Hydrogen Storage and Supply for Vehicular Fuel Systems  

alternative-fuel systems have been proposed for passenger vehicles and light-duty trucks to reduce the worldwide reliance on fossils fuels and thus mitigate their polluting effects. †Replacing gasoline and other refined hydrocarbon fuels ...

190

Behavior of Spent Nuclear Fuel in Water Pool Storage  

Office of Scientific and Technical Information (OSTI)

Behavior of Spent Nuclear Behavior of Spent Nuclear Fuel in Water Pool Storage A. 0; Johnson, jr. , I ..: . Prepared Cor the Energy Research and Development Administration under Contract EY-76-C-06-1830 ---- Pat t i ~ < N ~ ~ r ~ t b w t ~ - ! I , ~ I ~ ~ ~ I . I I ~ ) ~ I I ~ ~ N O T I C E T‚ā¨& - was prepad pnpn4. m w n t of w k spon-d by the Unitd S t . & ) C a u n m ~ (*WU ij*. M t e d $tam w the Wqy R e s e w & a d Ohrsropmcnt ~dmhirmlion, nor m y d thair ewhew,,nq Pny @fw a n t r ~ ~ t 0 ~ 1 , s ~ k m r i t r i l t t q r , ~ , m r tWf ernpfQw, r(tLltm any wartany, s x p r e s or kWld,= w w aAql -9 . o r r w p a m l ~ ~ t y for e~ o r uodruincvr of any infomutim, 9 F p d + d - , or repratants that -would nat 1 d - e privately owned rfghas. ,i PAQFIC NORTHWEST UBORATORY operated b ;"' SArnLLE ' fw the E M R m RESEARCH AND DEVELOPMENT ADMINISTRAT1QN Wk.Cwfraa rv-76c-ts-is38

191

DEMONSTRATION OF LONG-TERM STORAGE CAPABILITY FOR SPENT NUCLEAR FUEL IN L BASIN  

Science Conference Proceedings (OSTI)

The U.S. Department of Energy decisions for the ultimate disposition of its inventory of used nuclear fuel presently in, and to be received and stored in, the L Basin at the Savannah River Site, and schedule for project execution have not been established. A logical decision timeframe for the DOE is following the review of the overall options for fuel management and disposition by the Blue Ribbon Commission on America's Nuclear Future (BRC). The focus of the BRC review is commercial fuel; however, the BRC has included the DOE fuel inventory in their review. Even though the final report by the BRC to the U.S. Department of Energy is expected in January 2012, no timetable has been established for decisions by the U.S. Department of Energy on alternatives selection. Furthermore, with the imminent lay-up and potential closure of H-canyon, no ready path for fuel disposition would be available, and new technologies and/or facilities would need to be established. The fuel inventory in wet storage in the 3.375 million gallon L Basin is primarily aluminum-clad, aluminum-based fuel of the Materials Test Reactor equivalent design. An inventory of non-aluminum-clad fuel of various designs is also stored in L Basin. Safe storage of fuel in wet storage mandates several high-level 'safety functions' that would be provided by the Structures, Systems, and Components (SSCs) of the storage system. A large inventory of aluminum-clad, aluminum-based spent nuclear fuel, and other nonaluminum fuel owned by the U.S. Department of Energy is in wet storage in L Basin at the Savannah River Site. An evaluation of the present condition of the fuel, and the Structures, Systems, or Components (SSCs) necessary for its wet storage, and the present programs and storage practices for fuel management have been performed. Activities necessary to validate the technical bases for, and verify the condition of the fuel and the SSCs under long-term wet storage have also been identified. The overall conclusion is that the fuel can be stored in L Basin, meeting general safety functions for fuel storage, for an additional 50 years and possibly beyond contingent upon continuation of existing fuel management activities and several augmented program activities. It is concluded that the technical bases and well-founded technologies have been established to store spent nuclear fuel in the L Basin. Methodologies to evaluate the fuel condition and characteristics, and systems to prepare fuel, isolate damaged fuel, and maintain water quality storage conditions have been established. Basin structural analyses have been performed against present NPH criteria. The aluminum fuel storage experience to date, supported by the understanding of the effects of environmental variables on materials performance, demonstrates that storage systems that minimize degradation and provide full retrievability of the fuel up to and greater than 50 additional years will require maintaining the present management programs, and with the recommended augmented/additional activities in this report.

Sindelar, R.; Deible, R.

2011-04-27T23:59:59.000Z

192

Fuel Cell Technologies Office: Storage Systems Analysis Working...  

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

Energy Efficiency and Renewable Energy EERE Home | Programs & Offices | Consumer Information Fuel Cell Technologies Office Search Search Help Fuel Cell Technologies Office HOME...

193

BOOK: Safety Related Issues of Spent Nuclear Fuel Storage  

Science Conference Proceedings (OSTI)

Sep 26, 2007... Trends in Nuclear Power, The Nuclear Fuel Cycle, Nuclear Science ... Fifteen papers cover aluminum-clad fuel discharged from research†...

194

Dry, portable calorimeter for nondestructive measurement of the activity of nuclear fuel  

DOE Patents (OSTI)

The activity of a quantity of heat-producing nuclear fuel is measured rapidly, accurately and nondestructively by a portable dry calorimeter comprising a preheater, an array of temperature-controlled structures comprising a thermally guarded temperature-controlled oven, and a calculation and control unit. The difference between the amounts of electric power required to maintain the oven temperature with and without nuclear fuel in the oven is measured to determine the power produced by radioactive disintegration and hence the activity of the fuel. A portion of the electronic control system is designed to terminate a continuing sequence of measurements when the standard deviation of the variations of the amount of electric power required to maintain oven temperature is within a predetermined value.

Beyer, Norman S. (Elmhurst, IL); Lewis, Robert N. (Clarendon Hills, IL); Perry, Ronald B. (Hinsdale, IL)

1976-01-01T23:59:59.000Z

195

Fuel Cell Technologies Office: Flow Cells for Energy Storage...  

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

Flow Cells for Energy Storage Workshop The U.S. Department of Energy's (DOE) Lawrence Berkeley National Laboratory (LBNL) held a Flow Cells for Energy Storage Workshop on March...

196

International management of spent fuel storage : technical alternatives and constraints, topical report  

E-Print Network (OSTI)

Some of the important technical issues involved in the implementation of a spent fuel storage regime under international auspices are discussed. In particular, we consider: the state of the art as far as the different ...

Miller, Marvin M.

1978-01-01T23:59:59.000Z

197

LESSONS LEARNED FROM CLEANING OUT THE SLUDGE FROM THE SPENT FUEL STORAGE BASINS AT HANFORD ICEM-07  

SciTech Connect

Until 2004, the K Basins at Hanford, in southeastern Washington State, held the largest collection of spent nuclear fuel in the United States Department of Energy (DOE) complex. The K East and K West Basins are massive pools each holding more than 4 million liters of water - that sit less than 450 meters from the Columbia River. In a significant multi-year campaign that ended in 2004, Fluor Hanford removed all of the fuel from the two Basins, over 2,300 metric tons (4.6 million pounds), dried it, and then placed it into dry storage in a specially designed facility away from the River. Removing the fuel, however, did not finish the cleanup work at the K Basins. The years of underwater storage had corroded the metallic uranium fuel, leaving behind a thick and sometimes hard-packed layer of sludge that coated the walls, floors and equipment inside the Basins. In places, the depth of the sludge was measured in feet rather than inches, and its composition was definitely not uniform. Together the Basins held an estimated 50 cubic meters of sludge (42 cubic meters in K East and 8 cubic meters in K West). The K East sludge retrieval and transfer work was completed in May 2007. Vacuuming up the sludge into large underwater containers in each of the Basins and then consolidating it all in containers in the K West Basin have presented significant challenges, some unexpected. This paper documents some of those challenges and presents the lessons learned so that other nuclear cleanup projects can benefit from the experience at Hanford.

KNOLLMEYER PM

2007-08-31T23:59:59.000Z

198

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

199

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

200

Analysis of drying wood waste fuels with boiler exhaust gases: simulation, performance, and economics  

DOE Green Energy (OSTI)

This study evaluates the feasibility of retrofitting a rotary dryer to a hog fuel boiler, using the boiler exhaust gases as the drying medium. Two simulation models were developed. Each model accurately predicts system performance given site-specific parameters such as boiler steam demand, fue moisture content, boiler exhaust temperature and combustion excess air. Three rotary dryers/hog fuel boilers currently in operation in the forest products industry were analyzed. The data obtained were used to validate te accuracy of the simulation models and to establish the performance of boiler/dryer systems under field conditions. The boiler exhaust temperatures observed ranged from 340 to 500/sup 0/F and indicated that significant drying could be realized at moderate stack temperatures, as substantitated by experimental moisture content data. The simulation models were used to evaluate a general boiler/dryer system's sensitivity to variation in operating conditions. The sensitivity analyses indicated that under moderate conditions (400/sup 0/F boiler exhaust, etc.) the installation of a rotary dryer results in a 15% increase in boiler efficiency and a 13% decrease in fuel consumption. Both the field data and sensitivity analyses indicated that a greater increase in boiler efficiency could be realized at higher stack temperatures, approximately a 30% increase in boiler efficiency for a stack temperature of 600/sup 0/F. The cash flow basis payback periods based on hog fuel savings due to dryer installation ranged from 2.7 years for a used dryer to 3.9 years for a new dryer. The payback periods for equivalent BTU savings of gas and oil ranged from 1.2 to 2.0 for gas and from 1.3 to 2.1 years for oil. This study concludes that retrofitting a rotary dryer to an existing hog fuel boiler is an economically feasible option to the forest products industry. 31 references, 24 figures, 18 tables.

Kirk, R.W.; Wilson, J.B.

1984-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel dry 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

Assessment of Non-Fuel, Advanced Compressed Air Energy Storage Systems to Support High Wind Penetration  

Science Conference Proceedings (OSTI)

This report summarizes the status and progress of the RD&D work at EPRI on adiabatic no-fuel Compressed Air Energy Storage (CAES) for wind integration. Bulk energy storage (BES) has latent value in the electric grid, enhances grid reliability, and is well suited to address wind integration related challenges. Without storage, extensive ramping and spinning reserve backup of thermal generators is required, at associated high costs, poor thermal performance, poor down ramp capability and high emissions. Fu...

2009-11-16T23:59:59.000Z

202

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

203

Safeguards Guidance for Independent Spent Fuel Storage Installations...  

National Nuclear Security Administration (NNSA)

during shipping off- site. A third case involves the use of a spent fuel conditioning hot cell or facility. In this case, the spent fuel would be reduced in volume by removing...

204

Solid State Ammonia Synthesis (SSAS) for Sustainable Fuel and Energy Storage Applications  

E-Print Network (OSTI)

Allen Haynes Energy Storage Claus Daniel Fossil Energy Peter Tortorelli Nuclear-Radioisotope Power Systems Jim King Nuclear Fuels Gary Bell* Nuclear­Light Water Reactors Jeremy Busby Office of Science BES Nuclear Fuel Materials Gary Bell* Nuclear Materials Science and Technology Randy Nanstad Physical

205

Alternatives for managing wastes from reactors and post-fission operations in the LWR fuel cycle. Volume 3. Alternatives for interim storage and transportation  

SciTech Connect

Volume III of the five-volume report contains information on alternatives for interim storage and transportation. Section titles are: interim storage of spent fuel elements; interim storage of chop-leach fuel bundle residues; tank storage of high-level liquid waste; interim storage of solid non-high-level wastes; interim storage of solidified high-level waste; and, transportation alternatives. (JGB)

1976-05-01T23:59:59.000Z

206

NREL: Hydrogen and Fuel Cells Research - Hydrogen Storage  

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

Hydrogen Storage Storing hydrogen for renewable energy technologies can be challenging, especially for intermittent resources such as solar and wind. Whether for stationary,...

207

NETL: Hydrogen & Clean Fuels - Abstract : Hydrogen Storage on...  

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

Hydrogen Storage on Carbon Nanotubes Single-walled carbon nanotubes are remarkable forms of elemental carbon. Their unique properties have stimulated the imaginations of many...

208

Preliminary Analysis of Energy Storage Options for Hydrogen Fuel Cell Buses for Urban Transport  

Science Conference Proceedings (OSTI)

The United Nations Development Program/Global Environment Facility (UNDP/GEF) Fuel Cell Bus Project will develop a fuel cell transit bus by combining two Ballard automotive fuel cells with an energy storage system. The battery system will be an important component of the bus and will assist the fuel cell systems (FC-S) to store regenerative baking energy in the hybrid system. The battery also has the potential to increase fuel cell system performance, efficiency, and durability by reducing FC-S transient...

2010-01-18T23:59:59.000Z

209

Technical and economic feasibility analysis of the no-fuel compressed air energy storage concept  

DOE Green Energy (OSTI)

The principal goal of this study was to evaluate the technical and economic feasibility of no-fuel compressed air energy storage (CAES) concepts for utility peaking applications. The analysis uncovered no insurmountable problems to preclude the technical feasibility of the no-fuel CAES concept. The results of the economic analysis are sufficiently unfavorable to conclude that no-fuel CAES technology could not compete with conventional CAES or standard gas turbine peaking facilities for conditions foreseeable at this time.

Kreid, D.K.

1976-05-01T23:59:59.000Z

210

Safety Aspects of Wet Storage of Spent Nuclear Fuel, OAS-L-13-11  

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

Safety Aspects of Wet Storage of Safety Aspects of Wet Storage of Spent Nuclear Fuel OAS-L-13-11 July 2013 Department of Energy Washington, DC 20585 July 10, 2013 MEMORANDUM FOR THE SENIOR ADVISOR FOR ENVIRONMENTAL MANAGEMENT FROM: Daniel M. Weeber Assistant Inspector General for Audits and Administration Office of Inspector General SUBJECT: INFORMATION: Audit Report on "Safety Aspects of Wet Storage of Spent Nuclear Fuel" BACKGROUND The Department of Energy (Department) is responsible for managing and storing spent nuclear fuel (SNF) generated by weapons and research programs and recovered through nonproliferation programs. The SNF consists of irradiated reactor fuel and cut up assemblies containing uranium, thorium and/or plutonium. The Department stores 34 metric tons of heavy metal SNF primarily

211

Storage of spent fuel from the nation`s nuclear reactors: Status, technology, and policy options  

SciTech Connect

Since the beginning of the commercial nuclear electric power industry, it has been recognized that spent nuclear reactor fuel must be able to be readily removed from the reactor vessel in the plant and safely stored on-site. The need for adjacent ready storage is first for safety. In the event of an emergency, or necessary maintenance that requires the removal of irradiated fuel from the reactor vessel, cooled reserve storage capacity for the full amount of fuel from the reactor core must be available. Also, the uranium fuel in the reactor eventually reaches the point where its heat generation is below the planned efficiency for steam production which drives the turbines and generators. It then must be replaced by fresh uranium fuel, with the ``spent fuel`` elements being removed to a safe and convenient storage location near the reactor vessel. The federal nuclear waste repository program, even without delays in the current schedule of disposal becoming available in 2003, will result in a large percentage of the 111 existing operable commercial reactors requiring expansion of their spent fuel storage capacity. How that need can and will be met raises issues of both technology and policy that will be reviewed in this report.

1989-10-01T23:59:59.000Z

212

Evaluation of potential for MSRE spent fuel and flush salt storage and treatment at the INEL  

SciTech Connect

The potential for interim storage as well as for treatment of the Molten Salt Reactor Experiment spent fuel at INEL has been evaluated. Provided that some minimal packaging and chemical stabilization prerequisites are satisfied, safe interim storage of the spent fuel at the INEL can be achieved in a number of existing or planned facilities. Treatment by calcination in the New Waste Calcining Facility at the INEL can also be a safe, effective, and economical alternative to treatment that would require the construction of a dedicated facility. If storage at the INEL is chosen for the Molten Salt Reactor Experiment (MSRE) spent fuel salts, their transformation to the more stable calcine solid would still be desirable as it would result in a lowering of risks. Treatment in the proposed INEL Remote-Handled Immobilization Facility (RHIF) would result in a waste form that would probably be acceptable for disposal at one of the proposed national repositories. The cost increment imputable to the treatment of the MSRE salts would be a small fraction of the overall capital and operating costs of the facility or the cost of building and operating a dedicated facility. Institutional and legal issues regarding shipments of fuel and waste to the INEL are summarized. The transfer of MSRE spent fuel for interim storage or treatment at the INEL is allowed under existing agreements between the State of idaho and the Department of energy and other agencies of the Federal Government. In contrast, current agreements preclude the transfer into Idaho of any radioactive wastes for storage or disposal within the State of Idaho. This implies that wastes and residues produced from treating the MSRE spent fuel at locations outside Idaho would not be acceptable for storage in Idaho. Present agreements require that all fuel and high-level wastes stored at the INEL, including MSRE spent fuel if received at the INEL, must be moved to a location outside Idaho by the year 2035.

Ougouag, A.M.; Ostby, P.A.; Nebeker, R.L.

1996-09-01T23:59:59.000Z

213

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:

214

A proliferation resistant hexagonal tight lattice BWR fueled core for increased burnup and reduced fuel storage requirements. Annual progress report: August, 1999 to July, 2000 [DOE NERI  

Science Conference Proceedings (OSTI)

(OAK/B204) A proliferation resistant hexagonal tight lattice BWR fueled core for increased burnup and reduced fuel storage requirements. Annual progress report: August, 1999 to July, 2000 [DOE NERI

Hiroshi Takahashi; Upendra Rohatgi; T.J. Downar

2000-08-04T23:59:59.000Z

215

High Pressure Fuel Storage Cylinders Periodic Inspection and End of Life Issues  

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

6/2010 6/2010 www.cleanvehicle.org 1 High Pressure Fuel Storage Cylinders Periodic Inspection and End of Life Issues DOE Vehicular Tank Workshop April 29, 2010 Douglas Horne, PE The Facts ÔĀ¨ High pressure Type 4 gaseous fuel tanks are now designed under standards that specify finite lifetimes of 15, 20 and 25 years based on specific design and testing (the HGV2 standard under development had a life as short as 10 years as an option) ÔĀ¨ It is unique within the transportation industry to have a critical device (the fuel tank) with a designated life that may be shorter than the vehicle itself ÔĀ¨ Although vehicle owners are told up front of the limited life fuel storage cylinders some tend to forget after 15 years ÔĀ¨ A parallel concern is the requirement for these fuel tanks

216

DOE Hydrogen and Fuel Cells Program Record 5037: Hydrogen Storage...  

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

37 Date: May 22, 2006 Title: Hydrogen Storage Materials - 2004 vs 2006 Originator: Sunita Satyapal Approved by: JoAnn Milliken Date: May 22, 2006 Item: "Identified materials with...

217

Fuel Cell Technologies Office: Hydrogen Storage Workshop Proceedings  

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

Thoughts on Fundamentals (PDF 255 KB), P. Teagan and M. Rona, TIAX Hydrogen Storage in Carbon Nanotubes (PDF 1.19 MB), Jack E. Fischer, University of Pennsylvania Advanced...

218

Down Select Report of Chemical Hydrogen Storage Materials, Catalysts, and Spent Fuel Regeneration Processes  

DOE Green Energy (OSTI)

The DOE Hydrogen Storage Program is focused on identifying and developing viable hydrogen storage systems for onboard vehicular applications. The program funds exploratory research directed at identifying new materials and concepts for storage of hydrogen having high gravimetric and volumetric capacities that have the potential to meet long term technical targets for onboard storage. Approaches currently being examined are reversible metal hydride storage materials, reversible hydrogen sorption systems, and chemical hydrogen storage systems. The latter approach concerns materials that release hydrogen in endothermic or exothermic chemical bond-breaking processes. To regenerate the spent fuels arising from hydrogen release from such materials, chemical processes must be employed. These chemical regeneration processes are envisioned to occur offboard the vehicle.

Ott, Kevin; Linehan, Sue; Lipiecki, Frank; Aardahl, Christopher L.

2008-08-24T23:59:59.000Z

219

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

220

Removal plan for Shippingport pressurized water reactor core 2 blanket fuel assemblies form T plant to the canister storage building  

Science Conference Proceedings (OSTI)

This document presents the current strategy and path forward for removal of the Shippingport Pressurized Water Reactor Core 2 blanket fuel assemblies from their existing storage configuration (wet storage within the T Plant canyon) and transport to the Canister Storage Building (designed and managed by the Spent Nuclear Fuel. Division). The removal plan identifies all processes, equipment, facility interfaces, and documentation (safety, permitting, procedures, etc.) required to facilitate the PWR Core 2 assembly removal (from T Plant), transport (to the Canister storage Building), and storage to the Canister Storage Building. The plan also provides schedules, associated milestones, and cost estimates for all handling activities.

Lata

1996-09-26T23:59:59.000Z

Note: This page contains sample records for the topic "fuel dry 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

Hanford Site existing irradiated fuel storage facilities description  

SciTech Connect

This document describes facilities at the Hanford Site which are currently storing spent nuclear fuels. The descriptions provide a basis for the no-action alternatives of ongoing and planned National Environmental Protection Act reviews.

Willis, W.L.

1995-01-11T23:59:59.000Z

222

Radiolysis Model Sensitivity Analysis for a Used Fuel Storage Canister  

SciTech Connect

This report fulfills the M3 milestone (M3FT-13PN0810027) to report on a radiolysis computer model analysis that estimates the generation of radiolytic products for a storage canister. The analysis considers radiolysis outside storage canister walls and within the canister fill gas over a possible 300-year lifetime. Previous work relied on estimates based directly on a water radiolysis G-value. This work also includes that effect with the addition of coupled kinetics for 111 reactions for 40 gas species to account for radiolytic-induced chemistry, which includes water recombination and reactions with air.

Wittman, Richard S.

2013-09-20T23:59:59.000Z

223

Low-Fuel Compressed Air Energy Storage System Development and Preliminary Evaluation  

Science Conference Proceedings (OSTI)

Compressed air energy storage (CAES) is a valuable solution for mitigating the current challenges of renewable power variability, facilitating future higher renewable penetration levels, enhancing grid reliability and improving the utilization of transmission and existing generation assets. Fuel-based CAES systems are subject to future natural gas price volatility and potential carbon dioxide (CO2) emission charges. Low-Fuel CAES (LFCAES) is a potential near-term technology that captures and stores heat ...

2010-12-17T23:59:59.000Z

224

Pelleting and characterization of dry distillers' grain with solubles pellets as bio-fuel .  

E-Print Network (OSTI)

??Bio fuels are made from an extensive selection of fuels derived from biomass, including wood waste, agricultural wastes, and alcohol fuels. As a result ofÖ (more)

Saha, Suparna

2011-01-01T23:59:59.000Z

225

Review of K Basin and Cold Vacuum Drying Facility Found Fuel Multi-Canister Overpack Operatioons, August 2012  

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

K Basin and Cold Vacuum Drying Facility Found Fuel Multi-Canister Overpack Operations May 2011 August 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 2

226

Review of K Basin and Cold Vacuum Drying Facility Found Fuel Multi-Canister Overpack Operatioons, August 2012  

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

K Basin and Cold Vacuum Drying Facility Found Fuel Multi-Canister Overpack Operations May 2011 August 2012 Office of Safety and Emergency Management Evaluations Office of Enforcement and Oversight Office of Health, Safety and Security U.S. Department of Energy i Table of Contents 1.0 Purpose ................................................................................................................................................... 1 2.0 Background ............................................................................................................................................ 1 3.0 Scope ...................................................................................................................................................... 2

227

Contribution of chemistry to energy. [Fuels from coal; solar energy storage/conversion  

DOE Green Energy (OSTI)

Chemistry has contributed in many ways to energy production and conversion in the fossil fuel era. The challenges facing chemists and chemical engineers as we look forward to the 21st Century are addressed. This paper discusses some of the means that can be employed to meet this challenge both in the near-term and long-term, particularly alternate fuels from coal and solar energy storage and conversion. A leading candidate for an energy supply medium is hydrogen; implementing this concept may well be the greatest challenge faced by chemists as we leave the age of fossil fuels and enter the era of renewable energy. (DLC)

Cox, K.E.

1978-01-01T23:59:59.000Z

228

US Department of Energy Storage of Spent Fuel and High Level Waste  

DOE Green Energy (OSTI)

ABSTRACT This paper provides an overview of the Department of Energy's (DOE) spent nuclear fuel (SNF) and high level waste (HLW) storage management. Like commercial reactor fuel, DOE's SNF and HLW were destined for the Yucca Mountain repository. In March 2010, the DOE filed a motion with the Nuclear Regulatory Commission (NRC) to withdraw the license application for the repository at Yucca Mountain. A new repository is now decades away. The default for the commercial and DOE research reactor fuel and HLW is on-site storage for the foreseeable future. Though the motion to withdraw the license application and delay opening of a repository signals extended storage, DOE's immediate plans for management of its SNF and HLW remain the same as before Yucca Mountain was designated as the repository, though it has expanded its research and development efforts to ensure safe extended storage. This paper outlines some of the proposed research that DOE is conducting and will use to enhance its storage systems and facilities.

Sandra M Birk

2010-10-01T23:59:59.000Z

229

FIELD-DEPLOYABLE SAMPLING TOOLS FOR SPENT NUCLEAR FUEL INTERROGATION IN LIQUID STORAGE  

SciTech Connect

Methodology and field deployable tools (test kits) to analyze the chemical and microbiological condition of aqueous spent fuel storage basins and determine the oxide thickness on the spent fuel basin materials were developed to assess the corrosion potential of a basin. this assessment can then be used to determine the amount of time fuel has spent in a storage basin to ascertain if the operation of the reactor and storage basin is consistent with safeguard declarations or expectations and assist in evaluating general storage basin operations. The test kit was developed based on the identification of key physical, chemical and microbiological parameters identified using a review of the scientific and basin operations literature. The parameters were used to design bench scale test cells for additional corrosion analyses, and then tools were purchased to analyze the key parameters. The tools were used to characterize an active spent fuel basin, the Savannah River Site (SRS) L-Area basin. The sampling kit consisted of a total organic carbon analyzer, an YSI multiprobe, and a thickness probe. The tools were field tested to determine their ease of use, reliability, and determine the quality of data that each tool could provide. Characterization confirmed that the L Area basin is a well operated facility with low corrosion potential.

Berry, T.; Milliken, C.; Martinez-Rodriguez, M.; Hathcock, D.; Heitkamp, M.

2012-09-12T23:59:59.000Z

230

Surveillance Guide - ERS 14.3 Underground and Above Ground Diesel Fuel Storage Tanks  

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

UNDERGROUND AND ABOVE GROUND DIESEL FUEL STORAGE TANKS UNDERGROUND AND ABOVE GROUND DIESEL FUEL STORAGE TANKS 1.0 Objective The objective of this surveillance is to verify underground and above ground diesel storage tanks are maintained, monitored, configured and marked as required. These surveillance activities provide a basis for evaluating the effectiveness of the contractor's program for implementation of appropriate controls and compliance with DOE requirements. 2.0 References 1. DOE O 440.1A, Worker Protection Management For DOE Federal And Contractor Employees [http://www.explorer.doe.gov:1776/cgi-bin/w3vdkhgw?qryBGD07_rSj;doe- 1261] 1. 29CFR1910.1200, Subpart Z, Hazard Communication [Access http://www.osha-slc.gov/OshStd_data/1910_1200.html ] 2. 29CFR1910.106, Subpart H, Flammable And Combustible Liquids [Access at

231

Results from Nevada Nuclear Waste Storage Investigations (NNWSI) Series 3 spent fuel dissolution tests  

SciTech Connect

The dissolution and radionuclide release behavior of spent fuel in groundwater is being studied by the Yucca Mountain Project (YMP), formerly the Nevada Nuclear Waste Storage Investigations (NNWSI) Project. Specimens prepared from pressurized water reactor fuel rod segments were tested in sealed stainless steel vessels in Nevada Test Site J-13 well water at 85{degree}C and 25{degree}C. The test matrix included three specimens of bare-fuel particles plus cladding hulls, two fuel rod segments with artificially defected cladding and water-tight end fittings, and an undefected fuel rod section with watertight end fittings. Periodic solution samples were taken during test cycles with the sample volumes replenished with fresh J-13 water. Test cycles were periodically terminated and the specimens restarted in fresh J-13 water. The specimens were run for three cycles for a total test duration of 15 months. 22 refs., 32 figs., 26 tabs.

Wilson, C.N.

1990-06-01T23:59:59.000Z

232

Fuel-Free Compressed-Air Energy Storage: Fuel-Free, Ubiquitous Compressed-Air Energy Storage and Power Conditioning  

SciTech Connect

GRIDS Project: General Compression has developed a transformative, near-isothermal compressed air energy storage system (GCAES) that prevents air from heating up during compression and cooling down during expansion. When integrated with renewable generation, such as a wind farm, intermittent energy can be stored in compressed air in salt caverns or pressurized tanks. When electricity is needed, the process is reversed and the compressed air is expanded to produce electricity. Unlike conventional compressed air energy storage (CAES) projects, no gas is burned to convert the stored high-pressure air back into electricity. The result of this breakthrough is an ultra-efficient, fully shapeable, 100% renewable and carbon-free power product. The GCAESô system can provide high quality electricity and ancillary services by effectively integrating renewables onto the grid at a cost that is competitive with gas, coal and nuclear generation.

None

2010-09-13T23:59:59.000Z

233

Regenerative Fuel Cells: Renewable Energy Storage Devices Based on Neutral Water Input  

SciTech Connect

GRIDS Project: Proton Energy Systems is developing an energy storage device that converts water to hydrogen fuel when excess electricity is available, and then uses hydrogen to generate electricity when energy is needed. The system includes an electrolyzer, which generates and separates hydrogen and oxygen for storage, and a fuel cell which converts the hydrogen and oxygen back to electricity. Traditional systems use acidic membranes, and require expensive materials including platinum and titanium for key parts of the system. In contrast, Proton Energy Systemsí new system will use an inexpensive alkaline membrane and will contain only inexpensive metals such as nickel and stainless steel. If successful, Proton Energy Systemsí system will have similar performance to todayís regenerative fuel cell systems at a fraction of the cost, and can be used to store electricity on the electric grid.

None

2010-09-01T23:59:59.000Z

234

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

235

Fueling up with Hydrogen: New Approaches to Hydrogen Storage (433rd Brookhaven Lecture)  

DOE Green Energy (OSTI)

Hydrogen, the most abundant element in the universe, burns excellently and cleanly, with only pure water as a byproduct. NASA has used hydrogen as fuel for years in the space program. So, why not use hydrogen to fuel cars? The bottleneck of developing hydrogen-fueled vehicles has been identified: the greatest problem is storage. The conventional storage method, compressed hydrogen gas, requires a large tank volume, and the possibility of a tank rupture poses a significant safety risk. Another method, low temperature liquid storage, is expensive and impractical for most automotive applications. An alternative is to store the hydrogen in the solid state. In his talk, Jason Graetz will describe the new approaches to hydrogen storage being studied by his group at BNL. These include using kinetically stabilized hydrides, bialkali alanates and reversible metal-organic hydrides. The researchers are also using novel synthesis approaches, state-of-the-art characterization and first principles modeling, all providing a better fundamental understanding of these interesting and useful new materials.

Graetz, Jason (Energy Sciences and Technology Dept)

2008-02-20T23:59:59.000Z

236

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

237

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

238

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

239

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

240

Storage  

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

Environmental Risks ¬Ľ Storage Environmental Risks ¬Ľ 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 "fuel dry 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

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

242

Analysis of H2 storage needs for early market non-motive fuel cell applications.  

DOE Green Energy (OSTI)

Hydrogen fuel cells can potentially reduce greenhouse gas emissions and the United States dependence on foreign oil, but issues with hydrogen storage are impeding their widespread use. To help overcome these challenges, this study analyzes opportunities for their near-term deployment in five categories of non-motive equipment: portable power, construction equipment, airport ground support equipment, telecom backup power, and man-portable power and personal electronics. To this end, researchers engaged end users, equipment manufacturers, and technical experts via workshops, interviews, and electronic means, and then compiled these data into meaningful and realistic requirements for hydrogen storage in specific target applications. In addition to developing these requirements, end-user benefits (e.g., low noise and emissions, high efficiency, potentially lower maintenance costs) and concerns (e.g., capital cost, hydrogen availability) of hydrogen fuel cells in these applications were identified. Market data show potential deployments vary with application from hundreds to hundreds of thousands of units.

Johnson, Terry Alan; Moreno, Marcina; Arienti, Marco; Pratt, Joseph William; Shaw, Leo; Klebanoff, Leonard E.

2012-03-01T23:59:59.000Z

243

Issues relating to spent nuclear fuel storage on the Oak Ridge Reservation  

Science Conference Proceedings (OSTI)

Currently, about 2,800 metric tons of spent nuclear fuel (SNF) is stored in the US, 1,000 kg of SNF (or about 0.03% of the nation`s total) are stored at the US Department of Energy (DOE) complex in Oak Ridge, Tennessee. However small the total quantity of material stored at Oak Ridge, some of the material is quite singular in character and, thus, poses unique management concerns. The various types of SNF stored at Oak Ridge will be discussed including: (1) High-Flux Isotope Reactor (HFIR) and future Advanced Neutron Source (ANS) fuels; (2) Material Testing Reactor (MTR) fuels, including Bulk Shielding Reactor (BSR) and Oak Ridge Research Reactor (ORR) fuels; (3) Molten Salt Reactor Experiment (MSRE) fuel; (4) Homogeneous Reactor Experiment (HRE) fuel; (5) Miscellaneous SNF stored in Oak Ridge National Laboratory`s (ORNL`s) Solid Waste Storage Areas (SWSAs); (6) SNF stored in the Y-12 Plant 9720-5 Warehouse including Health. Physics Reactor (HPRR), Space Nuclear Auxiliary Power (SNAP-) 10A, and DOE Demonstration Reactor fuels.

Klein, J.A.; Turner, D.W.

1994-12-31T23:59:59.000Z

244

A Critical Review of Practice of Equating the Reactivity of Spent Fuel to Fresh Fuel in Burnup Credit Criticality Safety Analyses for PWR Spent Fuel Pool Storage  

SciTech Connect

This research examines the practice of equating the reactivity of spent fuel to that of fresh fuel for the purpose of performing burnup credit criticality safety analyses for PWR spent fuel pool (SFP) storage conditions. The investigation consists of comparing k{sub inf} estimates based on reactivity equivalent fresh fuel enrichment (REFFE) to k{sub inf} estimates using the actual spent fuel isotopics. Analyses of selected storage configurations common in PWR SFPs show that this practice yields nonconservative results (on the order of a few tenths of a percent) in configurations in which the spent fuel is adjacent to higher-reactivity assemblies (e.g., fresh or lower-burned assemblies) and yields conservative results in configurations in which spent fuel is adjacent to lower-reactivity assemblies (e.g., higher-burned fuel or empty cells). When the REFFE is determined based on unborated water moderation, analyses for storage conditions with soluble boron present reveal significant nonconservative results associated with the use of the REFFE. This observation is considered to be important, especially considering the recent allowance of credit for soluble boron up to 5% in reactivity. Finally, it is shown that the practice of equating the reactivity of spent fuel to fresh fuel is acceptable, provided the conditions for which the REFFE was determined remain unchanged. Determination of the REFFE for a reference configuration and subsequent use of the REFFE for different configurations violates the basis used for the determination of the REFFE and, thus, may lead to inaccurate, and possibly, nonconservative estimates of reactivity. A significant concentration ({approximately}2000 ppm) of soluble boron is typically (but not necessarily required to be) present in PWR SFPs, of which only a portion ({le} 500 ppm) may be credited in safety analyses. Thus, a large subcritical margin currently exists that more than accounts for errors or uncertainties associated with the use of the REFFE. Consequently, the findings presented here do not represent a significant safety concern unless/until the subcritical margin associated with the soluble boron (that is not currently explicitly credited) is offset by the uncertainties associated with burnup credit and/or the expanded allowance of credit for the soluble boron.

Wagner, J.C.; Parks, C.V.

2000-09-01T23:59:59.000Z

245

Handbook of Neutron Absorber Materials for Spent Nuclear Fuel Transportation and Storage Applications  

Science Conference Proceedings (OSTI)

This handbook is intended to become a single source of information regarding technical characteristics of neutron absorber materials that have been used for storage and transportation of spent nuclear fuel as well as to provide a summary of users' experience. The second edition of this handbook was published in 2006. This third edition, the 2009 Edition, updates materials covered in the 2006 Edition, presents new products introduced since 2006, and reflects recent realignments of neutron absorber suppliers.

2009-11-25T23:59:59.000Z

246

Climatic Corrosion Considerations for Independent Spent Fuel Storage Installations in Marine Environments  

Science Conference Proceedings (OSTI)

It has been clearly demonstrated in laboratory and field studies plus field experience with actual and simulated components that the stress corrosion cracking (SCC) of austenitic stainless steel can occur at ambient temperatures in marine-type environments. Therefore, the SCC concerns for spent fuel storage canisters identified in a November 2004 presentation by Nuclear and Industrial Safety Agency (NISA) and Central Research Institute of Electric Power Industry (CRIEPI) representatives are clearly warra...

2006-06-28T23:59:59.000Z

247

Federal fees and contracts for storage and disposal of spent LWR fuel  

SciTech Connect

The methodology for establishing a fee for federal spent fuel storage and disposal services is explained along with a presentation of the cost centers and cost data used to calculate the fee. Results of the initial fee calculation and the attendant sensitivity studies are also reviewed. The current status of the fee update is presented. The content of the proposed contract for federal services is briefly reviewed.

Clark, H.J.

1979-01-01T23:59:59.000Z

248

Feasibility study and preliminary design for fishing (TUNA) vessel fuel storage and distribution. Final report. Export trade information  

SciTech Connect

The report is divided into the following sections: (1) Introduction; (2) Conclusions and Recommendations; (3) Existing Conditions and Facilities for a Fuel Distribution Center; (4) Pacific Ocean Regional Tuna Fisheries and Resources; (5) Fishing Effort in the FSMEEZ 1992-1994; (6) Current Transshipping Operations in the Western Pacific Ocean; (7) Current and Probale Bunkering Practices of United States, Japanese, Koren, and Taiwanese Offshore-Based Vessels Operating in FSM and Adjacent Waters; (8) Shore-Based Fish-Handling/Processing; (9) Fuels Forecast; (10) Fuel Supply, Storage and Distribution; (11) Cost Estimates; (12) Economic Evaluation of Fuel Supply, Storage and Distribution.

NONE

1995-07-01T23:59:59.000Z

249

DOE Hydrogen and Fuel Cells Program Record 9014: Hydrogen Storage Materials: 2007 ¬Ö 2009  

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

RCB (12/02/09) RCB (12/02/09) 1 DOE Hydrogen and Fuel Cells Program Record Record #: 9014 Date: December 02, 2009 Title: Hydrogen Storage Materials: 2007 - 2009 Originator: Robert C. Bowman, Ned T. Stetson Approved by: Sunita Satyapal Date: December 02, 2009 Item: This record summarizes the status of hydrogen (H 2 ) storage capacities that were determined for materials investigated between 2007 and 2009 within the Hydrogen Storage sub-program. Figure 1 shows the current status of materials development in terms of their gravimetric (in wt.%) capacities for just the materials themselves as a function of H 2 release or uptake temperature. The system targets for weight and temperatures as recently revised [1] for the 2015 and ultimate metrics are the areas enclosed by dashed lines in Figure 1. The arrow within the "windows"

250

THERMAL PERFORMANCE SENSITIVITY STUDIES IN SUPPORT OF MATERIAL MODELING FOR EXTENDED STORAGE OF USED NUCLEAR FUEL  

SciTech Connect

The work reported here is an investigation of the sensitivity of component temperatures of a storage system, including fuel cladding temperatures, in response to age-related changes that could degrade the design-basis thermal behavior of the system. Three specific areas of interest were identified for this study. ē degradation of the canister backfill gas from pure helium to a mixture of air and helium, resulting from postulated leakage due to stress corrosion cracking (SCC) of canister welds ē changes in surface emissivity of system components, resulting from corrosion or other aging mechanisms, which could cause potentially significant changes in temperatures and temperature distributions, due to the effect on thermal radiation exchange between components ē changes in fuel and basket temperatures due to changes in fuel assembly position within the basket cells in the canister The purpose of these sensitivity studies is to provide a realistic example of how changes in the physical properties or configuration of the storage system components can affect temperatures and temperature distributions. The magnitudes of these sensitivities can provide guidance for identifying appropriate modeling assumptions for thermal evaluations extending long term storage out beyond 50, 100, 200, and 300 years.

Cuta, Judith M.; Suffield, Sarah R.; Fort, James A.; Adkins, Harold E.

2013-08-15T23:59:59.000Z

251

Energy Department Awards More Than $7 Million for Innovative Hydrogen Storage Technologies in Fuel Cell Electric Vehicles  

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

The U.S. Department of Energy today announced more than $7 million to fund four projects in California, Washington and Oregon to advance hydrogen storage technologies to be used in fuel cell electric vehicles.

252

Hanford spent nuclear fuel cold vacuum drying test specification and test plan  

SciTech Connect

This document provides the test plan and test specification for SNF cold vacuum drying proof of concept, CVD process equipment validation, and proof of performance testing.

McCracken, K.J., Westinghouse Hanford

1996-07-10T23:59:59.000Z

253

Accident safety analysis for 300 Area N Reactor Fuel Fabrication and Storage Facility  

SciTech Connect

The purpose of the accident safety analysis is to identify and analyze a range of credible events, their cause and consequences, and to provide technical justification for the conclusion that uranium billets, fuel assemblies, uranium scrap, and chips and fines drums can be safely stored in the 300 Area N Reactor Fuel Fabrication and Storage Facility, the contaminated equipment, High-Efficiency Air Particulate filters, ductwork, stacks, sewers and sumps can be cleaned (decontaminated) and/or removed, the new concretion process in the 304 Building will be able to operate, without undue risk to the public, employees, or the environment, and limited fuel handling and packaging associated with removal of stored uranium is acceptable.

Johnson, D.J.; Brehm, J.R.

1994-01-01T23:59:59.000Z

254

Solar Thermal Energy Storage Device: Hybrid Nanostructures for High-Energy-Density Solar Thermal Fuels  

SciTech Connect

HEATS Project: MIT is developing a thermal energy storage device that captures energy from the sun; this energy can be stored and released at a later time when it is needed most. Within the device, the absorption of sunlight causes the solar thermal fuelís photoactive molecules to change shape, which allows energy to be stored within their chemical bonds. A trigger is applied to release the stored energy as heat, where it can be converted into electricity or used directly as heat. The molecules would then revert to their original shape, and can be recharged using sunlight to begin the process anew. MITís technology would be 100% renewable, rechargeable like a battery, and emissions-free. Devices using these solar thermal fuelsócalled Hybrisolócan also be used without a grid infrastructure for applications such as de-icing, heating, cooking, and water purification.

None

2012-01-09T23:59:59.000Z

255

Storage of LWR (light-water-reactor) spent fuel in air  

Science Conference Proceedings (OSTI)

An experimental program is being conducted at Pacific Northwest Laboratory (PNL) to determine the oxidation response of light-water-reactor (LWR) spent fuels under conditions appropriate to fuel storage in air. The program is designed to investigate several independent variables that might affect the oxidation behavior of spent fuel. Included are temperature (135 to 230{degree}C), fuel burnup (to about 34 MWd/kgM), reactor type (pressurized and boiling water reactors), moisture level in the air, and the presence of a high gamma field. In continuing tests with declad spent fuel and nonirradiated UO{sub 2} specimens, oxidation rates were monitored by weight-gain measurements and the microstructures of subsamples taken during the weighing intervals were characterized by several analytical methods. The oxidation behavior indicated by weight gain and time to form powder will be reported in Volume III of this series. The characterization results obtained from x-ray diffractometry, transmission electron microscopy, scanning electron microscopy, and Auger electron spectrometry of oxidized fuel samples are presented in this report. 28 refs., 21 figs., 3 tabs.

Thomas, L.E.; Charlot, L.A.; Coleman, J.E. (Pacific Northwest Lab., Richland, WA (USA)); Knoll, R.W. (Johnson Controls, Inc., Madison, WI (USA))

1989-12-01T23:59:59.000Z

256

Thermal analysis for a spent reactor fuel storage test in granite  

Science Conference Proceedings (OSTI)

A test is conducted in which spent fuel assemblies from an operating commercial nuclear power reactor are emplaced in the Climax granite at the US Department of Energy`s Nevada Test Site. In this generic test, 11 canisters of spent PWR fuel are emplaced vertically along with 6 electrical simulator canisters on 3 m centers, 4 m below the floor of a storage drift which is 420 m below the surface. Two adjacent parallel drifts contain electrical heaters, operated to simulate (in the vicinity of the storage drift) the temperature fields of a large repository. This test, planned for up to five years duration, uses fairly young fuel (2.5 years out of core) so that the thermal peak will occur during the time frame of the test and will not exceed the peak that would not occur until about 40 years of storage had older fuel (5 to 15 years out of core) been used. This paper describes the calculational techniques and summarizes the results of a large number of thermal calculations used in the concept, basic design and final design of the spent fuel test. The results of the preliminary calculations show the effects of spacing and spent fuel age. Either radiation or convection is sufficient to make the drifts much better thermal conductors than the rock that was removed to create them. The combination of radiation and convection causes the drift surfaces to be nearly isothermal even though the heat source is below the floor. With a nominal ventilation rate of 2 m{sup 3}/s and an ambient rock temperature of 23{sup 0}C, the maximum calculated rock temperature (near the center of the heat source) is about 100{sup 0}C while the maximum air temperature in the drift is around 40{sup 0}C. This ventilation (1 m{sup 3}/s through the main drift and 1/2 m{sup 3}/s through each of the side drifts) will remove about 1/3 of the heat generated during the first five years of storage.

Montan, D.N.

1980-09-01T23:59:59.000Z

257

Compact fuel cell system utilizing a combination of hydrogen storage materials for optimized performance.  

SciTech Connect

An entirely new class of light-weight reversible hydrides was recently discovered (the Ti-doped alanates)[1]. These NaAIH{sub 4}-based materials have demonstrated reversible hydrogen storage capacities of up to 5 wt%, nearly 4 times the gravimetrically density of commercial metal hydrides. For this reason, they have been considered a breakthrough for hydrogen storage in fuel cell vehicles. This project is the first to publish the use of alanates for the generation of electrical power and the first demonstration of a hydride-fueled elevated-temperature PEM Fuel Cell. Because the kinetics of hydrogen uptake and release by the alanate improves with elevated temperatures, novel concepts were tested for the purpose of developing a highly efficient stand-alone power system. A major focus of this work was on the modeling, design, construction and testing of an integrated fuel cell stack and hydrogen storage system that eliminates the need of complicated heat transfer systems and media. After extensive modeling efforts, a proof-of-concept system was built that employs an integrated fuel cell stack and hydride beds that balancing the generation of fuel cell waste heat with the endothermic release of hydrogen from the alanates. Our demonstration unit was capable of greater than one hour of operation on a single charge of hydrogen from the integrated 173 gram alanate bed. In addition, composite hydride materials with synergistic reaction heats were evaluated and tested to enhance the operational performance of the alanates. The composites provide a unique opportunity to utilize the heat produced from hydriding classic metal hydrides to improve both absorption and desorption rates of the alanates. A particular focus of the mixed storage materials work was to balance the thermodynamics and kinetics of the hydrides for start-up conditions. Modeling of the sorption properties proved invaluable in evaluating the optimum composition of hydrides. The modeling efforts were followed by full validation by experimental measurements. This project successfully completed the proof-of-concept goals and generated a powerful set of tools for optimizing the complete power-generation system. It has also created a new direction for hydrogen power generation as well the potential for new R&D based on this work.

Chan, Jennifer P.; Dedrick, Daniel E.; Gross, Karl J.; Ng, Greg L.

2004-12-01T23:59:59.000Z

258

Fuel Summary Report: Shippingport Light Water Breeder Reactor - Rev. 2  

Science Conference Proceedings (OSTI)

The Shippingport Light Water Breeder Reactor (LWBR) was developed by Bettis Atomic Power Laboratory to demonstrate the potential of a water-cooled, thorium oxide fuel cycle breeder reactor. The LWBR core operated from 1977-82 without major incident. The fuel and fuel components suffered minimal damage during operation, and the reactor testing was deemed successful. Extensive destructive and nondestructive postirradiation examinations confirmed that the fuel was in good condition with minimal amounts of cladding deformities and fuel pellet cracks. Fuel was placed in wet storage upon arrival at the Expended Core Facility, then dried and sent to the Idaho Nuclear Technology and Engineering Center for underground dry storage. It is likely that the fuel remains in good condition at its current underground dry storage location at the Idaho Nuclear Technology and Engineering Center. Reports show no indication of damage to the core associated with shipping, loading, or storage.

Olson, Gail Lynn; Mc Cardell, Richard Keith; Illum, Douglas Brent

2002-09-01T23:59:59.000Z

259

COBRA-SFS (Spent Fuel Storage): A thermal-hydraulic analysis computer code: Volume 3, Validation assessments  

Science Conference Proceedings (OSTI)

This report presents the results of the COBRA-SFS (Spent Fuel Storage) computer code validation effort. COBRA-SFS, while refined and specialized for spent fuel storage system analyses, is a lumped-volume thermal-hydraulic analysis computer code that predicts temperature and velocity distributions in a wide variety of systems. Through comparisons of code predictions with spent fuel storage system test data, the code's mathematical, physical, and mechanistic models are assessed, and empirical relations defined. The six test cases used to validate the code and code models include single-assembly and multiassembly storage systems under a variety of fill media and system orientations and include unconsolidated and consolidated spent fuel. In its entirety, the test matrix investigates the contributions of convection, conduction, and radiation heat transfer in spent fuel storage systems. To demonstrate the code's performance for a wide variety of storage systems and conditions, comparisons of code predictions with data are made for 14 runs from the experimental data base. The cases selected exercise the important code models and code logic pathways and are representative of the types of simulations required for spent fuel storage system design and licensing safety analyses. For each test, a test description, a summary of the COBRA-SFS computational model, assumptions, and correlations employed are presented. For the cases selected, axial and radial temperature profile comparisons of code predictions with test data are provided, and conclusions drawn concerning the code models and the ability to predict the data and data trends. Comparisons of code predictions with test data demonstrate the ability of COBRA-SFS to successfully predict temperature distributions in unconsolidated or consolidated single and multiassembly spent fuel storage systems.

Lombardo, N.J.; Cuta, J.M.; Michener, T.E.; Rector, D.R.; Wheeler, C.L.

1986-12-01T23:59:59.000Z

260

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

Note: This page contains sample records for the topic "fuel dry 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

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

262

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

263

DOE Hydrogen and Fuel Cells Program Record 9017: On-Board Hydrogen Storage Systems ¬Ö Projected Performance and Cost Parameters  

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

DOE Hydrogen and Fuel Cells Program Record DOE Hydrogen and Fuel Cells Program Record Record #: 9017 Date: July 02, 2010 Title: On-Board Hydrogen Storage Systems - Projected Performance and Cost Parameters Originators: Robert C. Bowman and Ned Stetson Approved by: Sunita Satyapal Date: August 10, 2010 This record summarizes the current technical assessments of hydrogen (H 2 ) storage system capacities and projected manufacturing costs for the scenario of high-volume production (i.e., 500,000 units/year) for various types of "on-board" vehicular storage systems. These analyses were performed within the Hydrogen Storage sub-program of the DOE Fuel Cell Technologies (FCT) program of the Office of Energy Efficiency and Renewable Energy. Item: It is important to note that all system capacities are "net useable capacities" able to be delivered to the

264

DEVELOPMENT OF METHODOLOGY AND FIELD DEPLOYABLE SAMPLING TOOLS FOR SPENT NUCLEAR FUEL INTERROGATION IN LIQUID STORAGE  

SciTech Connect

This project developed methodology and field deployable tools (test kits) to analyze the chemical and microbiological condition of the fuel storage medium and determine the oxide thickness on the spent fuel basin materials. The overall objective of this project was to determine the amount of time fuel has spent in a storage basin to determine if the operation of the reactor and storage basin is consistent with safeguard declarations or expectations. This project developed and validated forensic tools that can be used to predict the age and condition of spent nuclear fuels stored in liquid basins based on key physical, chemical and microbiological basin characteristics. Key parameters were identified based on a literature review, the parameters were used to design test cells for corrosion analyses, tools were purchased to analyze the key parameters, and these were used to characterize an active spent fuel basin, the Savannah River Site (SRS) L-Area basin. The key parameters identified in the literature review included chloride concentration, conductivity, and total organic carbon level. Focus was also placed on aluminum based cladding because of their application to weapons production. The literature review was helpful in identifying important parameters, but relationships between these parameters and corrosion rates were not available. Bench scale test systems were designed, operated, harvested, and analyzed to determine corrosion relationships between water parameters and water conditions, chemistry and microbiological conditions. The data from the bench scale system indicated that corrosion rates were dependent on total organic carbon levels and chloride concentrations. The highest corrosion rates were observed in test cells amended with sediment, a large microbial inoculum and an organic carbon source. A complete characterization test kit was field tested to characterize the SRS L-Area spent fuel basin. The sampling kit consisted of a TOC analyzer, a YSI multiprobe, and a thickness probe. The tools were field tested to determine their ease of use, reliability, and determine the quality of data that each tool could provide. Characterization was done over a two day period in June 2011, and confirmed that the L Area basin is a well operated facility with low corrosion potential.

Berry, T.; Milliken, C.; Martinez-Rodriguez, M.; Hathcock, D.; Heitkamp, M.

2012-06-04T23:59:59.000Z

265

Systems Modeling of Chemical Hydride Hydrogen Storage Materials for Fuel Cell Applications  

Science Conference Proceedings (OSTI)

A fixed bed reactor was designed, modeled and simulated for hydrogen storage on-board the vehicle for PEM fuel cell applications. Ammonia Borane (AB) was selected by DOE's Hydrogen Storage Engineering Center of Excellence (HSECoE) as the initial chemical hydride of study because of its high hydrogen storage capacity (up to {approx}16% by weight for the release of {approx}2.5 molar equivalents of hydrogen gas) and its stability under typical ambient conditions. The design evaluated consisted of a tank with 8 thermally isolated sections in which H2 flows freely between sections to provide ballast. Heating elements are used to initiate reactions in each section when pressure drops below a specified level in the tank. Reactor models in Excel and COMSOL were developed to demonstrate the proof-of-concept, which was then used to develop systems models in Matlab/Simulink. Experiments and drive cycle simulations showed that the storage system meets thirteen 2010 DOE targets in entirety and the remaining four at greater than 60% of the target.

Brooks, Kriston P.; Devarakonda, Maruthi N.; Rassat, Scot D.; Holladay, Jamelyn D.

2011-10-05T23:59:59.000Z

266

Storage of spent fuel from the nation's nuclear reactors: Status, technology, and policy options  

SciTech Connect

Since the beginning of the commercial nuclear electric power industry, it has been recognized that spent nuclear reactor fuel must be able to be readily removed from the reactor vessel in the plant and safely stored on-site. The need for adjacent ready storage is first for safety. In the event of an emergency, or necessary maintenance that requires the removal of irradiated fuel from the reactor vessel, cooled reserve storage capacity for the full amount of fuel from the reactor core must be available. Also, the uranium fuel in the reactor eventually reaches the point where its heat generation is below the planned efficiency for steam production which drives the turbines and generators. It then must be replaced by fresh uranium fuel, with the spent fuel'' elements being removed to a safe and convenient storage location near the reactor vessel. The federal nuclear waste repository program, even without delays in the current schedule of disposal becoming available in 2003, will result in a large percentage of the 111 existing operable commercial reactors requiring expansion of their spent fuel storage capacity. How that need can and will be met raises issues of both technology and policy that will be reviewed in this report.

1989-10-01T23:59:59.000Z

267

Management of HFIR spent fuel  

Science Conference Proceedings (OSTI)

The High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL) has been unable to ship its spent fuel off-site for reprocessing since 1985. The HFIR storage pools are expected to fill up by the end of 1994. If a management alternative to existing HFIR pool storage is not identified and implemented by that time, the HFIR will be forced to shut down. This study identified and investigated five alternatives to managing the HFIR spent fuel, to determine the feasibility of implementing each in time to prevent shutdown of the HFIR: (1) increasing HFIR pool storage capacity, (2) storing the spent fuel at another ORNL pool, (3) storing the spent fuel in one or more hot cells at ORNL, (4) shipping the spent fuel off-site for reprocessing or storage elsewhere, and (5) installing a dedicated dry storage facility at ORNL. Of the alternatives investigated, only two could prevent the shutdown of the HFIR in the near term: increasing HFIR pool storage capacity or shipping the spent fuel off-site. Both options have been vigorously pursued because neither is assured of success, and at least one of the options must be successfully implemented if the HFIR is to continue operation. In addition, a third option was selected for implementation as an intermediate-term storage solution: installing a dedicated dry storage facility for the HFIR. An intermediate-term storage solution is needed because neither of the short-term solutions could ensure long-term continued operation of the HFIR.

Green, V.M.; Begovich, J.M.; Flanagan, G.F. [Oak Ridge National Lab., TN (United States); Lotts, A.L.

1994-09-01T23:59:59.000Z

268

Graphene-based Electrochemical Energy Conversion and Storage: Fuel cells, Supercapacitors and Lithium Ion Batteries  

SciTech Connect

Graphene has attracted extensive research interest due to its strictly 2-dimensional (2D) structure, which results in its unique electronic, thermal, mechanical, and chemical properties and potential technical applications. These remarkable characteristics of graphene, along with the inherent benefits of a carbon material, make it a promising candidate for application in electrochemical energy devices. This article reviews the methods of graphene preparation, introduces the unique electrochemical behavior of graphene, and summarizes the recent research and development on graphene-based fuel cells, supercapacitors and lithium ion batteries. In addition, promising areas are identified for the future development of graphene-based materials in electrochemical energy conversion and storage systems.

Hou, Junbo; Shao, Yuyan; Ellis, Michael A.; Moore, Robert; Yi, Baolian

2011-09-14T23:59:59.000Z

269

Container for reprocessing and permanent storage of spent nuclear fuel assemblies  

DOE Patents (OSTI)

A single canister process container is described for reprocessing and permanent storage of spent nuclear fuel assemblies comprising zirconium-based cladding and fuel, which process container comprises a collapsible container, having side walls that are made of a high temperature alloy and an array of collapsible support means wherein the container is capable of withstanding temperature necessary to oxidize the zirconium-based cladding and having sufficient ductility to maintain integrity when collapsed under pressure. The support means is also capable of maintaining its integrity at a temperature necessary to oxidize the zirconium-based cladding. The process container also has means to introduce and remove fluids to and from the container. 10 figs.

Forsberg, C.W.

1992-03-24T23:59:59.000Z

270

Dry low NOx combustion system with pre-mixed direct-injection secondary fuel nozzle  

Science Conference Proceedings (OSTI)

A combustion system includes a first combustion chamber and a second combustion chamber. The second combustion chamber is positioned downstream of the first combustion chamber. The combustion system also includes a pre-mixed, direct-injection secondary fuel nozzle. The pre-mixed, direct-injection secondary fuel nozzle extends through the first combustion chamber into the second combustion chamber.

Zuo, Baifang; Johnson, Thomas; Ziminsky, Willy; Khan, Abdul

2013-12-17T23:59:59.000Z

271

Multi-fuel reformers for fuel cells used in transportation: Assessment of hydrogen storage technologies. Phase 2: Final report  

DOE Green Energy (OSTI)

During Phase 1 of this program, the authors evaluated all known hydrogen storage technologies (including those that are now practiced and those that are development) in the context of fuel cell vehicles. They determined that among the development technologies, carbon sorbents could most benefit from closer scrutiny. During Phase 2 of this program, they tested ten different carbon sorbents at various practical temperatures and pressures, and developed the concept of the usable Capacity Ratio, which is the ratio of the mass of hydrogen that can be released from a carbon-filled tank to the mass of hydrogen that can be released from an empty tank. The authors also commissioned the design, fabrication, and NGV2 (Natural Gas Vehicle) testing of an aluminum-lined, carbon-composite, full-wrapped pressure vessel to store hydrogen at 78 K and 3,000 psi. They constructed a facility to pressure cycle the tank at 78 K and to temperature cycle the tank at 3,000 psi, tested one such tank, and submitted it for a burst test. Finally, they devised a means by which cryogenic compressed hydrogen gas tanks can be filled and discharged using standard hardware--that is, without using filters, valves, or pressure regulators that must operate at both low temperature and high pressure. This report describes test methods and test results of carbon sorbents and the design of tanks for cold storage. 7 refs., 91 figs., 10 tabs.

NONE

1995-05-01T23:59:59.000Z

272

Fuel Cycle Technologies Near Term Planning for Storage and Transportation of Used Nuclear Fuel  

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

of Section 180(c) of the Nuclear of Section 180(c) of the Nuclear Waste Policy Act, as amended National Transportation Stakeholder's Forum Buffalo, NY May 15, 2013 Section 180(c) Mandate "The Secretary shall provide technical assistance and funds to States for training for public safety officials of appropriate units of local government and Indian tribes through whose jurisdiction the Secretary plans to transport spent nuclear fuel or high-level radioactive waste [to an NWPA-authorized facility]. * The training shall cover procedures for safe routine transportation of these materials and procedures for dealing with emergency response situations. * Covers all modes of transport 2 Section 180(c) - Background Ôāß DOE nearly implemented Section 180(c) in the mid-

273

Spent nuclear fuel project cold vacuum drying facility supporting data and calculation database  

Science Conference Proceedings (OSTI)

This document provides a database of supporting calculations for the Cold Vacuum Drying Facility (CVDF). The database was developed in conjunction with HNF-SD-SNF-SAR-002, ''Safety Analysis Report for the Cold Vacuum Drying Facility'', Phase 2, ''Supporting Installation of Processing Systems'' (Garvin 1998). The HNF-SD-SNF-DRD-002, 1997, ''Cold Vacuum Drying Facility Design Requirements'', Rev. 2, and the CVDF Summary Design Report. The database contains calculation report entries for all process, safety and facility systems in the CVDF, a general CVD operations sequence and the CVDF System Design Descriptions (SDDs). This database has been developed for the SNFP CVDF Engineering Organization and shall be updated, expanded, and revised in accordance with future design, construction and startup phases of the CVDF until the CVDF final ORR is approved.

IRWIN, J.J.

1999-02-26T23:59:59.000Z

274

End-of-Life Rod Internal Pressures in Spent Pressurized Water Reactor Fuel  

Science Conference Proceedings (OSTI)

The end-of-reactor-life (EOL) rod internal pressure (RIP) is the primary protagonist for several evolutionary changes during long-term dry storage, which affect cladding resistance to failure when spent fuel assemblies are subjected to normal and accident conditions of transport. At the maximum temperature attained, either during vacuum drying or dry storage, EOL RIP determines the maximum stress state in the fuel rod cladding, which in turn sets the initial conditions for potential time-dependent ...

2013-12-17T23:59:59.000Z

275

Maintenance and storage of fuel oil for residential heating systems: A guide for residential heating system maintenance personnel  

SciTech Connect

The quality of No. 2 fuel affects the performance of the heating system and is an important parameter in the proper and efficient operation of an oil-burning system. The physical and chemical characteristics of the fuel can affect the flow, atomization and combustion processes, all of which help to define and limit the overall performance of the heating system. The use of chemical additives by fuel oil marketershas become more common as a method of improving the quality of the fuel, especially for handling and storage. Numerous types of additives are available, but reliable information on their effectiveness and proper use is limited. This makes selecting an additive difficult in many situations. Common types of problems that contribute to poor fuel quality and how they affect residential heating equipment are identified inof this booklet. It covers the key items that are needed in an effective fuel quality monitoring program, such as what to look for when evaluating the quality of fuel as it is received from a supplier, or how to assess fuel problems associated with poor storage conditions. References to standard procedures and brief descriptions of the procedures also are given. Approaches for correcting a fuel-related problem, including the potential uses of chemical additives are discussed. Different types of additives are described to help users understand the functions and limitations of chemical treatment. Tips on how to select andeffectively use additives also are included. Finally, the importance of preventative maintenance in any fuel monitoring program is emphasized.

Litzke, Wai-Lin

1992-12-01T23:59:59.000Z

276

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

277

A PROCESS FOR THE RECOVERY OF URANIUM FROM NUCLEAR FUEL ELEMENTS USING FLUID-BED DRYING AND VOLATILITY TECHNIQUES  

SciTech Connect

A process scheme for the recovery of uranium from fuel elements has been developed. The scheme combines continuous fluid-bed drying and fluoride volatility techniques after initial dissolution of the fuel element in the appropriate aqueous system, hence the designation ADF, Aqueous Dry Fluorination Process. The application of this process to the recovery of uranium from highly enriched, low uranium-zirconium alloy plate-type fuels is described. ln the process, the feed solution is sprayed horizontally through a two-fluid nozzle and is atomized directly in the heated fluidized bed. The spray droplets are dried on the fluidized particles and form a dense coating. Excessive particle growth was limited by the use of air attrition-jets inserted directly in the bed. Aqueous hydrofluoric acid solutions containing l.2 to 3.6 M zirconiuni, 0.007 to 0.03 M uranium, and free acid concentrations from 1 to about l0 M were successfully processed in a 6-in.-diameter Inconel fluid-bed spray dryer. Rates equivalent to about 3.l kg/hr of zirconium were achieved, 160 ml/min with the most concentrated feed solution. Experiments were successfully carried out from 240 to 450 deg C. A new design for a two-fluid nozzle was developed. Extensive work was done to identify the various zirconium fluoride compounds formed. The granular dryer product was subsequently fluorinated at temperatures to 600 deg C in fluid beds and to 700 deg C in static beds to remove the uranium as the volatile hexafluoride. About 90 to 95% uranium removal was consistently achieved near 600 deg C. The relatively low uranium recovery under these conditions is a disadvantage for the application to zirconium-base fuels. It was found necessary to resort to static beds and higher temperatures to achieve greater removal. Since the fluorine attack on nickel, the material of construction, is prohibitive at temperatures above 600 deg C, a disposable fluorinator concept for use with static beds is described. Results of corrosion studies are reported. A preliminary chemical flowsheet with a design capacity of 1l00 kg of uranium (93% enriched) annually is presented. (auth)

Levitz, N.; Barghusen, J.; Carls, E.; Jonke, A.A.

1961-11-01T23:59:59.000Z

278

U.S. Environmental Protection Agency Clear Air Act notice of construction for the spent nuclear fuel project - Cold Vaccum Drying Facility, project W-441  

Science Conference Proceedings (OSTI)

This document provides information regarding the source and the estimated quantity of potential airborne radionuclide emissions resulting from the operation of the Cold Vacuum Drying (CVD) Facility. The construction of the CVD Facility is scheduled to commence on or about December 1996, and will be completed when the process begins operation. This document serves as a Notice of Construction (NOC) pursuant to the requirements of 40 Code of Federal Regulations (CFR) 61 for the CVD Facility. About 80 percent of the U.S. Department of Energy`s spent nuclear fuel (SNF) inventory is stored under water in the Hanford Site K Basins. Spent nuclear fuel in the K West Basin is contained in closed canisters, while the SNF in the K East Basin is in open canisters, which allow release of corrosion products to the K East Basin water. Storage of the current inventory in the K Basins was originally intended to be on an as-needed basis to sustain operation of the N Reactor while the Plutonium-Uranium Extraction (PUREX) Plant was refurbished and restarted. The decision in December 1992 to deactivate the PURF-X Plant left approximately 2,100 MT (2,300 tons) of uranium as part of the N Reactor SNF in the K Basins with no means for near-term removal and processing. The CVD Facility will be constructed in the 100 Area northwest of the 190 K West Building, which is in close proximity to the K East and K West Basins (Figures 1 and 08572). The CVD Facility will consist of five processing bays, with four of the bays fully equipped with processing equipment and the fifth bay configured as an open spare bay. The CVD Facility will have a support area consisting of a control room, change rooms, and other functions required to support operations.

Turnbaugh, J.E.

1996-11-25T23:59:59.000Z

279

Combined cooling and purification system for nuclear reactor spent fuel pit, refueling cavity, and refueling water storage tank  

DOE Patents (OSTI)

The spent fuel pit of a pressured water reactor (PWR) nuclear power plant has sufficient coolant capacity that a safety rated cooling system is not required. A non-safety rated combined cooling and purification system with redundant branches selectively provides simultaneously cooling and purification for the spent fuel pit, the refueling cavity, and the refueling water storage tank, and transfers coolant from the refueling water storage tank to the refueling cavity without it passing through the reactor core. Skimmers on the suction piping of the combined cooling and purification system eliminate the need for separate skimmer circuits with dedicated pumps.

Corletti, Michael M. (New Kensington, PA); Lau, Louis K. (Monroeville, PA); Schulz, Terry L. (Murrysville Boro, PA)

1993-01-01T23:59:59.000Z

280

Combined cooling and purification system for nuclear reactor spent fuel pit, refueling cavity, and refueling water storage tank  

DOE Patents (OSTI)

The spent fuel pit of a pressured water reactor (PWR) nuclear power plant has sufficient coolant capacity that a safety rated cooling system is not required. A non-safety rated combined cooling and purification system with redundant branches selectively provides simultaneously cooling and purification for the spent fuel pit, the refueling cavity, and the refueling water storage tank, and transfers coolant from the refueling water storage tank to the refueling cavity without it passing through the reactor core. Skimmers on the suction piping of the combined cooling and purification system eliminate the need for separate skimmer circuits with dedicated pumps. 1 figures.

Corletti, M.M.; Lau, L.K.; Schulz, T.L.

1993-12-14T23:59:59.000Z

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

Vision and framework for technical and management support to facilitate foreign spent fuel storage and geologic disposal in Russia  

SciTech Connect

This ''Technical and Management Support'' program would facilitate the transfer of spent fuel from commercial power plants in Taiwan to a storage and geologic repository site near Krasnoyarsk, Russia. This program resolves issues of disposition of Taiwan spent fuel (including US origin fuel) and provides revenue for Russia to develop an integrated spent fuel storage and radioactive waste management system including a geologic repository. LLNL has ongoing contracts and collaborations with all the principal parties and is uniquely positioned to facilitate the development of such a program. A three-phase approach over 20 years is proposed: namely, an initial feasibility investigation followed by an engineering development phase, and then implementation.

Halsey, W G; Jardine, L J; Smith, C F

1999-07-01T23:59:59.000Z

282

Corrective Action Investigation Plan for Corrective Action Unit 321: Area 22 Weather Station Fuel Storage, Nevada Test Site, Nevada  

SciTech Connect

This Corrective Action Investigation Plan (CAIP) has been developed in accordance with the Federal Facility Agreement and Consent Order (FFACO) that was agreed to by the US Department of Energy, Nevada Operations Office (DOE/NV); the State of Nevada Division of Environmental Protection (NDEP); and the US Department of Defense (FFACO, 1996). The CAIP is a document that provides or references all of the specific information for investigation activities associated with Corrective Action Units (CAUs) or Corrective Action Sites (CASs). According to the FFACO (1996), CASs are sites potentially requiring corrective action(s) and may include solid waste management units or individual disposal or release sites. A CAU consists of one or more CASs grouped together based on geography, technical similarity, or agency responsibility for the purpose of determining corrective actions. This CAIP contains the environmental sample collection objectives and the criteria for conducting site investigation activities at the CAU 321 Area 22 Weather Station Fuel Storage, CAS 22-99-05 Fuel Storage Area. For purposes of this discussion, this site will be referred to as either CAU 321 or the Fuel Storage Area. The Fuel Storage Area is located in Area 22 of the Nevada Test Site (NTS). The NTS is approximately 105 kilometers (km) (65 miles [mi]) northwest of Las Vegas, Nevada (Figure 1-1) (DOE/NV, 1996a). The Fuel Storage Area (Figure 1-2) was used to store fuel and other petroleum products necessary for motorized operations at the historic Camp Desert Rock facility which was operational from 1951 to 1958 at the Nevada Test Site, Nevada. The site was dismantled after 1958 (DOE/NV, 1996a).

DOE /NV

1999-01-28T23:59:59.000Z

283

CTR Fuel recovery system using regeneration of a molecular sieve drying bed  

DOE Patents (OSTI)

A primary molecular sieve drying bed is regenerated by circulating a hot inert gas through the heated primary bed to desorb water held on the bed. The inert gas plus water vapor is then cooled and passed through an auxiliary molecular sieve bed which adsorbs the water originally desorbed from the primary bed. The main advantage of the regeneration technique is that the partial pressure of water can be reduced to the 10.sup.-9 atm. range. This is significant in certain CTR applications where tritiated water (T.sub.2 O, HTO) must be collected and kept at very low partial pressure.

Folkers, Charles L. (Livermore, CA)

1981-01-01T23:59:59.000Z

284

Analysis of Underground Storage Tanks System Materials to Increased Leak Potential Associated with E15 Fuel  

DOE Green Energy (OSTI)

The Energy Independence and Security Act (EISA) of 2007 was enacted by Congress to move the nation toward increased energy independence by increasing the production of renewable fuels to meet its transportation energy needs. The law establishes a new renewable fuel standard (RFS) that requires the nation to use 36 billion gallons annually (2.3 million barrels per day) of renewable fuel in its vehicles by 2022. Ethanol is the most widely used renewable fuel in the US, and its production has grown dramatically over the past decade. According to EISA and RFS, ethanol (produced from corn as well as cellulosic feedstocks) will make up the vast majority of the new renewable fuel requirements. However, ethanol use limited to E10 and E85 (in the case of flex fuel vehicles or FFVs) will not meet this target. Even if all of the E0 gasoline dispensers in the country were converted to E10, such sales would represent only about 15 billion gallons per year. If 15% ethanol, rather than 10% were used, the potential would be up to 22 billion gallons. The vast majority of ethanol used in the United States is blended with gasoline to create E10, that is, gasoline with up to 10% ethanol. The remaining ethanol is sold in the form of E85, a gasoline blend with as much as 85% ethanol that can only be used in FFVs. Although DOE remains committed to expanding the E85 infrastructure, that market will not be able to absorb projected volumes of ethanol in the near term. Given this reality, DOE and others have begun assessing the viability of using intermediate ethanol blends as one way to transition to higher volumes of ethanol. In October of 2010, the EPA granted a partial waiver to the Clean Air Act allowing the use of fuel that contains up to 15% ethanol for the model year 2007 and newer light-duty motor vehicles. This waiver represents the first of a number of actions that are needed to move toward the commercialization of E15 gasoline blends. On January 2011, this waiver was expanded to include model year 2001 light-duty vehicles, but specifically prohibited use in motorcycles and off-road vehicles and equipment. UST stakeholders generally consider fueling infrastructure materials designed for use with E0 to be adequate for use with E10, and there are no known instances of major leaks or failures directly attributable to ethanol use. It is conceivable that many compatibility issues, including accelerated corrosion, do arise and are corrected onsite and, therefore do not lead to a release. However, there is some concern that higher ethanol concentrations, such as E15 or E20, may be incompatible with current materials used in standard gasoline fueling hardware. In the summer of 2008, DOE recognized the need to assess the impact of intermediate blends of ethanol on the fueling infrastructure, specifically located at the fueling station. This includes the dispenser and hanging hardware, the underground storage tank, and associated piping. The DOE program has been co-led and funded by the Office of the Biomass Program and Vehicle Technologies Program with technical expertise from the Oak Ridge National Laboratory (ORNL) and the National Renewable Energy Laboratory (NREL). The infrastructure material compatibility work has been supported through strong collaborations and testing at Underwriters Laboratories (UL). ORNL performed a compatibility study investigating the compatibility of fuel infrastructure materials to gasoline containing intermediate levels of ethanol. These results can be found in the ORNL report entitled Intermediate Ethanol Blends Infrastructure Materials Compatibility Study: Elastomers, Metals and Sealants (hereafter referred to as the ORNL intermediate blends material compatibility study). These materials included elastomers, plastics, metals and sealants typically found in fuel dispenser infrastructure. The test fuels evaluated in the ORNL study were SAE standard test fuel formulations used to assess material-fuel compatibility within a relatively short timeframe. Initially, these material studies included test fuels of Fuel C,

Kass, Michael D [ORNL; Theiss, Timothy J [ORNL; Janke, Christopher James [ORNL; Pawel, Steven J [ORNL

2012-07-01T23:59:59.000Z

285

Analysis of Underground Storage Tanks System Materials to Increased Leak Potential Associated with E15 Fuel  

Science Conference Proceedings (OSTI)

The Energy Independence and Security Act (EISA) of 2007 was enacted by Congress to move the nation toward increased energy independence by increasing the production of renewable fuels to meet its transportation energy needs. The law establishes a new renewable fuel standard (RFS) that requires the nation to use 36 billion gallons annually (2.3 million barrels per day) of renewable fuel in its vehicles by 2022. Ethanol is the most widely used renewable fuel in the US, and its production has grown dramatically over the past decade. According to EISA and RFS, ethanol (produced from corn as well as cellulosic feedstocks) will make up the vast majority of the new renewable fuel requirements. However, ethanol use limited to E10 and E85 (in the case of flex fuel vehicles or FFVs) will not meet this target. Even if all of the E0 gasoline dispensers in the country were converted to E10, such sales would represent only about 15 billion gallons per year. If 15% ethanol, rather than 10% were used, the potential would be up to 22 billion gallons. The vast majority of ethanol used in the United States is blended with gasoline to create E10, that is, gasoline with up to 10% ethanol. The remaining ethanol is sold in the form of E85, a gasoline blend with as much as 85% ethanol that can only be used in FFVs. Although DOE remains committed to expanding the E85 infrastructure, that market will not be able to absorb projected volumes of ethanol in the near term. Given this reality, DOE and others have begun assessing the viability of using intermediate ethanol blends as one way to transition to higher volumes of ethanol. In October of 2010, the EPA granted a partial waiver to the Clean Air Act allowing the use of fuel that contains up to 15% ethanol for the model year 2007 and newer light-duty motor vehicles. This waiver represents the first of a number of actions that are needed to move toward the commercialization of E15 gasoline blends. On January 2011, this waiver was expanded to include model year 2001 light-duty vehicles, but specifically prohibited use in motorcycles and off-road vehicles and equipment. UST stakeholders generally consider fueling infrastructure materials designed for use with E0 to be adequate for use with E10, and there are no known instances of major leaks or failures directly attributable to ethanol use. It is conceivable that many compatibility issues, including accelerated corrosion, do arise and are corrected onsite and, therefore do not lead to a release. However, there is some concern that higher ethanol concentrations, such as E15 or E20, may be incompatible with current materials used in standard gasoline fueling hardware. In the summer of 2008, DOE recognized the need to assess the impact of intermediate blends of ethanol on the fueling infrastructure, specifically located at the fueling station. This includes the dispenser and hanging hardware, the underground storage tank, and associated piping. The DOE program has been co-led and funded by the Office of the Biomass Program and Vehicle Technologies Program with technical expertise from the Oak Ridge National Laboratory (ORNL) and the National Renewable Energy Laboratory (NREL). The infrastructure material compatibility work has been supported through strong collaborations and testing at Underwriters Laboratories (UL). ORNL performed a compatibility study investigating the compatibility of fuel infrastructure materials to gasoline containing intermediate levels of ethanol. These results can be found in the ORNL report entitled Intermediate Ethanol Blends Infrastructure Materials Compatibility Study: Elastomers, Metals and Sealants (hereafter referred to as the ORNL intermediate blends material compatibility study). These materials included elastomers, plastics, metals and sealants typically found in fuel dispenser infrastructure. The test fuels evaluated in the ORNL study were SAE standard test fuel formulations used to assess material-fuel compatibility within a relatively short timeframe. Initially, these material studies included test fuels of Fuel C,

Kass, Michael D [ORNL; Theiss, Timothy J [ORNL; Janke, Christopher James [ORNL; Pawel, Steven J [ORNL

2012-07-01T23:59:59.000Z

286

North Portal Fuel Storage System Fire Hazard Analysis-ESF Surface Design Package ID  

SciTech Connect

The purpose of the fire hazard analysis is to comprehensively assess the risk from fire within the individual fire areas. This document will only assess the fire hazard analysis within the Exploratory Studies Facility (ESF) Design Package ID, which includes the fuel storage system area of the North Portal facility, and evaluate whether the following objectives are met: 1.1.1--This analysis, performed in accordance with the requirements of this document, will satisfy the requirements for a fire hazard analysis in accordance with U.S. Department of Energy (DOE) Order 5480.7A. 1.1.2--Ensure that property damage from fire and related perils does not exceed an acceptable level. 1.1.3--Provide input to the ESF Basis For Design (BFD) Document. 1.1.4 Provide input to the facility Safety Analysis Report (SAR) (Paragraph 3.8).

N.M. Ruonavaara

1995-01-18T23:59:59.000Z

287

Addendum 1 to CSER 78-001 PWR Core 2 Blanket Fuel Storage Cell 4 221T building  

SciTech Connect

Irradiated pressurized water reactor (PWR) Core 2 (PWR-2) blanket fuel assemblies from the Shippingport PWR have been stored in the 221-T canyon water pool for twenty years. The fuel is in the form of small wafers of UO{sub 2}, which were initially natural enriched uranium (0.72% {sup 235}U). The uranium oxide wafers have a pyrolytic carbon coating, which prevents the fuel from reacting with a zircaloy-4 grid which provides structural strength and holds the wafers in place to form fuel plates. Thirty fuel plates comprise a sub-assembly which are held together by zircaloy-4 end plates. Two identical oxide fuel plate sub-assemblies are welded together to form a square structure with two zircaloy-4 extensions welded to the ends. Seventy-two PWR-2 assemblies are stored in the 221-T canyon water pool. Eight of these assemblies were irradiated in the center of the reactor core to an average burnup of 24,538 Mwd/MTU. The remaining assemblies had a burnup of 16,200 Mwd/MTU. These assemblies were placed in the canyon in 1978 and 1979 (WHC 1996). The original Criticality Safety Analysis Report (CSAR) (WHC 1990) analyzed the criticality safety of their storage and concluded that they were safe from a criticality standpoint. It was also mentioned in this CSAR that the assemblies were scheduled to be stored for twenty years. The Criticality Prevention Specification (CPS) for this storage configuration (RHO 1978), included in (WHC 1990), specifies that the fuel ''will be stored in Cell 4 up to 20 years'', and that ''no special handling or storage requirements for criticality control during interim storage up to 20 years'' were necessary. The purpose of this addendum is to extend the period of coverage for this material. The analysis examines zircaloy-clad fuel degradation and extends the permitted storage time by ten years for Shippingport Core 2 blanket fuel assemblies in the 221-T, Cell 4 storage pool.

GOLDBERG, H.J.

1999-12-03T23:59:59.000Z

288

Dry halide method for separating the components of spent nuclear fuels  

DOE Patents (OSTI)

The invention is a nonaqueous, single method for processing multiple spent nuclear fuel types by separating the fission- and transuranic products from the nonradioactive and fissile uranium product. The invention has four major operations: exposing the spent fuels to chlorine gas at temperatures preferably greater than 1200.degree. C. to form volatile metal chlorides; removal of the fission product chlorides, transuranic product chlorides, and any nickel chloride and chromium chloride in a molten salt scrubber at approximately 400.degree. C.; fractional condensation of the remaining volatile chlorides at temperatures ranging from 164.degree. C. to 2.degree. C.; and regeneration and recovery of the transferred spent molten salt by vacuum distillation. The residual fission products, transuranic products, and nickel- and chromium chlorides are converted to fluorides or oxides for vitrification. The method offers the significant advantages of a single, compact process that is applicable to most of the diverse nuclear fuels, minimizes secondary wastes, segregates fissile uranium from the high level wastes to resolve potential criticality concerns, segregates nonradioactive wastes from the high level wastes for volume reduction, and produces a common waste form glass or glass-ceramic.

Christian, Jerry Dale (Idaho Falls, ID); Thomas, Thomas Russell (Rigby, ID); Kessinger, Glen F. (Idaho Falls, ID)

1998-01-01T23:59:59.000Z

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

Utilization of a finite element model to verify spent nuclear fuel storage rack welds  

Science Conference Proceedings (OSTI)

Elastic and plastic finite element analyses were performed for the inner tie block assembly of a 25 port fuel rack designed for installation at the Idaho National Engineering and Environmental Laboratory (INEEL) Idaho Chemical Processing Plant (ICPP). The model was specifically developed to verify the adequacy of certain welds joining components of the fuel storage rack assembly. The work scope for this task was limited to an investigation of the stress levels in the inner tie welds when the rack was subjected to seismic loads. Structural acceptance criteria used for the elastic calculations performed were as defined by the rack`s designer. Structural acceptance criteria used for the plastic calculations performed as part of this effort were as defined in Subsection NF and Appendix F of Section III of the ASME Boiler and Pressure Vessel Code. The results confirm that the welds joining the inner tie block to the surrounding rack structure meet the acceptance criteria. The analysis results verified that the inner tie block welds should be capable of transferring the expected seismic load without structural failure.

Nitzel, M.E.

1998-07-01T23:59:59.000Z

291

COBRA-SFS (Spent Fuel Storage): A thermal-hydraulic analysis computer code: Volume 2, User's manual  

Science Conference Proceedings (OSTI)

COBRA-SFS (Spent Fuel Storage) is a general thermal-hydraulic analysis computer code used to predict temperatures and velocities in a wide variety of systems. The code was refined and specialized for spent fuel storage system analyses for the US Department of Energy's Commercial Spent Fuel Management Program. The finite-volume equations governing mass, momentum, and energy conservation are written for an incompressible, single-phase fluid. The flow equations model a wide range of conditions including natural circulation. The energy equations include the effects of solid and fluid conduction, natural convection, and thermal radiation. The COBRA-SFS code is structured to perform both steady-state and transient calculations; however, the transient capability has not yet been validated. This volume contains the input instructions for COBRA-SFS and an auxiliary radiation exchange factor code, RADX-1. It is intended to aid the user in becoming familiar with the capabilities and modeling conventions of the code.

Rector, D.R.; Cuta, J.M.; Lombardo, N.J.; Michener, T.E.; Wheeler, C.L.

1986-11-01T23:59:59.000Z

292

COBRA-SFS (Spent Fuel Storage): A thermal-hydraulic analysis computer code: Volume 1, Mathematical models and solution method  

Science Conference Proceedings (OSTI)

COBRA-SFS (Spent Fuel Storage) is a general thermal-hydraulic analysis computer code used to predict temperatures and velocities in a wide variety of systems. The code was refined and specialized for spent fuel storage system analyses for the US Department of Energy's Commercial Spent Fuel Management Program. The finite-volume equations governing mass, momentum, and energy conservation are written for an incompressible, single-phase fluid. The flow equations model a wide range of conditions including natural circulation. The energy equations include the effects of solid and fluid conduction, natural convection, and thermal radiation. The COBRA-SFS code is structured to perform both steady-state and transient calculations: however, the transient capability has not yet been validated. This volume describes the finite-volume equations and the method used to solve these equations. It is directed toward the user who is interested in gaining a more complete understanding of these methods.

Rector, D.R.; Wheeler, C.L.; Lombardo, N.J.

1986-11-01T23:59:59.000Z

293

Nuclear Maintenance Applications Center: Guide for the Storage and Handling of Fuel Oil for Standby Diesel Generator Systems, Revisi on 3  

Science Conference Proceedings (OSTI)

Diesel engines are used to operate the emergency generators that supply power for many applications such as hospitals, communication facilities, fire water pumps, and nuclear power plants. In order for these engines to perform their intended function, they must have a readily available supply of suitable fuel. This revised guide addresses the concerns associated with long term storage of fuel, as well as techniques for monitoring and reducing the effects of contaminants, which can affect fuel storage sys...

2007-12-21T23:59:59.000Z

294

Down Select Report of Chemical Hydrogen Storage Materials, Catalysts, and Spent Fuel Regeneration Processes - May 2008  

Fuel Cell Technologies Publication and Product Library (EERE)

Chemical Hydrogen Storage Center of Excellence FY2008 Second Quarter Milestone Report: Technical report describing assessment of hydrogen storage materials and progress towards meeting DOEís hydrogen

295

DOE Fuel Cell Technologies Office Record 13010: Onboard Type IV Compressed Hydrogen Storage Systems - Current Performance and Cost  

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

DOE Fuel Cell Technologies Office Record Record #: 13010 Date: June 11, 2013 Title: Onboard Type IV Compressed Hydrogen Storage Systems - Current Performance and Cost Originators: Scott McWhorter and Grace Ordaz Approved by: Sunita Satyapal Date: July 17, 2013 Item: This record summarizes the current status of the projected capacities and manufacturing costs of Type IV, 350- and 700-bar compressed hydrogen storage systems, storing 5.6 kg of usable hydrogen, for onboard light-duty automotive applications when manufactured at a volume of 500,000 units per year. The current projected performance and cost of these systems are presented in Table 1 against the DOE Hydrogen Storage System targets. These analyses were performed in support of the Hydrogen Storage

296

Apparatus for in situ determination of burnup, cooling time and fissile content of an irradiated nuclear fuel assembly in a fuel storage pond  

DOE Patents (OSTI)

A detector head for in situ inspection of irradiated nuclear fuel assemblies submerged in a water-filled nuclear fuel storage pond. The detector head includes two parallel arms which extend from a housing and which are spaced apart so as to be positionable on opposite sides of a submerged fuel assembly. Each arm includes an ionization chamber and two fission chambers. One fission chamber in each arm is enclosed in a cadmium shield and the other fission chamber is unshielded. The ratio of the outputs of the shielded and unshielded fission chambers is used to determine the boron content of the pond water. Correcting for the boron content, the neutron flux and gamma ray intensity are then used to verify the declared exposure, cooling time and fissile material content of the irradiated fuel assembly.

Phillips, J.R.; Halbig, J.K.; Menlove, H.O.; Klosterbuer, S.F.

1984-01-01T23:59:59.000Z

297

Apparatus for in situ determination of burnup, cooling time and fissile content of an irradiated nuclear fuel assembly in a fuel storage pond  

DOE Patents (OSTI)

A detector head for in situ inspection of irradiated nuclear fuel assemblies submerged in a water-filled nuclear fuel storage pond. The detector head includes two parallel arms which extend from a housing and which are spaced apart so as to be positionable on opposite sides of a submerged fuel assembly. Each arm includes an ionization chamber and two fission chambers. One fission chamber in each arm is enclosed in a cadmium shield and the other fission chamber is unshielded. The ratio of the outputs of the shielded and unshielded fission chambers is used to determine the boron content of the pond water. Correcting for the boron content, the neutron flux and gamma ray intensity are then used to verify the declared exposure, cooling time and fissile material content of the irradiated fuel assembly.

Phillips, John R. (Los Alamos, NM); Halbig, James K. (Los Alamos, NM); Menlove, Howard O. (Los Alamos, NM); Klosterbuer, Shirley F. (Los Alamos, NM)

1985-01-01T23:59:59.000Z

298

Spent nuclear fuel project detonation phenomena of hydrogen/oxygen in spent fuel containers  

DOE Green Energy (OSTI)

Movement of Spent N Reactor fuels from the Hanford K Basins near the Columbia River to Dry interim storage facility on the Hanford plateau will require repackaging the fuel in the basins into multi-canister overpacks (MCOs), drying of the fuel, transporting the contained fuel, hot conditioning, and finally interim storage. Each of these functions will be accomplished while the fuel is contained in the MCOs by several mechanisms. The principal source of hydrogenand oxygen within the MCOs is residual water from the vacuum drying and hot conditioning operations. This document assesses the detonation phenomena of hydrogen and oxygen in the spent fuel containers. Several process scenarios have been identified that could generate detonation pressures that exceed the nominal 10 atmosphere design limit ofthe MCOS. Only 42 grams of radiolized water are required to establish this condition.

Cooper, T.D.

1996-09-30T23:59:59.000Z

299

Technical Issues and Characterization for Fuel and Sludge in Hanford K Basins  

SciTech Connect

Technical Issues for the interim dry storage of N Reactor Spent Nuclear Fuel (SNF) are discussed. Characterization data from fuel, to support resolution of these issues, are reviewed and new results for the oxidation of fuel in a moist atmosphere and the drying of whole fuel elements are presented. Characterization of associated K basin sludge is also discussed in light of a newly adopted disposal pathway.

MAKENAS, B.J.

2000-06-01T23:59:59.000Z

300

Spent fuel handling and packaging program. Management summary report  

SciTech Connect

Objective is to design, develop, and demonstrate a spent fuel package for geologic storage and disposal; to design, license, and construct the facilities to produce this package; and to develop and demonstrate technology for the dry, passive surface storage of spent fuel. Progress is reported on engineering and system studies, technical R and D studies, demonstrations, project support studies, spent fuel facility project, and program management.

1978-09-01T23:59:59.000Z

Note: This page contains sample records for the topic "fuel dry 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

Extended-burnup LWR (light-water reactor) fuel: The amount, characteristics, and potential effects on interim storage  

Science Conference Proceedings (OSTI)

The results of a study on extended-burnup, light-water reactor (LWR) spent fuel are described in this report. The study was performed by Pacific Northwest Laboratory for the US Department of Energy (DOE). The purpose of the study was to collect and evaluate information on the status of in-reactor performance and integrity of extended-burnup LWR fuel and initiate the investigation of the effects of extending fuel burnup on the subsequent handling, interim storage, and other operations (e.g., rod consolidation and shipping) associated with the back end of the fuel cycle. The results of this study will aid DOE and the nuclear industry in assessing the effects on waste management of extending the useful in-reactor life of nuclear fuel. The experience base with extended-burnup fuel is now substantial and projections for future use of extended-burnup fuel in domestic LWRs are positive. The basic performance and integrity of the fuel in the reactor has not been compromised by extending the burnup, and the potential limitations for further extending the burnup are not severe. 104 refs., 15 tabs.

Bailey, W.J.

1989-03-01T23:59:59.000Z

302

DOE Hydrogen and Fuel Cells Program: 2006 Annual Progress Report - Storage  

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

Storage Storage Printable Version 2006 Annual Progress Report IV. Storage This section of the 2006 Progress Report for the DOE Hydrogen Program focuses on storage. Each technical report is available as an individual Adobe Acrobat PDF. Download Adobe Reader. Hydrogen Storage Sub-Program Overview, Sunita Satyapal, Storage Team Lead, DOE Hydrogen Program (PDF 298 KB) A. Metal Hydrides High Density Hydrogen Storage System Demonstration Using NaAlH4 Based Complex Compound Hydrides, Dan Mosher, United Technologies Research Center (PDF 763 KB) Discovery of Novel Complex Metal Hydrides for Hydrogen Storage through Molecular Modeling and Combinatorial Methods, David Lesch, UOP LLC (PDF 780 KB) Complex Hydride Compounds with Enhanced Hydrogen Storage Capacity, Dan Mosher, United Technologies Research Center (PDF 678 KB)

303

Strategy for Used Fuel Acquisition  

SciTech Connect

The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), Office of Fuel Cycle Technology, has established the Used Fuel Disposition Campaign (UFDC) to conduct the research and development activities related to storage, transportation, and disposal of used nuclear fuel and high-level radioactive waste. The mission of the UFDC is to identify alternatives and conduct scientific research and technology development to enable storage, transportation and disposal of used nuclear fuel (UNF) and wastes generated by existing and future nuclear fuel cycles. The Storage and Transportation staffs within the UFDC are responsible for addressing issues regarding the extended or long-term storage of UNF and its subsequent transportation. The near-term objectives of the Storage and Transportation task are to use a science-based approach to develop the technical bases to support the continued safe and secure storage of UNF for extended periods, subsequent retrieval, and transportation. While both wet and dry storage have been shown to be safe options for storing UNF, the focus of the program is on dry storage at reactor or centralized locations. Because limited information is available on the properties of high burnup fuel (exceeding 45 gigawatt-days per metric tonne of uranium [GWd/MTU]), and because much of the fuel currently discharged from todayís reactors exceeds this burnup threshold, a particular emphasis of this program is on high burnup fuels. Since high burnup used fuels have only been loaded into dry storage systems in the past decade or so, these materials are available to the UFDC for testing in only very limited quantities. Much of what is available has come via NRC testing programs. Some of these fuels may have achieved "high burnup," but that does not mean they were designed for high burnup use (e.g. lower enrichments, smaller plenum spaces, extra reactor cycles). The handling and transfer of these materials from utility to laboratory has not always been prototypical of how used nuclear fuel is prepared for dry storage; these fuels are not subjected to the same vacuum drying conditions that can lead to changes in hydride morphology that will affect the mechanical properties of the fuel. It is recognized that sources of used high burnup fuel that can be handled in a manner consistent with how fuel is readied for dry storage is essential to the mission of the UFDC. This report documents what types of fuel are of interest to the campaign, and how those fuels could be acquired and shipped to the Idaho National Laboratory (INL) for incorporation into the campaign R&D mission. It also identifies any gaps in INL capabilities that might preclude working with one fuel type or another.

Steven C. Marschman; Chris Rusch

2013-09-01T23:59:59.000Z

304

Toward a Common Method of Cost Estimation for CO2 Capture and Storage at Fossil Fuel Power Plants  

Science Conference Proceedings (OSTI)

There are significant differences in the methods employed by various organizations to estimate the cost of carbon capture and storage (CCS) systems for fossil fuel power plants. Such differences often are not readily apparent in publicly reported CCS cost estimates. As a consequence, there is a significant degree of misunderstanding, confusion, and mis-representation of CCS cost information, especially among audiences not familiar with the details of CCS costing. Given the international importance ...

2013-03-18T23:59:59.000Z

305

System Level Analysis of Hydrogen Storage Options - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

4 4 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Rajesh K. Ahluwalia (Primary Contact), T. Q. Hua, J-K Peng, Hee Seok Roh, and Romesh Kumar Argonne National Laboratory 9700 South Cass Avenue Argonne, IL 60439 Phone: (630) 252-5979 Email: walia@anl.gov DOE Manager HQ: Grace Ordaz Phone: (202) 586-8350 Email: Grace.Ordaz@ee.doe.gov Start Date: October 1, 2004 Projected End Date: September 30, 2014 Objective The overall objective of this effort is to support DOE with independent system level analyses of various H 2 storage approaches, to help to assess and down-select options, and to determine the feasibility of meeting DOE targets. Fiscal Year (FY) 2012 Objectives Model various developmental hydrogen storage systems. * Provide results to Hydrogen Storage Engineering Center *

306

Hydrogen Storage Cost Analysis, Preliminary Results - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

2 2 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Brian D. James (Primary Contact), Andrew B. Spisak, Whitney G. Colella Strategic Analysis, Inc. 4075 Wilson Blvd. Suite 200 Arlington, VA 22203 Phone: (703) 778-7114 E-mail: bjames@sainc.com DOE Managers HQ: Grace Ordaz Phone: (202) 586-8350 Email: Grace.Ordaz@ee.doe.gov GO: Katie Randolph Phone: (720) 356-1759 Email: Katie.Randolph@go.doe.gov Contract Number: DE-EE0005253 Project Start Date: September 30, 2012 Project End Date: September 29, 2016 Fiscal Year (FY) 2012 Objectives Develop cost models of carbon fiber hydrogen storage * pressure vessels. Explore the sensitivity of pressure vessel cost to design * parameters including hydrogen storage quantity, storage

307

DOE Hydrogen and Fuel Cells Program: 2005 Annual Progress Report - Storage  

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

Storage Storage Printable Version 2005 Annual Progress Report VI. Storage This section of the 2005 Progress Report for the DOE Hydrogen Program focuses on storage. Each technical report is available as an individual Adobe Acrobat PDF. Download Adobe Reader. Hydrogen Storage Sub-program Overview, Sunita Satyapal, Department of Energy (PDF 244 KB) A. Metal Hydrides Catalytically Enhanced Hydrogen Storage Systems, Craig M. Jensen, University of Hawaii (PDF 441 KB) High Density Hydrogen Storage System Demonstration using NaAlH4 Based Complex Compound Hydrides, Donald L. Anton, United Technologies Research Center (PDF 633 KB) Discovery of Novel Complex Metal Hydrides for Hydrogen Storage through Molecular Modeling and Combinatorial Methods, David A. Lesch, UOP LLC (PDF 308 KB)

308

Fuels generated from renewable energy: a possible solution for large scale energy storage  

E-Print Network (OSTI)

-powered engines. Fig. 1 shows its ability to restore the lubricity of sulfur-free (Fischer-Tropsch) diesel fuel-boron additive concentration in 0 ppm sulfur diesel Fischer-Tropsch fuel with Argonne's boron additives at different concentrations Fischer-Tropsch synthetic diesel fuel Number 2 diesel fuel sulfur(500ppm) 0

Franssen, Michael

309

Spent Fuel Pool Cooling and Cleanup During Decommissioning: Experience at Trojan Nuclear Power Plant  

Science Conference Proceedings (OSTI)

Operation of original in-plant spent fuel pool facilities at shutdown power plants is expensive compared to available alternatives and can interfere with the decommissioning process. This report describes the approach taken in the Trojan Decommissioning Project to establish independent cooling and cleanup services for the fuel pool until the spent fuel is placed in dry storage.

1999-03-15T23:59:59.000Z

310

Advanced onboard storage concepts for natural gas-fueled automotive vehicles  

SciTech Connect

The objective of this study was the evaluation, both through experimentation and a literature review, of several advanced concepts for storing natural gas at reduced pressure. The advanced concepts included adsorption on high surface area carbon, adsorption in high porosity zeolite, storage in clathration compounds, and storage by dissolution in liquid solvents. Results indicated that high surface area carbons with high packing density were the best low pressure storage mediums. A simple mathematical model was used to compare adsorption storage on a state-of-the-art carbon with compression storage. The model indicated that a vehicle using adsorption storage of natural gas at 3.6 MPa will have 36% of the range, on the EPA city cycle, of a vehicle operating on a compression storage system having the same physical size and a peak storage pressure of 21 MPa. However, preliminary experiments and current literature suggest that the storage capacity of state-of-the-art carbons could be improved by as much as 50%, and that adsorption systems having a capacity equal to compression storage at 14 MPa are possible without exceeding a maximum pressure of 3.6 MPa.

Remick, R.J.; Elkins, R.H.; Camara, E.H.; Bulicz, T.

1984-06-01T23:59:59.000Z

311

Hydrogen Storage: U.S. Department of Energy Hydrogen and Fuel...  

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

ST-019: Multiply Surface-Functionalized Nanoporous Carbon for Vehicular Hydrogen Storage Peter Pfeifer; University of Missouri Brief Summary of Project: The objective of this...

312

Criticality safety criteria for the handling, storage, and transportation of LWR fuel outside reactors: ANS-8.17-1984  

SciTech Connect

The potential for criticality accidents during the handling, storage, and transportation of fuel for nuclear reactors represents a health and safety risk to personnel involved in these activities, as well as to the general public. Appropriate design of equipment and facilities, handling procedures, and personnel training can minimize this risk. Even though the focus of the American National Standard, `Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors,` ANSI/ANS-8.1-1983, is general criteria for the ensurance of criticality safety, ANS-8.17-1984, provides additional guidance applicable to handling, storage, and transportation of light-water- reactor (LWR) nuclear fuel units in any phase of the fuel cycle outside the reactor core. ANS-8.17 had its origin in the late 1970s when a work group consisting of representatives from private industry, personnel from government contractor facilities, and scientists and engineers from the national laboratories was established. The work of this group resulted in the issuance of ANSI/ANS-8.17 in January 1984. This document provides a discussion of this standard.

Whitesides, G.E.

1996-09-01T23:59:59.000Z

313

Hydrogen and Fuel Cells R&D  

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

Liquids --Hydrogen Storage Materials --Hydrogen Storage Systems Modeling and Analysis --Thermochemical Hydrogen * Fuel Cells --Polymer Electrolyte --Modeling & Analysis --Fuel...

314

Development of High Pressure Hydrogen Storage Tank for Storage and Gaseous Truck Delivery - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

2 2 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Jon Knudsen (Primary Contact), Don Baldwin Lincoln Composites 5117 N.W. 40 th Street Lincoln, NE 68524 Phone: (402) 470-5039 Email: jknudsen@lincolncomposites.com DOE Managers HQ: Erika Sutherland Phone: (202) 586-3152 Email: Erika.Sutherland@ee.doe.gov GO: Katie Randolph Phone: (720) 356-1759 Email: Katie.Randolph@go.doe.gov Contract Number: DE-FG36-08GO18062 Project Start Date: July 1, 2008 Project End Date: April 30, 2013 Fiscal Year (FY) 2012 Objectives The objective of this project is to design and develop the most effective bulk hauling and storage solution for hydrogen in terms of: Cost * Safety * Weight * Volumetric Efficiency * Technical Barriers This project addresses the following technical barriers

315

Department of Energy Programmatic Spent Nuclear Fuel Management and Idaho National Engineering Laboratory Environmental Restoration and Waste Management Programs Draft Environmental Impact Statement. Volume 1, Appendix D, Part B: Naval spent nuclear fuel management  

SciTech Connect

This volume contains the following attachments: transportation of Naval spent nuclear fuel; description of Naval spent nuclear receipt and handling at the Expended Core Facility at the Idaho National Engineering Laboratory; comparison of storage in new water pools versus dry container storage; description of storage of Naval spent nuclear fuel at servicing locations; description of receipt, handling, and examination of Naval spent nuclear fuel at alternate DOE facilities; analysis of normal operations and accident conditions; and comparison of the Naval spent nuclear fuel storage environmental assessment and this environmental impact statement.

1994-06-01T23:59:59.000Z

316

Hydrogen Storage by Novel CBN Heterocycle Materials - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

4 4 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Shih-Yuan Liu University of Oregon Department of Chemistry 1253 University of Oregon Eugene, OR 97403-1253 Phone: (541) 346-5573 Email: lsy@uoregon.edu DOE Managers HQ: Grace Ordaz Phone: (202) 586-8350 Email: Grace.Ordaz@ee.doe.gov GO: Katie Randolph Phone: (720) 356-1759 Email: Katie.Randolph@go.doe.gov Contract Number: DE-FG36-08GO18143 Project Start Date: September 1, 2008 Project End Date: September 30, 2012 Fiscal Year (FY) 2012 Objectives The objective of this project is to develop novel boron- nitrogen heterocycles as liquid-phase hydrogen storage materials with storage capacities and thermodynamic properties that have the potential to lead to rechargeable systems capable of meeting DOE targets. We seek to:

317

Novel Molecular Materials for Hydrogen Storage Applications - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

6 6 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Maddury Somayazulu (Primary Contact), Timothy Strobel, Robert Potter, Raja Chellappa, Viktor Struzhkin, Russell J Hemley Geophysical Laboratory Carnegie Institution of Washington 5251 Broad Branch Rd NW Washington, D.C. 20015 Phone: (202) 478-8911 Email: zulu@gl.ciw.edu DOE Program Manager: Dr. P. Thiyagarajan Phone: (301) 903-9706 Email: P.Thiyagarajan@science.doe.gov Objectives Discover, identify and characterize novel hydrogen-rich * compounds that can be used for hydrogen storage or as agents for rehydrogenation of hydrogen storage materials at high pressures. Investigate high pressure routes to rehydrogenating * ammonia borane and polymeric complexes of ammonia borane. Investigate interaction of hydrogen with metallo-organic *

318

Radioactive waste shipments to Hanford retrievable storage from Westinghouse Advanced Reactors and Nuclear Fuels Divisions, Cheswick, Pennsylvania  

Science Conference Proceedings (OSTI)

During the next two decades the transuranic (TRU) waste now stored in the burial trenches and storage facilities at the Hanford Sits in southeastern Washington State is to be retrieved, processed at the Waste Receiving and Processing Facility, and shipped to the Waste Isolation Pilot Plant (WIPP), near Carlsbad, New Mexico for final disposal. Approximately 5.7 percent of the TRU waste to be retrieved for shipment to WIPP was generated by the decontamination and decommissioning (D&D) of the Westinghouse Advanced Reactors Division (WARD) and the Westinghouse Nuclear Fuels Division (WNFD) in Cheswick, Pennsylvania and shipped to the Hanford Sits for storage. This report characterizes these radioactive solid wastes using process knowledge, existing records, and oral history interviews.

Duncan, D. [Westinghouse Hanford Co., Richland, WA (United States); Pottmeyer, J.A.; Weyns, M.I.; Dicenso, K.D.; DeLorenzo, D.S. [Los Alamos Technical Associates, Inc., NM (United States)

1994-04-01T23:59:59.000Z

319

Computational studies of hydrogen interactions with storage materials - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

6 6 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Chris G. Van de Walle (Primary Contact), Lars Ismer, Anindya Roy, and Anderson Janotti Materials Department, University of California Santa Barbara, CA 93106-5050 Phone: (805) 893-7144 Email: vandewalle@mrl.ucsb.edu DOE Program Officer: James Davenport Phone: (301) 903-0035 Email: James.Davenport@science.doe.gov Objectives Building on our accumulated knowledge of hydrogen interactions with semiconductors and insulators we have been conducting computational studies with the goal of developing new insights for hydrogen interactions with hydrogen storage materials. Using state-of-the-art density functional calculations, our research addresses the energetics

320

Theory of Hydrogen Storage in Complex Hydrides - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

53 53 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Christopher Wolverton Department of Materials Science & Engineering, Northwestern University 2220 Campus Drive, Room 2036 Evanston, IL 60208-3108 Phone: (734) 678-6319 Email: c-wolverton@northwestern.edu Vidvuds Ozolins Department of Materials Science & Engineering, University of California, Los Angeles DOE Program Officer: James Davenport Program Manager Theoretical Condensed Matter Physics Office of Basic Energy Sciences Email: James.Davenport@science.doe.gov Phone: (301) 903-0035 Objectives Using first-principles methods, determine the atomic- level processes that are rate limiting in hydrogen storage

Note: This page contains sample records for the topic "fuel dry 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

Groundwater monitoring results for the 100-K Area fuel storage basins: January 1 to March 31, 1994  

SciTech Connect

Fuel storage basins associated with the 105-KE and 105-KW reactor buildings are currently being used to store irradiated fuel rods from past operations. Each reactor building contains a basin that holds approximately 1.3 million gal of water. The water provides a radiation shield, as well as a thermal sink for heat generated by the stored fuel. Some of the fuel rods stored in the K-East basin have damaged cladding and are stored in open canisters, allowing contact between the metallic uranium fuel and basin water. The interaction results in radionuclides being released to the basin water. Various exchange columns and filters associated with a closed-circuit circulation system are in place to reduce radionuclide concentrations in basin water. Tritium cannot be removed by these methods and is present in K-East basin water at a concentration of several million pCi/L. In contrast, K-West basin, where only fully encapsulated, undamaged fuel is stored, exhibits tritium concentrations at much lower levels--several hundred thousand pCi/L. The water budget for the basins includes water losses resulting from evaporation and possibly leakage, and the addition of make-up water to maintain a specific level. Water loss calculations are based on water level decreases during time intervals when no make-up water is added. A calculated loss rate beyond what is expected due to evaporation and uncertainty in the calculations, is assumed to be leakage to the soil column. Given sufficiently high leakage rates, and/or a preferential pathway for downward migration through the soil column, basin water may contaminate groundwater flowing beneath the basins.

Peterson, R.E.

1994-08-29T23:59:59.000Z

322

New applications of high-temperature solar energy for the production of transportable fuels and chemicals and for energy storage  

DOE Green Energy (OSTI)

The solar fuels and chemicals study was limited to the examination of processes requiring temperatures in excess of 1000/sup 0/K since lower temperature processes had already been examined in studies concerned with the application of waste heat from nuclear power plants to industrial processes. In developing the carbon cycle processes, the primary activity included an extensive literature search and the thermodynamic evaluation of a number of candidate chemical cycles. Although both hydrogen and carbon closed- and open-loop chemical cycles were studied, it was concluded that the carbon cycles offered sufficient additional potential to warrant concentrating on them in subsequent work. The section on new ideas for transportable fuels presents the elements of a new concept for a carbon cycle recovery technique to produce transportable fuels. The elements discussed are sources of carbon dioxide, solar energy reduction of CO/sub 2/, potential carbon cycles, and use of carbon monoxide as fuel and feedstocks. Another section presents some new concepts for the use of high-temperature solar energy in the production of essential materials and for closed-loop chemical storage, as well as for the production of hydrogen as a fuel and open-loop applications. Potential problem areas pertinent to solar-derived fuels and chemicals have been identified. These problems are primarily associated with the limited high temperature experience in industry and include materials compatibility, separation of reaction products, development of solid electrolytes and high-temperature electrodes, selective emission of receiver coatings at high temperature, and a lack of chemical kinetics data, and high-temperature thermodynamic data.

Not Available

1979-01-19T23:59:59.000Z

323

Characterization and hydrogen storage of surface-modified multiwalled carbon nanotubes for fuel cell application  

Science Conference Proceedings (OSTI)

The synthesis, identification, and H2 storage of multiwalled carbon nanotubes (MWCNTs) have been investigated in the present work. MWCNTs were produced from the catalytic-assembly solvent (benzene)-thermal (solvothermal) route. Reduction of ...

Kuen-Song Lin, Yao-Jen Mai, Shin-Rung Li, Chia-Wei Shu, Chieh-Hung Wang

2012-01-01T23:59:59.000Z

324

Development of Design Basis Earthquake Parameters for TMI-2 Independent Spent Fuel Storage Installation at the INEEL  

SciTech Connect

Probabilistically-based Design Basis Earthquake (DBE) ground motion parameters have been developed for the TMI-2 Independent Spent Fuel Storage Installation (ISFSI) located at the Idaho Nuclear Technology and Engineering Center (INTEC), Idaho National Engineering and Environmental Laboratory. The probabilistic seismic hazard at INTEC has been recomputed using ground motion attenuation relationships more appropriate for extensional tectonic regimes. The empirical attenuation relationships used in this analysis were adjusted for extensional tectonic regimes as part of the Yucca Mountain Project. Seismic hazard curves and uniform hazard spectra for rock produced using the revised attenuation relationships result in lower ground motions when compared to the results of the 1996 INEEL site-wide seismic hazard evaluation. The DBE ground motions for rock and soil have been developed to be applicable to the TMI-2 ISFSI and the entire INTEC site by incorporating variations in the rock and soil properties over the INTEC area. The DBE rock and soil ground motions presented in the report are recommended for use in developing final design earthquake parameters. Peer reviewers of this report support this recommendation. Because the Nuclear Regulatory Commission regulations have recently evolved to incorporate probabilistically-based seismic design for independent fuel storage facilities, a deterministic Maximum Credible Earthquake analysis performed for INTEC earlier in this study is also presented in this report.

URS Greiner Woodward Clyde Federal Services; Geomatrix Consultants; Pacific Engineering and Analysis; S. M. Payne (INEEL POC)

1999-11-01T23:59:59.000Z

325

Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys | Department  

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

Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys Embrittlement and DBTT of High-Burnup PWR Fuel Cladding Alloys Structural analyses of high-burnup (HBU) fuel require cladding mechanical properties and failure limits to assess fuel behavior during long-term dry-cask storage and transportation. Pre-storage drying-transfer operations and early stage storage subject cladding to higher temperatures and pressure-induced tensile hoop stresses relative to in-reactor operation and pool storage. Under these conditions, radial hydrides may precipitate during slow cooling and provide an additional embrittlement mechanism as the cladding temperature decreases below the ductile-to-brittle transition temperature (DBTT). Graphic and photographic details of the testing are

326

Final LDRD report : nanoscale mechanisms in advanced aging of materials during storage of spent %22high burnup%22 nuclear fuel.  

Science Conference Proceedings (OSTI)

We present the results of a three-year LDRD project focused on understanding microstructural evolution and related property changes in Zr-based nuclear cladding materials towards the development of high fidelity predictive simulations for long term dry storage. Experiments and modeling efforts have focused on the effects of hydride formation and accumulation of irradiation defects. Key results include: determination of the influence of composition and defect structures on hydride formation; measurement of the electrochemical property differences between hydride and parent material for understanding and predicting corrosion resistance; in situ environmental transmission electron microscope observation of hydride formation; development of a predictive simulation for mechanical property changes as a function of irradiation dose; novel test method development for microtensile testing of ionirradiated material to simulate the effect of neutron irradiation on mechanical properties; and successful demonstration of an Idaho National Labs-based sample preparation and shipping method for subsequent Sandia-based analysis of post-reactor cladding.

Clark, Blythe G.; Rajasekhara, Shreyas; Enos, David George; Dingreville, Remi Philippe Michel; Doyle, Barney Lee; Hattar, Khalid Mikhiel; Weiner, Ruth F.

2013-09-01T23:59:59.000Z

327

On selection and operation of an international interim storage facility for spent nuclear fuel  

E-Print Network (OSTI)

Disposal of post-irradiation fuel from nuclear reactors has been an issue for the nuclear industry for many years. Most countries currently have no long-term disposal strategy in place. Therefore, the concept of an ...

Burns, Joe, 1966-

2004-01-01T23:59:59.000Z

328

Away-from-reactor storage of spent nuclear fuel: factors affecting demand  

SciTech Connect

This report analyzes factors that affect the magnitude and timing of demand for government AFRs, relative to the demand for other storage options, to assist policymakers in predicting this demand. Past predictions of AFT demand range widely and often appear to conflict. This report helps to explain the apparent conflicts among existing demand predictions by demonstrating their sensitivity to changes in key assumptions. Specifically, the report analyzes factors affecting the demand for government AFR storage facilities; illustrates why demand estimates may vary; and identifies actions that may be undertaken by groups, within and outside the government, to influence the level and timing of demands.

Dinneen, P.M.; Solomon, K.A.; Triplett, M.B.

1980-10-01T23:59:59.000Z

329

SNFP detonation phenomena of hydrogen/oxygen in spent fuel containers  

DOE Green Energy (OSTI)

Movement of spent nuclear fuels from the Hanford K Basins near the Columbia River to dry interim storage facility on the Hanford plateau will require repackaging the fuel in the basin into multi-canister overpacks (MCOs), drying of the fuel, transporting the contained fuel, hot conditioning, and finally interim storage. Each of these functions will be accomplished while the fuel is contained in the MCOs. Hydrogen and oxygen can be generated within the MCOs by several mechanisms. The principal source of hydrogen and oxygen within the MCOs is residual water from the vacuum drying and hot conditioning operations. This document assesses the detonation phenomena of hydrogen and oxygen in the spent fuel containers. Several process scenarios have been identified that could generate detonation pressures that exceed the nominal 10 atmosphere design limit of the MCOs. Only 42 grams of radiolized water are required to establish this condition.

Cooper, T.D.

1996-05-30T23:59:59.000Z

330

Lightweight Metal Hydrides for Hydrogen Storage - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Ji-Cheng Zhao (Primary Contact), Xuenian Chen, Sheldon G. Shore The Ohio State University, Department of Materials Science and Engineering, 286 Watts Hall, 2041 College Road Columbus, OH 43210 Phone: (614) 292-9462 Email: zhao.199@osu.edu DOE Managers HQ: Ned Stetson Phone: (202) 586-9995 Email: Ned.Stetson@ee.doe.gov GO: Katie Randolph Phone: (720) 356-1759 Email: Katie.Randolph@go.doe.gov Contract Number: DE-FC3605GO15062 Project Start Date: January 1, 2005 Project End Date: August 31, 2011 (No-cost extension to December 31, 2012) Fiscal Year (FY) 2012 Objectives Develop a high-capacity lightweight hydride for * reversible vehicular hydrogen storage, capable of meeting or exceeding the 2010 DOE FreedomCAR

331

Energy Storage in Clathrate Hydrogen Material - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

9 9 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Carolyn A. Koh (Primary Contact), Amadeu K. Sum, R. Gary Grim, Matthew R. Walsh, Prasad B. Kerkar Center for Hydrate Research Colorado School of Mines 1600 Illinois Street Golden, CO 80401 Phone: (303) 273-3237 Email: ckoh@mines.edu DOE Program Officer: Bonnie Gersten Phone: (303) 903-0002 Email: Bonnie.Gersten@science.doe.gov Objectives The current project aims to probe key questions surrounding the metastability of hydrates relating to synthesis, structure, and composition. The questions on metastability are crucial in all energy applications of clathrate hydrates including energy storage, energy transportation, and energy recovery. Specifically, this project

332

Spent N fuel project preliminary saftey evaluation of the cold vacuum drying system -- calculations for the flammable gas ignition scenario  

DOE Green Energy (OSTI)

For a preliminary safety evaluation of the Cold Vacuum Drying System, calculations for the flammable gas ignition scenario are provided. Hydrogen buildup from uranium corrosion in the MCO followed by inadvertent injection of oxygen and the presence of an ignition source leads to hydrogen deflagration that over pressurizes and releases radioactive particulate matter to the environment. The adiabatic flame temperature, MCO pressure and source term are calculated.

Scott, D.L.

1996-06-12T23:59:59.000Z

333

REACTOR FUEL WASTE DISPOSAL PROJECT PRESSURE-TEMPERATURE EFFECT ON SALT CAVITIES AND SURVEY OF LIQUEFIED PETROLEUM GAS STORAGE  

SciTech Connect

It is deemed feasible to store reactor fuel wastes in a salt dome cavity to a depth where the differential in pressure between the soil over-burden pressure and pressure of the fluid inside the cavity does not exceed 3000 psi, and the temperature is less than 400 deg F. Tests at pressure increments of 1000 psi were conducted on a 2" cylindrical cavity contained in a 6-in. long by 6-in. cylindrical salt core. Tests indicate that the cavity exhibited complete stability under pressures to 3000 psi and temperatures to 300 deg F. At temperatures of 100 to 400 deg F and pressures to 5000 psi continuous deformation of the cavity resulted. Initial movement of the salt was observed at all pressures. This was evidenced by vertical deformation and cavity size reduction. It was noted that a point of structural equilibrium was reached at lower temperatures when the pressure did not exceed 5000 psi. A literature study reveals that the most common type of cavity utilized in liquefied petroleum gas storage is either cylindrical or ellipsoidal. A few are pear or inverted cone shaped. There was no indication of leakage for cavities when pressure tested for as long as 72 hr. This indicates that the salt mass is not permeable under conditions of prevailing underground temperature and pressure. Salt specimens tested under atmospheric Pressure and temperature exhibited permeabilities of 0.1 to 0.2 millidarcys. The cost of completing underground storage cavities in salt masses is expected to be approximately 05 per barrel of storage space. (auth)

Brown, K.E.; Jessen, F.W.; Gloyna, E.F.

1959-01-15T23:59:59.000Z

334

Experimental investigation of burnup credit for safe transport, storage, and disposal of spent nuclear fuel.  

SciTech Connect

This report describes criticality benchmark experiments containing rhodium that were conducted as part of a Department of Energy Nuclear Energy Research Initiative project. Rhodium is an important fission product absorber. A capability to perform critical experiments with low-enriched uranium fuel was established as part of the project. Ten critical experiments, some containing rhodium and others without, were conducted. The experiments were performed in such a way that the effects of the rhodium could be accurately isolated. The use of the experimental results to test neutronics codes is demonstrated by example for two Monte Carlo codes. These comparisons indicate that the codes predict the behavior of the rhodium in the critical systems within the experimental uncertainties. The results from this project, coupled with the results of follow-on experiments that investigate other fission products, can be used to quantify and reduce the conservatism of spent nuclear fuel safety analyses while still providing the necessary level of safety.

Berry, Donald T.; Harms, Gary A.; Ford, John T.; Walker, Sharon Ann; Helmick, Paul H.; Pickard, Paul S.

2004-04-01T23:59:59.000Z

335

U.S. Army Energy and Environmental Requirements and Goals: Opportunities for Fuel Cells and Hydrogen - Facility Locations and Hydrogen Storage/Delivery Logistics  

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

US Army Corps US Army Corps of Engineers ¬ģ Engineer Research and Development Center U.S. Army Energy and Environmental Requirements and Goals: Opportunities for Fuel Cells and Hydrogen Facility Locations and Hydrogen Storage/Delivery Logistics Nicholas M. Josefik 217-373-4436 N-josefik@cecer.army.mil www.dodfuelcell.com Franklin H. Holcomb Project Leader, Fuel Cell Team 27 OCT 08 Distributed Generation H 2 Generation & Storage Material Handling H2 Vehicles 2 US Army Corps of Engineers ¬ģ Engineer Research and Development Center Presentation Outline * DoD Energy Use * Federal Facilities Goals and Requirements * Federal Vehicles and Fuel Goals * Opportunities & Conclusions 3 US Army Corps of Engineers ¬ģ Engineer Research and Development Center Where Does the Energy Go? * Tactical and Combat Vehicles (Jets,

336

Fuel Cell Powered Vehicles Using Supercapacitors: Device Characteristics, Control Strategies, and Simulation Results  

E-Print Network (OSTI)

Direct hydrogen fuel cell vehicles without energy storage.hydrogen fuel cell vehicles (FCVs) without energy storage (hydrogen fuel cell vehicles (FCVs) without energy storage

Zhao, Hengbing; Burke, Andy

2010-01-01T23:59:59.000Z

337

Alternatives for the disposition of fuel stored in the PUREX facility  

SciTech Connect

This document provides an evaluation of five alternatives for the disposition of 3.4 metric tons of irradiated fuel from PUREX to support facility turnover following deactivation. The alternatives for disposition of the fuel include transfer to the K Basins, transfer to T Plant, passivation and dry vault storage, and dissolution and underground tank storage. The five alternatives were compared and it was determined that the fuel should be transferred from PUREX to the K Basins where it would be placed into pool storage.

Enghusen, M.B.; Gore, D.B.

1995-01-01T23:59:59.000Z

338

Spent fuel pool storage calculations using the ISOCRIT burnup credit tool  

Science Conference Proceedings (OSTI)

In order to conservatively apply burnup credit in spent fuel pool criticality safety analyses, Westinghouse has developed a software tool, ISOCRIT, for generating depletion isotopics. This tool is used to create isotopics data based on specific reactor input parameters, such as design basis assembly type; bounding power/burnup profiles; reactor specific moderator temperature profiles; pellet percent theoretical density; burnable absorbers, axial blanket regions, and bounding ppm boron concentration. ISOCRIT generates burnup dependent isotopics using PARAGON; Westinghouse's state-of-the-art and licensed lattice physics code. Generation of isotopics and passing the data to the subsequent 3D KENO calculations are performed in an automated fashion, thus reducing the chance for human error. Furthermore, ISOCRIT provides the means for responding to any customer request regarding re-analysis due to changed parameters (e.g., power uprate, exit temperature changes, etc.) with a quick turnaround.

Kucukboyaci, Vefa [Westinghouse Electric Company, Cranberry Township, PA; Marshall, William BJ J [ORNL

2012-01-01T23:59:59.000Z

339

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

340

State of Washington Department of Health Radioactive air emissions notice of construction phase 1 for spent nuclear fuel project - cold vacuum drying facility, project W-441  

SciTech Connect

This notice of construction (NOC) provides information regarding the source and the estimated annual possession quantity resulting from operation of the Cold Vacuum Drying Facility (CVDF). Additional details on emissions generated by the operation of the CVDF will be discussed again in the Phase 11 NOC. This document serves as a NOC pursuant to the requirements of WAC 246-247-060 for the completion of Phase I NOC, defined as the pouring of concrete for the foundation flooring, construction of external walls, and construction of the building excluding the installation of CVDF process equipment. A Phase 11 NOC will be submitted for approval prior to installing and is defined as the completion of the CVDF, which consisted installation of process equipment, air emissions control, and emission monitoring equipment. About 80 percent of the U.S. Department of Energy`s spent nuclear fuel (SNF) inventory is stored under water in the Hanford Site K Basins. Spent nuclear fuel in the K West Basin is contained in closed canisters while the SNF in the K East Basin is in open canisters, which allow free release of corrosion products to the K East Basin water.

Turnbaugh, J.E.

1996-08-15T23:59:59.000Z

Note: This page contains sample records for the topic "fuel dry 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

Unique challenges for storage and disposal of DOE-owned SNF at the INEEL  

SciTech Connect

Non-commercial Spent Nuclear Fuel (SNF) owned by the Department of Energy presents some unique challenges for interim storage as well as ultimate disposal in a repository. There is an important link between Yucca Mountain Repository work and the future needs of the DOE SNF program. Close coordination and early definition of acceptance criteria are essential. Much of the Yucca Mountain Repository work has focused on commercial SNF which has very high structural integrity and a well documented set of characteristics and burn-up histories. In contrast, DOE non-commercial SNF at the Idaho National Environmental and Engineering Laboratory (INEEL) represents over two hundred fifty fuel types, much of which is degraded. Fuel designs by DOE were centered around various test objectives in experimental reactors. The result was a proliferation of fuel types. Interest in enhanced heat transfer led to use of sodium as a bond between the fuel and cladding. The desire for smaller more compact reactors with higher power densities led to a variety of enrichments from less than 20% to greater than 90%. INEEL has most of the US U-233 spent nuclear fuel, which came from breeder reactor concepts and consideration of a thorium fuel cycle. These various fuel types now must be placed in safe, stable interim dry storage. Emphasis is being placed on the use of commercially available dry storage designs and independent spent fuel storage installations licensed under NRC criteria. A lot of technological development is being done to characterize fuels that do not have the documented fabrication and operational histories of commercial LWR fuels. Program objectives are safe interim storage and least cost transition to geological repository storage.

Mathews, T.A.

1998-03-01T23:59:59.000Z

342

Hydrogen storage via metal hydrides for utility and automotive energy storage applications. [HCl electrolysis for H/sub 2/--Cl/sub 2/ fuel cells  

DOE Green Energy (OSTI)

Brookhaven National Laboratory is currently supported by ERDA to develop the technology and techniques for storing hydrogen via metal hydrides. Hydrogen is able to react with a wide variety of metal and metal alloy materials to form hydride compounds of hydrogen and metals. These compounds differ in stability--some are relatively unstable and can be readily formed and decomposed at low temperatures. The use of these systems for hydrogen storage involves the design of heat exchanger and mass transfer systems, i.e., removal of heat during the charging reaction and addition of heat during the discharge reaction. The most notable example of a metal hydride material is iron titanium which shows promise of being economical for a number of near term hydrogen storage applications. Recent work and progress on the development of metal hydrides for hydrogen storage connected with utility energy storage applications and natural gas supplementation are discussed and electric-to-electric storage system is described in some detail. A system of energy storage involving the electrolysis of hydrochloric acid is described which would utilize metal hydrides to store the hydrogen. In addition, the use of metal hydrides for hydrogen storage in automotive systems is described.

Salzano, F J; Braun, C; Beaufrere, A; Srinivasan, S; Strickland, G; Reilly, J J; Waide, C

1976-08-01T23:59:59.000Z

343

Portable instrument for inspecting irradiated nuclear-fuel assemblies in a water-filled storage pond by measurement of induced Cerenkov radiation  

DOE Patents (OSTI)

A portable instrument for measuring induced Cerenkov radiation associated with irradiated nuclear fuel assemblies in a water-filled storage pond is disclosed. The instrument includes a photomultiplier tube and an image intensifier which are operable in parallel and simultaneously by means of a field lens assembly and an associated beam splitter. The image intensifier permits an operator to aim and focus the apparatus on a submerged fuel assembly. Once the instrument is aimed and focused, an illumination reading can be obtained with the photomultiplier tube. The instrument includes a lens cap with a carbon-14/phosphor light source for calibrating the apparatus in the field.

Nicholson, N.; Dowdy, E.J.; Holt, D.M.; Stump, C.J. Jr.

1982-05-13T23:59:59.000Z

344

Fuel Chemistry Preprints  

Science Conference Proceedings (OSTI)

Papers are presented under the following symposia titles: advances in fuel cell research; biorefineries - renewable fuels and chemicals; chemistry of fuels and emerging fuel technologies; fuel processing for hydrogen production; membranes for energy and fuel applications; new progress in C1 chemistry; research challenges for the hydrogen economy, hydrogen storage; SciMix fuel chemistry; and ultraclean transportation fuels.

NONE

2005-09-30T23:59:59.000Z

345

Maine Yankee: Making the Transition from an Operating Plant to an Independent Spent Fuel Storage Installation (ISFSI)  

Science Conference Proceedings (OSTI)

The purpose of this paper is to describe the challenges faced by Maine Yankee Atomic Power Company in making the transition from an operating nuclear power plant to an Independent Spent Fuel Storage Installation (ISFSI). Maine Yankee (MY) is a 900-megawatt Combustion Engineering pressurized water reactor whose architect engineer was Stone & Webster. Maine Yankee was put into commercial operation on December 28, 1972. It is located on an 820-acre site, on the shores of the Back River in Wiscasset, Maine about 40 miles northeast of Portland, Maine. During its operating life, it generated about 1.2 billion kilowatts of power, providing 25% of Maine's electric power needs and serving additional customers in New England. Maine Yankee's lifetime capacity factor was about 67% and it employed more than 450 people. The decision was made to shutdown Maine Yankee in August of 1997, based on economic reasons. Once this decision was made planning began on how to accomplish safe and cost effective decommissioning of the plant by 2004 while being responsive to the community and employees.

Norton, W.; McGough, M. S.

2002-02-26T23:59:59.000Z

346

Corrective Action Plan for Corrective Action Unit 321: Area 22 Weather Station Fuel Storage Nevada Test Site, Nevada  

Science Conference Proceedings (OSTI)

The purpose of this Corrective Action Plan (CAP) is to provide the strategy and methodology to close the Area 22 Weather Station Fuel Storage. The CAU will be closed following state and federal regulations and the FFACO (1996). Site characterization was done during February 1999. Soil samples were collected using a direct-push method. Soil samples were collected at 0.6-m (2-ft) intervals from the surface to 1.8 m (6 ft) below ground surface. The results of the characterization were reported in the Corrective Action Decision Document (CADD) (DOE, 1999b). Soil sample results indicated that two locations in the bermed area contain total petroleum hydrocarbons (TPH) as diesel at concentrations of 124 milligrams per kilogram (mg/kg) and 377 mg/kg. This exceeds the Nevada Division of Environmental Protection (NDEP) regulatory action level for TPH of 100 mg/kg (Nevada Administrative Code, 1996). The TPH-impacted soil will be removed and disposed as part of the corrective action.

D. S. Tobiason

2000-06-01T23:59:59.000Z

347

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...

348

EM Safely and Efficiently Manages Spent Nuclear Fuel | Department of Energy  

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

Services ¬Ľ Waste Management ¬Ľ Nuclear Materials & Waste ¬Ľ EM Services ¬Ľ Waste Management ¬Ľ Nuclear Materials & Waste ¬Ľ EM Safely and Efficiently Manages Spent Nuclear Fuel EM Safely and Efficiently Manages Spent Nuclear Fuel Dry storage casks at Idaho National Laboratory can safely house spent nuclear fuel for decades. Dry storage casks at Idaho National Laboratory can safely house spent nuclear fuel for decades. EM's mission is to safely and efficiently manage its spent nuclear fuel and prepare it for disposal in a geologic repository. Previously, the Office of Environmental Management's (EM) mission had included the safe and efficient management of its spent nuclear fuel (SNF) and preparation for its disposal in a geologic repository. However, in May 2009, the planned geologic repository at Yucca Mountain was cancelled. The

349

Encapsulation of Mg-Zr Fuel Cladding in Geopolymer Material  

Science Conference Proceedings (OSTI)

Symposium, Materials Science of Nuclear Waste Management ... Mg-Zr. Strategy could be to encapsulate these wastes into a geopolymer in a form suitable ... Delayed Hydride Cracking Susceptibility of Spent Fuel Rods in Dry Storage ... Isolation of Matrices for High-Level Radioactive Waste Using Metal Coatings Prepared†...

350

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

351

Spent Nuclear Fuel project stage and store K basin SNF in canister storage building functions and requirements. Revision 1  

SciTech Connect

This document establishes the functions and requirements baseline for the implementation of the Canister Storage Building Subproject. The mission allocated to the Canister Storage Building Subproject is to provide safe, environmentally sound staging and storage of K Basin SNF until a decision on the final disposition is reached and implemented

Womack, J.C.

1995-10-24T23:59:59.000Z

352

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 optionís 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. Argonís 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, ďSilo Storage Concepts, Cathodic Protection Options StudyĒ (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

353

TECHNOLOGY DEVELOPMENT AND DEPLOYMENT OF SYSTEMS FOR THE RETRIEVAL AND PROCESSING OF REMOTE-HANDLED SLUDGE FROM HANFORD K-WEST FUEL STORAGE BASIN  

SciTech Connect

In 2011, significant progress was made in developing and deploying technologies to remove, transport, and interim store remote-handled sludge from the 105-K West Fuel Storage Basin on the Hanford Site in south-central Washington State. The sludge in the 105-K West Basin is an accumulation of degraded spent nuclear fuel and other debris that collected during long-term underwater storage of the spent fuel. In 2010, an innovative, remotely operated retrieval system was used to successfully retrieve over 99.7% of the radioactive sludge from 10 submerged temporary storage containers in the K West Basin. In 2011, a full-scale prototype facility was completed for use in technology development, design qualification testing, and operator training on systems used to retrieve, transport, and store highly radioactive K Basin sludge. In this facility, three separate systems for characterizing, retrieving, pretreating, and processing remote-handled sludge were developed. Two of these systems were successfully deployed in 2011. One of these systems was used to pretreat knockout pot sludge as part of the 105-K West Basin cleanup. Knockout pot sludge contains pieces of degraded uranium fuel ranging in size from 600 {mu}m to 6350 {mu}m mixed with pieces of inert material, such as aluminum wire and graphite, in the same size range. The 2011 pretreatment campaign successfully removed most of the inert material from the sludge stream and significantly reduced the remaining volume of knockout pot product material. Removing the inert material significantly minimized the waste stream and reduced costs by reducing the number of transportation and storage containers. Removing the inert material also improved worker safety by reducing the number of remote-handled shipments. Also in 2011, technology development and final design were completed on the system to remove knockout pot material from the basin and transport the material to an onsite facility for interim storage. This system is scheduled for deployment in 2012. The prototype facility also was used to develop technology for systems to retrieve remote-handled transuranic sludge smaller than 6350 {mu}m being stored in underwater containers. After retrieving the sludge, the system will be used to load and transport the sludge for interim storage. During 2011, full-scale prototype systems were developed and tested to a Technology Readiness Level 6 as defined by U.S. Department of Energy standards. This system is scheduled for deployment in 2013. Operations also are scheduled for completion in 2014.

RAYMOND RE

2011-12-27T23:59:59.000Z

354

Spent Fuel Working Group report on inventory and storage of the Department`s spent nuclear fuel and other reactor irradiated nuclear materials and their environmental, safety and health vulnerabilities. Volume 3, Site team reports  

Science Conference Proceedings (OSTI)

A self assessment was conducted of those Hanford facilities that are utilized to store Reactor Irradiated Nuclear Material, (RINM). The objective of the assessment is to identify the Hanford inventories of RINM and the ES & H concerns associated with such storage. The assessment was performed as proscribed by the Project Plan issued by the DOE Spent Fuel Working Group. The Project Plan is the plan of execution intended to complete the Secretary`s request for information relevant to the inventories and vulnerabilities of DOE storage of spent nuclear fuel. The Hanford RINM inventory, the facilities involved and the nature of the fuel stored are summarized. This table succinctly reveals the variety of the Hanford facilities involved, the variety of the types of RINM involved, and the wide range of the quantities of material involved in Hanford`s RINM storage circumstances. ES & H concerns are defined as those circumstances that have the potential, now or in the future, to lead to a criticality event, to a worker radiation exposure event, to an environmental release event, or to public announcements of such circumstances and the sensationalized reporting of the inherent risks.

Not Available

1993-11-01T23:59:59.000Z

355

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

356

Technical strategy for the management of INEEL spent nuclear fuel  

SciTech Connect

This report presents evaluations, findings, and recommendations of the Idaho National Engineering and Environmental Laboratory (INEEL) Spent Nuclear Fuel Task Team. The technical strategy developed by the Task Team includes stabilization, near term storage, packaging, transport, and ultimate disposal. Key issues identified and discussed include waste characterization, criticality, packaging, waste form performance, and special fuels. Current plans focus on onsite needs, and include three central elements: (1) resolution of near-term vulnerabilities, (2) consolidation of storage locations, and (3) achieving dry storage in transportable packages. In addition to the Task Team report, appendices contain information on the INEEL spent fuel inventory; regulatory decisions and agreements; and analyses of criticality, packaging, storage, transportation, and system performance of a geological repository. 16 refs., 6 figs., 4 tabs.

1997-03-01T23:59:59.000Z

357

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

358

Large Scale U.S. Unconventional Fuels Production and the Role of Carbon Dioxide Capture and Storage Technologies in Reducing Their Greenhouse Gas Emissions  

Science Conference Proceedings (OSTI)

This paper examines the role that carbon dioxide capture and storage technologies could play in reducing greenhouse gas emissions if a significant unconventional fuels industry were to develop within the United States. Specifically, the paper examines the potential emergence of a large scale domestic unconventional fuels industry based on oil shale and coal-to-liquids (CTL) technologies. For both of these domestic heavy hydrocarbon resources, this paper models the growth of domestic production to a capacity of 3 MMB/d by 2050. For the oil shale production case, we model large scale deployment of an in-situ retorting process applied to the Eocene Green River formation of Colorado, Utah, and Wyoming where approximately 75% of the high grade oil shale resources within the United States lies. For the CTL case, we examine a more geographically dispersed coal-based unconventional fuel industry. This paper examines the performance of these industries under two hypothetical climate policies and concludes that even with the wide scale availability of cost effective carbon dioxide capture and storage technologies, these unconventional fuels production industries would be responsible for significant increases in CO2 emissions to the atmosphere. The oil shale production facilities required to produce 3MMB/d would result in net emissions to the atmosphere of between 3000-7000 MtCO2 in addition to storing potentially 1000 to 5000 MtCO2 in regional deep geologic formations in the period up to 2050. A similarly sized domestic CTL industry could result in 4000 to 5000 MtCO2 emitted to the atmosphere in addition to potentially 21,000 to 22,000 MtCO2 stored in regional deep geologic formations over the same period up to 2050. Preliminary analysis of regional CO2 storage capacity in locations where such facilities might be sited indicates that there appears to be sufficient storage capacity, primarily in deep saline formations, to accommodate the CO2 from these industries. However, additional analyses plus detailed regional and site characterization is needed, along with a closer examination of competing storage demands.

Dooley, James J.; Dahowski, Robert T.

2008-11-18T23:59:59.000Z

359

Fuels  

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

Goals > Fuels Goals > Fuels XMAT for nuclear fuels XMAT is ideally suited to explore all of the radiation processes experienced by nuclear fuels.The high energy, heavy ion accleration capability (e.g., 250 MeV U) can produce bulk damage deep in the sample, achieving neutron type depths (~10 microns), beyond the range of surface sputtering effects. The APS X-rays are well matched to the ion beams, and are able to probe individual grains at similar penetrations depths. Damage rates to 25 displacements per atom per hour (DPA/hr), and doses >2500 DPA can be achieved. MORE¬Ľ Fuels in LWRs are subjected to ~1 DPA per day High burn-up fuel can experience >2000 DPA. Traditional reactor tests by neutron irradiation require 3 years in a reactor and 1 year cool down. Conventional accelerators (>1 MeV/ion) are limited to <200-400 DPAs, and

360

ERS 14.3 Underground and Above Ground Diesel Fuel Storage Tanks FPS 12.1, 1/9/01  

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

The objective of this surveillance is to verify underground and above ground diesel storage tanks are maintained, monitored, configured and marked as required.† These surveillance activities...

Note: This page contains sample records for the topic "fuel dry 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

ERS 14.3 Underground and Above Ground Diesel Fuel Storage Tanks FPS 12.1, 1/9/01  

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

†The objective of this surveillance is to verify underground and above ground diesel storage tanks are maintained, monitored, configured and marked as required.† These surveillance activities...

362

Spent Fuel Background Report Volume I  

Science Conference Proceedings (OSTI)

This report is an overview of current spent nuclear fuel management in the DOE complex. Sources of information include published literature, internal DOE documents, interviews with site personnel, and information provided by individual sites. Much of the specific information on facilities and fuels was provided by the DOE sites in response to the questionnaire for data for spent fuels and facilities data bases. This information is as accurate as is currently available, but is subject to revision pending results of further data calls. Spent fuel is broadly classified into three categories: (a) production fuels, (b) special fuels, and (c) naval fuels. Production fuels, comprising about 80% of the total inventory, are those used at Hanford and Savannah River to produce nuclear materials for defense. Special fuels are those used in a wide variety of research, development, and testing activities. Special fuels include fuel from DOE and commercial reactors used in research activities at DOE sites. Naval fuels are those developed and used for nuclear-powered naval vessels and for related research and development. Given the recent DOE decision to curtail reprocessing, the topic of main concern in the management of spent fuel is its storage. Of the DOE sites that have spent nuclear fuel, the vast majority is located at three sites-Hanford, INEL, and Savannah River. Other sites with spent fuel include Oak Ridge, West Valley, Brookhaven, Argonne, Los Alamos, and Sandia. B&W NESI Lynchburg Technology Center and General Atomics are commercial facilities with DOE fuel. DOE may also receive fuel from foreign research reactors, university reactors, and other commercial and government research reactors. Most DOE spent fuel is stored in water-filled pools at the reactor facilities. Currently an engineering study is being performed to determine the feasibility of using dry storage for DOE-owned spent fuel currently stored at various facilities. Delays in opening the deep geologic repository and the decision to phase out reprocessing of production fuels are extending the need for interim storage. The report describes the basic storage conditions and the general SNF inventory at individual DOE facilities.

Abbott, D.

1994-03-01T23:59:59.000Z

363

Spent Fuel Background Report Volume II  

Science Conference Proceedings (OSTI)

This Volume II contains tables that describe DOE fuel storage facilities and the fuel contained in those facilities.

Abbott, D.

1994-03-01T23:59:59.000Z

364

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

365

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

366

Nuclear Waste Imaging and Spent Fuel Verification by Muon Tomography  

E-Print Network (OSTI)

This paper explores the use of cosmic ray muons to image the contents of shielded containers and detect high-Z special nuclear materials inside them. Cosmic ray muons are a naturally occurring form of radiation, are highly penetrating and exhibit large scattering angles on high Z materials. Specifically, we investigated how radiographic and tomographic techniques can be effective for non-invasive nuclear waste characterization and for nuclear material accountancy of spent fuel inside dry storage containers. We show that the tracking of individual muons, as they enter and exit a structure, can potentially improve the accuracy and availability of data on nuclear waste and the contents of Dry Storage Containers (DSC) used for spent fuel storage at CANDU plants. This could be achieved in near real time, with the potential for unattended and remotely monitored operations. We show that the expected sensitivity, in the case of the DSC, exceeds the IAEA detection target for nuclear material accountancy.

Jonkmans, G; Jewett, C; Thompson, M

2012-01-01T23:59:59.000Z

367

Multiply Surface-Functionalized Nanoporous Carbon for Vehicular Hydrogen Storage - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

2 2 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report P. Pfeifer (Primary Contact), C. Wexler, P. Yu, G. Suppes, F. Hawthorne, S. Jalisatgi, M. Lee, D. Robertson University of Missouri 223 Physics Building Columbia, MO 65211 Phone: (573) 882-2335 Email: pfeiferp@missouri.edu DOE Managers HQ: Ned Stetson Phone: (202) 586-9995 Email: Ned.Stetson@ee.doe.gov GO: Jesse Adams Phone: (720) 356-1421 Email: Jesse.Adams@go.doe.gov Contract Number: DE-FG36-08GO18142 Subcontractors: Midwest Research Institute, Kansas City, MO Project Start Date: September 1, 2008 Project End Date: November 30, 2013 Fiscal Year (FY) 2012 Objectives Fabricate high-surface-area, multiply surface- * functionalized carbon ("substituted materials") for reversible hydrogen storage with superior storage

368

Microscale Enhancement of Heat and Mass Transfer for Hydrogen Energy Storage - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

6 6 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Kevin Drost (Primary Contact), Goran Jovanovic, Vinod Narayanan, Brian Paul School of Mechanical, Industrial and Manufacturing Engineering Rogers Hall Oregon State University (OSU) Corvallis, OR 97331 Phone: (541) 713-1344 Email: Kevin.Drost@oregonstate.edu DOE Managers HQ: Ned Stetson Phone: (202) 586-9995 Email: Ned.Stetson@ee.doe.gov GO: Jesse Adams Phone: (720) 356-1421 Email: Jesse.Adams@go.doe.gov Contract Number: DE-FC36-09GO19005 Project Start Date: February 1, 2009 Project End Date: June 30, 2014 Fiscal Year (FY) 2012 Objectives Use microchannel processing techniques to: Demonstrate reduction in size and weight of hydrogen * storage systems. Improve charge/and discharge rates of hydrogen storage *

369

Advancement of Systems Designs and Key Engineering Technologies for Materials-Based Hydrogen Storage - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

0 0 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Bart van Hassel (Primary Contact), Jose Miguel Pasini, Andi Limarga, John Holowczak, Igor Fedchenia, John Khalil, Reddy Karra, Ron Brown, Randy McGee United Technologies Research Center (UTRC) 411 Silver Lane East Hartford, CT 06108 Phone: (860) 610-7701 Email: vanhasba@utrc.utc.com DOE Managers HQ: Ned Stetson Phone: (202) 586-9995 Email: Ned.Stetson@ee.doe.gov GO: Jesse Adams Phone: (720) 356-1421 Email: Jesse.Adams@go.doe.gov Contract Number: DE-FC36-09GO19006 Project Start Date: February 1, 2009 Project End Date: June 30, 2014 Fiscal Year (FY) 2012 Objectives Collaborate closely with the Hydrogen Storage * Engineering Center of Excellence (HSECoE) partners to advance materials-based hydrogen storage system

370

MANAGING SPENT NUCLEAR FUEL WASTES AT THE IDAHO NATIONAL LABORATORY  

SciTech Connect

The Idaho National Engineering Laboratory (INL) has a large inventory of diverse types of spent nuclear fuel (SNF). This legacy is in part due to the history of the INL as the National Reactor Testing Station, in part to its mission to recover highly enriched uranium from SNF and in part to itís mission to test and examine SNF after irradiation. The INL also has a large diversity of SNF storage facility, some dating back 50 years in the site history. The success of the INL SNF program is measured by its ability to: 1) achieve safe existing storage, 2) continue to receive SNF from other locations, both foreign and domestic, 3) repackage SNF from wet storage to interim dry storage, and 4) prepare the SNF for dispositioning in a federal repository. Because of the diversity in the SNF and the facilities at the INL, the INL is addressing almost very condition that may exist in the SNF world. Many of solutions developed by the INL are applicable to other SNF storage sites as they develop their management strategy. The SNF being managed by the INL are in a variety of conditions, from intact assemblies to individual rods or plates to powders, rubble, and metallurgical mounts. Some of the fuel has been in wet storage for over forty years. The fuel is stored bare, or in metal cans and either wet under water or dry in vaults, caissons or casks. Inspections have shown varying degrees of corrosion and degradation of the fuel and the storage cans. Some of the fuel has been recanned under water, and the conditions of the fuel inside the second or third can are unknown. The fuel has been stored in one of 10 different facilities: five wet pools and one casks storage pad, one vault, two generations of caisson facilities, and one modular Independent Spent Fuel Storage Installation (ISFSI). The wet pools range from forty years old to the most modern pool in the US Department of Energy (DOE) complex. The near-term objective is moving the fuel in the older wet storage facilities to interim dry storage facilities, thus permitting the shutdown and decommission of the older facilities. Two wet pool facilities, one at the Idaho Nuclear Technology and Engineering Center and the other at Test Area North, were targeted for initial SNF movements since these were some of the oldest at the INL. Because of the difference in the SNF materials different types of drying processes had to be developed. Passive drying, as is done with typical commercial SNF was not an option because on the condition of some of the fuel, the materials to be dried, and the low heat generation of some of the SNF. There were also size limitations in the existing facility. Active dry stations were designed to address the specific needs of the SNF and the facilities.

Hill, Thomas J

2005-09-01T23:59:59.000Z

371

Synthetic Design of New Metal-Organic Framework Materials for Hydrogen Storage - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

9 9 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Pingyun Feng (Primary Contact), Qipu Lin, Xiang Zhao Department of Chemistry University of California Riverside, CA 92521 Phone: (951) 827-2042 Email: pingyun.feng@ucr.edu DOE Program Officer: Dr. Michael Sennett Phone: (301) 903-6051 Email: Michael.Sennett@science.doe.gov Objectives Design and * synthesize new metal-organic framework materials using lightweight chemical elements to help improve gravimetric hydrogen storage capacity. Develop new synthetic strategies to generate novel * active binding sites on metal ions and ligands to enhance solid-gas interactions for increased uptake near ambient conditions.

372

Managing Spent Nuclear Fuel at the Idaho National Laboratory  

SciTech Connect

The Idaho National Laboratory (INL) has a large inventory of diverse types of spent nuclear fuel (SNF). This legacy derives from the history of the INL as the National Reactor Testing Station, and from its mission to recover HEU from SNF and to test and examine SNF after irradiation. The INL also has a large diversity of SNF storage facilities, some 50 years old. SNF at INL has many formsófrom intact assemblies down to metallurgical mounts, and some fuel has been wet stored for over 40 years. SNF is stored bare or in metal cans under water, or dry in vaults, caissons or casks. Inspection shows varying corrosion and degradation of the SNF and its storage cans. SNF has been stored in 10 different facilities: 5 pools, one cask storage pad, one vault, two generations of caisson facilities, and one modular Independent Spent Fuel Storage Installation (ISFSI). The pools range in age from 40 years old to the most modern in the US Department of Energy (DOE) complex. The near-term objective is to move SNF from older pools to interim dry storage, allowing shutdown and decommissioning of the older facilities. This move involves drying methods that are dependent on fuel type. The long-term objective is to have INL SNF in safe dry storage and ready to be shipped to the National Repository. The unique features of the INL SNF requires special treatments and packaging to meet the proposed repository acceptance criteria and SNF will be repackaged in standardized canisters for shipment and disposal in the National Repository. Disposal will use the standardized canisters that can be co-disposed with High Level Waste glass logs to limit the total fissile material in a repository waste package. The DOE standardized canister also simplifies the repository handling of the multitude of DOE SNF sizes and shapes.

Thomas Hill; Denzel L. Fillmore

2005-10-01T23:59:59.000Z

373

Energy Basics: Conventional Storage Water Heaters  

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

heater can range from 20 to hundreds of gallons. Conventional storage water heater fuel sources include natural gas, propane, fuel oil, and electricity. Natural gas and...

374

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

375

STORAGE, TRANSPORTATION AND DISPOSAL SYSTEM FOR USED NUCLEAR ...  

STORAGE, TRANSPORTATION AND DISPOSAL SYSTEM FOR USED NUCLEAR FUEL ASSEMBLIES United States Patent Application

376

Hydrogen, Fuel Cells, & Infrastructure - Program Areas - Energy...  

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

fuel cell Welcome> Program Areas> Program Areas Hydrogen, Fuel Cells & Infrastructure Production & Delivery | Storage | Fuel Cell R&D | Systems Integration & Analysis | Safety...

377

Fuel  

E-Print Network (OSTI)

heavy-water-moderated, light-water-moderated and liquid-metal cooled fast breeder reactors fueled with natural or low-enriched uranium and containing thorium mixed with the uranium or in separate target channels. U-232 decays with a 69-year half-life through 1.9-year half-life Th-228 to Tl-208, which emits a 2.6 MeV gamma ray upon decay. We find that pressurized light-water-reactors fueled with LEU-thorium fuel at high burnup (70 MWd/kg) produce U-233 with U-232 contamination levels of about 0.4 percent. At this contamination level, a 5 kg sphere of U-233 would produce a gammaray dose rate of 13 and 38 rem/hr at 1 meter one and ten years after chemical purification respectively. The associated plutonium contains 7.5 percent of the undesirable heat-generating 88-year half-life isotope Pu-238. However, just as it is possible to produce weapon-grade plutonium in low-burnup fuel, it is also practical to use heavy-water reactors to produce U-233 containing only a few ppm of U-232 if the thorium is segregated in ďtarget Ē channels and discharged a few times more frequently than the natural-uranium ďdriver Ē fuel. The dose rate from a 5-kg solid sphere of U-233 containing 5 ppm U-232 could be reduced by a further factor of 30, to about 2 mrem/hr, with a close-fitting lead sphere weighing about 100 kg. Thus the proliferation resistance of thorium fuel cycles depends very much upon how they are implemented. The original version of this manuscript was received by Science & Global Security on

Jungmin Kang A

2001-01-01T23:59:59.000Z

378

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

379

Technology and Manufacturing Readiness of Early Market Motive and Non-Motive Hydrogen Storage Technologies for Fuel Cell Applications  

SciTech Connect

PNNLís objective in this report is to provide DOE with a technology and manufacturing readiness assessment to identify hydrogen storage technologiesí maturity levels for early market motive and non-motive applications and to provide a path forward toward commercialization. PNNLís Technology Readiness Assessment (TRA) is based on a combination of Technology Readiness Level (TRL) and Manufacturing Readiness Level (MRL) designations that enable evaluation of hydrogen storage technologies in varying levels of development. This approach provides a logical methodology and roadmap to enable the identification of hydrogen storage technologies, their advantages/disadvantages, gaps and R&D needs on an unbiased and transparent scale that is easily communicated to interagency partners. The TRA report documents the process used to conduct the TRA, reports the TRL and MRL for each assessed technology and provides recommendations based on the findings.

Ronnebro, Ewa

2012-06-16T23:59:59.000Z

380

Spent fuel test project, Climax granitic stock, Nevada Test Site  

SciTech Connect

The Spent Fuel Test-Climax (SFT-C) is a test of dry geologic storage of spent nuclear reactor fuel. The SFT-C is located at a depth of 420 m in the Climax granitic stock at the Nevada Test Site. Eleven canisters of spent commercial PWR fuel assemblies are to be stored for 3 to 5 years. Additional heat is supplied by electrical heaters, and more than 800 channels of technical information are being recorded. The measurements include rock temperature, rock displacement and stress, joint motion, and monitoring of the ventilation air volume, temperature, and dewpoint.

Ramspott, L.D.

1980-10-24T23:59:59.000Z

Note: This page contains sample records for the topic "fuel dry 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

Fuel Cell Technologies Office: Reversible Fuel Cells Workshop  

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

of Reversible Fuel Cell Systems at Proton Energy, Mr. Everett Anderson, PROTON ON SITE Regenerative Fuel Cells for Energy Storage, Mr. Corky Mittelsteadt, Giner Electrochemical...

382

DOE Fuel Cell Technologies Office  

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

500 2007 2013 Cumulative Number of Patents Fuel Cells ProductionDelivery Storage * DOE funding has led to 40 commercial hydrogen and fuel cell technologies and 65 emerging...

383

Fuel Cell Technologies Office: Education  

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

& Local Governments For Early Adopters For Students & Educators Careers in Hydrogen & Fuel Cells Quick Links Hydrogen Production Hydrogen Delivery Hydrogen Storage Fuel Cells...

384

Interim report spent nuclear fuel retrieval system fuel handling development testing  

Science Conference Proceedings (OSTI)

Fuel handling development testing was performed in support of the Fuel Retrieval System (FRS) Sub-Project at the Hanford Site. The project will retrieve spent nuclear fuel, clean and remove fuel from canisters, repackage fuel into baskets, and load fuel into a multi-canister overpack (MCO) for vacuum drying and interim dry storage. The FRS is required to retrieve basin fuel canisters, clean fuel elements sufficiently of uranium corrosion products (or sludge), empty fuel from canisters, sort debris and scrap from whole elements, and repackage fuel in baskets in preparation for MCO loading. The purpose of fuel handling development testing was to examine the systems ability to accomplish mission activities, optimization of equipment layouts for initial process definition, identification of special needs/tools, verification of required design changes to support performance specification development, and validation of estimated activity times/throughput. The test program was set up to accomplish this purpose through cold development testing using simulated and prototype equipment; cold demonstration testing using vendor expertise and systems; and graphical computer modeling to confirm feasibility and throughput. To test the fuel handling process, a test mockup that represented the process table was fabricated and installed. The test mockup included a Schilling HV series manipulator that was prototypic of the Schilling Hydra manipulator. The process table mockup included the tipping station, sorting area, disassembly and inspection zones, fuel staging areas, and basket loading stations. The test results clearly indicate that the Schilling Hydra arm cannot effectively perform the fuel handling tasks required unless it is attached to some device that can impart vertical translation, azimuth rotation, and X-Y translation. Other test results indicate the importance of camera locations and capabilities, and of the jaw and end effector tool design. 5 refs., 35 figs., 3 tabs.

Ketner, G.L.; Meeuwsen, P.V.; Potter, J.D.; Smalley, J.T.; Baker, C.P.; Jaquish, W.R.

1997-06-01T23:59:59.000Z

385

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

386

NREL: Continuum Magazine - Hydrogen: A Promising Fuel and Energy...  

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

Hydrogen: A Promising Fuel and Energy Storage Solution Issue 4 Print Version Share this resource Hydrogen: A Promising Fuel and Energy Storage Solution Electrolysis-generated...

387

Report to Congress on Plan for Interim Storage of Spent Nuclear...  

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

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

388

Electrometallurgical treatment of degraded N-reactor fuel  

Science Conference Proceedings (OSTI)

N-Reactor fuel constitutes almost 80% of the entire mass of the US Department of Energy's (DOE's) spent fuel inventory. The current plan for disposition of this fuel calls for interim dry storage, followed by direct repository disposal. However, this approach may not be viable for the entire inventory of N-Reactor fuel. The physical condition and chemical composition of much of the fuel have changed during the period that it has been in storage. The cladding of many of the fuel elements has been breached, allowing the metallic uranium fuel to react with water in the storage pools producing uranium oxides (U{sub x}O{sub y}) and uranium hydride (UH{sub 3}). Even if the breached fuel is placed in dry storage, it may continue to undergo significant changes caused by the reaction of exposed uranium with any remaining water in the container. Uranium oxides, uranium hydride, and hydrogen gas are expected to form as a result of this reaction. The presence of potentially explosive hydrogen and uranium hydride, which under certain conditions is pyrophoric, raises technical concerns that will need to be addressed. The electrometallurgical treatment process developed by Argonne National Laboratory (ANL) has potential for conditioning degraded N-Reactor fuel for long-term storage or disposal. The first step in evaluating the applicability of this process is the preparation of degraded fuel that is similar to the actual degraded N-Reactor fuel. Subsequently, the simulated degraded fuel can be introduced into an electrorefiner to examine the effect of corrosion products on the electrorefining process. Some of the technical issues to be resolved include the viability of direct electrorefining without a head-end reduction step, the effect of adherent corrosion products on the electrorefining kinetics, and the recovery and treatment of loose corrosion products that pull away from the degraded fuel. This paper presents results from an experimental study of the preparation, characterization, and subsequent electrometallurgical treatment of samples of simulated degraded N-Reactor fuel.

Gourishankar, K. V.; Karell, E. J.; Everhart, R. E.; Indacochea, E.

2000-03-03T23:59:59.000Z

389

Development of a Practical Hydrogen Storage System Based on Liquid Organic Hydrogen Carriers and a Homogeneous Catalyst - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

5 5 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Craig Jensen 1 (Primary Contact), Daniel Brayton 1 , and Scott Jorgensen 2 1 Hawaii Hydrogen Carriers, LLC 531 Cooke Street Honolulu, HI 96813 Phone: (808) 339-1333 Email: hhcllc@hotmail.com 2 General Motors Technical Center DOE Managers HQ: Ned Stetson Phone: (202) 586-9995 Email: Ned.Stetson@ee.doe.gov GO: Katie Randolph Phone: (720) 356-1759 Email: Katie.Randolph@go.doe.gov Contract Number: DE-EE0005020 Project Start Date: July 1, 2011 Project End Date: June 30, 2013 *Congressionally directed project Fiscal Year (FY) 2012 Objectives The objective of this project is to optimize a hydrogen storage media based on a liquid organic carrier (LOC) for hydrogen and design a commercially viable hydrogen

390

From Fundamental Understanding to Predicting New Nanomaterials for High-Capacity Hydrogen Storage - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

0 0 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Taner Yildirim 1,2 1 Department of Materials Science and Eng. University of Pennsylvania Philadelphia, PA 19104 2 National Institute of Standards and Technology, NCNR Gaithersburg, MD 20899 Phone: (301) 975-6228 Email: taner@seas.upenn.edu DOE Program Manager: Dr. Thiyaga P. Thiyagarajan Phone: (301) 903-9706 Email: P.Thiyagarajan@science.doe.gov Objectives Use neutron scattering methods along with first- * principles computation to achieve fundamental understanding of the chemical and structural interactions governing the storage and release of hydrogen/methane and carbon capture in a wide spectrum of candidate materials. Study the effect of scaffolding, nanosizing, doping of *

391

Design and Synthesis of Chemically and Electronically Tunable Nanoporous Organic Polymers for Use in Hydrogen Storage Applications - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

6 6 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Hani M. El-Kaderi (Primary Contact), Mohammad G. Rabbani, Thomas E. Reich, Karl T. Jackson, Refaie M. Kassab Virginia Commonwealth University Department of Chemistry 1001 West Main St Richmond, VA 23284-2006 Phone: (804) 828-7505 Email: helkaderi@vcu.edu DOE Program Officer: Michael Sennett Phone: (301) 903-6051 Email: Michael.Sennett@science.doe.go Objectives Design and synthesis of new classes of low density * nanoporous organic polymers that are linked by strong covalent bonds and composed of chemically and electronically tunable building blocks. Use gas sorption experiments to investigate porosity and * determine hydrogen storage at variable temperature and

392

Key Technologies, Thermal Management, and Prototype Testing for Advanced Solid-State Hydrogen Storage Systems - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

9 9 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Joseph W. Reiter (Primary Contact), Alexander Raymond, Channing C. Ahn (Caltech), Bret Naylor, Otto Polanco, Rajeshuni Ramesham, and Erik Lopez Jet Propulsion Laboratory (JPL) 4800 Oak Grove Drive, Mail Stop 79-24 Pasadena, CA 91109-8099 Phone: (818) 354-4224; Email: Joseph.W.Reiter@jpl.nasa.gov DOE Managers HQ: Ned Stetson Phone: (202) 586-9995 Email: Ned.Stetson@ee.doe.gov GO: Jesse Adams Phone: (720) 356-1421 Email: Jesse.Adams@go.doe.gov Subcontractor: California Institute of Technology, Pasadena, CA Project Start Date: February, 2009 Project End Date: September, 2014 Fiscal Year (FY) 2012 Objectives Identify state-of-art concepts and designs for * cryosorbent-based hydrogen storage systems

393

Second Record of Decision for a Dry Storage Container System for the Management of Naval Spent Nuclear Fuel (DOE/EIS-0251) (5/1/97)  

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

70 70 Federal Register / Vol. 62, No. 84 / Thursday, May 1, 1997 / Notices HQ USAF/XOO-CA, 1480 Air Force Pentagon, Washington DC 20330-1480. FOR FURTHER INFORMATION CONTACT: To request more information on this proposed information collection or to obtain a copy of the proposal and associated collection instruments, please write to the above address or call (703) 697-5967. Title, Associated Form, and OMB Number: Civil Aircraft Certificate of Insurance, DD Form 2400, OMB Number 0701-0050; Civil Aircraft Landing Permit, DD Form 2401, OMB Number 0701-0050; and DD Form 2402, Civil Aircraft Hold Harmless Agreement, OMB Number 0701-0050. Needs and Uses: The collection of information is necessary to ensure that the security and operational integrity of military airfields are maintained; to

394

Fuel Cell Technologies Office: Webinars  

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

Databases Glossary Quick Links Hydrogen Production Hydrogen Delivery Hydrogen Storage Fuel Cells Technology Validation Manufacturing Codes & Standards Education Systems...

395

Fuel Cycle Potential Waste Inventory for Disposition Rev 5 | Department of  

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

Fuel Cycle Potential Waste Inventory for Disposition Rev 5 Fuel Cycle Potential Waste Inventory for Disposition Rev 5 Fuel Cycle Potential Waste Inventory for Disposition Rev 5 The United States currently utilizes a once-through fuel cycle where used nuclear fuel is stored onsite in either wet pools or in dry storage systems with ultimate disposal envisioned in a deep mined geologic repository. This report provides an estimate of potential waste inventory and waste form characteristics for the DOE used nuclear fuel and high-level radioactive waste and a variety of commercial fuel cycle alternatives in order to support subsequent system-level evaluations of disposal system performance. Fuel Cycle Potential Waste Inventory for Disposition R5a.docx More Documents & Publications Repository Reference Disposal Concepts and Thermal Load Management Analysis

396

Solar energy storage through the homogeneous electrocatalytic reduction of carbon dioxide : photoelectrochemical and photovoltaic approaches  

E-Print Network (OSTI)

Quantum Capture and Energy Storage. Photochem. Photobio.D ISSERTATION Solar Energy Storage through the Homogeneoussolar based fuels and energy storage. At present, it is not

Sathrum, Aaron John

2011-01-01T23:59:59.000Z

397

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect

The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S; (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated; (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass; and (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

Jones, R.; Carter, J.

2010-10-13T23:59:59.000Z

398

FUEL CYCLE POTENTIAL WASTE FOR DISPOSITION  

SciTech Connect

The United States (U.S.) currently utilizes a once-through fuel cycle where used nuclear fuel (UNF) is stored on-site in either wet pools or in dry storage systems with ultimate disposal in a deep mined geologic repository envisioned. Within the Department of Energy's (DOE) Office of Nuclear Energy (DOE-NE), the Fuel Cycle Research and Development Program (FCR&D) develops options to the current commercial fuel cycle management strategy to enable the safe, secure, economic, and sustainable expansion of nuclear energy while minimizing proliferation risks by conducting research and development of advanced fuel cycles, including modified open and closed cycles. The safe management and disposition of used nuclear fuel and/or nuclear waste is a fundamental aspect of any nuclear fuel cycle. Yet, the routine disposal of used nuclear fuel and radioactive waste remains problematic. Advanced fuel cycles will generate different quantities and forms of waste than the current LWR fleet. This study analyzes the quantities and characteristics of potential waste forms including differing waste matrices, as a function of a variety of potential fuel cycle alternatives including: (1) Commercial UNF generated by uranium fuel light water reactors (LWR). Four once through fuel cycles analyzed in this study differ by varying the assumed expansion/contraction of nuclear power in the U.S. (2) Four alternative LWR used fuel recycling processes analyzed differ in the reprocessing method (aqueous vs. electro-chemical), complexity (Pu only or full transuranic (TRU) recovery) and waste forms generated. (3) Used Mixed Oxide (MOX) fuel derived from the recovered Pu utilizing a single reactor pass. (4) Potential waste forms generated by the reprocessing of fuels derived from recovered TRU utilizing multiple reactor passes.

Carter, J.

2011-01-03T23:59:59.000Z

399

Fluid Phase Chemical Hydrogen Storage Materials - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

8 8 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Benjamin L. Davis (Primary Contact), Tessui Nakagawa, Biswajit Paik, and Troy A. Semelsberger Materials Physics and Applications, Materials Chemistry Los Alamos National Laboratory (LANL), MS J514 P.O. Box 1663 Los Alamos, NM 87545 Phone: (505) 500-2463 Email: bldavis@lanl.gov DOE Manager Grace Ordaz Phone: (202) 586-8350 Email: Grace.Ordaz@hq.doe.gov Partner Tom Baker, University of Ottawa, Ontario, Canada Project Start Date: October 1, 2010 Project End Date: Project continuation and direction determined annually by DOE Fiscal Year (FY) 2012 Objectives Develop fluid, pumpable ammonia-borane (AB)-based fuels with high-H 2 content. Technical Barriers

400

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

Note: This page contains sample records for the topic "fuel dry 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

Hanford Cold Vacuum Drying Facility, Multi-Canister Overpack...  

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

that was designed to dry the irradiated fuel rods which were previously stored underwater in the K-Basins. Upon completion of the drying process in the CVDF, the MCOs,...

402

Ammonia as an Alternative Energy Storage Medium for Hydrogen Fuel Cells: Scientific and Technical Review for Near-Term Stationary Power Demonstration Projects, Final Report  

E-Print Network (OSTI)

as a fuel in solid oxide fuel cells,Ē J. Power Sources 118:L. and Bloomfield, D.P. , ďAmmonia Cracker for Fuel CellsĒ,1998 Fuel Cell Seminar Abstracts, November 16-19, Palm

Lipman, Tim; Shah, Nihar

2007-01-01T23:59:59.000Z

403

Extended Storage Collaboration Program International Subcommittee Report  

Science Conference Proceedings (OSTI)

With the prospect of spent nuclear fuel being stored at reactor sites for the foreseeable future, EPRI established the Extended Storage Collaboration Program (ESCP) in 2009 to investigate aging effects and mitigation options for the extended storage and transportation of spent nuclear fuel. ESCPís International Subcommittee developed this summary of the regulatory status, operational status, fuel inventory, and technical gaps identified for extended storage of spent fuel for each ...

2012-11-12T23:59:59.000Z

404

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.

405

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...

406

Ammonia-Borane: a Promising Material for Hydrogen Storage - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

0 0 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Larry G. Sneddon (Primary Contact), Martin Bluhm, Dan Himmelberger, William Ewing, Laif Alden, Emily Berkeley, Chang Won Yoon and Allegra Marchione University of Pennsylvania Department of Chemistry 231 S. 34 th Street Philadelphia, PA 19104-6323 Phone: (215) 898-8632 Email: lsneddon@sas.upenn.edu DOE Program Officer: Larry Rahn Phone: (301) 903-2508 Email: Larry.Rahn@science.doe.gov Subcontractors: R. Tom Baker, Richard Burchell, Felix Gaertner, Hassan Kalviri, Morgane Le Fur, Larena Menant, Giovanni Rachiero Matthew Rankin, Johannes Thomas,

407

Hydrogen Storage in Metal-Organic Frameworks - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

7 7 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Jeffrey Long (Primary Contact), Martin Head-Gordon Lawrence Berkeley National Laboratory 1 Cyclotron Road Berkeley, CA 95720 Phone: (510) 642-0860 Email: jrlong@berkeley.edu DOE Managers HQ: Ned Stetson Phone: (202) 586-9995 Email: Ned.Stetson@ee.doe.gov GO: Jesse Adams Phone: (720) 356-1421 Email: Jesse.Adams@go.doe.gov Subcontractors: * National Institute of Standards and Technology, Gaithersburg, MD (Craig Brown) * General Motors Corporation, Warren, MI (Anne Dailly) Project Start Date: April 1, 2012 Project End Date: March 31, 2015 Fiscal Year (FY) 2012 Objectives

408

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 +¬Ĺ O 2 ‚Üí 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. ő∑ 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

409

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

410

Hydrogen Storage atHydrogen Storage at Lawrence Berkeley National LaboratoryLawrence Berkeley National Laboratory  

E-Print Network (OSTI)

Hydrogen Storage atHydrogen Storage at Lawrence Berkeley National LaboratoryLawrence Berkeley National Laboratory Presentation at thePresentation at the Hydrogen Storage Grand ChallengeHydrogen Storage expertise to hydrogen storage, fuel cells, and system integration issues ­Novel membranes and other

411

HEATS: Thermal Energy Storage  

SciTech Connect

HEATS Project: The 15 projects that make up ARPA-Eís HEATS program, short for ďHigh Energy Advanced Thermal Storage,Ē 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

412

Independent Oversight Review, Hanford K Basin and Cold Vacuum Drying Facility- August 2012  

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

Review of Hanford K Basin and Cold Vacuum Drying Facility Found Fuel Multi-Canister Overpack Operations

413

HGMS: Glasses and Nanocomposites for Hydrogen Storage - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

8 8 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Kris Lipinska (Primary Contact), Oliver Hemmers Harry Reid Center, University of Nevada Las Vegas (UNLV) 4505 Maryland Parkway, Box 454009 Las Vegas, NV 89154-4009 Phones: (702) 895-4450, (702) 895-3742 Emails: kristina.lipinska@unlv.edu, oliver.hemmers@unlv.edu DOE Managers HQ: Grace Ordaz Phone: (202) 586-8350 Email: Grace.Ordaz@ee.doe.gov GO: Jesse Adams Phone: (720) 356-1421 Email: Jesse.Adams@go.doe.gov Contract Number: DE-EE0000269 Project Start Date: November 25, 2009 Project End Date: October 31, 2012 *Congressionally directed project Fiscal Year (FY) 2012 Objectives Fabricate glasses and nanocrystalline composites: * improve materials composition by introducing functional dopants Demonstrate controlled nucleation of nanocrystals

414

Hydrogen Storage Engineering Center of Excellence - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

4 4 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Donald L. Anton (Primary Contact), Theodore Motyka, Bruce Hardy and David Tamburello Savannah River National Laboratory (SRNL) Bldg. 999-2W Aiken, SC 29808 Phone: (803) 507-8551 Email: DONALD.ANTON@SRNL.DOE.GOV DOE Managers HQ: Ned Stetson Phone: (202) 586-9995 Email: Ned.Stetson@ee.doe.gov GO: Jesse Adams Phone: (720) 356-1421 Email: Jesse.Adams@go.doe.gov Technical Advisor Robert Bowman Phone: 818-354-7941 Email: rcbjr1967@gmail.com Subcontractors: * Pacific Northwest National Laboratory (PNNL) * United Technologies Research Center (UTRC) * General Motors Corp (GM) * Ford Motor Corp. (FMC)

415

Development of Improved Composite Pressure Vessels for Hydrogen Storage - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

0 0 DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report Norman Newhouse (Primary Contact), Jon Knudsen, John Makinson Lincoln Composites, Inc. 5117 NW 40 th Street Lincoln, NE 68524 Phone: (402) 470-5035 Email: nnewhouse@lincolncomposites.com DOE Managers HQ: Ned Stetson Phone: (202) 586-9995 Email: Ned.Stetson@ee.doe.gov GO: Jesse Adams Phone: (720) 356-1421 Email: Jesse.Adams@go.doe.gov Contract Number: DE-FC36-09GO19004 Project Start Date: February 1, 2009 Project End Date: June 30, 2014 Fiscal Year (FY) 2012 Objectives Improve the performance characteristics, including * weight, volumetric efficiency, and cost, of composite pressure vessels used to contain hydrogen in adsorbants. Evaluate design, materials, or manufacturing process *

416

Lifecycle Verification of Polymeric Storage Tank Liners - DOE Hydrogen and Fuel Cells Program FY 2012 Annual Progress Report  

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

7 7 FY 2012 Annual Progress Report DOE Hydrogen and Fuel Cells Program Barton Smith (Primary Contact) and Lawrence M. Anovitz Oak Ridge National Laboratory P.O. Box 2008 Oak Ridge, TN 37831 Phone: (865) 574-2196 Email: smithdb@ornl.gov DOE Manager HQ: Ned Stetson Phone: (202) 586-9995 Email: Ned.Stetson@ee.doe.gov Start Date: June 2008 Projected End Date: Project continuation and direction determined annually by DOE Fiscal Year (FY) 2012 Objectives Continue temperature cycling and permeation * measurements on tank liner polymers, and use permeation data to assess ability of tank liners to retain a steady-state hydrogen discharge rate that does not exceed 110% of the 75 normal cubic centimeters per minute (Ncc)/min permeation requirement of SAE International

417

Using population risk assessment as a basis for administrative decisions related to storage of irradiated nuclear fuel  

SciTech Connect

Available in abstract form only. Full text of publication follows: Optimization of safety related decisions by local authorities could be improved using information on potential risks to a regional population. A joint Russia-US effort in 2001-2002 modeled potential population health risks for a proposed nuclear waste storage facility in northern Russia. Conducting such an assessment in addition to the standard PRA is proposed as an innovation in Russia aimed at better meeting the needs of local decision makers. This case-study analysis was conducted for the proposed facility to provide insights into potential population health risks. In the case study results, the background population risks from radiation accident exposures were very low compared to risks from chemical background exposures - an unexpected outcome for those that perceive any nuclear facility as very hazardous to the local population. The paper notes that rather than requiring a proposed low-risk facility for hazardous materials be made even safer, these results give the local authority the option of proposing a trade-off of having a major unrelated regional risks mitigated. The results show the value of conducting a population risk assessment in addition to a facility-oriented PRA as a means of better defining the potential impacts. (authors)

Droppo, James G. [Pacific Northwest National Laboratory, PO Box 999, Richland WA 99352 (United States); Eremenko, V.A. [International Knowledge Bridge LLC (Russian Federation); Linde, J. [Association on Computer Technology and Informational Systems - ACTIS (Russian Federation); Shilova, E. [Moscow Institute of International Economic Relations, 76, Vernadsky av. 119454 Moscow (Russian Federation)

2007-07-01T23:59:59.000Z