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Viability of Existing INL Facilities for Dry Storage Cask Handling

Description: 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 l… more
Date: April 1, 2013
Creator: Bohachek, Randy; Park, Charles; Wallace, Bruce; Winston, Phil & Marschman, Steve
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Managing Aging Effects on Dry Cask Storage Systems for Extended Long-Term Storage and Transportation of Used Fuel - Rev. 0

Description: 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 ma… more
Date: July 6, 2012
Creator: Chopra, O. K.; Diercks, D.; Fabian, R.; Ma, D.; Shah, V.; Tam, S. W. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Overcoming the Recalcitrance of Cellulosic Biomass by Value Prior to Pulping: Cooperative Research and Development Final Report, CRADA Number CRD-07-221

Description: The Value Prior to Pulping (VPP) project goal was to demonstrate the technical and commercial feasibility of introducing a new value stream into existing pulp and paper mills. Essentially the intent was to transfer the energy content of extracted hemicellulose from electricity and steam generated in the recovery boiler to a liquid transportation fuel. The hemicellulose fraction was extracted prior to pulping, fractionated, or conditioned if necessary, and fermented to ethanol. Commercial adapta… more
Date: April 1, 2012
Creator: Lowell, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

IDAHO NATIONAL LABORATORY TRANSPORTATION TASK REPORT ON ACHIEVING MODERATOR EXCLUSION AND SUPPORTING STANDARDIZED TRANSPORTATION

Description: Following the defunding of the Yucca Mountain Project, it is reasonable to assume that commercial used fuel will remain in storage for the foreseeable future. This report proposes supplementing the ongoing research and development work related to potential degradation of used fuel, baskets, poisons, and storage canisters during an extended period of storage with a parallel path. This parallel path can assure criticality safety during transportation by implementing a concept that achieves modera… more
Date: September 1, 2011
Creator: Morton, D.K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CONTAINMENT EVALUATION OF PU-METAL TRANSPORT USING MULTIPLE BARRIERS

Description: A methodology was developed previously by SRNL to show that Al-SNF with cladding breaches can be directly transported in standard casks and maintained within the allowable release rates. This novel approach may be extended to other nuclear material systems. Utilizing an adaptation to the methodology, a containment analysis has been performed for the scenario of non-routine transfer of a damaged 9975 package containing plutonium metal from K-area monitored storage to F-area on the Savannah River… more
Date: July 18, 2011
Creator: Vinson, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

SLUDGE TREATMENT PROJECT ENGINEERED CONTAINER RETRIEVAL AND TRANSFER SYSTEM PRELMINARY DESIGN HAZARD AND OPERABILITY STUDY

Description: This Hazard and Operability (HAZOP) study addresses the Sludge Treatment Project (STP) Engineered Container Retrieval and Transfer System (ECRTS) preliminary design for retrieving sludge from underwater engineered containers located in the 105-K West (KW) Basin, transferring the sludge as a sludge-water slurry (hereafter referred to as 'slurry') to a Sludge Transport and Storage Container (STSC) located in a Modified KW Basin Annex, and preparing the STSC for transport to T Plant using the Slud… more
Date: July 15, 2011
Creator: Carro, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A GAMMA RAY SCANNING APPROACH TO QUANTIFY SPENT FUEL CASK RADIONUCLIDE CONTENTS

Description: The International Atomic Energy Agency (IAEA) has outlined a need to develop methods of allowing re-verification of LWR spent fuel stored in dry storage casks without the need of a reference baseline measurement. Some scanning methods have been developed, but improvements can be made to readily provide required data for spent fuel cask verification. The scanning process should be conditioned to both confirm the contents and detect any changes due to container/contents degradation or unauthorize… more
Date: July 1, 2011
Creator: Branney, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Technical Data to Justify Full Burnup Credit in Criticality Safety Licensing Analysis

Description: Enercon Services, Inc. (ENERCON) was requested under Task Order No.2 to identify scientific and technical data needed to benchmark and justify Full Burnup Credit, which adds 16 fission products and 4 minor actinides1 to Actinide-Only burnup credit. The historical perspective for Full Burnup Credit is discussed, and interviews of organizations participating in burnup credit activities are summarized as a basis for identifying additional data needs and making recommendation. Input from burnup cre… more
Date: March 14, 2011
Creator: Enercon Services, Inc.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THERMAL MODELING ANALYSIS OF SRS 70 TON CASK

Description: The primary objective of this work was to perform the thermal calculations to evaluate the Material Test Reactor (MTR) fuel assembly temperatures inside the SRS 70-Ton Cask loaded with various bundle powers. MTR fuel consists of HFBR, MURR, MIT, and NIST. The MURR fuel was used to develop a bounding case since it is the fuel with the highest heat load. The results will be provided for technical input for the SRS 70 Ton Cask Onsite Safety Assessment. The calculation results show that for the SRS… more
Date: March 8, 2011
Creator: Lee, S.; Jordan, J. & Hensel, S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Radiation Detection Scenario Analysis Toolbox (RADSAT) Test Case Implementation Final Report

Description: Final report for the project. This project was designed to demonstrate the use of the Radiation Detection Scenario Analysis Toolbox (RADSAT) radiation detection transport modeling package (developed in a previous NA-22 project) for specific radiation detection scenarios important to proliferation detection.
Date: September 27, 2010
Creator: Shaver, Mark W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

CONTAINMENT ANALYSIS METHODOLOGY FOR TRANSPORT OF BREACHED CLAD ALUMINUM SPENT FUEL

Description: Aluminum-clad, aluminum-based spent nuclear fuel (Al-SNF) from foreign and domestic research reactors (FRR/DRR) is being shipped to the Savannah River Site and placed in interim storage in a water basin. To enter the United States, a cask with loaded fuel must be certified to comply with the requirements in the Title 10 of the U.S. Code of Federal Regulations, Part 71. The requirements include demonstration of containment of the cask with its contents under normal and accident conditions. Many … more
Date: July 11, 2010
Creator: Vinson, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

MANAGEMENT OF RESEARCH AND TEST REACTOR ALUMINUM SPENT NUCLEAR FUEL - A TECHNOLOGY ASSESSMENT

Description: The Department of Energy's Environmental Management (DOE-EM) Program is responsible for the receipt and storage of aluminum research reactor spent nuclear fuel or used fuel until ultimate disposition. Aluminum research reactor used fuel is currently being stored or is anticipated to be returned to the U.S. and stored at DOE-EM storage facilities at the Savannah River Site and the Idaho Nuclear Technology and Engineering Center. This paper assesses the technologies and the options for safe trans… more
Date: July 11, 2010
Creator: Vinson, D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Air Shipment of Highly Enriched Uranium Spent Nuclear Fuel from Romania

Description: Romania safely air shipped 23.7 kilograms of Russian origin highly enriched uranium (HEU) spent nuclear fuel from the VVR S research reactor at Magurele, Romania, to the Russian Federation in June 2009. This was the world’s first air shipment of spent nuclear fuel transported in a Type B(U) cask under existing international laws without special exceptions for the air transport licenses. This shipment was coordinated by the Russian Research Reactor Fuel Return Program (RRRFR), part of the U.S. D… more
Date: July 1, 2010
Creator: Allen, K. J.; Bolshinsky, I.; Biro, L. L.; Budu, M. E.; Zamfir, N. V. & Dragusin, M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

AIR SHIPMENT OF HIGHLY ENRICHED URANIUM SPENT NUCLEAR FUEL FROM ROMANIA AND LIBYA

Description: In June 2009 Romania successfully completed the world’s first air shipment of highly enriched uranium (HEU) spent nuclear fuel transported in Type B(U) casks under existing international laws and without special exceptions for the air transport licenses. Special 20-foot ISO shipping containers and cask tiedown supports were designed to transport Russian TUK 19 shipping casks for the Romanian air shipment and the equipment was certified for all modes of transport, including road, rail, water, an… more
Date: July 1, 2010
Creator: Landers, Christopher; Bolshinsky, Igor; Allen, Ken & Moses, Stanley
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Storage for Transportation Equipment, Unfueled Convertors, and Fueled Convertors at the INL for the Radioisotope Power Systems Program

Description: This report contains an evaluation of the storage conditions required for several key components and/or systems of the Radioisotope Power Systems (RPS) Program at the Idaho National Laboratory (INL). These components/systems (transportation equipment, i.e., type ‘B’ shipping casks and the radioisotope thermo-electric generator transportation systems (RTGTS), the unfueled convertors, i.e., multi-hundred watt (MHW) and general purpose heat source (GPHS) RTGs, and fueled convertors of several type… more
Date: May 1, 2010
Creator: Johnson, S. G. & Lively, K. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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

Description: This work addresses the neutronic performance and criticality safety issues of transport casks for fuel pertaining to low conversion ratio sodium cooled fast reactors, conventionally known as Advanced Burner Reactors. The criticality of a one, three, seven and 19-assembly cask capacity is presented. Both dry “helium” and flooded “water” filled casks are considered. No credit for fuel burnup or fission products was assumed. As many as possible of the conservatisms used in licensing light water r… more
Date: May 1, 2010
Creator: Bays, Samuel & Alajo, Ayodeji
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

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

Description: The Sludge Treatment Project (STP) is responsible for the disposition of sludge contained in the six engineered containers and Settler tank within the 105-K West (KW) Basin. The STP is retrieving and transferring sludge from the Settler tank into engineered container SCS-CON-230. Then, the STP will retrieve and transfer sludge from the six engineered containers in the KW Basin directly into a Sludge Transport and Storage Containers (STSC) contained in a Sludge Transport System (STS) cask. The S… more
Date: April 29, 2010
Creator: RD, CROWE; R, APTHORPE; SJ, LEE & MG, PLYS
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Sludge Treatment Project Cost Comparison Between Hydraulic Loading and Small Canister Loading Concepts

Description: The Sludge Treatment Project (STP) is considering two different concepts for the retrieval, loading, transport and interim storage of the K Basin sludge. The two design concepts under consideration are: (1) Hydraulic Loading Concept - In the hydraulic loading concept, the sludge is retrieved from the Engineered Containers directly into the Sludge Transport and Storage Container (STSC) while located in the STS cask in the modified KW Basin Annex. The sludge is loaded via a series of transfer, se… more
Date: August 24, 2009
Creator: Conrad, E. A. & Rhoadarmer, D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Dose estimates in a loss of lead shielding truck accident.

Description: The radiological transportation risk & consequence program, RADTRAN, has recently added an updated loss of lead shielding (LOS) model to it most recent version, RADTRAN 6.0. The LOS model was used to determine dose estimates to first-responders during a spent nuclear fuel transportation accident. Results varied according to the following: type of accident scenario, percent of lead slump, distance to shipment, and time spent in the area. This document presents a method of creating dose estimates… more
Date: August 1, 2009
Creator: Dennis, Matthew L.; Osborn, Douglas M.; Weiner, Ruth F. & Heames, Terence John (Alion Science & Technology Albuquerque, NM)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Structural Analyses of Fuel Casks Subjected to Bolt Preload, Internal Pressure and Sequential Dynamic Impacts

Description: Large fuel casks subjected to the combined loads of closure bolt tightening, internal pressure and sequential dynamic impacts present challenges when evaluating their performance in the Hypothetical Accident Conditions (HAC) specified in the Code of Federal Regulations Title 10 Part 71 (10CFR71). Testing is often limited by cost, difficulty in preparing test units and the limited availability of facilities which can carry out such tests. In the past, many casks were evaluated without testing by… more
Date: June 25, 2009
Creator: Wu, T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

High-Solids Enzymatic Saccharification Screening Method for Lignocellulosic Biomass (Poster)

Description: The ability to screen new biomass pretreatments and advanced enzyme systems at process-relevant conditions is key to developing economically viable lignocellulosic ethanol. While much research is being invested in developing pretreatment technologies and enzyme systems that will more efficiently convert cellulosic biomass to sugars, the current standard reactor vessel, a shake flask, that is used for screening enzymatic saccharification of cellulosic biomass is inadequate at high-solids conditi… more
Date: May 1, 2009
Creator: Roche, C. M. & Stickel, J. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Fresh and Spent Nuclear Fuel Repatriation from the IRT-2000 Research Reactor Facility, Sofia, Bulgaria

Description: The IRT 2000 research reactor, operated by the Bulgarian Institute for Nuclear Research and Nuclear Energy (INRNE), safely shipped all of their Russian-origin nuclear fuel from the Republic of Bulgaria to the Russian Federation beginning in 2003 and completing in 2008. These fresh and spent fuel shipments removed all highly enriched uranium (HEU) from Bulgaria. The fresh fuel was shipped by air in December 2003 using trucks and a commercial cargo aircraft. One combined spent fuel shipment of HE… more
Date: March 1, 2009
Creator: Allen, K. J.; Apostolov, T. G. & Dimitrov, I. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Highly Selective Synthesis of Catalytically Active Monodisperse Rhodium Nanocubes

Description: Synthesis of monodisperse and shape-controlled colloidal inorganic nanocrystals (NCs) is of increasing scientific interest and technological significance. Recently, shape control of Pt, Pd, Ag, Au, and Rh NCs has been obtained by tuning growth kinetics in various solution-phase approaches, including modified polyol methods, seeded growth by polyol reduction, thermolysis of organometallics, and micelle techniques. Control of reduction kinetics of the noble metal precursors and regulation of the … more
Date: February 21, 2009
Creator: Zhang, Y.; Grass, M. E.; Kuhn, J. N.; Tao, F.; Habas, S. E.; Huang, W. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Kootenai River Nutrient Dosing System and N-P Consumption: Year 2008.

Description: In early 2006 we designed and built low energy consumption, pump-operated system, for dosing of the liquid nutrient in the summer 2006 season. This operated successfully, and the system was used again during the 2007 and 2008 seasons for dosing. During the early winter period, 2008, laboratory tests were made of the liquid nutrient pump system, and it was noted that small amounts of air were being entrained on the suction side of the pump, during conditions when the inlet pressure was low. It w… more
Date: February 19, 2009
Creator: Holderman, Charles
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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