Project management plan for Reactor 105-C Interim Safe Storage project

International Nuclear Information System (INIS)

Plagge, H.A.

1996-09-01

Reactor 105-C (located on the Hanford Site in Richland, Washington) will be placed into an interim safe storage condition such that (1) interim inspection can be limited to a 5-year frequency; (2) containment ensures that releases to the environmental are not credible under design basis conditions; and (3) final safe storage configuration shall not preclude or significantly increase the cost for any decommissioning alternatives for the reactor assembly.This project management plan establishes plans, organizational responsibilities, control systems, and procedures for managing the execution of Reactor 105-C interim safe storage activities to meet programmatic requirements within authorized funding and approved schedules

Heat transport and storage

International Nuclear Information System (INIS)

Despois, J.

1977-01-01

Recalling the close connections existing between heat transport and storage, some general considerations on the problem of heat distribution and transport are presented 'in order to set out the problem' of storage in concrete form. This problem is considered in its overall plane, then studied under the angle of the different technical choices it involves. The two alternatives currently in consideration are described i.e.: storage in a mined cavity and underground storage as captive sheet [fr

UFD Storage and Transportation - Transportation Working Group Report

International Nuclear Information System (INIS)

Maheras, Steven J.; Ross, Steven B.

2011-01-01

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

High-Level Radioactive Waste: Safe Storage and Ultimate Disposal.

Science.gov (United States)

Dukert, Joseph M.

Described are problems and techniques for safe disposal of radioactive waste. Degrees of radioactivity, temporary storage, and long-term permanent storage are discussed. Included are diagrams of estimated waste volumes to the year 2000 and of an artist's conception of a permanent underground disposal facility. (SL)

30 years of experience in safe transportation of nuclear materials

International Nuclear Information System (INIS)

Kaneko, K.

2004-01-01

In April 2003, Nuclear Fuel Transport Co., Ltd. (NFT) marked the 30 th anniversary of its founding. NFT was established in 1973 and in 1978, commenced SF transport to the reprocessing plant in Tokai-mura. And then, after making preparations to transport nuclear materials to the various facilities at the Nuclear Fuel Cycle Center in Rokkasho-mura, NFT successfully started transportation of LLW (low level waste) to Rokksho-mura's LLW disposal center in 1992, domestic land transportation of HLW returned from overseas to the HLW storage center in 1995, domestic land transportation of natural hexafluoride delivered from overseas to the uranium enrichment plant in 1996, and transportation of SF to the reprocessing plant in 2000. NFT has realized an annual SF transportation capacity of 300 MTU and is currently making great company wide efforts to meet the Rokkasho Reprocessing Plant's future SF annual reprocessing capacity of 800MTU. At the end of FY2003, NFT had successfully transported 560 casks (about 1,730 MTU) of SF in more than 200 voyages in total, about 160,000 drums of LLW in around 100 voyages in total. This paper introduces the record of safe transport and its experience over the past 30 years and prospect for future transport business

30 years of experience in safe transportation of nuclear materials

Energy Technology Data Exchange (ETDEWEB)

Kaneko, K. [Nuclear Fuel Transport Co., Ltd., Tokyo (Japan)

2004-07-01

In April 2003, Nuclear Fuel Transport Co., Ltd. (NFT) marked the 30{sup th} anniversary of its founding. NFT was established in 1973 and in 1978, commenced SF transport to the reprocessing plant in Tokai-mura. And then, after making preparations to transport nuclear materials to the various facilities at the Nuclear Fuel Cycle Center in Rokkasho-mura, NFT successfully started transportation of LLW (low level waste) to Rokksho-mura's LLW disposal center in 1992, domestic land transportation of HLW returned from overseas to the HLW storage center in 1995, domestic land transportation of natural hexafluoride delivered from overseas to the uranium enrichment plant in 1996, and transportation of SF to the reprocessing plant in 2000. NFT has realized an annual SF transportation capacity of 300 MTU and is currently making great company wide efforts to meet the Rokkasho Reprocessing Plant's future SF annual reprocessing capacity of 800MTU. At the end of FY2003, NFT had successfully transported 560 casks (about 1,730 MTU) of SF in more than 200 voyages in total, about 160,000 drums of LLW in around 100 voyages in total. This paper introduces the record of safe transport and its experience over the past 30 years and prospect for future transport business.

Manipulation technology optimization for the interim storage of HAW transport and storage containers; Optimierung der Handhabungstechnik zur Zwischenlagerung von HAW-Transport- und Lagerbehaeltern

Energy Technology Data Exchange (ETDEWEB)

Emmrich, Uwe; Krueger, Michael; Schulze, Hartmut [GNS Gesellschaft fuer Nuklear-Service mbH, Essen (Germany)

2011-07-01

The handling of high-level radioactive waste transport and storage containers from reprocessing plants is determined by the cask configuration and the radiation protection measures with respect to the safe enclosure of the radioactive inventory and shielding of gamma and neutron radiation. The new of CASTOR {sup registered} HAW28M was designed for higher radioactive inventories, the heat generation is has rarely been changed with respect to the former design. The essential structural modifications are shock absorbers that have to be demounted before storage in the interim storage facility Gorleben. Due to public acceptance forcings the ALARA principle is not the only basis for manipulation technology optimizations, the minimization of dose rate for the operational personnel is of increasing importance. The authors describe the optimizations and the resulting dose reductions.

Regulations for the safe transport of radioactive materials. 1973 revised edition (as amended).

International Nuclear Information System (INIS)

1979-01-01

On the basis of a comprehensive review carried out by a panel of experts, a revised version of the International Atomic Energy Agency's Regulations for the Safe Transport of Radioactive Materials was approved by the Board of Governors in September 1972 and published in April 1973 as Safety Series No.6 - 1973 Revised Edition. Minor amendments, together with a number of changes of detail were promulgated by the Director General in 1975 and 1977. In October 1978, the Standing Advisory Group on the Safe Transport of Radioactive Materials, established by the Director General in 1977, reviewed and recommended a small number of additional amendments. The recommendations of SAGSTRAM were subsequently accepted by the Director General. All these minor amendments and changes of detail are incorporated in the present text of the Regulations. The purpose of these Regulations is to establish standards of safety which provide an acceptable level of control of the radiation hazards to persons, property and the environment that are associated with the transport of radioactive material. They apply to the transport by land, water or air, including transport on own account, of radioactive material other than that which is an integral part of the means of transport. Transport includes any operation incidental to the whole course of carriage, such as loading, unloading and storage in transit. The term includes both normal transport and that under accident conditions

The safe transport of radioactive materials

International Nuclear Information System (INIS)

Messenger, W. de L.M.

1979-02-01

The hazards of radioactive materials in transport are surveyed. The system whereby they are safely transported between nuclear establishments in the United Kingdom and overseas is outlined. Several popular misconceptions are dealt with. (author)

Development of a container for the transportation and storage of plutonium bearing materials

International Nuclear Information System (INIS)

Ammerman, D.; Geinitz, R.; Thorp, D.; Rivera, M.

1998-03-01

There is a large backlog of plutonium contaminated materials at the Rocky Flats Environmental Technology Site near Denver, Colorado, USA. The clean-up of this site requires this material to be packaged in such a way as to allow for efficient transportation to other sites or to a permanent geologic repository. Prior to off-site shipment of the material, it may be stored on-site for a period of time. For this reason, it is desirable to have a container capable of meeting the requirements for storage as well as the requirements for transportation. Most of the off-site transportation is envisioned to take place using the TRUPACT-II Type B package, with the Waste Isolation Pilot Plant (WIPP) as the destination. Prior to the development of this new container, the TRUPACT-II had a limit of 325 FGE (fissile gram equivalents) of plutonium due to criticality control concerns. Because of the relatively high plutonium content in the material to be transported, transporting 325 FGE per TRUPACT-II is uneconomical. Thus, the purpose of the new containers is to provide criticality control to increase the allowed TRUPACT-II payload and to provide a safe method for on-site storage prior to transport. This paper will describe the analysis and testing used to demonstrate that the Pipe Overpack Container provides safe on-site storage of plutonium bearing materials in unhardened buildings and provides criticality control during transportation within the TRUPACT-II. Analyses included worst-case criticality analyses, analyses of fork-lift time impacts, and analyses of roof structure collapse onto the container. Testing included dynamic crush tests, bare pipe impact tests, a 30-minute totally engulfing pool-fire test, and multiple package impact tests in end-on and side-on orientations

A concept of a nonfissile uranium hexafluoride overpack for storage, transport, and processing of corroded cylinders

International Nuclear Information System (INIS)

Pope, R.B.; Cash, J.M.; Singletary, B.H.

1996-01-01

There is a need to develop a means of safely transporting breached 48-in. cylinders containing depleted uranium hexafluoride (UF 6 ) from current storage locations to locations where the contents can be safely removed. There is also a need to provide a method of safely and easily transporting degraded cylinders that no longer meet the US Department of Transportation (DOT) and American National Standards Institute, Inc., (ANSI) requirements for shipments of depleted UF 6 . A study has shown that an overpack can be designed and fabricated to satisfy these needs. The envisioned overpack will handle cylinder models 48G, 48X, and 48Y and will also comply with the ANSI N14.1 and the American Society of Mechanical Engineers (ASME) Sect. 8 requirements

Safe transport of radioactive material

International Nuclear Information System (INIS)

1994-01-01

Delivering radioactive material to where it is needed is a vital service to industry and medicine. Millions of packages are shipped all over the world by all modes of transport. The shipments pass through public places and must meet stringent safety requirements. This video explains how radioactive material is safely transported and describes the rules that carriers and handlers must follow

Considerations applicable to the transportability of a transportable storage cask at the end of the storage period

International Nuclear Information System (INIS)

Sanders, T.L.; Ottinger, C.A.; Brimhall, J.L.; Creer, J.M.; Gilbert, E.R.; Jones, R.H.; McConnell, P.E.

1991-11-01

Additional spent fuel storage capacity is needed at many nuclear power plant sites where spent fuel storage pools have either reached or are expected to reach maximum capacities before spent fuel can be removed. This analysis examines certain aspects of Transportable Storage Casks (TSC) to assist in the determination of their feasibility as an option for at-reactor dry storage. Factors that can affect in-transport reliability include: the quality of design, development, and fabrication activities; the possibilities of damage or error during loading and closure; in-storage deterioration or unanticipated storage conditions; and the potential for loss of storage period monitoring/measurement data necessary for verifying the TSC fitness-for-transport. The reported effort utilizes a relative reliability comparison of TSCs to Transport-Only Casks (TOC) to identify and prioritize those issues and activities that are unique to TSCs. TSC system recommendations combine certain design and operational features, such as in-service monitoring, pretransport assessments, and conservation design assumptions, which when implemented and verified, should sufficiently ensure that the system will perform as intended in a later transport environment

Safe transport of radioactive material

International Nuclear Information System (INIS)

1990-01-01

Recently the Agency redefined its policy for education and training in radiation safety. The emphasis is now on long-term strategic planning of general education and training programmes. In line with this general policy the Agency's Standing Advisory Group for the Safe Transport of Radioactive Material (SAGSTRAM) in its 7th meeting (April 1989) agreed that increased training activity should be deployed in the area of transport. SAGSTRAM specifically recommended the development of a standard training programme on this subject area, including audio-visual aids, in order to assist Member States in the implementation of the Agency's Regulations for the Safe Transport of Radioactive Material. This training programme should be substantiated by a biennial training course which is thought to be held either as an Interregional or a Regional Course depending on demand. This training manual, issued as a first publication in the Training Course Series, represents the basic text material for future training courses in transport safety. The topic areas covered by this training manual and most of the texts have been developed from the course material used for the 1987 Bristol Interregional Course on Transport Safety. The training manual is intended to give guidance to the lecturers of a course and will be provided to the participants for retention. Refs, figs and tabs

Procedures for the Safe Transport of Radioactive Material

Energy Technology Data Exchange (ETDEWEB)

Kim, Jang Lyul; Chung, K. K.; Lee, J. I.; Chang, S. Y.; Lee, T. Y

2007-11-15

This technical report describes the procedure and work responsibility along with the regulation and standard necessary for the safe transport of radioactive or contaminated materials. This report, therefore, can be effectively used to secure the public safety as well as to prevent the disastrous event which might be resulted from the transport process of radioactive materials by establishing a procedure and method on the safe packing, handling and transport of radioactive materials.

Interim guidance on the safe transport of uranium hexafluoride

International Nuclear Information System (INIS)

1991-06-01

Uranium hexafluoride (UF 6 ) is a radioactive material that has significant non-radiological hazardous properties. In conformity with international regulatory practice for dangerous goods transport, these properties are classed as ''subsidiary risks'', although they predominate in the cases of depleted and natural UF 6 . UF 6 is transported as a solid material below atmospheric pressure. The IAEA Regulations for the Safe Transport of Radioactive Material, 1985 Edition, Safety Series No. 6, make recommendations that aimed to provide an adequate level of safety against radiological and criticality hazards. The basis for these is that the stringency of package performance requirements, operational procedures and approval and administrative procedures is graded relative to the severity of the hazard. The cylinders used for transporting UF 6 are also used in the production, storage and use of the material and that the fraction of their life cycle in which transport is involved is small. Consideration must also be given to the large number of existing cylinders (estimated to be between 60,000 and 70,000). Specific recommendations provided for UF 6 transport, listed in Section II, are additional to the requirements of the Regulations. The intent of these additional recommendations is to restrict contamination and to provide protection to workers and to the general public against the chemical hazard possibly resulting from a severe accident involving the transport of UF 6 , and in addition against the consequences of explosive rupture of small bare cylinders of UF 6 . 20 refs, figs and tabs

Contributions to LWR spent fuel storage and transport

International Nuclear Information System (INIS)

The papers included in this document describe the aspects of spent LWR fuel storage and transport-behaviour of spent fuel during storage; use of compact storage packs; safety of storage; design of storage facilities AR and AFR; description of transport casks and transport procedures

Lessons learned from commercial experience with nuclear plant decontamination to safe storage

International Nuclear Information System (INIS)

Fischer, S.R.; Partain, W.L.; Sype, T.

1995-01-01

The Department of Energy (DOE) has successfully performed decontamination and decommissioning (D ampersand D) on many production reactors it. DOE now has the challenge of performing D ampersand D on a wide variety of other nuclear facilities. Because so many facilities are being closed, it is necessary to place many of them into a safe-storage status before conducting D ampersand D-for perhaps as much as 20 yr. The challenge is to achieve this safe-storage condition in a cost-effective manner while remaining in compliance with applicable regulations. The DOE Office of Environmental Management, Office of Transition and Management, commissioned a lessons learned study of commercial experience with safe storage and transition to D ampersand D. Although the majority of the commercial experience has been with reactors, many of the lessons learned presented in this paper are directly applicable to transitioning the DOE Weapons Complex

Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide provides recommendations on achieving and demonstrating compliance with IAEA Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, 2005 Edition, establishing safety requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material; these include the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Series No. TS-G-1.1, 2002 Edition

The Safe Transportation of Radioactive Materials

International Nuclear Information System (INIS)

Megrahi, Abdulhafeed; Abu-Ali, Giuma; Enhaba; Ahmed

2008-01-01

In this paper, we present the essential conditions that should be required for transporting the radioactive materials. We demonstrate the procedure for transporting the radioactive iodine-131 from the Centre of Renewable Energies and Desalination of Water in Tajoura, Libya to Tripoli Medical Center. The safe measures were taken during the process of the transportation of the isotope produced in the centre including dosimetry analysis and the thickness of the container. (author)

Analysis of the interim safe storage of reactors at the Hanford site

International Nuclear Information System (INIS)

Wang Hailiang

2014-01-01

The nine production reactors, i.e. B, C, D, DR, F, H, KE, KW and N, at the Hanford site are all water-cooled and graphite-moderated reactors with natural uranium fuel. In 1993, the U.S. Department of Energy (DOE) decided to put eight production reactors (except for B) into Interim Safe Storage (ISS) for 75 years followed by deferred one-piece removal. Reactor B will remain as a national historical landmark. By the end of 2013, six reactors C, F, D, DR, H and N had been successfully put into the ISS. Reactors KE and KW will be put into the ISS in the coming years. Taking reactor C as an example, this paper mainly talks about how to put the production reactors in the Interim Safe Storage, e.g. how to make site preparation, how to construct the safe storage enclosure (SSE) and how to perform surveillance and maintenance during the ISS period, etc. (authors)

105-C Reactor interim safe storage project technology integration plan

International Nuclear Information System (INIS)

Pulsford, S.K.

1997-01-01

The 105-C Reactor Interim Safe Storage Project Technology Integration Plan involves the decontamination, dismantlement, and interim safe storage of a surplus production reactor. A major goal is to identify and demonstrate new and innovative D and D technologies that will reduce costs, shorten schedules, enhance safety, and have the potential for general use across the RL complex. Innovative technologies are to be demonstrated in the following areas: Characterization; Decontamination; Waste Disposition; Dismantlement, Segmentation, and Demolition; Facility Stabilization; and Health and Safety. The evaluation and ranking of innovative technologies has been completed. Demonstrations will be selected from the ranked technologies according to priority. The contractor team members will review and evaluate the demonstration performances and make final recommendations to DOE

Apparatus for the storage of transport- and storage-containers containing radioactive fuel elements

International Nuclear Information System (INIS)

Vox, A.

1983-01-01

The invention concerns an apparatus for the storage of transport and storage containers containing radioactive fuel elements. For each transport or storage container there is a separate silo-type container of steel, concrete, prestressed concrete or suchlike breakproof and fireproof material, to be placed in the open, that can be opened for removal and placing of the transport or storage container respectively. (orig.) [de

Regulations for the safe transport of radioactive material

International Nuclear Information System (INIS)

1995-01-01

Regulations and rules for the safe transport of radioactive materials by all kinds of conveyance are offered. Different types of packages and the conditions associated with the methods of safe packaging are given

Transport and storage of spent fuel in Germany - possibilities for more safety

International Nuclear Information System (INIS)

Brennecke, P.; Fasten, Ch.; Nitsche, F.

2004-01-01

The safe transport of spent fuel from nuclear power plants in Germany is ensured by compliance with the dangerous goods transport regulations of class 7 which are fully consistent with the IAEA Transport Regulations and in parallel with the regulations of the German Atomic Energy Act. The purpose of this paper is to give an overview of this legal basis and the appropriate regulations applicable to spent fuel transport in Germany. Some aspects of the status and the future development of spent fuel shipments are described including experiences since resumption of those shipments in 2001. Furthermore, the status of licensing of on-site interim storage, assessments of an terrorist attack as well as consequences resulting from changes in energy policy are given

Safe and secure: transportation of radioactive materials

International Nuclear Information System (INIS)

Howe, D.

2015-01-01

Western Waste Management Facility is Central Transportation Facility for Low and Intermediate waste materials. Transportation support for Stations: Reactor inspection tools and heavy water between stations and reactor components and single bundles of irradiated fuel to AECL-Chalk River for examination. Safety Track Record: 3.2 million kilometres safely travelled and no transportation accident - resulting in a radioactive release.

IAEA'S International Working Group on Integrated Transport and Storage Safety case for Dual Purpose Casks

International Nuclear Information System (INIS)

Kumano, Yumiko; Varley, Kasturi; ); Droste, Bernhard; Wolff, Dietmar; Hirose, Makoto; Harvey, John; Reiche, Ingo; McConnell, Paul

2014-01-01

Spent nuclear fuel is generated from the operation of nuclear reactors and it is imperative that it is safely managed following its removal from reactor cores. Reactor pools are usually designed based on the assumption that the fuel will be removed after a short period of time either for reprocessing, disposal, or further storage. As a result of storing higher burn-up fuel, significantly increased time-frame till disposal solutions are prepared, and delays in decisions on strategies for spent fuel management, the volume of spent fuel discharged from reactors which needs to be managed and stored is on the increase. Consequently, additional storage capacity is needed following the initial storage in reactor pools. Options for additional storage include wet storage or dry storage in a dedicated facility or in storage casks. One of these options is the use of a Dual Purpose Cask (DPC), which is a specially designed cask for both storage and transport. The management of spent fuel using a DPC generally involves on-site and off-site transportation before and after storage. Most countries require package design approval for the DPC to be transported. In addition, it is required in many countries to have a licence for storage of the spent fuel in the DPC or a licence for a storage facility that contains DPCs. Therefore, demonstration of compliance of the DPC with national and international transport regulations as well as with the storage requirements is necessary. In order to address this increasing need among Member States, the IAEA established an international working group in 2010 to develop a guidance for integrating safety cases for both storage and transport in a holistic manner. The working group consists of experts from regulatory bodies, Technical Support Organizations, operators for both transportation and storage, and research institutes. This activity is planned to be completed by 2013. Currently, a technical report has been drafted and is expected to be

Surveillance and Maintenance Plan for the 105-C Reactor Safe Storage Enclosure

International Nuclear Information System (INIS)

Logan, T. E.

1998-01-01

This document provides a plan for implementing surveillance and maintenance activities to ensure that the 105-C Reactor Safe Storage Enclosure is maintained in a safe, environmentally secure, and cost-effective manner until subsequent closure during the final disposition phase of decommissioning

Storage and transport of hazardous materials

International Nuclear Information System (INIS)

Jaeger, P.; Haferkamp, K.

1986-01-01

The attempt has been made to characterise the present risk scenario, and to set out approaches or methods for remedy and risk control. For this purpose, a retrospective analysis has been made of accidents, damage and consequential damage that occurred in the past either during storage of hazardous materials, or during road transport. A risk-benefit model facilitates assessment of accident frequency. The history of accidents during storage or transport allows assessment of the dangerousness of various materials. Another important aspect discussed is the property and behaviour of containers used for storage or transport. (DG) [de

Criticality Safety Evaluation for 30B and 48X UF6 Cylinders for Transportation and Storage

International Nuclear Information System (INIS)

Mokhatri, Homami Zahra; Nematollahi, Mohammadreza; Kamyab, Shahabeddin

2011-01-01

30B and 48X cylinders are two standard containers have been used for transportation and storage of uranium hexafluoride with 21/2-ton and 10-ton loading capacity, respectively. For the sake of nuclear safety, the long-term safe storage and transportation of the cylinders are necessary to be concerned. Safe limits in handling and storage of 30B and 48X cylinders from the criticality safety considerations, has been investigated in this paper, by using the MCNP.4C code with ENDF/B-VI library data for the neutron cross sections. An infinite array model (with and without over pack) incorporating an internal H/U ratio of 0.088 was then developed to determine the optimal interstitial moderation. The maximum k eff value for the conditions of optimal interstitial moderation with the premise of no water leakage into the UF 6 cylinder has been shown to be 0.79209 ± 0.0011 for the 30B cylinder and 0.7625±0.0013 for 48X cylinder with 5 wt % 235 U enrichment. Based on this evaluation, the 30B and 48X UF 6 cylinders with 5 wt % 235 U enrichment meet the 10 CFR part 71 criteria for Fissile Class I packages, even in the worst case, and has a Transport Index (TI) of zero for criticality safety purposes

Regulatory requirements on management of radioactive material safe transport in China

International Nuclear Information System (INIS)

Chu, C.

2016-01-01

Since 1980s, the IAEA Regulation for safe transport of radioactive material was introduced into China; the regulatory system of China began with international standards, and walked towards the institutionalized. In 2003 the National People’s Congress (NPC) promulgated “the Act on the Prevention of Radioactive Pollution of the People's Republic of China”. In 2009 “Regulation for the Safe Transport of Radioactive Material” (Referred to “Regulation”) was promulgated by the State Council. Subsequently, the National Nuclear Safety Administration (NNSA) began to formulate executive detailed department rules, regulations guidelines and standards. The present system of acts, regulations and standards on management of safe transport of radioactive material in China and future planning were introduced in this paper. Meanwhile, the paper described the specific administration requirements of the Regulation on classification management of radioactive materials, license management of transport packaging including design, manufacture and use, licensing management of transport activities and the provisions of illegal behaviors arising in safe transport of radioactive material. (author)

Extending Spent Fuel Storage until Transport for Reprocessing or Disposal

Energy Technology Data Exchange (ETDEWEB)

Carlsen, Brett; Chiguer, Mustapha; Grahn, Per; Sampson, Michele; Wolff, Dietmar; Bevilaqua, Arturo; Wasinger, Karl; Saegusa, Toshiari; Seelev, Igor

2016-09-01

Spent fuel (SF) must be stored until an end point such as reprocessing or geologic disposal is imple-mented. Selection and implementation of an end point for SF depends upon future funding, legisla-tion, licensing and other factors that cannot be predicted with certainty. Past presumptions related to the availability of an end point have often been wrong and resulted in missed opportunities for properly informing spent fuel management policies and strategies. For example, dry cask storage systems were originally conceived to free up needed space in reactor spent fuel pools and also to provide SFS of up to 20 years until reprocessing and/or deep geological disposal became available. Hundreds of dry cask storage systems are now employed throughout the world and will be relied upon well beyond the originally envisioned design life. Given present and projected rates for the use of nuclear power coupled with projections for SF repro-cessing and disposal capacities, one concludes that SF storage will be prolonged, potentially for several decades. The US Nuclear Regulatory Commission has recently considered 300 years of storage to be appropriate for the characterization and prediction of ageing effects and ageing management issues associated with extending SF storage and subsequent transport. This paper encourages addressing the uncertainty associated with the duration of SF storage by de-sign – rather than by default. It suggests ways that this uncertainty may be considered in design, li-censing, policy, and strategy decisions and proposes a framework for safely extending spent fuel storage until SF can be transported for reprocessing or disposal – regardless of how long that may be. The paper however is not intended to either encourage or facilitate needlessly extending spent fuel storage durations. Its intent is to ensure a design and safety basis with sufficient margin to accommodate the full range of potential future scenarios. Although the focus is primarily on

Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (2012 Ed.). Specific Safety Guide

Energy Technology Data Exchange (ETDEWEB)

NONE

2014-06-15

This Safety Guide provides recommendations and guidance on achieving and demonstrating compliance with IAEA Safety Standards Series No. SSR-6, Regulations for the Safe Transport of Radioactive Material (2012 Edition), which establishes the requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material, including the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Standards Series No. TS-G-1.1 Rev. 1, which was issued in 2008.

Hydrogen transport and storage in engineered glass microspheres

Energy Technology Data Exchange (ETDEWEB)

Rambach, G.D.

1994-04-20

New, high-strength, hollow, glass microspheres filled with pressurized hydrogen exhibit storage densities which make them attractive for bulk hydrogen storage and transport. The hoop stress at failure of our engineered glass microspheres is about 150,000 psi, permitting a three-fold increase in pressure limit and storage capacity above commercial microspheres, which fail at wall stresses of 50,000 psi. For this project, microsphere material and structure will be optimized for storage capacity and charge/discharge kinetics to improve their commercial practicality. Microsphere production scale up will be performed, directed towards large-scale commercial use. Our analysis relating glass microspheres for hydrogen transport with infrastructure and economics` indicate that pressurized microspheres can be economically competitive with other forms of bulk rail and truck transport such as hydride beds, cryocarbons and pressurized tube transports. For microspheres made from advanced materials and processes, analysis will also be performed to identify the appropriate applications of the microspheres considering property variables, and different hydrogen infrastructure, end use, production and market scenarios. This report presents some of the recent modelling results for large beds of glass microspheres in hydrogen storage applications. It includes plans for experiments to identify the properties relevant to large-bed hydrogen transport and storage applications, of the best, currently producible, glass microspheres. This work began in March, 1994. Project successes will be manifest in the matching of cur-rent glass microspheres with a useful application in hydrogen bulk transport and storage, and in developing microsphere materials and processes that increase the storage density and reduce the storage energy requirement.

Safe transport of radioactive material. 3. ed

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-12-01

The IAEA has developed a standardized approach to transport safety training as a means of helping Member States to implement the Transport Regulations. The training manual is an anchor of this standardized approach to training: it contains all the topics presented in the sequential order recommended by the IAEA for the student to gain a thorough understanding of the body of knowledge that is needed to ensure that radioactive material ranked as Class 7 in the United Nations' nomenclature for dangerous goods - is transported safely. The explanations in the text refer, where needed, to the appropriate requirements in the IAEA's Transport Regulations; additional useful information is also provided. Thus, the training manual in addition to the Transport Regulations and their supporting documents is used by the IAEA as the basis for delivering all of its training courses on the safe transport of radioactive material. Enclosed with the training manual is a CD-ROM that contains the text of the manual as well as the visual aids that are used at the IAEA's training courses. The following topics are covered: review of radioactivity and radiation; review of radiation protection principles; regulatory terminology; basic safety concepts: materials and packages; activity limits and material restrictions; selection of optimal package type; test procedures: material and packages; requirements for transport; control of material in transport; fissile material: regulatory requirements and operational aspects; quality assurance; national competent authority; additional regulatory constraints for transport; international liability and insurance; emergency planning and preparedness; training; services provided by the IAEA.

Safe transport of radioactive material. 3. ed

International Nuclear Information System (INIS)

2002-01-01

The IAEA has developed a standardized approach to transport safety training as a means of helping Member States to implement the Transport Regulations. The training manual is an anchor of this standardized approach to training: it contains all the topics presented in the sequential order recommended by the IAEA for the student to gain a thorough understanding of the body of knowledge that is needed to ensure that radioactive material ranked as Class 7 in the United Nations' nomenclature for dangerous goods - is transported safely. The explanations in the text refer, where needed, to the appropriate requirements in the IAEA's Transport Regulations; additional useful information is also provided. Thus, the training manual in addition to the Transport Regulations and their supporting documents is used by the IAEA as the basis for delivering all of its training courses on the safe transport of radioactive material. Enclosed with the training manual is a CD-ROM that contains the text of the manual as well as the visual aids that are used at the IAEA's training courses. The following topics are covered: review of radioactivity and radiation; review of radiation protection principles; regulatory terminology; basic safety concepts: materials and packages; activity limits and material restrictions; selection of optimal package type; test procedures: material and packages; requirements for transport; control of material in transport; fissile material: regulatory requirements and operational aspects; quality assurance; national competent authority; additional regulatory constraints for transport; international liability and insurance; emergency planning and preparedness; training; services provided by the IAEA

76 FR 47577 - Enstor Grama Ridge Storage and Transportation, L.L.C.; Enstor Katy Storage and Transportation, L...

Science.gov (United States)

2011-08-05

... DEPARTMENT OF ENERGY Federal Energy Regulatory Commission [Docket No. PR10-97-003; Docket No. PR10-101-003; Not Consolidated] Enstor Grama Ridge Storage and Transportation, L.L.C.; Enstor Katy Storage and Transportation, L.P.; Notice of Filing Take notice that on July 29, 2011, the applicants listed...

Safe transport of radioactive material. Second edition

International Nuclear Information System (INIS)

1991-01-01

The transport of radioactive material embraces the carriage of radioisotopes for industrial, medical and research uses, and the movement of waste, in addition to consignments of nuclear fuel cycle material. It has been estimated that between eighteen and thirty-eight million package shipments take place each year. On the recommendation of the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM), which enjoys wide representations from the Agency's Member States and international organizations, the Secretariat is preparing a training kit comprising this training manual and complementary visual aids. The kit is intended to be the basis for an extensive course on the subject and can be used in whole or in part for inter-regional, regional and even national training purposes. Member States can thus benefit from the material either through training courses sponsored by the Agency, or, alternatively, organized by themselves. As a step towards achieving that goal, the current training manual was compiled using material from the first Inter-Regional Training Course on the Safe Transport of Radioactive material that was held in co-operation with the Nuclear Power Training Centre of the then Central Electricity Generating Board at Bristol, United Kingdom. This Manual was initially published in 1990. On the recommendation of the Agency's Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM), the Manual has since been expanded and updated in time for the second Inter-Regional Training Course, that will in 1991 similarly be held in Bristol. Refs, figs, tabs

Development of assessment methods for transport and storage containers with higher content of metallic recycling material

International Nuclear Information System (INIS)

Zencker, U.; Qiao Linan; Droste, B.

2004-01-01

The mechanical behaviour of transport and storage containers made of ductile cast iron melted with higher content of metallic recycling material from decommissioning and dismantling of nuclear installations is investigated. With drop tests of cubic container-like models, the influence of different real targets on the stresses in the cask body and the fracture behaviour is examined. A test stand foundation is suggested, which can be manufactured simply and improves the reproducibility of the test results strongly. The test objects are partially equipped with artificial cracklike defects. Dynamic fracture mechanics analyses of these defects were performed by means of finite element calculations to uncover safety margins. Numerous test results show depending on the requirements that containers for final disposal can be built by means of a ductile cast iron with fracture toughness more than half under the lower bound value for the licensed material qualities yet. The application limits of the material are determined also by the opportunities of the safety assessment methods. This project supports the application of brittle fracture safe transport and storage packages for radioactive materials as recommended in App. VI of the Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (IAEA No. TS-G-1.1)

Development of assessment methods for transport and storage containers with higher content of metallic recycling material

Energy Technology Data Exchange (ETDEWEB)

Zencker, U.; Qiao Linan; Droste, B. [Bundesanstalt fuer Materialforschung und -pruefung (BAM), Berlin (Germany)

2004-07-01

The mechanical behaviour of transport and storage containers made of ductile cast iron melted with higher content of metallic recycling material from decommissioning and dismantling of nuclear installations is investigated. With drop tests of cubic container-like models, the influence of different real targets on the stresses in the cask body and the fracture behaviour is examined. A test stand foundation is suggested, which can be manufactured simply and improves the reproducibility of the test results strongly. The test objects are partially equipped with artificial cracklike defects. Dynamic fracture mechanics analyses of these defects were performed by means of finite element calculations to uncover safety margins. Numerous test results show depending on the requirements that containers for final disposal can be built by means of a ductile cast iron with fracture toughness more than half under the lower bound value for the licensed material qualities yet. The application limits of the material are determined also by the opportunities of the safety assessment methods. This project supports the application of brittle fracture safe transport and storage packages for radioactive materials as recommended in App. VI of the Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (IAEA No. TS-G-1.1).

Safe Transport of Radioactive Material, Philosophy and Overview

Energy Technology Data Exchange (ETDEWEB)

EL-Shinawy, R M.K. [Radiation Protection Dept., Nuclear Rasearch Center, Atomic Energy Authority, Cairo (Egypt)

2008-07-01

Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international and national regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1(ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series Nos 7and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series Nos 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS no.113), compliance assurance (SS no. 112), the training manual and others.

Safe Transport of Radioactive Material, Philosophy and Overview

International Nuclear Information System (INIS)

EL-Shinawy, R.M.K.

2008-01-01

Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international and national regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1(ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series Nos 7and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series Nos 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS no.113), compliance assurance (SS no. 112), the training manual and others

Criteria for the safe storage of enriched uranium at the Y-12 Plant

International Nuclear Information System (INIS)

Cox, S.O.

1995-07-01

Uranium storage practices at US Department of Energy (DOE) facilities have evolved over a period spanning five decades of programmatic work in support of the nuclear deterrent mission. During this period, the Y-12 Plant in Oak Ridge, Tennessee has served as the principal enriched uranium facility for fabrication, chemical processing, metallurgical processing and storage. Recent curtailment of new nuclear weapons production and stockpile reduction has created significant amounts of enriched uranium available as a strategic resource which must be properly and safely stored. This standard specifies criteria associated with the safe storage of enriched uranium at the Y-12 Plant. Because programmatic needs, compliance regulations and desirable materials of construction change with time, it is recommended that these standards be reviewed and amended periodically to ensure that they continue to serve their intended purpose

Electronic Monitoring Of Storage And Transport Temperatures Of ...

African Journals Online (AJOL)

Electronic Monitoring Of Storage And Transport Temperatures Of Thermostable Newcastle ... 22) were monitored during storage and transport from vaccine production laboratory in Temeke, Dar es ... EMAIL FULL TEXT EMAIL FULL TEXT

Standardized, utility-DOE compatible, spent fuel storage-transport systems

International Nuclear Information System (INIS)

Smith, M.L.

1991-01-01

Virginia Power has developed and licensed a facility for dry storage of spent nuclear fuel in metal spent fuel storage casks. The modifications to the design of these casks necessary for licensing for both storage and transport of spent fuel are discussed along with the operational advantages of dual purpose storage-transport casks. Dual purpose casks can be used for storage at utility and DOE sites (MRS or repository) and for shipment between these sites with minimal spent fuel handling. The cost for a standardized system of casks that are compatible for use at both DOE and utility sites is discussed along with possible arrangements for sharing both the cost and benefits of dual purpose storage-transport casks

Quality assurance for the safe transport of radioactive material

International Nuclear Information System (INIS)

1994-01-01

All activities related to the safe transport of radioactive material should be covered by a quality assurance programme. This publication recognizes that a single transport operation often involves several different organizations, each having specific responsibilities. Hence, it is unlikely that the operation will be covered by a single quality assurance programme. Each quality assurance programme should be tailored to the specific organizational structure for which the programme is prepared, with account taken of the particular transport activities of that organization and the interfaces with other organizations. The aim of this publication is to give a detailed interpretation of what must be done by whom to produce a quality assurance programme for radioactive material transport. This publication provides guidance on methods and practical examples to develop QA programmes for the safe transport of radioactive material. It provides information on how to develop the programme, the standards and the common features of a QA programme

Selection of exception limits for all actinide nuclides based on revised criteria for safe international transport and including storage delay

International Nuclear Information System (INIS)

Lavarenne, C.; Rouyer, V.; Mennerdahl, D.; Dean, C.; Barton, N.; Jean, F.

2004-01-01

Since 1998, there have been some speculations about future transport of significant quantities and concentrations of other actinide nuclides than the four currently listed in the regulation for the safe transport of the radioactive material. Therefore, it raised a need to specify exception limits for such actinides. In order to define credible exception limits, it was necessary to have reasonably accurate data for all actinide nuclides. Then the DGTREN/participants decided to perform calculations with different codes (MONK, MCNP, CRISTAL and SCALE) and different cross-section libraries (JEF2.2, ENDFB, etc.). The parameters of interest (such as k-infinite, critical masses) were determined. This article presents the work achieved and the questions raised, e.g. related to the effect of the radioactive decay of the isotopes on the criticality risks. It also points out the need for an evolution of the regulation of the safe transport of radioactive materials and gives a proposition of modification for the IAEA requirements related to, firstly, the list of the fissile materials, secondly, the rule to determine the quantities of actinide nuclides that can be excepted from the requirements for the packages containing fissile materials

Plutonium storage criteria

Energy Technology Data Exchange (ETDEWEB)

Chung, D. [Scientech, Inc., Germantown, MD (United States); Ascanio, X. [Dept. of Energy, Germantown, MD (United States)

1996-05-01

The Department of Energy has issued a technical standard for long-term (>50 years) storage and will soon issue a criteria document for interim (<20 years) storage of plutonium materials. The long-term technical standard, {open_quotes}Criteria for Safe Storage of Plutonium Metals and Oxides,{close_quotes} addresses the requirements for storing metals and oxides with greater than 50 wt % plutonium. It calls for a standardized package that meets both off-site transportation requirements, as well as remote handling requirements from future storage facilities. The interim criteria document, {open_quotes}Criteria for Interim Safe Storage of Plutonium-Bearing Solid Materials{close_quotes}, addresses requirements for storing materials with less than 50 wt% plutonium. The interim criteria document assumes the materials will be stored on existing sites, and existing facilities and equipment will be used for repackaging to improve the margin of safety.

The safe transport of radioactive material in South Africa

International Nuclear Information System (INIS)

Jutle, K.K.

1997-01-01

An overview is presented of the activities related to the transport of radioactive material in South Africa. In particular, the applicable legislation, the scope of authority and regulatory functions of the Competent Authority are discussed. The categories of radioactive materials transported and the packaging requirements for the safe transport of these radioactive materials are also described. (Author)

The safe transport of radioactive material in South Africa

International Nuclear Information System (INIS)

Jutle, K.K.

2000-01-01

An overview is presented of the activities related to the transport of radioactive material in South Africa. In particular, the applicable legislation, the scope of authority and the regulatory functions of the Competent Authority are discussed. The categories of radioactive materials transported and the packaging requirements for the safe transport of these radioactive materials are also described. (author)

Hydrogen transport and storage in engineered glass microspheres

Energy Technology Data Exchange (ETDEWEB)

Rambach, G.D.

1995-02-28

New, high strength glass microspheres filled with pressurized hydrogen exhibit densities which make them attractive for bulk hydrogen storage and transport. The membrane tensile stress at failure for engineered glass microspheres is about 150,000 psi, permitting a three-fold increase in pressure limit and storage capacity above commercial microspheres, which have been studied a decade ago and have been shown to fail at membrane stresses of 50,000 psi. This analysis relating glass microspheres for hydrogen transport with infrastructure and economics, indicate that pressurized microspheres can be economically competitive with other forms of bulk rail and truck transport such as pressurized tube transports and liquid hydrogen trailers. This paper will describe the matching of current glass microspheres with the useful application in commercial hydrogen bulk transport and storage.

Final hazard classification and auditable safety analysis for the 105-C Reactor Interim Safe Storage Project

International Nuclear Information System (INIS)

Rodovsky, T.J.; Larson, A.R.; Dexheimer, D.

1996-12-01

This document summarizes the inventories of radioactive and hazardous materials present in the 105-C Reactor Facility and the operations associated with the Interim Safe Storage Project which includes decontamination and demolition and interim safe storage of the remaining facility. This document also establishes a final hazard classification and verifies that appropriate and adequate safety functions and controls are in place to reduce or mitigate the risk associated with those operations

Use of polyethylene pellets in the design and construction of a storage safe, a transport vessel and a portable shield for californium-252

International Nuclear Information System (INIS)

Sharma, S.

1986-01-01

A storage and shielding facility for 300 μg of Californium-252 sources was designed and constructed. Though the safe was in a permanent location, the fact that it consisted of a lead bucket surrounded by polyethylene pellets made it simple, movable and inexpensive. If need be, more quantities of Cf-252 could be added without altering the basic design and sacrificing the radiation protection guidelines. The measured radiation levels from 300 μg of stored Cf-252 in and around the storage vault were lower than the expected dose rates by a factor of 5. The measured radiation levels around the occupied environs of the facility were below the maximum permissible yearly dose of 500mrem for non-occupational workers. A transport vessel was designed and constructed to carry up to 50 μg of Californium-252 sources. It consisted of a standard 55 gallon steel drum on casters containing cylindrical lead shield surrounded by polyethylene pellets. The measured maximum surface dose rates on the drum and at one meter away were within the radiation protection guidelines and were less than the expected dose rates. A portable shield was designed and constructed to protect the body in afterloading operations and handling of the sources. It consisted of polyethylene pellets in an aluminum box and an attached 10 cm thick plexiglass eye shield. The simple design, with the ease of using polyethylene pellets can be extended to construct bedside shields

Qualification testing facility for packages to be used for transport and storage of radioactive materials

International Nuclear Information System (INIS)

Vieru, Gheorghe

2009-01-01

The radioactive materials (RAM) packaging have to comply to all modes and transport condition, routine or in accident conditions possibly to occur during transportation operations. It is well known that the safety in the transport of RAM is dependent on packaging appropriate for the contents being shipped rather than on operational and/or administrative actions required for the package. The quality of these packages - type A, B or C has to be proved by performing qualification tests in accordance with the ROMANIAN nuclear regulation conditions provided by CNCAN Order no. 357/22.12.2005- 'Norms for a Safe Transport of Radioactive Material', the IAEA Vienna Recommendation stipulated in the Safety standard TS-R-1- Regulation for the Safe Transport of Radioactive Material, 2005 Edition, and other applicable international recommendations. The paper will describe the components of the designed testing facilities, and the qualification testing to be performed for all type A, B and C packages subjected to the testing. In addition, a part of the qualification tests for a package (designed and manufactured in INR Pitesti) used for transport and storage of spent fuel LEU elements of a TRIGA nuclear reactor will be described and analyzed. Quality assurance and quality controls measures taken in order to meet technical specification provided by the design are also presented and commented. The paper concludes that the new Romanian Testing Facilities for RAM packages will comply with the national safe standards as well as with the IAEA applicable recommendation provided by the TS-R-1 safety standard. (author)

10 CFR 34.35 - Labeling, storage, and transportation.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Labeling, storage, and transportation. 34.35 Section 34.35 Energy NUCLEAR REGULATORY COMMISSION LICENSES FOR INDUSTRIAL RADIOGRAPHY AND RADIATION SAFETY REQUIREMENTS FOR INDUSTRIAL RADIOGRAPHIC OPERATIONS Equipment § 34.35 Labeling, storage, and transportation. (a...

Storage/transport cask design and challenges

International Nuclear Information System (INIS)

Houston, J.V.; Viebrock, J.M.

1989-01-01

The concept of spent-fuel casks that could be used for both storage and for transport has been around for some years, but was only seriously evaluated when utilities started becoming concerned about adequate fuel storage. In the early 1980s, the U.S. Department of Energy proposed to solve the problem with their away-from-reactor storage facility concept. This was superceded by passage of the Nuclear Waste Policy Act of 1982, which directed the development of one or more waste repositories, the first of which was to be in operation by 1998. Delays in this program now indicate an opening data of 2003 or later. This, together with the lack of significant progress on a monitored retrievable storage facility, leaves the utility companies to solve their storage problems individually. One alternative is to use dual-purpose casks. The use of such a cask should eliminate the need to move the cask and fuel back into the spent-fuel pool for transfer to a transport cask. However, a dual-purpose cask must be licensed for use under both 10CFR71 and 10CFR72 of the U.S. Code of Federal Regulations. The purpose of this paper is to examine the differences between the requirements of 10CFR71 and 10CFR72, to note the changes over the past several years in the NRC's interpretation of 10CFR71 requirements, and to review the design modifications that the Nuclear Assurance Corporation (NAC) believes are required to make a licensed storage cask acceptable for transport under 10CFR71

Augmenting Transport versus Increasing Cold Storage to Improve Vaccine Supply Chains

Science.gov (United States)

Haidari, Leila A.; Connor, Diana L.; Wateska, Angela R.; Brown, Shawn T.; Mueller, Leslie E.; Norman, Bryan A.; Schmitz, Michelle M.; Paul, Proma; Rajgopal, Jayant; Welling, Joel S.; Leonard, Jim; Chen, Sheng-I; Lee, Bruce Y.

2013-01-01

Background When addressing the urgent task of improving vaccine supply chains, especially to accommodate the introduction of new vaccines, there is often a heavy emphasis on stationary storage. Currently, donations to vaccine supply chains occur largely in the form of storage equipment. Methods This study utilized a HERMES-generated detailed, dynamic, discrete event simulation model of the Niger vaccine supply chain to compare the impacts on vaccine availability of adding stationary cold storage versus transport capacity at different levels and to determine whether adding stationary storage capacity alone would be enough to relieve potential bottlenecks when pneumococcal and rotavirus vaccines are introduced by 2015. Results Relieving regional level storage bottlenecks increased vaccine availability (by 4%) more than relieving storage bottlenecks at the district (1% increase), central (no change), and clinic (no change) levels alone. Increasing transport frequency (or capacity) yielded far greater gains (e.g., 15% increase in vaccine availability when doubling transport frequency to the district level and 18% when tripling). In fact, relieving all stationary storage constraints could only increase vaccine availability by 11%, whereas doubling the transport frequency throughout the system led to a 26% increase and tripling the frequency led to a 30% increase. Increasing transport frequency also reduced the amount of stationary storage space needed in the supply chain. The supply chain required an additional 61,269L of storage to relieve constraints with the current transport frequency, 55,255L with transport frequency doubled, and 51,791L with transport frequency tripled. Conclusions When evaluating vaccine supply chains, it is important to understand the interplay between stationary storage and transport. The HERMES-generated dynamic simulation model showed how augmenting transport can result in greater gains than only augmenting stationary storage and can reduce

Augmenting transport versus increasing cold storage to improve vaccine supply chains.

Science.gov (United States)

Haidari, Leila A; Connor, Diana L; Wateska, Angela R; Brown, Shawn T; Mueller, Leslie E; Norman, Bryan A; Schmitz, Michelle M; Paul, Proma; Rajgopal, Jayant; Welling, Joel S; Leonard, Jim; Chen, Sheng-I; Lee, Bruce Y

2013-01-01

When addressing the urgent task of improving vaccine supply chains, especially to accommodate the introduction of new vaccines, there is often a heavy emphasis on stationary storage. Currently, donations to vaccine supply chains occur largely in the form of storage equipment. This study utilized a HERMES-generated detailed, dynamic, discrete event simulation model of the Niger vaccine supply chain to compare the impacts on vaccine availability of adding stationary cold storage versus transport capacity at different levels and to determine whether adding stationary storage capacity alone would be enough to relieve potential bottlenecks when pneumococcal and rotavirus vaccines are introduced by 2015. Relieving regional level storage bottlenecks increased vaccine availability (by 4%) more than relieving storage bottlenecks at the district (1% increase), central (no change), and clinic (no change) levels alone. Increasing transport frequency (or capacity) yielded far greater gains (e.g., 15% increase in vaccine availability when doubling transport frequency to the district level and 18% when tripling). In fact, relieving all stationary storage constraints could only increase vaccine availability by 11%, whereas doubling the transport frequency throughout the system led to a 26% increase and tripling the frequency led to a 30% increase. Increasing transport frequency also reduced the amount of stationary storage space needed in the supply chain. The supply chain required an additional 61,269L of storage to relieve constraints with the current transport frequency, 55,255L with transport frequency doubled, and 51,791L with transport frequency tripled. When evaluating vaccine supply chains, it is important to understand the interplay between stationary storage and transport. The HERMES-generated dynamic simulation model showed how augmenting transport can result in greater gains than only augmenting stationary storage and can reduce stationary storage needs.

What is plutonium stabilization, and what is safe storage of plutonium?

International Nuclear Information System (INIS)

Forsberg, C.W.

1995-01-01

The end of the cold war has resulted in the shutdown of nuclear weapons production and the start of dismantlement of significant numbers of nuclear weapons. This, in turn, is creating an inventory of plutonium requiring interim and long-term storage. A key question is, ''What is required for safe, multidecade, plutonium storage?'' The requirements for storage, in turn, define what is needed to stabilize the plutonium from its current condition into a form acceptable for interim and long-term storage. Storage requirements determine if research is required to (1) define required technical conditions for interim and long-term storage and (2) develop or improve current stabilization technologies. Storage requirements depend upon technical, policy, and economic factors. The technical issues are complicated by several factors. Plutonium in aerosol form is highly hazardous. Plutonium in water is hazardous. The plutonium inventory is in multiple chemical forms--some of which are chemically reactive. Also, some of the existing storage forms are clearly unsuitable for storage periods over a few years. Gas generation by plutonium compounds complicates storage: (1) all plutonium slowly decays creating gaseous helium and (2) the radiation from plutonium decay can initiate many chemical reactions-some of which generate significant quantities of gases. Gas generation can pressurize sealed storage packages. Last nuclear criticality must be avoided

CASTOR(r) and CONSTOR(r) type transport and storage casks for spent fuel and high active waste

International Nuclear Information System (INIS)

Kuehne, B.; Sowa, W.

2002-01-01

The German company GNB has developed, tested, licensed, fabricated, loaded, transported and stored a large number of casks for spent fuel and high-level waste. CASTOR(r) casks are used at 18 sites on three continents. Spent fuel assemblies of the types PWR, BWR, VVER, RBMK, MTR and THTR as well as vitrified high active waste (HAW) containers are stored in these kinds of casks. More than 600 CASTOR(r) casks have been loaded for long-term storage. The two decades of storage have shown that the basic requirements, which are safe confinement, criticality safety, sufficient shielding and appropriate heat transfer have been fulfilled in each case. There is no indication that problems will arise in the future. Of course, the experience of 20 years has resulted in improvements of the cask design. One basic improvement is GNB's development since the mid 1990s of a sandwich cask design using heavy concrete and steel as basic materials, for economical and technical reasons. This CONSTOR(r) cask concept also fulfils all design criteria for transport and storage given by the IAEA recommendations and national authorities. By May 2002 40 CONSTOR(r) casks had been delivered and 15 had been successfully loaded and stored. In this paper the different types of casks are presented. Experiences gained during the large number of cask loadings and more than 4000 cask-years of storage will be summarised. The presentation of recent and future development shows the optimisation potential of the CASTOR(r) and CONSTOR(r) cask families for safe and economical management of spent fuel. (author)

Safe dry storage of intermediate-level waste at CRL

International Nuclear Information System (INIS)

Chiu, A.; Sanderson, T.; Lian, J.

2011-01-01

Ongoing operations at Atomic Energy of Canada Limited's (AECL) Chalk River Laboratories (CRL) generate High-, Intermediate- and Low-Level Waste (HLW, ILW and LLW) that will require safe storage for several decades until a long-term management facility is available. This waste is stored in below grade concrete structures (i.e. tile holes or bunkers) or the above-ground Shielded Modular Above Ground Storage (SMAGS) facility depending on the thermal and shielding requirements of the particular waste package. Existing facilities are reaching their capacity and alternate storage is required for the future storage of this radioactive material. To this end, work has been undertaken at CRL to design, license, construct and commission the next generation of waste management facilities. This paper provides a brief overview of the existing radioactive-waste management facilities used at CRL and focuses on the essential requirements and issues to be considered in designing a new waste storage facility. Fundamentally, there are four general requirements for a new storage facility to dry store dry non-fissile ILW. They are the need to provide: (1) containment, (2) shielding, (3) decay heat removal, and (4) ability to retrieve the waste for eventual placement in an appropriate long-term management facility. Additionally, consideration must be given to interfacing existing waste generating facilities with the new storage facility. The new facilities will be designed to accept waste for 40 years followed by 60 years of passive storage for a facility lifespan of 100 years. The design should be modular and constructed in phases, each designed to accept ten years of waste. This strategy will allow for modifications to subsequent modules to account for changes in waste characteristics and generation rates. Two design concepts currently under consideration are discussed. (author)

Evaluation of storage/transportation options to support criteria development for the Phase I MRS [Monitored Retrievable Storage

International Nuclear Information System (INIS)

Sorenson, K.B.; Brown, N.N.; Bennett, P.C.; Lake, W.

1991-01-01

The Department of Energy's (DOE) Office of Civilian Waste Management (OCRWM) plans to develop an interim storage facility to enable acceptance of spent fuel in 1998. It is estimated that this interim storage facility would be needed for about two years. A Monitored Retrievable Storage (MRS) facility is anticipated in 2000 and a repository in 2010. Acceptance and transport of spent fuel by DOE/OCRWM in 1998 will require an operating transportation system. Because this interim storage facility is not yet defined, development of an optimally compatible transportation system is not a certainty. In order to assure a transport capability for 1998 acceptance of spent fuel, it was decided that the OCRWM transportation program had to identify likely options for an interim storage facility, including identification of the components needed for compatibility between likely interim storage facility options and transportation. Primary attention was given to existing hardware, although conceptual designs were also considered. A systems-based probabilistic decision model was suggested by Sandia National Laboratories and accepted by DOE/OCRWM's transportation program. Performance of the evaluation task involved several elements of the transportation program. This paper describes the decision model developed to accomplish this task, along with some of the results and conclusions. 1 ref., 4 figs

The challenge of improving boiling: lessons learned from a randomized controlled trial of water pasteurization and safe storage in Peru.

Science.gov (United States)

Heitzinger, K; Rocha, C A; Quick, R E; Montano, S M; Tilley, D H; Mock, C N; Carrasco, A J; Cabrera, R M; Hawes, S E

2016-07-01

Boiling is the most common method of household water treatment in developing countries; however, it is not always effectively practised. We conducted a randomized controlled trial among 210 households to assess the effectiveness of water pasteurization and safe-storage interventions in reducing Escherichia coli contamination of household drinking water in a water-boiling population in rural Peru. Households were randomized to receive either a safe-storage container or a safe-storage container plus water pasteurization indicator or to a control group. During a 13-week follow-up period, households that received a safe-storage container and water pasteurization indicator did not have a significantly different prevalence of stored drinking-water contamination relative to the control group [prevalence ratio (PR) 1·18, 95% confidence interval (CI) 0·92-1·52]. Similarly, receipt of a safe-storage container alone had no effect on prevalence of contamination (PR 1·02, 95% CI 0·79-1·31). Although use of water pasteurization indicators and locally available storage containers did not increase the safety of household drinking water in this study, future research could illuminate factors that facilitate the effective use of these interventions to improve water quality and reduce the risk of waterborne disease in populations that boil drinking water.

Transport casks help solve spent fuel interim storage problems

International Nuclear Information System (INIS)

Dierkes, P.; Janberg, K.; Baatz, H.; Weinhold, G.

1980-01-01

Transport casks can be used as storage modules, combining the inherent safety of passive cooling with the absence of secondary radioactive waste and the flexibility to build up storage capacity according to actual requirements. In the Federal Republic of Germany, transport casks are being developed as a solution to its interim storage problems. Criteria for their design and licensing are outlined. Details are given of the casks and the storage facility. Tests are illustrated. (U.K.)

USING POLYMERIC HYDROGEN GETTERS TO PREVENT COMBUSTIBLE ATMOSPHERES DURING INTERIM SAFE STORAGE OF PLUTONIUM OXIDE

International Nuclear Information System (INIS)

Woodsmall, T

2007-01-01

Nuclear Materials Management (NMM) of WSRC has recently installed the capability to perform both non-destructive and destructive examination of 3013 containers of Pu oxide in accordance with DOE-STD-3013. The containers will be opened and the oxide will be sampled for analysis. The remaining bulk oxide must then be safely stored in a non-3013-compliant configuration. Available processing equipment and controls cannot prevent the oxide from adsorbing moisture during this process. Subsequent radiolysis of moisture during storage may generate combustible quantities of gases while waiting final processing, and satisfying DOE Interim Safe Storage Criteria (ISSC) would require that storage containers be vented at impractical frequencies. With support from an independent National Laboratory, WSRC/NMM has demonstrated that a commercial hydrogen getter material will effectively prevent the accumulation of combustible gas concentrations. A project overview, including storage requirements and strategies, as well as getter technology, current test results, and anticipated future developments will be addressed

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

Energy Technology Data Exchange (ETDEWEB)

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

1978-04-01

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.

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

International Nuclear Information System (INIS)

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

1978-04-01

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

Concept study for interim storage of research reactor fuel elements in transport and storage casks. Transport and storage licensing procedure for the CASTOR MTR 2 cask. Final report

International Nuclear Information System (INIS)

Weiss, M.

2001-01-01

As a result of the project, a concept was to be developed for managing spent fuel elements from research reactors on the basis of the interim storage technology existing in Germany, in order to make the transition to direct disposal possible in the long term. This final report describes the studies for the spent fuel management concept as well as the development of a transport and storage cask for spent fuel elements from research reactors. The concept analyses were based on data of the fuel to be disposed of, as well as the handling conditions for casks at the German research reactors. Due to the quite different conditions for handling of casks at the individual reactors, it was necessary to examine different cask concepts as well as special solutions for loading the casks outside of the spent fuel pools. As a result of these analyses, a concept was elaborated on the basis of a newly developed transport and storage cask as well as a mobile fuel transfer system for the reactor stations, at which a direct loading of the cask is not possible, as the optimal variant. The cask necessary for this concept with the designation CASTOR trademark MTR 2 follows in ist design the tried and tested principles of the CASTOR trademark casks for transport and interim storage of spent LWR fuel. With the CASTOR trademark MTR 2, it is possible to transport and to place into long term interim storage various fuel element types, which have been and are currently used in German research reactors. The technical development of the cask has been completed, the documents for the transport license as type B(U)F package design and for obtaining the storage license at the interim storage facility of Ahaus have been prepared, submitted to the licensing authorities and to a large degree already evaluated positively. The transport license of the CASTOR trademark MTR 2 has been issued for the shipment of VKTA-contents and FRM II compact fuel elements. (orig.)

Hydrogen transport and storage in engineered glass microspheres

Energy Technology Data Exchange (ETDEWEB)

Rambach, G.D.

1995-04-18

New, high strength glass microspheres filled with pressurized hydrogen exhibit densities which make them attractive for bulk hydrogen storage and transport. The membrane tensile stress at failure for our engineered glass microspheres is about 150,000 psi, permitting a threefold increase in pressure limit and storage capacity above commercial microspheres, which have been studied a decade ago and have been shown to fail at membrane stresses of 50,000 psi. Our analysis relating glass microspheres for hydrogen transport with infrastructure and economics, indicate that pressurized microspheres can be economically competitive with other forms of bulk rail and truck transport such as pressurized tube transports and liquid hydrogen trailers.

The amended regulations for the safe transport of radioactive materials in Japan

International Nuclear Information System (INIS)

Takemura, Yoshio

1978-01-01

To cope with the inadequacies of the laws and regulations including the Law Concerning Prevention of Radiation Injuries Due to Radioisotopes, Etc., the Amended Regulations for the Safe Transport of Radioactive Materials in Japan has been issued. It is based on the Regulations of IAEA for the Safe Transport of Radioactive Materials and the Technical Standards for the Transport of Radioactive Materials decided by the AEC of Japan. In the amended regulations, emphasis is placed on the safety design of transporting goods. They are classified in Types L, A and B according to shock resistance and fire resistance, and the quantities of radioisotopes allowed to be contained in respective types are specified. The following matters are described: basic ideas concerning the types of transporting goods, test standards for the goods, transport standards for the goods, and nondestructive test apparatuses in transport. (Mori, K.)

Integrated spent fuel storage and transportation system using NUHOMS

International Nuclear Information System (INIS)

Lehnert, R.; McConaghy, W.; Rosa, J.

1990-01-01

As utilities with nuclear power plants face increasing near term spent fuel store needs, various systems for dry storage such as the NUTECH Horizontal Modular Storage (NUHOMS) system are being implemented to augment existing spent fuel pool storage capacities. These decisions are based on a number of generic and utility specific considerations including both short term and long term economics. Since the US Department of Energy (DOE) is tasked by the Nuclear Waste Policy Act with the future responsibility of transporting spent fuel from commercial nuclear power plants to a Monitored Retrievable Storage (MRS) facility anchor a permanent geologic repository, the interfaces between the utilities at-reactor dry storage system and the DOE's away-from-reactor transportation system become important. This paper presents a study of the interfaces between the current at-reactor NUHOMS system and the future away-from-reactor DOE transportation system being developed under the Office of Civilian Radioactive Waste Management (OCRWM) program. 7 refs., 9 figs., 1 tab

Inherently safe aircooling for the storage of self-heating configurations of radionuclides

International Nuclear Information System (INIS)

Hame, W.; Klein, D.; Pirk, H.

1980-01-01

NUKEM developed a technical concept of a radionuclide storage facility based on aircooling, which provides that - the radionuclides, i.e. spent fuel elements, are tightly canned in steel canisters - the canned elements are put into individual cooling channels, which form the storage rack within the storage cell - the produced heat is removed from the surface of the canisters through free convection. This cooling concept shows the following advantages: - The cooling is inherently safe, as the driving force of the coolant is reliably supplied by the heat production of the system to be cooled. - The system is self-controlled and self-regulated because of the physically based correlation of heat production, heat transfer coefficients and air flow resistances. (orig.) 891 RB/orig. 892 MKO [de

An Indian perspective for transportation and storage of spent fuel

International Nuclear Information System (INIS)

Dey, P.K.

2005-01-01

The spent fuel discharged from the reactors are temporarily stored at the reactor pool. After a certain cooling time, the spent fuel is moved to the storage locations either on or off reactor site depending on the spent fuel management strategy. As India has opted for a closed fuel cycle for its nuclear energy development, reprocessing of the spent fuel, recycling of the reprocessed plutonium and uranium and disposal of the wastes from the reprocessing operations forms the spent fuel management strategy. Since the reprocessing operations are planned to match the nuclear energy programme, storage of the spent fuel in ponds are adopted prior to reprocessing. Transport of the spent fuel to the storage locations are carried out adhering to international and national guide lines. India is having 14 operating power reactors and three research reactors. The spent fuel from the two safeguarded BWRs are stored at-reactor (AR) storage pond. A separate wet storage facility away-from-reactor (AFR) has been designed, constructed and made operational since 1991 for additional fuel storage. Storage facilities are provided in ARs at other reactor locations to cater to 10 reactor-years of operation. A much lower capacity spent fuel storage is provided in reprocessing plants on the same lines of AR fuel storage design. Since the reprocessing operations are carried out on a need basis, to cater to the increased storage needs two new spent fuel storage facilities (SFSF) are being designed and constructed near the existing nuclear plant sites. India has mastered the technology for design, construction and operation of wet spent fuel storage facility meeting all the international standards Wet storage of the spent fuel is the most commonly adopted mode all over the world. Recently an alternate mode viz. dry storage has also been considered. India has designed, constructed and operated lead shielded dry storage casks and is operational at one site. A dry storage cask made of concrete

Safe transport of radioactive material. 4. ed

International Nuclear Information System (INIS)

2006-01-01

The IAEA has been publishing Regulations for the Safe Transport of Radioactive Material since 1961. Meeting its statutory obligation to foster the exchange and training of scientists and experts in the field of peaceful uses of atomic energy, the IAEA has developed a standardized approach to transport safety training. This training manual is an anchor of the standardized approach to training. It is a compendium of training modules for courses related to the different aspects of safety of transport of radioactive material. Keeping in view the specific needs of the potential users, the manual includes material that can be used for a variety of training programmes of duration ranging from half-a-day to ten days, for specific audiences such as competent authority personnel, public authorities, emergency response personnel and cargo handlers

Sediment transport-storage relations for degrading, gravel bed channels

Science.gov (United States)

Thomas E. Lisle; Michael Church

2002-01-01

In a drainage network,sediment is transferred through a series of channel/valley segments (natural sediment storage reservoirs) that are distinguished from their neighbors by their particular capacity to store and transport sediment. We propose that the sediment transport capacity of each reservoir is a unique positive function of storage volume, which influences...

Universal storage/transport/disposal packages

International Nuclear Information System (INIS)

Smith, M.L.

1992-01-01

In this paper a concept for a more robust Engineered Barrier System (EBS) that is part of an integrated waste management system is presented. This integrated system uses a thick walled metal package as the basic component of an integrated system for utility site storage, MRS storage, transportation, and disposal. Overpacks are used where necessary to supplement the basic package in each application. This integrated system combines the advantages of a robust EBS (improved margin and confidence in the repository) with a systems approach that can simplify the waste management system and reduce costs

AT-400A Type B transportation and storage package

International Nuclear Information System (INIS)

Cockrell, G.D.; Franklin, K.W.

1995-01-01

This paper discusses the design considerations for the AT-400A container which will meet the requirements for the transportation and long-term storage of plutonium pits. The AT-400A was designed by a joint effort between Sandia National Labs, Los Alamos National Labs, Lawrence Livermore National Laboratory, and Mason and Hanger Silas Mason Co., Inc.. The paper will outline the problems and impact on the design of the container necessitated by the need to meet DOT TYPE B transportation requirements and undefined requirements for the interim and long-term storage of pits. Areas covered will include: (1) determining the storage requirements, (2) surveillance program for interim storage, and (3) impact of storage requirements on the containment vessel and inner fixturing design

Integrated System for Retrieval, Transportation and Consolidated Storage of Used Nuclear Fuel in the US - 13312

International Nuclear Information System (INIS)

Bracey, William; Bondre, Jayant; Shelton, Catherine; Edmonds, Robert

2013-01-01

The current inventory of used nuclear fuel assemblies (UNFAs) from commercial reactor operations in the United States totals approximately 65,000 metric tons or approximately 232,000 UNFAs primarily stored at the 104 operational reactors in the US and a small number of decommissioned reactors. This inventory is growing at a rate of roughly 2,000 to 2,400 metric tons each year, (Approx. 7,000 UNFAs) as a result of ongoing commercial reactor operations. Assuming an average of 10 metric tons per storage/transportation casks, this inventory of commercial UNFAs represents about 6,500 casks with an additional of about 220 casks every year. In January 2010, the Blue Ribbon Commission (BRC) [1] was directed to conduct a comprehensive review of policies for managing the back end of the nuclear fuel cycle and recommend a new plan. The BRC issued their final recommendations in January 2012. One of the main recommendations is for the United States to proceed promptly to develop one or more consolidated storage facilities (CSF) as part of an integrated, comprehensive plan for safely managing the back end of the nuclear fuel cycle. Based on its extensive experience in storage and transportation cask design, analysis, licensing, fabrication, and operations including transportation logistics, Transnuclear, Inc. (TN), an AREVA Subsidiary within the Logistics Business Unit, is engineering an integrated system that will address the complete process of commercial UNFA management. The system will deal with UNFAs in their current storage mode in various configurations, the preparation including handling and additional packaging where required and transportation of UNFAs to a CSF site, and subsequent storage, operation and maintenance at the CSF with eventual transportation to a future repository or recycling site. It is essential to proceed by steps to ensure that the system will be the most efficient and serve at best its purpose by defining: the problem to be resolved, the criteria to

Integrated System for Retrieval, Transportation and Consolidated Storage of Used Nuclear Fuel in the US - 13312

Energy Technology Data Exchange (ETDEWEB)

Bracey, William; Bondre, Jayant; Shelton, Catherine [Transnuclear, Inc., 7135 Minstrel Way Suite 300, Columbia MD 21045 (United States); Edmonds, Robert [AREVA Federal Services, 7207 IBM Drive, Charlotte NC 28262 (United States)

2013-07-01

The current inventory of used nuclear fuel assemblies (UNFAs) from commercial reactor operations in the United States totals approximately 65,000 metric tons or approximately 232,000 UNFAs primarily stored at the 104 operational reactors in the US and a small number of decommissioned reactors. This inventory is growing at a rate of roughly 2,000 to 2,400 metric tons each year, (Approx. 7,000 UNFAs) as a result of ongoing commercial reactor operations. Assuming an average of 10 metric tons per storage/transportation casks, this inventory of commercial UNFAs represents about 6,500 casks with an additional of about 220 casks every year. In January 2010, the Blue Ribbon Commission (BRC) [1] was directed to conduct a comprehensive review of policies for managing the back end of the nuclear fuel cycle and recommend a new plan. The BRC issued their final recommendations in January 2012. One of the main recommendations is for the United States to proceed promptly to develop one or more consolidated storage facilities (CSF) as part of an integrated, comprehensive plan for safely managing the back end of the nuclear fuel cycle. Based on its extensive experience in storage and transportation cask design, analysis, licensing, fabrication, and operations including transportation logistics, Transnuclear, Inc. (TN), an AREVA Subsidiary within the Logistics Business Unit, is engineering an integrated system that will address the complete process of commercial UNFA management. The system will deal with UNFAs in their current storage mode in various configurations, the preparation including handling and additional packaging where required and transportation of UNFAs to a CSF site, and subsequent storage, operation and maintenance at the CSF with eventual transportation to a future repository or recycling site. It is essential to proceed by steps to ensure that the system will be the most efficient and serve at best its purpose by defining: the problem to be resolved, the criteria to

Demonstration of a transportable storage system for spent nuclear fuel

International Nuclear Information System (INIS)

Shetler, J.R.; Miller, K.R.; Jones, R.E.

1993-01-01

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

DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

Energy Technology Data Exchange (ETDEWEB)

T. A. Lee

2005-09-15

The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

DQO Summary Report for 105-N/109-N Interim Safe Storage Project Waste Characterization

International Nuclear Information System (INIS)

Lee, T.A.

2005-01-01

The DQO summary report provides the results of the DQO process completed for waste characterization activities for the 105-N/109-N Reactor Interim Safe Storage Project including decommission, deactivate, decontaminate, and demolish activities for six associated buildings.

State gun safe storage laws and child mortality due to firearms.

Science.gov (United States)

Cummings, P; Grossman, D C; Rivara, F P; Koepsell, T D

1997-10-01

Since 1989, several states have passed laws that make gun owners criminally liable if someone is injured because a child gains unsupervised access to a gun. These laws are controversial, and their effect on firearm-related injuries is unknown. To determine if state laws that require safe storage of firearms are associated with a reduction in child mortality due to firearms. An ecological study of firearm mortality from 1979 through 1994. All 50 states and the District of Columbia. All children younger than 15 years. Unintentional deaths, suicides, and homicides due to firearms. Laws that make gun owners responsible for storing firearms in a manner that makes them inaccessible to children were in effect for at least 1 year in 12 states from 1990 through 1994. Among children younger than 15 years, unintentional shooting deaths were reduced by 23% (95% confidence interval, 6%-37%) during the years covered by these laws. This estimate was based on within-state comparisons adjusted for national trends in unintentional firearm-related mortality. Gun-related homicide and suicide showed modest declines, but these were not statistically significant. State safe storage laws intended to make firearms less accessible to children appear to prevent unintentional shooting deaths among children younger than 15 years.

Quality performance-based training enhances safe and effective transport operations

International Nuclear Information System (INIS)

McCall, D.L.

1993-01-01

If the hazardous materials transportation industry is to reduce human error, reduce accidents, and improve its public image, there must be assurance that transportation personnel are properly trained and qualified to perform their jobs in a safe and efficient manner. This training must make them intimately aware of the hazards and risks associated with transport activities, ensure understanding of responsibilities and liabilities unique to their job, and ensure that they can competently perform functional duties vital to safety. To ensure that trained and qualified personnel are on the job, it is essential that the training be performance-based and require trainees to demonstrate functional proficiency. Performance-based training has proven to be a highly effective means of ensuring personnel are qualified to conduct their assignments safely and efficiently. This training is designed around the basic premise that training must be provided that supplies the information necessary for each worker to perform their assigned duties at a predetermined and acceptable level of expertise and skill. (J.P.N.)

Safe transport of tritium-producing burnable absorber rods: Intergovernmental regulations perspective

International Nuclear Information System (INIS)

Steinhoff, R.L.; Patterson, J.; Helvey, E.

2000-01-01

The state, tribal, and local governments along the shipment corridors share the US Department of Energy's (DOE's) goal of safe and uneventful radioactive materials transportation. The various governmental bodies involved can have different interpretations of a safe and uneventful shipping campaign. However, that gap has narrowed in recent years, due in part to improved coordination among DOE and the affected states, tribes, and municipal governments. This paper describes how the interactions between a new DOE radioactive materials transportation program and the corridor governments bridged that gap to create a shipping campaign that most of those involved viewed as safer and more publicly acceptable than had the process not occurred. It also describes the successful interaction between two DOE shipment campaigns transporting along much of the same route during the same time period

CASTOR registered HAW28M - a high heat load cask for transport and storage of vitrified high level waste containers

International Nuclear Information System (INIS)

Vossnacke, A.; Klein, K.; Kuehne, B.

2004-01-01

Within the German return programme for vitrified high level waste (HLW) from reprocessing at COGEMA and BNFL up to now 39 casks loaded with 28 containers each were transported back to Germany and are stored in the Interim Storage Facility Gorleben (TBL-G) for up to 40 years. For transport and storage in all but one case the GNB casks CASTOR registered HAW 20/28 CG have been used. This cask type is designed to accommodate 20 or 28 HLW containers with a total thermal power of 45 kW maximum. In the near future, among the high level waste, which has to be returned to Germany, there will be an increasing number of containers of which the heat capacity and radioactive inventory will exceed the technical limits of the CASTOR registered HAW 20/28 CG. Therefore GNB has started the development of a new cask generation, named CASTOR registered HAW28M, meeting these future requirements. The CASTOR registered HAW28M is especially developed for the transport of vitrified residues from France and Great Britain to Germany. It complies with the international regulations for type B packages according to IAEA (International Atomic Energy Agency). It is thus guaranteed that even in case of any accident the cask body and the lid system remain functional and the safe confinement of the radioactive contents remains intact during transport. The CASTOR registered HAW28M fulfills not only the requirements for transport but also the acceptance criteria of interim storage: radiation shielding, heat dissipation, safe confinement under both normal and hypothetical accident conditions. Storage buildings such as the TBL-G simply support the safety functions of the cask. The challenge for the development results from higher requirements of the technical specification, particularly related to fuel which is reprocessed. As a consequence of the reprocessing of fuel with increased enrichment and burn up, higher heat capacity and sophisticated shielding measures have to be considered. For the CASTOR

Influence of geologic layering on heat transport and storage in an aquifer thermal energy storage system

Science.gov (United States)

Bridger, D. W.; Allen, D. M.

2014-01-01

A modeling study was carried out to evaluate the influence of aquifer heterogeneity, as represented by geologic layering, on heat transport and storage in an aquifer thermal energy storage (ATES) system in Agassiz, British Columbia, Canada. Two 3D heat transport models were developed and calibrated using the flow and heat transport code FEFLOW including: a "non-layered" model domain with homogeneous hydraulic and thermal properties; and, a "layered" model domain with variable hydraulic and thermal properties assigned to discrete geological units to represent aquifer heterogeneity. The base model (non-layered) shows limited sensitivity for the ranges of all thermal and hydraulic properties expected at the site; the model is most sensitive to vertical anisotropy and hydraulic gradient. Simulated and observed temperatures within the wells reflect a combination of screen placement and layering, with inconsistencies largely explained by the lateral continuity of high permeability layers represented in the model. Simulation of heat injection, storage and recovery show preferential transport along high permeability layers, resulting in longitudinal plume distortion, and overall higher short-term storage efficiencies.

Specific transport and storage solutions: Waste management facing current and future stakes of the nuclear fuel cycle

International Nuclear Information System (INIS)

Deniau, Helene; Gagner, Laurent; Gendreau, Francoise; Presta, Anne

2006-01-01

With major projects ongoing or being planned, and also with the daily management of radioactive waste from nuclear facilities, the role of transport and/or storage packaging has been often overlooked. Indeed, the packaging development process and transport solutions implemented are a key part of the waste management challenge: protection of people and environment. During over four decades, the AREVA Group has developed a complete and coherent system for the transport of waste produced by nuclear industries. The transport solutions integrate the factors to consider, as industrial transportation needs, various waste forms, associated hazards and current regulations. Thus, COGEMA LOGISTICS has designed, licensed and manufactured a large number of different transport, storage and dual purpose cask models for residues and all kinds of radioactive wastes. The present paper proposes to illustrate how a company acting both as a cask designer and a carrier is key to the waste management issue and how it can support the waste management policy of nuclear producers through their operational choices. We will focus on the COGEMA LOGISTICS technical solutions implemented to guarantee safe and secure transportation and storage solutions. We will describe different aspects of the cask design process, insisting on how it enables to fulfill both customer needs and regulation requirements. We will also mention the associated services developed by the AREVA Business Unit Logistics (COGEMA LOGISTICS, TRANSNUCLEAR, MAINCO, and LEMARECHAL CELESTIN) in order to manage transportation of liquid and solid waste towards interim or final storage sites. The paper has the following contents: About radioactive waste; - Radioactive waste classification; - High level activity waste and long-lived intermediate level waste; - Long-lived low level waste; - Short-lived low- and intermediate level waste; - Very low level waste; - The radioactive waste in nuclear fuel cycle; - Packaging design and

Safe Transport of Radioactive Material, International Regulations and its Supporting Documents

International Nuclear Information System (INIS)

El-Shinawy, R.M.K.

2005-01-01

Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1 ( ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series No 7 and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series No 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS=113), compliance assurance (SS=112), the training manual and other

Safe Transport of Radioactive Material, International Regulations and its Supporting Documents

Energy Technology Data Exchange (ETDEWEB)

El-Shinawy, R M.K. [Radiation Protection Dept., NRC, Atomic Energy Authority, Cairo (Egypt)

2005-04-01

Safe transport of radioactive material regulations issued by IAEA since 1961, provide standards for insuring a high level of safety of people,transport workers, property and environment against radiation, contamination and criticality hazards as well as thermal effects associated with the transport of the radioactive wastes and material. The history ,development, philosophy and scope of these international regulations were mentioned as well as the different supporting documents to the regulations for safe transport of radioactive material were identified.The first supporting document , namely TS - G-1.1 ( ST-2) ,Advisory material is also issued by the IAEA.It contains both the advisory and explanatory materials previously published in safety series No 7 and 37 and therefore TS-G-1.1 (ST-2) will supersede safety series No 7 and 37. The second supporting document namely TS-G-1.2 (ST-3), planning and preparing for emergency response to transport accidents involving radioactive material ,which will supersede safety series No 87. In addition to quality assurance (SS=113), compliance assurance (SS=112), the training manual and other.

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

Energy Technology Data Exchange (ETDEWEB)

CROWE RD; APTHORPE R; LEE SJ; PLYS MG

2010-04-29

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

Progress and future direction for the interim safe storage and disposal of Hanford high level waste (HLW)

International Nuclear Information System (INIS)

Wodrich, D.D.

1996-01-01

This paper describes the progress made at the largest environmental cleanup program in the United States. Substantial advances in methods to start interim safe storage of Hanford Site high-level wastes, waste characterization to support both safety- and disposal-related information needs, and proceeding with cost-effective disposal by the US DOE and its Hanford Site contractors, have been realized. Challenges facing the Tank Waste Remediation System Program, which is charged with the dual and parallel missions of interim safe storage and disposal of the high-level tank waste stored at the Hanford Site, are described

German Approach for the Transport of Spent Fuel Packages after Interim Storage

International Nuclear Information System (INIS)

Wille, Frank; Wolff, Dietmar; Droste, Bernhard; Voelzke, Holger

2014-01-01

In Germany the concept of dry interim storage of spent nuclear fuel in dual purpose metal casks is implemented, currently for periods of up to 40 years. The casks being used have an approved package design in accordance with the international transport regulations. The license for dry storage is granted on the German Atomic Energy Act with respect to the recently (in 2012) revised 'Guidelines for dry cask storage of spent nuclear fuel and heat-generating waste' by the German Waste management Commission (ESK) which are very similar to the former RSK (reactor safety commission) guidelines. For transport on public routes between or after long term interim storage periods, it has to be ensured that the transport and storage casks fulfil the specifications of the transport approval or other sufficient properties which satisfy the proofs for the compliance of the safety objectives at that time. In recent years the validation period of transport approval certificates for manufactured, loaded and stored packages were discussed among authorities and applicants. A case dependent system of 3, 5 and 10 years was established. There are consequences for the safety cases in the Package Design Safety Report including evaluation of long term behavior of components and specific operating procedures of the package. Present research and knowledge concerning the long term behavior of transport and storage cask components have to be consulted as well as experiences from interim cask storage operations. Challenges in the safety assessment are e.g. the behavior of aged metal and elastomeric seals under IAEA test conditions to ensure that the results of drop tests can be transferred to the compliance of the safety objectives at the time of transport after the interim storage period (aged package). Assessment methods for the material compatibility, the behavior of fuel assemblies and the aging behavior of shielding parts are issues as well. This paper describes the state

Risk Assessment of Structural Integrity of Transportation Casks after Extended Storage

Energy Technology Data Exchange (ETDEWEB)

Ibarra, Luis; Medina, Ricardo; Yang, Haori

2018-03-23

This study assessed the risk of loss of structural integrity of transportation casks and fuel cladding after extended storage. Although it is known that fuel rods discharged from NPPs have a small percentage of rod cladding defects, the behavior of fuel cladding and the structural elements of assemblies during transportation after long-term storage is not well understood. If the fuel degrades during extended storage, it could be susceptible to damage from vibration and impact loads during transport operations, releasing fission-product gases into the canister or the cask interior (NWTRB 2010). Degradation of cladding may occur due to mechanisms associated with hydrogen embrittlement, delayed hydride cracking, low temperature creep, and stress corrosion cracking (SCC) that may affect fuel cladding and canister components after extended storage of hundreds of years. Over extended periods at low temperatures, these mechanisms affect the ductility, strength, and fracture toughness of the fuel cladding, which becomes brittle. For transportation purposes, the fuel may be transferred from storage to shipping casks, or dual-purpose casks may be used for storage and transportation. Currently, most of the transportation casks will be the former case. A risk assessment evaluation is conducted based on results from experimental tests and simulations with advanced numerical models. A novel contribution of this study is the evaluation of the combined effect of component aging and vibration/impact loads in transportation scenarios. The expected levels of deterioration will be obtained from previous and current studies on the effect of aging on fuel and cask components. The emphasis of the study is placed on the structural integrity of fuel cladding and canisters.

CASTOR {sup registered} HAW28M - a high heat load cask for transport and storage of vitrified high level waste containers

Energy Technology Data Exchange (ETDEWEB)

Vossnacke, A.; Klein, K.; Kuehne, B. [GNS Gesellschaft fuer Nuklear-Service mbH/GNB, Essen (Germany)

2004-07-01

Within the German return programme for vitrified high level waste (HLW) from reprocessing at COGEMA and BNFL up to now 39 casks loaded with 28 containers each were transported back to Germany and are stored in the Interim Storage Facility Gorleben (TBL-G) for up to 40 years. For transport and storage in all but one case the GNB casks CASTOR {sup registered} HAW 20/28 CG have been used. This cask type is designed to accommodate 20 or 28 HLW containers with a total thermal power of 45 kW maximum. In the near future, among the high level waste, which has to be returned to Germany, there will be an increasing number of containers of which the heat capacity and radioactive inventory will exceed the technical limits of the CASTOR {sup registered} HAW 20/28 CG. Therefore GNB has started the development of a new cask generation, named CASTOR {sup registered} HAW28M, meeting these future requirements. The CASTOR {sup registered} HAW28M is especially developed for the transport of vitrified residues from France and Great Britain to Germany. It complies with the international regulations for type B packages according to IAEA (International Atomic Energy Agency). It is thus guaranteed that even in case of any accident the cask body and the lid system remain functional and the safe confinement of the radioactive contents remains intact during transport. The CASTOR {sup registered} HAW28M fulfills not only the requirements for transport but also the acceptance criteria of interim storage: radiation shielding, heat dissipation, safe confinement under both normal and hypothetical accident conditions. Storage buildings such as the TBL-G simply support the safety functions of the cask. The challenge for the development results from higher requirements of the technical specification, particularly related to fuel which is reprocessed. As a consequence of the reprocessing of fuel with increased enrichment and burn up, higher heat capacity and sophisticated shielding measures have to be

Only adding stationary storage to vaccine supply chains may create and worsen transport bottlenecks.

Science.gov (United States)

Haidari, Leila A; Connor, Diana L; Wateska, Angela R; Brown, Shawn T; Mueller, Leslie E; Norman, Bryan A; Schmitz, Michelle M; Paul, Proma; Rajgopal, Jayant; Welling, Joel S; Leonard, Jim; Claypool, Erin G; Weng, Yu-Ting; Chen, Sheng-I; Lee, Bruce Y

2013-01-01

Although vaccine supply chains in many countries require additional stationary storage and transport capacity to meet current and future needs, international donors tend to donate stationary storage devices far more often than transport equipment. To investigate the impact of only adding stationary storage equipment on the capacity requirements of transport devices and vehicles, we used HERMES (Highly Extensible Resource for Modeling Supply Chains) to construct a discrete event simulation model of the Niger vaccine supply chain. We measured the transport capacity requirement for each mode of transport used in the Niger vaccine cold chain, both before and after adding cold rooms and refrigerators to relieve all stationary storage constraints in the system. With the addition of necessary stationary storage, the average transport capacity requirement increased from 88% to 144% for cold trucks, from 101% to 197% for pickup trucks, and from 366% to 420% for vaccine carriers. Therefore, adding stationary storage alone may worsen or create new transport bottlenecks as more vaccines flow through the system, preventing many vaccines from reaching their target populations. Dynamic modeling can reveal such relationships between stationary storage capacity and transport constraints.

75 FR 38168 - Hazardous Materials: International Regulations for the Safe Transport of Radioactive Material (TS...

Science.gov (United States)

2010-07-01

... may also provide contact information, such as a telephone number and/or e-mail address. PHMSA and the.... PHMSA-2010-0130 (Notice No.10-2)] Hazardous Materials: International Regulations for the Safe Transport... (IAEA) ``Regulations for the Safe Transport of Radioactive Material'' (TS-R-1), which is scheduled for...

Engineering and planning for reactor 105-C interim safe storage project subcontract no. 0100C-SC-G0001 conceptual design report. Volume 1

International Nuclear Information System (INIS)

1996-04-01

The 105-C Reactor, one of eight surplus production reactors at the Hanford Site, has been proposed by the U.S. Department of Energy, Richland, Operations Office to be the first large-scale technology demonstration project in the decontamination and decommissioning (D ampersand D) focus area as part of the project for dismantlement and interim safe storage. The 105-C Reactor will be placed in an interim safe storage condition, then undergo the decontamination and decommissioning phase. After D ampersand D, the reactor will be placed in long- term safe storage. This report provides the conceptual design for these activities

Equipment for RAW handling, packaging, transport and storage from ZTS VVU KOSICE a.s

International Nuclear Information System (INIS)

Vargovcik, L.

2004-01-01

Since 1988, the company ZTS VVU KOSICE has devoted a great part of its activities to the development of equipment for RAW handling, packaging, transport and storage, mainly for application in the decommissioning of NPP A1 at Jaslovske Bohunice in Slovakia. This is a HWGCR NPP shut down following a breakdown in 1977. This incident was caused by disruption of the technological channel serving as a barrier between heavy water moderator and fuel assembly. Damage of this barrier enabled heavy water leakage into the primary circuit with partial fuel elements cladding damage and subsequent additional contamination of the primary circuit. During two consecutive years after the incident main effort was focused on activities related to personnel and environment protection, moderator draining, reactor defuelling, dry cleaning of the primary circuit, repair and maintenance of equipment. The next step was the preparation of the concept of NPP A-1 introduction into dry safe state. The order of importance of RAW liquidation was as follows: 1. Spent fuel - spent fuel assemblies from NPP A-1 were, after short cooling, stored temporarily in storage pipe containers filled at the beginning of NPP operation with ''chrompik'' (an aqueous solution of K 2 Cr 2 O 7 with concentration of 3-5%), later with ''dowtherm'' (mixture of bi-phenyl oxide and bi-phenyl). The containers were placed in a storage pond filled with water. 2. Liquid RAW - combustible (dowtherm, oils) and non-combustible (chrompik, Demi water, decontaminating solutions, sludge, sorbents, etc.) 3. Solid RAW - metallic and non-metallic For this purpose, it was necessary to build RAW processing lines, intermediate storage facilities and systems for manipulation and transport of RAW

Regulatory Framework and Current Practices of the Radioactive Material Safe and Secure Transport in Albania

International Nuclear Information System (INIS)

Dollani, K.; Grillo, B.; Telhaj, E.

2016-01-01

Attempts for the establishing of a safe and secure radioactive material transport in Albania began a decade ago with formulation of the different regulation in the field of safe and secure handling of the radioactive materials. In 2004 a special regulation for the safe transport of radioactive material was prepared and approved by the National Radiation Protection Commission). This regulation has been based in the IAEA standards for the radioactive material transport and was reviewed periodically. The last regulation of the radioactive material transport was approved by Albanian government through a governmental ordinance. The transport of the radioactive material in Albania is performed by licensed subjects, which fulfill all requirements of the mentioned governmental ordinance. Based in the existing regulation, for each transport of radioactive material, a special permission is issued by NRPC. The issuing of permission allows competent authority to provide necessary information on transport regularity and to have under survey all transports of the radioactive material carried out inside the country. Last year were issued more than 80 permissions for the transport of the different types and categories of the radioactive sources. (author)

Comparison of the Transportation Risks Resulting from Accidents during the Transportation of the Spent Fuel

International Nuclear Information System (INIS)

Jeong Jong Tae; Cho, Dong Kuen; Choi, Heui Joo; Choi, Jong Won

2007-01-01

The safe, environmentally sound and publicly acceptable disposal of high level wastes and spent fuels is becoming a very important issue. The operational safety assessment of a repository including a transportation safety assessment is a fundamental part in order to achieve this goal. According to the long term management strategy for spent fuels in Korea, they will be transported from the spent fuel pools in each nuclear power plant to the central interim storage facility (CISF) which is to start operation in 2016. Therefore, we have to determine the safe and economical logistics for the transportation of these spent fuels by considering their transportation risks and costs. In this study, we developed four transportation scenarios by considering the type of transportation casks and transport means in order to suggest safe and economical transportation logistics for spent fuels. Also, we estimated and compared the transportation risks resulting from the accidents during the transportation of spent fuels for these four transportation scenarios

Safety aspects of dry spent fuel storage and spent fuel management

International Nuclear Information System (INIS)

Botsch, W.; Smalian, S.; Hinterding, P.; Voelzke, H.; Wolff, D.; Kasparek, E.

2014-01-01

The storage of spent nuclear fuel (SF) and high-level radioactive waste (HLW) must conform to safety requirements. Safety aspects like safe enclosure of radioactive materials, safe removal of decay heat, nuclear criticality safety and avoidance of unnecessary radiation exposure must be achieved throughout the storage period. The implementation of these safety requirements can be achieved by dry storage of SF and HLW in casks as well as in other systems such as dry vault storage systems or spent fuel pools, where the latter is neither a dry nor a passive system. In Germany dual purpose casks for SF or HLW are used for safe transportation and interim storage. TUV and BAM, who work as independent experts for the competent authorities, present the storage licensing process including sites and casks and inform about spent nuclear fuel management and issues concerning dry storage of spent nuclear fuel, based on their long experience in these fields (authors)

Thermal performance of a depleted uranium shielded storage, transportation, and disposal package

International Nuclear Information System (INIS)

Wix, S.D.; Yoshimura, H.R.

1994-01-01

The US Department of Energy (DOE) is responsible for management and disposal of large quantities of depleted uranium (DU) in the DOE complex. Viable economic options for the use and eventual disposal of the material are needed. One possible option is the use of DU as shielding material for vitrified Defense High-Level Waste (DHLW) storage, transportation, and disposal packages. Use of DU as a shielding material provides the potential benefit of disposing of significant quantities of DU during the DHLW storage and disposal process. Two DU package concepts have been developed by Sandia National Laboratories. The first concept is the Storage/Disposal plus Transportation (S/D+T) package. The S/D+T package consists of two major components: a storage/disposal (S/D) container and a transportation overpack. The second concept is the S/D/T package which is an integral storage, transportation, and disposal package. The package concept considered in this analysis is the S/D+T package with seven DHLW waste canisters

Safe transport of radioactive material. Second edition

International Nuclear Information System (INIS)

1996-01-01

In 1991, the International Atomic Energy Agency published Training Course Series No. 1 (TCS-1), a training manual that provides in 20 chapters a detailed discussion of the background, philosophy, technical bases and requirements and implementation aspects of the Regulations for the Safe Transport of Radioactive Material. The Transport Regulations are widely implemented by the IAEA's Member States and are also used as the bases for radioactive material transport requirements of modal organisations such as the International Maritime Organization and the International Civil Aviation Organization. This document is a supplement of TCS-1 to provide additional material in the form of learning aids and new exercises, that have been developed with the use of TCS-1 at succeeding IAEA training courses. The learning aids in the first part of the supplement are hitherto unpublished material that provide detailed guidance useful in solving the exercises presented in the second part. Solutions to the exercises are on field at the IAEA Secretariat and are available by arrangement to lectures presenting IAEA training courses. 4 refs, 1 fig., 6 tabs

Assuring safe interim storage of Hanford high-level tank wastes

International Nuclear Information System (INIS)

Bacon, R.F.; Babad, H.; Lerch, R.E.

1996-01-01

The federal government established the Hanford Site in South-Eastern Washington near the City of Richland in 1943 to produce plutonium for national defense purposes. The Hanford Site occupies approximately 1,450 square kilometers (560 square miles) of land North of the City of Richland. The production mission ended in 1988, transforming the Hanford Site mission to waste management, environmental restoration, and waste disposal. Thus the primary site mission has shifted from production to the management and disposal of radioactive, hazardous, and mixed waste that exist at the Hanford Site. This paper describes the focus and challenges facing the Tank Waste Remediation System (TWRS) Program related to the dual and parallel missions of interim safe storage and disposal of the tank associated waste. These wastes are presently stored in 2.08E+05 liters (55,000) to 4.16E+06 liters (1,100,000) gallon low-carbon steel tanks. There are 149 single- and 28 double-shell radioactive underground storage tanks, as well as approximately 40 inactive miscellaneous underground storage tanks. In addition, the TWRS mission includes the storage and disposal of the inventory of 1,929 cesium and strontium capsules created as part of waste management efforts. Tank waste was a by-product of producing plutonium and other defense related materials. From 1944 through 1990, four (4) different major chemical processing facilities at the Hanford Site processed irradiated (spent) fuel from defense reactors to separate and recover plutonium for weapons production. As new and improved processes were developed over the last 50 years, the processing efficiency improved and the waste compositions sent to the tanks for storage changed both chemically and radiologically. The earliest separation processes (e.g., bismuth phosphate coprecipitation) carried out in T Plant (1944-1956) and B Plant (1945-1952) recovered only plutonium

Storage, transportation and disposal system for used nuclear fuel assemblies

Science.gov (United States)

Scaglione, John M.; Wagner, John C.

2017-01-10

An integrated storage, transportation and disposal system for used fuel assemblies is provided. The system includes a plurality of sealed canisters and a cask sized to receive the sealed canisters in side by side relationship. The plurality of sealed canisters include an internal basket structure to receive a plurality of used fuel assemblies. The internal basket structure includes a plurality of radiation-absorbing panels and a plurality of hemispherical ribs generally perpendicular to the canister sidewall. The sealed canisters are received within the cask for storage and transportation and are removed from the cask for disposal at a designated repository. The system of the present invention allows the handling of sealed canisters separately or collectively, while allowing storage and transportation of high burnup fuel and damaged fuel to the designated repository.

Evaluation of storage/transportation options to support criteria development for the Phase I MRS

International Nuclear Information System (INIS)

Sorenson, K.B.; Brown, N.N.; Bennett, P.C.; Lake, W.

1991-01-01

The DOE's Office of Civilian Waste Management (OCRWM) plans to develop an interim storage facility to enable acceptance of spent fuel in 1998. It is estimated that this interim storage facility would be needed for about two years. A Monitored Retrievable Storage (MRS) facility is anticipated in 2000 and a repository in 2010. Acceptance and transport of spent fuel by DOE/OCRWM in 1998 will require an operating transportation system. Because this interim storage facility is not yet defined, development of an optimally compatible transportation system is not a certainty. In order to assure a transport capability for 1998 acceptance of spent fuel, it was decided that the OCRWM transportation program had to identify likely options for an interim storage facility, including identification of the components needed for compatibility between likely interim storage facility options and transportation. Primary attention was given to existing hardware, although conceptual designs were also considered. A systems-based probabilistic decision model was suggested by Sandia National Labs. and accepted by DOE/OCRWM's transportation program. Performance of the evaluation task involved several elements of the transportation program. This paper describes the decision model developed to accomplish this task, along with some of the results and conclusions

The safe road transport system approach

Directory of Open Access Journals (Sweden)

Vollpracht Hans-Joachim

2016-07-01

Full Text Available More than 1,24 million people die each year on the worlds roads and between 20 to 50 million suffer from nonfatal injuries. The UN Road Safety Collaboration Meetings under the leadership of WHO developed the Programme for the Decade of Actions for road safety taking nations into the responsibility of improving their accident figures by the five pillars of a national Road Safety Policy, safer Roads, safer Vehicles, safer Road Users and Post Crash Care. It is this Safe System Approach that takes into consideration the land use, infrastructure and transport planning, road user’s abilities and limitations and the close cooperation of all governmental and none governmental stakeholders involved.

Separation of British Gas' transportation and storage business

International Nuclear Information System (INIS)

McGregor, G.

1992-12-01

In making his substantive reference of the transportation and storage business of British Gas to the Monopolies and Mergers Commission, the Director General of Gas Supply identified the following principal effects adverse to the public interest: ''The absence of provision for the establishment of an independent undertaking to operate the pipe-line system and other facilities used by British Gas for the conveyance and storage of gas which would not be subject to conflicting interests in securing (a) transparency of the prices charged, the costs incurred and the operating methods in respect of the conveyance and storage of gas; (b) proper allocation to various parts of the Gas Supply Business of costs incurred and returns by that business; and (c) protection of information relating to the conveyance and storage of gas from which British Gas might obtain unfair commercial advantage, and thereby avoid the restriction or distortion of competition between British Gas and other persons whose business consists of or includes the supply of gas''. This paper considers the structural issues associated with achieving effective competition and looks at how the relationship between the businesses of supply and transportation might be organised in the short and longer term. (Author)

Thermal performance of a depleted uranium shielded storage, transportation, and disposal package

International Nuclear Information System (INIS)

Wix, S.D.; Yoshimura, H.R.

1994-01-01

The US Department of Energy (DOE) is responsible for management and disposal of large quantities of depleted uranium (DU) in the DOE complex. Viable economic options for the use and eventual disposal of the material are needed. One possible option is the use of DU as shielding material for vitrified Defense High-Level Waste (DHLW) storage, transportation, and disposal packages. Use of DU as a shielding material provides the potential benefit of disposing of significant quantities of DU during the DHLW storage and disposal process. Two DU package concepts have been developed by Sandia National Laboratories. The first concept is the Storage/Disposal plus Transportation (S/D+T) package. The S/D+T package consists of two major components: a storage/disposal (S/D) container and a transportation overpack. The second concept is the S/D/T package which is an integral storage, transportation, and disposal package. The package concept considered in this analysis is the S/D+T package with seven DHLW waste canisters. The S/D+T package provides shielding and containment for the DHLW waste canisters. The S/D container is intended to be used as an on-site storage and repository disposal container. In this analysis, the S/D container is constructed from a combination of stainless steel and DU. Other material combinations, such as mild steel and DU, are potential candidates. The transportation overpack is used to transport the S/D containers to a final geological repository and is not included in this analysis

Graphene oxide/metal nanocrystal multilaminates as the atomic limit for safe and selective hydrogen storage.

Science.gov (United States)

Cho, Eun Seon; Ruminski, Anne M; Aloni, Shaul; Liu, Yi-Sheng; Guo, Jinghua; Urban, Jeffrey J

2016-02-23

Interest in hydrogen fuel is growing for automotive applications; however, safe, dense, solid-state hydrogen storage remains a formidable scientific challenge. Metal hydrides offer ample storage capacity and do not require cryogens or exceedingly high pressures for operation. However, hydrides have largely been abandoned because of oxidative instability and sluggish kinetics. We report a new, environmentally stable hydrogen storage material constructed of Mg nanocrystals encapsulated by atomically thin and gas-selective reduced graphene oxide (rGO) sheets. This material, protected from oxygen and moisture by the rGO layers, exhibits exceptionally dense hydrogen storage (6.5 wt% and 0.105 kg H2 per litre in the total composite). As rGO is atomically thin, this approach minimizes inactive mass in the composite, while also providing a kinetic enhancement to hydrogen sorption performance. These multilaminates of rGO-Mg are able to deliver exceptionally dense hydrogen storage and provide a material platform for harnessing the attributes of sensitive nanomaterials in demanding environments.

Transport or Store? Synthesizing Flow-based Microfluidic Biochips using Distributed Channel Storage

DEFF Research Database (Denmark)

Liu, Chunfeng; Li, Bing; Yao, Hailong

2017-01-01

of the performance of biochips. In this paper, we propose the first architectural synthesis framework considering distributed storage constructed temporarily from transportation channels to cache fluid samples. Since distributed storage can be accessed more efficiently than a dedicated storage unit and channels can...... switch between the roles of transportation and storage easily, biochips with this distributed computing architecture can achieve a higher execution efficiency even with fewer resources. Experimental results confirm that the execution efficiency of a bioassay can be improved by up to 28% while the number...

Safety Aspects of Long Term Spent Fuel Dry Storage

International Nuclear Information System (INIS)

Botsch, Wolfgang; Smalian, S.; Hinterding, P.; Drotleff, H.; Voelzke, H.; Wolff, D.; Kasparek, E.

2014-01-01

As a consequence of the lack of a final repository for spent nuclear fuel (SF) and high level waste (HLW), long term interim storage of SF and HLW will be necessary. As with the storage of all radioactive materials, the long term storage of SF and HLW must conform to safety requirements. Safety aspects such as safe enclosure of radioactive materials, safe removal of decay heat, sub-criticality and avoidance of unnecessary radiation exposure must be achieved throughout the complete storage period. The implementation of these safety requirements can be achieved by dry storage of SF and HLW in casks as well as in other systems such as dry vault storage systems or spent fuel pools, where the latter is neither a dry nor a passive system. After the events of Fukushima, the advantages of passively and inherently safe dry storage systems have become more obvious. In Germany, dry storage of SF in casks fulfils both transport and storage requirements. Mostly, storage facilities are designed as concrete buildings above the ground; one storage facility has also been built as a rock tunnel. In all these facilities the safe enclosure of radioactive materials in dry storage casks is achieved by a double-lid sealing system with surveillance of the sealing system. The safe removal of decay heat is ensured by the design of the storage containers and the storage facility, which also secures to reduce the radiation exposure to acceptable levels. TUV and BAM, who work as independent experts for the competent authorities, inform about spent fuel management and issues concerning dry storage of spent nuclear fuel, based on their long experience in these fields. All relevant safety issues such as safe enclosure, shielding, removal of decay heat and sub-criticality are checked and validated with state-of-the-art methods and computer codes before the license approval. In our presentation we discuss which of these aspects need to be examined closer for a long term interim storage. It is shown

Advances in the safe transport of irradiated Magnox fuel

International Nuclear Information System (INIS)

Jackson, C.N.

1997-01-01

This paper reviews the significant advances that have been made by Magnox Electric plc in ensuring that the Mk M2 Magnox flasks maintain the highest level of safety during transport and are used in the most efficient manner in meeting Company objectives. These advances have been achieved by improvement to the seal design, introduction of modern, state-of-the-art leak test equipment and optimisation of the generic Safety Case underpinning the UK Competent Authority (the Department of Transport, DoT) Approval Certificates. A step-by-step approach has been adopted in implementing these advances, consulting the DoT at each stage, to ensure that the safe transport of spent Magnox fuel, achieved over the past 35 years, with its enviable track record, continues into the next century. (Author)

Comprehensive training structure for the safe transport of radioactive materials in Switzerland

International Nuclear Information System (INIS)

Pfeiffer, H.J.; Smith, L.

1993-01-01

The introduction of the 1985 IAEA Regulations for the Safe Transport of Radioactive Materials into Swiss national dangerous goods transport regulations has induced significant changes to the national radiation protection regulations. The combination of these two sets of regulatory requirements has in turn given rise to a major expansion in the national training infrastructure for the safe transport of RAM material. The established nationally recognized courses for vehicle drivers in accordance with national and regional regulations is now supplemented by an IAEA level 2 course for managers and responsible persons with consignors and shippers. A new IAEA level 3 course specifically for inspectors carrying out inspections during shipment is planned to commence in 1993. National one day general information seminars on RAM transportation are now an established part of the training scenario in Switzerland. Commencing in 1992, annual two day seminars for supervising authority inspectors involved in organizational compliance assurance are planned. Experience to date for this significantly increased activity in training has been that of enthusiastic cooperation between all parties concerned. (J.P.N.)

Regulatory status of burnup credit for storage and transport of spent fuel in Germany

International Nuclear Information System (INIS)

Neuber, J.C.; Schweer, H.H.; Johann, H.G.

2001-01-01

This paper describes the regulatory status of burnup credit applications to pond storage and dry-cask transport and storage of spent fuel in Germany. Burnup credit for wet storage of LWR fuel at nuclear power plants has to comply with the newly developed safety standard DIN 25471. This standard establishes the safety requirements for burnup credit criticality safety analysis of LWR fuel storage ponds and gives guidance on meeting these requirements. Licensing evaluations of dry transport systems are based on the application of the IAEA Safety Standards Series No.ST-1. However, because of the fact that burnup credit for dry-cask transport becomes more and more inevitable due to increasing initial enrichment of the fuel, and because of the increasing importance of dry-cask storage in Germany, the necessity of giving regulatory guidance on applying burnup credit to dry-cask transport and storage is seen. (author)

Red cell concentrate storage and transport temperature.

Science.gov (United States)

Hancock, V; Cardigan, R; Thomas, S

2011-10-01

This study investigated the current U.K. guidelines for storage and transport of red cell concentrates (RCC) in saline, adenine, glucose and mannitol (SAGM). The guidelines stipulate storage at 2-6 °C but allow exposure to between 1-10 °C core temperature in a single occurrence of less than 5 h and a surface temperature of 2-10 °C for no more than 12 h during transportation. Twenty RCC units in SAGM were selected on the day of blood collection (day 0) and in vitro quality was tested pre- and post-temperature deviation at 10 °C and up to day 42 of storage. Each group of 10 RCC units was incubated for either 12 h or for both 5 and 12 h. Haemolysis was below the 0·8% U.K. limit at day 42 in all units, although there was an unexpected trend towards lower haemolysis in packs incubated for 5 and 12 h rather than just 12 h alone. Supernatant potassium was significantly higher than reference data on day 35 (P levels of adenosine triphosphate and, 2,3-diphosphoglycerate to reference data from previous studies, throughout storage. These results suggest that exposure to 10 °C for 12 h or for 5 and 12 h did not adversely affect in vitro red cell quality for the remainder of the components shelf life. © 2011 The Authors. Transfusion Medicine © 2011 British Blood Transfusion Society.

75 FR 43906 - Hazardous Materials: Requirements for the Storage of Explosives During Transportation

Science.gov (United States)

2010-07-27

... program in emergency response procedures for all employees working at the safe haven. NFPA 498 section 4.5... safe havens used for unattended storage of Division 1.1, 1.2, and 1.3 explosives. DATES: Comments must... circumstances and operational environment. B. Federal Motor Carrier Safety Regulations (FMCSRs), 49 CFR Parts...

Shipment and Storage Containers for Tritium Production Transportation Casks

International Nuclear Information System (INIS)

Massey, W.M.

1998-04-01

The need for a shipping and storage container for the Tritium production transportation casks is addressed in this report. It is concluded that a shipping and storage container is not required. A recommendation is made to eliminate the requirement for this container because structural support and inerting requirements can be satisfied completely by the cask with a removable basket

Radioactive waste management decommissioning spent fuel storage. V. 3. Waste transport, handling and disposal spent fuel storage

International Nuclear Information System (INIS)

1985-01-01

As part of the book entitled Radioactive waste management decommissioning spent fuel storage, vol. 3 dealts with waste transport, handling and disposal, spent fuel storage. Twelve articles are presented concerning the industrial aspects of nuclear waste management in France [fr

The impact of the new IAEA transport regulations for the safe transport of radioactive materials on package design and transport

International Nuclear Information System (INIS)

Schneider, K.

1989-01-01

In April 1985 the 1985 Edition of the IAEA Safety Series No. 6, Regulations for the Safe Transport of Radioactive Materials, was issued. This is a completely revised edition which shall come into force internationally in the late eighties. This edition will supersede the 1973 (As Amended, 1979) edition. A paragraph by paragraph comparison is carried through, followed by a consideration on the impact on general requirements for packaging and transport. A detailed estimate on packaging design and transport is performed for typical products of the nuclear fuel cycle. The major practical consequences likely to be encountered are presented

Relevant documents to IAEA regulations for the safe transport of radioactive materials

International Nuclear Information System (INIS)

El-Shinawy, R.M.K.; Sabek, M.G.; Gomma, M.

1998-01-01

IAEA regulations for the safe transport of radioactive materials provide standards for insuring a high level of safety of people, property, and environment against radiation, contamination, and criticality hazards as well as thermal effects associated with the transport of radioactive materials. IAEA routinely publishes technical reports which are relevant to radioactive material transportation such as INTERTRAN, directory of transport packaging test facilities, and others. A case study was performed to assess the impact of transporting radioactive materials through the suez canal using the two computer codes namely INTERTRAN and RADTRAN-4 which are part of IAEA technical documents. A comparison of the results of these two codes is given

European model code of safe practice for the prevention of ground and surface water pollution by oil from storage tanks and during the transport of oil

Energy Technology Data Exchange (ETDEWEB)

1974-01-01

The code outlines general requirements for pollution prevention and provides guidelines for corrosion protection of mild steel tanks, pipe and fitting assemblies, and for storage tank installations. The transportation and delivery of petroleum fuels are discussed, and operating procedures are suggested.

Shielded Canister Transporter

International Nuclear Information System (INIS)

Eidem, G.G. Jr.; Fages, R.

1993-01-01

The Hanford Waste Vitrification Plant (HWVP) will produce canisters filled with high-level radioactive waste immobilized in borosilicate glass. This report discusses a Shielded Canister Transporter (SCT) which will provide the means for safe transportation and handling of the canisters from the Vitrification Building to the Canister Storage Building (CSB). The stainless steel canisters are 0.61 meters in diameter, 3.0 meters tall, and weigh approximately 2,135 kilograms, with a maximum exterior surface dose rate of 90,000 R/hr. The canisters are placed into storage tubes to a maximum of three tall (two for overpack canisters) with an impact limiter placed at the tube bottom and between each canister. A floor plug seals the top of the storage tube at the operating floor level of the CSB

Thick nickel plating of spent fuel transport and storage casks CASTOR and POLLUX

International Nuclear Information System (INIS)

Wilbuer, K.

1991-01-01

Spent fuel elements have to be safely handled in containers for transport and storage. These large casks (100-120 t) are made by various firms according to the specifications given by the nuclear plant operator. For shielding and protection of the hazardous material, the casks' inner surface is coated with a nickel plating about 3000 μm thick. The product and the production process are subject to very stringent requirements, due to the hazardous potential of the material to be shipped or stored. Therefore, both the extremely high quality standards to be met by the nickel plating and the dimensions and capability of the plating plant required for the process are problems that cannot be solved by a usual commercial plating plant. The new concept and process that had to be established are explained in the paper. (orig./MM) [de

Pre-disposal storage, transport and handling of vitrified high level waste

International Nuclear Information System (INIS)

Kempe, T.F.; Martin, A.

1981-05-01

The objectives of the study were to review non site-specific engineering features of the storage, transport and handling of vitrified high level radioactive waste prior to its transfer into an underground repository, and to identify those features which require validation or development. Section headings are: introduction (historical and technical background); characteristics and arisings of vitrified high level waste; overpacks (additional containment barrier, corrosion resistant); interim storage of HLW; transport of HLW; handling; conclusions and recommendations. (U.K.)

A complete NUHOMS {sup registered} solution for storage and transport of high burnup spent fuel

Energy Technology Data Exchange (ETDEWEB)

Bondre, J. [Transnuclear, Inc. (AREVA Group), Fremont, CA (United States)

2004-07-01

The discharge burnups of spent fuel from nuclear power plants keep increasing with plants discharging or planning to discharge fuel with burnups in excess of 60,000 MWD/MTU. Due to limited capacity of spent fuel pools, transfer of older cooler spent fuel from fuel pool to dry storage, and very limited options for transport of spent fuel, there is a critical need for dry storage of high burnup, higher heat load spent fuel so that plants could maintain their full core offload reserve capability. A typical NUHOMS {sup registered} solution for dry spent fuel storage is shown in the Figure 1. Transnuclear, Inc. offers two advanced NUHOMS {sup registered} solutions for the storage and transportation of high burnup fuel. One includes the NUHOMS {sup registered} 24PTH system for plants with 90.7 Metric Ton (MT) crane capacity; the other offers the higher capacity NUHOMS {sup registered} 32PTH system for higher crane capacity. These systems include NUHOMS {sup registered} - 24PTH and -32PTH Transportable Canisters stored in a concrete storage overpack (HSM-H). These canisters are designed to meet all the requirements of both storage and transport regulations. They are designed to be transported off-site either directly from the spent fuel pool or from the storage overpack in a suitable transport cask.

Containment performance of transportable storage casks at 9m drop test

Energy Technology Data Exchange (ETDEWEB)

Tobita, H. [Hitachi Zosen Corp., Osaka (Japan); Araki, K. [Hitachi Zosen Diesel and Engineering Co., Ltd., Tokyo (Japan)

2004-07-01

Spent fuel transportable storage casks usually have a double lid closure system, which consists of primary and secondary lids, and gaskets, to keep the containment function during transportation and storage, and to monitor a leakage or containment function during storage. Metal gasket is planning to be used not only during storage but transportation of both before and after storage. As metal gasket will degrade its containment function by creep during storage period of 50 years, relative displacement such as opening and slide displacement between the flange of the containment vessel and the lid should be restricted to a small range. To maintain the containment performance, we provisionally adopted the maximum opening limit of 0.1mm and the maximum slide displacement limit of 3.0mm in the full-scale cask design based on the report of the fundamental experiment on the metal gasket which examines the relation between leakage rate and sealing gap. The purpose of this study is to analyse the behaviour of the sealed parts (lid and vessel body) under 9m-drop impact test conditions and to establish some analytical method to evaluate this behaviour. In this study, the drop test of 1/3scale model of Hitz-B69 cask with the double lids closure system was carried out, the behaviours of the seal part were measured by displacement sensors, and they were compared with the result of the numerical analysis carried out separateley.

Thermal performance and heat transport in aquifer thermal energy storage

Science.gov (United States)

Sommer, W. T.; Doornenbal, P. J.; Drijver, B. C.; van Gaans, P. F. M.; Leusbrock, I.; Grotenhuis, J. T. C.; Rijnaarts, H. H. M.

2014-01-01

Aquifer thermal energy storage (ATES) is used for seasonal storage of large quantities of thermal energy. Due to the increasing demand for sustainable energy, the number of ATES systems has increased rapidly, which has raised questions on the effect of ATES systems on their surroundings as well as their thermal performance. Furthermore, the increasing density of systems generates concern regarding thermal interference between the wells of one system and between neighboring systems. An assessment is made of (1) the thermal storage performance, and (2) the heat transport around the wells of an existing ATES system in the Netherlands. Reconstruction of flow rates and injection and extraction temperatures from hourly logs of operational data from 2005 to 2012 show that the average thermal recovery is 82 % for cold storage and 68 % for heat storage. Subsurface heat transport is monitored using distributed temperature sensing. Although the measurements reveal unequal distribution of flow rate over different parts of the well screen and preferential flow due to aquifer heterogeneity, sufficient well spacing has avoided thermal interference. However, oversizing of well spacing may limit the number of systems that can be realized in an area and lower the potential of ATES.

Classification of transportation packaging and dry spent fuel storage system components according to importance to safety

International Nuclear Information System (INIS)

McConnell, J.W., Jr; Ayers, A.L. Jr; Tyacke, M.J.

1996-02-01

This report provides a graded approach for classification of components used in transportation packaging and dry spent fuel storage systems. This approach provides a method for identifying, the classification of components according to importance to safety within transportation packagings and dry spent fuel storage systems. Record retention requirements are discussed to identify the documentation necessary to validate that the individual components were fabricated in accordance with their assigned classification. A review of the existing regulations pertaining to transportation packagings and dry storage systems was performed to identify current requirements The general types of transportation packagings and dry storage systems were identified. Discussions were held with suppliers and fabricators of packagings and storage systems to determine current practices. The methodology used in this report is based on Regulatory Guide 7.10, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material. This report also includes a list of generic components for each of the general types of transportation packagings and spent fuel storage systems. The safety importance of each component is discussed, and a classification category is assigned

Project management plan for the 105-C Reactor interim safe storage project. Revision 1

International Nuclear Information System (INIS)

Miller, R.L.

1997-01-01

In 1942, the Hanford Site was commissioned by the US Government to produce plutonium. Between 1942 and 1955, eight water-cooled, graphite-moderated reactors were constructed along the Columbia River at the Hanford Site to support the production of plutonium. The reactors were deactivated from 1964 to 1971 and declared surplus. The Surplus Production Reactor Decommissioning Project (BHI 1994b) will decommission these reactors and has selected the 105-C Reactor to be used as a demonstration project for interim safe storage at the present location and final disposition of the entire reactor core in the 200 West Area. This project will result in lower costs, accelerated schedules, reduced worker exposure, and provide direct benefit to the US Department of Energy for decommissioning projects complex wide. This project sets forth plans, organizational responsibilities, control systems, and procedures to manage the execution of the Project Management Plan for the 105-C Reactor Interim Safe Storage Project (Project Management Plan) activities to meet programmatic requirements within authorized funding and approved schedules. The Project Management Plan is organized following the guidelines provided by US Department of Energy Order 4700.1, Project Management System and the Richland Environmental Restoration Project Plan (DOE-RL 1992b)

Safety analysis of spent fuel transport and storage casks under extreme impact conditions

International Nuclear Information System (INIS)

Wolff, D.; Wieser, G.; Ballheimer, V.; Voelzke, H.; Droste, B.

2005-01-01

Full text: Worldwide the security of transport and storage of spent fuel with respect to terrorism threats is a matter of concern. In Germany a spent nuclear fuel management program was developed by the government including a new concept of dry on-site interim storage instead of centralized interim storage. In order to minimize transports of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities, the operators of NPPs have to erect and to use interim storage facilities for spent nuclear fuel on the site or in the vicinity of nuclear power plants. Up to now, 11 on-site interim storage buildings, one storage tunnel and 4 on-site interim storage areas (preliminary cask storage till the on-site interim storage building is completed) have been licensed at 12 nuclear power plant sites. Inside the interim storage buildings the casks are kept in upright position, whereas at the preliminary interim storage areas horizontal storage of the casks on concrete slabs is used and each cask is covered by concrete elements. Storage buildings and concrete elements are designed only for gamma and neutron radiation shielding reasons and as weather protection. Therefore the security of spent fuel inside a dual purpose transport and storage cask depends on the inherent safety of the cask itself. For nearly three decades BAM has been investigating cask safety under severe accident conditions like drop tests from more than 9 m onto different targets and without impact limiters as well as artificially damaged prototype casks. Since the terror attacks of 11 September 2001 the determination of casks' inherent safety also under extreme impact conditions due to terrorist attacks has been of our increasing interest. With respect to spent fuel storage one of the most critical scenarios of a terrorist attack for a cask is the centric impact of a dynamic load onto the lid-seal-system caused e.g. by direct aircraft crash or its engine as well as by a

Safety in transport and storage of radioactive materials

International Nuclear Information System (INIS)

Mezrahi, A.; Xavier, A.M.

1987-01-01

The increasing utilization of radioisotopes in Industrial, Medical and Research Facilities as well as the processing of Nuclear Materials involve transport activities in a routine basis. The present work has the following main objectives: I) the identification of the safety aspects related to handling, transport and storage of radioactive materials; II) the orientation of the personnel responsible for the radiological safety of Radioactive Installations viewing the elaboration and implementation of procedures to minimize accidents; III) the report of case-examples of accidents that have occured in Brazil due to non-compliance with Transport Regulations. (author) [pt

Use of burnup credit for transportation and storage

International Nuclear Information System (INIS)

Sanders, T.L.; Ewing, R.I.; Lake, W.H.

1991-01-01

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

Regulations for the safe transport of radioactive material. 1996 ed.

International Nuclear Information System (INIS)

1996-01-01

This publication is the revised version of the IAEA's Regulations for the Safe Transport of Radioactive Materials as approved by the Board of Governors in September 1996. It establishes standards of safety which provide an acceptable level of control of the radiation, criticality and thermal hazards to persons, property and the environment that are associated with the transport of radioactive material. After an introductory section, the publication is structured as follows: Section 2 defines the terms that are required for the purposes of the Regulations; Section 3 provides general provisions; Section 4 gives the activity limits and material restrictions used throughout these Regulations; Section 5 provides requirements and controls for transport; Section 6 provides requirements for radioactive materials and for packagings and packages; Section 7 provides requirements for test procedures; Section 8 provides approval and administrative requirements. The requirements for the transport of specified types of consignments are included in an abbreviated form as Schedules. Refs, figs, tabs

Possible use of dual purpose dry storage casks for transportation and future storage of spent nuclear fuel from IRT-Sofia

International Nuclear Information System (INIS)

Manev, L.; Baltiyski, M.

2003-01-01

Objectives: The main objective of the present paper is related to one of the priority goals stipulated in Bulgarian Governmental Decision No.332 from May 17, 1999 - removal of SNF from IRT-Sofia site and its exporting for reprocessing and/or for temporary storage at Kozloduy NPP site. The variant of using dual purpose dry storage casks for transportation and future temporary storage of SNF from IRT-Sofia aims to find out a reasonable alternative of the existing till now variant for temporary SNF storage under water in the existing Kozloduy NPP Spent Fuel Storage Facility until its export for reprocessing. Results: Based on the given data for the condition of 73 Spent Nuclear Fuel Assemblies (SNFA) stored in the storage pool and technical data as well as data for available equipment and IRT-Sofia layout the following framework are specified: draft technical features of dual purpose dry storage casks and their overall dimensions; the suitability of the available equipment for safety and reliable performance of transportation and handling operations of assemblies from storage pool to dual purpose dry storage casks; the necessity of new equipment for performance of the above mentioned operations; Assemblies' transportation and handling operations are described; requirements to and conditions for future safety and reliable storage of SNFA loaded casks are determined. When selecting the technical solutions for safety assurance during performance of site handling operations of IRT-Sofia and for description of the exemplary casks the Effective Bulgarian Regulations are considered. The experience of other countries in performance of transfer and transportation of SNFA from such types of research reactors is taken into account. Also, Kozloduy NPP experience in SNF handling operations is taken into account. Conclusions: The Decision of Council of Minister for refurbishment of research reactor into a low power one and its future utilization for experimental and training

Interim guidance for the safe transport of reprocessed uranium

International Nuclear Information System (INIS)

1994-06-01

Increasingly reprocessed uranium is being used for the fabrication of nuclear fuel elements. Different intermediate reprocessing steps are carried out at different locations. Therefore, transportation of uranium material is necessary. Due to the difference in isotope composition of reprocessed uranium then unirradiated uranium a doubt is casted on the presumption that packages used for the transport of unirradiated uranium are automatically suitable for reprocessed uranium compounds. The Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM) recommended that the issue be reviewed by consultants and that a document be developed that would give guidance to users of the Regulations. This TECDOC is the result of the endeavors of the experts convened at two Consultants Services meetings. It contains guidance on the provisions in the current Regulations as well as proposals for changes to the new Revised Edition whose publication is planned for 1996. This document demonstrates that under the present Transport Regulations it is possible in most cases to ship reprocessed uranium compounds in the same packages as unirradiated uranium compounds. In few cases a more stringent package type is required. 8 refs, 22 figs, 19 tabs

Japanese version transport/storage packaging 'TN24'

International Nuclear Information System (INIS)

Kakunai, H.; Iida, T.; Tsuda, K.; Akamatsu, H.

1993-01-01

Since 1983, Kobe Steel has been engaged jointly with the French company Transnucleaire in the development of 'TN24', a dry-type transport and storage packaging for irradiated fuel elements. This report describes the packaging, which has been adapted for use in domestic power stations using BWRs on the basis of the results of this development. (J.P.N.)

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

International Nuclear Information System (INIS)

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

1982-11-01

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

The Audit of Explosives Storage and Transport Within the Australian Defence Force

Science.gov (United States)

1994-08-01

Headquarters Australian Defence Force Australian Ordnance Council THE AUDIT OF EXPLOSIVES STORAGE AND TRANSPORT WITHIN THE AUSTRALIAN DEFENCE FORCE...control number. 1. REPORT DATE AUG 1994 2. REPORT TYPE 3. DATES COVERED 00-00-1994 to 00-00-1994 4. TITLE AND SUBTITLE The Audit of Explosives...8-98) Prescribed by ANSI Std Z39-18 THE AUDIT OF EXPLOSIVES STORAGE AND TRANSPORT WITHIN THE AUSTRALIAN DFFENCE FORCE - by R.W. Johnson and M.J

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-07-06

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

Long-term storage and safe retrieval of DNA from microorganisms for molecular analysis using FTA matrix cards.

Science.gov (United States)

Rajendram, D; Ayenza, R; Holder, F M; Moran, B; Long, T; Shah, H N

2006-12-01

We assessed the potential use of Whatman FTA paper as a device for archiving and long-term storage of bacterial cell suspensions of over 400 bacterial strains representing 61 genera, the molecular applications of immobilised DNA on FTA paper, and tested its microbial inactivation properties. The FTA paper extracted bacterial DNA is of sufficiently high quality to successfully carryout the molecular detection of several key genes including 16S rRNA, esp (Enterococcus surface protein), Bft (Bacteroides fragilis enterotoxin) and por (porin protein) by PCR and for DNA fingerprinting by random amplified polymorphic DNA-PCR (RAPD-PCR). To test the long-term stability of the FTA immobilised DNA, 100 of the 400 archived bacterial samples were randomly selected following 3 years of storage at ambient temperature and PCR amplification was used to monitor its success. All of the 100 samples were successfully amplified using the 16S rDNA gene as a target and confirmed by DNA sequencing. Furthermore, the DNA was eluted into solution from the FTA cards using a new alkaline elution procedure for evaluation by real-time PCR-based assays. The viability of cells retained on the FTA cards varied among broad groups of bacteria. For the more fragile gram-negative species, no viable cells were retained even at high cell densities of between 10(7) and 10(8) colony forming units (cfu) ml(-1), and for the most robust species such as spore-formers and acid-fast bacteria, complete inactivation was achieved at cell densities ranging between 10(1) and 10(4) cfu ml(-1). The inactivation of bacterial cells on FTA cards suggest that this is a safe medium for the storage and transport of bacterial nucleic acids.

Risk assessment in spent fuel storage and transportation

International Nuclear Information System (INIS)

Pandimani, S.

1989-01-01

Risk assessment in various stages of nuclear fuel cycle is still an active area of Nuclear safety studies. From the results of risk assessment available in literature, it can be determined that the risk resulting from shipments of plutonium and spent-fuel are much greater than that resulting from the transport of other materials within the nuclear fuel cycle. In India spent fuels are kept in Spent Fuel Storage Pool (SFSP) for about 240-400 days, which is relatively a longer period compared to the usual 120 days as recommended by regulatory authorities. After cooling spent fuels are transported to the reprocessing sites which are mostly situated close to the plants. India has two high level waste treatment facilities, one PREFRE (Plutonium Reprocessing and Fuel Recycling) at Tarapur and the other one, a unit of Nuclear Fuel Complex at Hyderabad. This paper presents the risk associated with spent fuel storage and transportation for the Indian conditions. All calculations are based on a typical CANDU reactor system. Simple fault tree models are evolved for SFSP and for Transportation Accident Mode (TAM) for both road and rail. Fault tree quantification and risk assessment are done to each of these models. All necessary data for SFSP are taken mostly from Reactor Safety Study, (1975). Similarly, the data for rail TAM are taken from Annual Statistical Statements, (1987-8) and that for road TAM from Special Issue on Motor Vehicle Accident Statistics in India, (1986). Simulation method is used wherever necessary. Risk is also estimated for normal/accident free transport

Transportation impacts on the Tennessee highway system proposed monitored retrievable storage

Energy Technology Data Exchange (ETDEWEB)

Cobble, C.

1985-12-12

The issue of the transport of spent fuels to the proposed monitored retrievable storage facility in Tennessee is discussed. Relevant issues include the ability of the roads and bridges on the transport routes to handle the weight of the trucks. (CBS)

Classification of transportation packaging and dry spent fuel storage system components according to importance to safety

International Nuclear Information System (INIS)

Tyacke, M.J.; McConnell, J.W. Jr.; Ayers, A.L. Jr.; O'Connor, S.C.; Jankovich, J.P.

1996-01-01

The Idaho National Engineering Laboratory prepared a technical report for the Office of Nuclear Material Safety and Safeguards of the US Nuclear Regulatory Commission, entitled Classification of Transportation Packaging and Dry Spent Fuel Storage System Components According to Importance to Safety, NUREG/CR-6407. This paper provides the results of that report. It also presents the graded approach for classification of components used in transportation packagings and dry spent fuel storage systems. This approach provides a method for identifying the classification of components according to importance to safety within transportation packagings and dry spent fuel storage systems. Record retention requirements are discussed to identify the documentation necessary to validate that the individual components were fabricated in accordance with their assigned classification. A review of the existing regulations pertaining to transportation packagings and dry storage systems was performed to identify current requirements. The general types of transportation packagings and dry storage systems are identified. The methodology used in this paper is based on Regulatory Guide 7.10, Establishing Quality Assurance Programs for Packaging Used in the Transport of Radioactive Material. This paper also includes a list of generic components for each of the general types of transportation packagings and spent fuel storage systems, with a classification category assigned to each component. Several examples concerning the safety importance of components are presented

Performance of CASTORR HAW Cask Cold Trials for Loading, Transport and Storage of HAW canisters

International Nuclear Information System (INIS)

Wilmsmeier, Marco; Vossnacke, Andre

2008-01-01

On the basis of reprocessing contracts, concluded between the German Nuclear Utilities (GNUs) and the reprocessing companies in France (AREVA NC) and the UK (Nuclear Decommissioning Authority), GNS has the task to return the resulting residues to Germany. The high active waste (HAW) residuals from nuclear fuel reprocessing are vitrified and filled into steel cans, the HAW canisters. According to reprocessing contracts the equivalent number of HAW canisters to heavy metals delivered has to be returned to the country of origin and stored at an interim storage facility where applicable. The GNS' CASTOR R HAW casks are designed and licensed to fulfil the requirements for transport and long-term storage of HAW canisters. The new cask type CASTOR R HAW28M is capable of storing 28 HAW canisters with a maximum thermal power of 56 kW in total. Prior to the first active cask loading at a reprocessing facility it is required to demonstrate all important handling steps with the CASTOR R HAW28M cask according to a specific and approved sequence plan (MAP). These cold trials have to be carried out at the cask loading plant and at the reception area of an interim storage facility in Gorleben (TBL-G), witnessed by the licensing authorities and their independent experts. At transhipment stations GNS performs internal trials to demonstrate safe handling. A brand-new, empty CASTOR R HAW28M cask has been shipped from the GNS cask assembly facility in Muelheim to the TBL-G for cold trials. With this cask, GNS has to demonstrate the transhipment of casks at the Dannenberg transfer station from rail to road, transport to and reception at the TBL-G as well as incoming dose rate and contamination measurements and preparation for storage. After removal of all shock absorbers with a cask specific handling frame, tilting operation and assembly of the secondary lid with a pressure sensor, the helium leak tightness and 'Block-mass' tests have to be carried out as well. GNS long-term CASTOR R

Role IAEA implementation of ICRP-60 on regulations the safe transport of radioactive material

International Nuclear Information System (INIS)

Elshinawy, R.K.M.; Gomaa, M.A.

1994-01-01

In november 1990, the (ICRP) adopted its 1990 recommendations (ICRP-60) ( 1). These recommendations will significantly influence not only IAEA's basic safety standards (safety series 9) ( 2), but also the IAEA regulations for the safe transport of radioactive material ( 3) and its supporting documents ( 4-6). IAEA experts are currently engaged in the revision of the transport regulations. This revision process led to the publication of the revised transport regulations of 1966. The transport regulations are developed to ensure safety during movement of radioactive materials, and to provide reasonable assurance that the transport activities comply with the basic safety standards for radiation protection

Multi-purpose canister storage unit and transfer cask thermal analysis

International Nuclear Information System (INIS)

Montgomery, R.A.; Niemer, K.A.; Lindner, C.N.

1997-01-01

Spent Nuclear Fuel (SNF) generated at commercial nuclear power plants throughout the US is a concern because of continued delays in obtaining a safe, permanent disposal facility. Most utilities maintain their SNF in wet storage pools; however, after decades of use, many pools are filled to capacity. Unfortunately, DOE's proposed final repository at Yucca Mountain is at least 10 years from completion, and commercial power utilities have few options for SNF storage in the interim. The Multi-Purpose Canister (MPC) system, sponsored by DOE's Office of Civilian Radioactive Waste Management, is a viable solution to the interim storage problem. The system is designed for interim dry storage, transport, and ultimate disposal of commercial SNF. The MPC system consists of four separate components: an MPC, Transfer Cask, Storage Unit, and Transport Cask. The SNF assemblies are loaded and sealed inside the helium-filled steel MPC. Once sealed, the MPC is not reopened, eliminating the need to re-handle the individual spent fuel assemblies. The MPC is transferred, using the MPC Transfer Cask, into a cylindrical, reinforced-concrete Storage Unit for on-site dry storage. The MPC may be removed from the Storage Unit at any time and transferred into the MPC Transport Cask for transport to the final repository. This paper discusses the analytical approach used to evaluate the heat transfer characteristics of an MPC containing SNF assemblies in the MPC Transfer Cask and Storage Unit

Conditioning of spent fuel assemblies from the Rossendorf RFR research reactor in transport and storage containers of the type CASTOR MTR 2

International Nuclear Information System (INIS)

Schneider, B.; Hofmann, G.

1994-09-01

Most of the spent fuel assemblies are temporarily stored in the flooded fuel ponds AB 1 and AB 2 of the RFR, and some are still in the reactor core. The conditioning task described here is part of the RFR spent fuel management concept and covers the safe emplacement of the spent fuel elements in the CASTOR MTR 2 shipping containers and the sealing of the containers in compliance with the nuclear licence issued for the conditioning task. The transfer of the spent fuel assemblies from the present wet storage conditions to the dry storage conditions in the CASTOR MTR 2 containers is done by a mobile manipulation equipment consisting essentially of the transfer sluice gate and a transfer container. Subsequent to conditioning, the shipping containers are to be transported to a licensed intermediate storage facility to await their transport to a national radwaste repository. The technical handling tools for the transfer and manipulation are briefly described, as well as the process steps involved, putting emphasis on the detailed description of processes and the accompanying time frame, so that the conditioning task can be incorporated into the work plan of the entire project. The report further presents the EDP concept established for the task, including the required data archivation and documentation. (orig.) [de

Regional training course on safe transport of radioactive material. Folder documentation

International Nuclear Information System (INIS)

1999-01-01

Folder including documentation distributed to the participants to the International Atomic Energy Agency (IAEA) Regional Training Course on Safe Transport of Radioactive Material organised by the IAEA in co-operation with the Government of Argentina through the Nuclear Regulatory Authority, held in Buenos Aires, Argentina, 13 September -1 October 1999. The course was intended to people from IAEA Member States in the Latin American and Caribbean region. The instruction language was spanish and some lectures was delivered in english. The documentation was Spanish and some lectures was delivered in English. The documentation was in Spanish and included: copies of transparencies used during lectures, exercises of application, main training document (introduction; shipments of radioactive material; applicable regulations; basic principles; scope and objective of the IAEA Transport Regulations; package design requirements; type of packages and their contents limits; Q system; special form radioactive material requirements; radiation protection requirements; fissile material transport requirements; controls, contamination, radiation level, transport index; operational and administrative requirements; consignors' responsibilities; approval certificates, transport under special arrangements; emergency planning and procedures; physical protection aspects during transport. Guidelines for consignors, radiation detectors, complement to the training manual on main changes included in the 1996 Edition of IAEA Transport Regulations

Regulations for the safe transport of radioactive materials. 1973 rev. ed

International Nuclear Information System (INIS)

1973-01-01

The purpose of these Regulations is to establish standards of safety which provide an acceptable level of control of the radiation hazards to persons, property and the environment that are associated with the transport of radioactive material. These Regulations shall apply to the transport by land, water or air, including transport on own account, of radioactive material other than that which is an integral part of the means of transport. Transport shall be deemed to include any operation incidental to the whole course of carriage, such as loading, unloading and storage in transit. The term includes both normal transport and that under accident conditions. These Regulations do not apply within establishments where the radioactive material is produced, used or stored, other than in the course of transport, and in respect of which other appropriate safety regulations are in force. In the transport of radioactive materials, any other hazardous characteristics of these materials such as explosiveness, inflammability, pyrophoricity, chemical toxicity, and corrosiveness must be taken into account in such a manner as to be in compliance with the relevant transport regulations for dangerous goods of each of the countries through or into which the materials will be transported, as well as in compliance with these Regulations.

Discussion of the influence of CO and CH4 in CO2 transport, injection, and storage for CCS technology.

Science.gov (United States)

Blanco, Sofía T; Rivas, Clara; Bravo, Ramón; Fernández, Javier; Artal, Manuela; Velasco, Inmaculada

2014-09-16

This paper discusses the influence of the noncondensable impurities CO and CH4 on Carbon Capture and Storage (CCS) technology. We calculated and drew conclusions about the impact of both impurities in the CO2 on selected transport, injection, and storage parameters (pipeline pressure drop, storage capacity, etc.), whose analysis is necessary for the safe construction and operation of CO2 pipelines and for the secure long-term geological storage of anthropogenic CO2. To calculate these parameters, it is necessary to acquire data on the volumetric properties and the vapor-liquid equilibrium of the fluid being subjected to CCS. In addition to literature data, we used new experimental data, which are presented here and were obtained for five mixtures of CO2+CO with compositions characteristic of the typical emissions of the E.U. and the U.S.A. Temperatures and pressures are based on relevant CO2 pipeline and geological storage site values. From our experimental results, Peng-Robinson, PC-SAFT, and GERG Equations of State for were validated CO2+CO under the conditions of CCS. We conclude that the concentration of both impurities strongly affects the studied parameters, with CO being the most influential and problematic. The overall result of these negative effects is an increase in the difficulties, risks, and overall costs of CCS.

Mobile heat storage containers and their transport by rail or road

Energy Technology Data Exchange (ETDEWEB)

Goldenberg, Philipp

2013-10-15

Mobile heat storage containers are capable of making a contribution to the meaningful use of energy which is needed for use at a location other than where it originates. The study presented in this report outlines the technology of mobile heat storage and analyses an example of its transport by rail or road. (orig.)

Changes in the regulations for the safe transport of radioactive material

International Nuclear Information System (INIS)

Lopez Vietri, Jorge R.; Vidal, Dora N.; Piumetti, Elsa H.; Capadona, Nancy M.

2000-01-01

The objective of this paper is to describe and to analyze the relevant changes, dealing with the design, operation and administrative requirements, to be introduced in the Revision 1 of the AR 10.16.1 standard 'Transport of radioactive material' that will be put into force on July, 1st 2001 by the Nuclear Regulatory Authority (competent authority of Argentina). In that way, the Revision 1 of the mentioned standard will be coincident with the 1996 edition (revised) of the 'Regulations for the safe transport of radioactive material', Safety Standards Series No. TS-R-1 (ST-1, revised) issued by the International Atomic Energy Agency (IAEA). (author)

Current issues in the transport of radioactive waste and spent fuel: work by the World Nuclear Transport Institute

Energy Technology Data Exchange (ETDEWEB)

Neau, H-J.; Bonnardel-Azzarelli, B. [World Nuclear Transport Inst., London (United Kingdom)

2014-07-01

Various kinds of radioactive waste are generated from nuclear power and fuel cycle facilities. These materials have to be treated, stored and eventually sent to a repository site. Transport of wastes between these various stages is crucial for the sustainable utilization of nuclear energy. The IAEA Regulations for the Safe Transport of Radioactive Material (SSR-6) have, for many decades, provided a safe and efficient framework for radioactive materials transport and continue to do so. However, some shippers have experienced that in the transport of certain specific radioactive wastes, difficulties can be encountered. For example, some materials produced in the decommissioning of nuclear facilities are unique in terms of composition or size and can be difficult to characterize as surface contaminated objects (SCO) or homogeneous. One way WNTI (World Nuclear Transport Institute) helps develop transport methodologies is through the use of Industry Working Groups, bringing together WNTI members with common interests, issues and experiences. The Back-End Transport Industry Working Group focuses on the following issues currently. - Characterization of Waste: techniques and methods to classify wastes - Large Objects: slightly contaminated large objects (ex. spent steam generators) transport - Dual Use Casks: transportable storage casks for spent nuclear fuels, including the very long term storage of spent fuel - Fissile Exceptions: new fissile exceptions provisions of revised TS-R-1 (SSR-6) The paper gives a broad overview of current issues for the packaging and transport of radioactive wastes and the associated work of the WNTI. (author)

A Survey of Restraint Methods for the Safe Transport of Children in Ground Ambulances.

Science.gov (United States)

Woods, Rashida H; Shah, Manish; Doughty, Cara; Gilchrest, Anthony

2018-03-01

The National Highway Traffic Safety Administration (NHTSA) released draft recommendations in 2010 on the safe transport of children in ground ambulances. The purpose of this study was to assess awareness of these guidelines among emergency medical service (EMS) agencies and to identify implementation barriers. We conducted a cross-sectional, anonymous online survey of 911-responding, ground transport EMS agencies in Texas. Demographics, modes of transport based on case scenarios, and barriers to implementation were assessed. Of 62 eligible EMS agencies that took the survey, 35.7% were aware of the NHTSA guidelines, 62.5% agreed they would improve safety, and 41.1% planned to implement them. Seventy-five percent of EMS agencies used the ideal or acceptable alternative to transport children requiring continuous monitoring, and 69.5% chose ideal or acceptable alternatives for children requiring spinal immobilization. The ideal or acceptable alternative was not chosen for children who were not injured or ill (93.2%), ill or injured but not requiring continuous monitoring (53.3%), and situations when multiple patients required transport (57.6%). The main requirements for implementation were provider education, ambulance interior modifications, new guidelines in the EMS agency, and purchase of new equipment. Few EMS agencies are aware of the NHTSA guidelines on safe transport of children in ground ambulances. Although most agencies appropriately transport children who require monitoring, interventions, or spinal immobilization, they use inappropriate means to transport children in situations with multiple patients, lack of injury or illness, or lack of need for monitoring.

[Anniversary of the medical department of the Federal Office for Safe Storage and Destruction of Chemical Weapons].

Science.gov (United States)

Kuz'menko, I E

2013-01-01

The article is devoted to the process of formation and development of CW destruction management system and medical support of professional activities of personnel. Founders of Medical department of the Federal Directorate for Safe Storage and Destruction of Chemical Weapons are presented. Main principles and ways of working of medical department in specific conditions are covered.

Shipment and Storage Containers for Tritium Production Transportation Casks

International Nuclear Information System (INIS)

Massey, W.M.

1998-01-01

A shipping and storage container for the Tritium production transportation casks may be required but requirements for protection of the irradiated rods and radioactive contamination have not been finalized. This report documents the various possibilities for the container depending on the final requirements

Safety Standard for Hydrogen and Hydrogen Systems: Guidelines for Hydrogen System Design, Materials Selection, Operations, Storage and Transportation. Revision

Science.gov (United States)

1997-01-01

The NASA Safety Standard, which establishes a uniform process for hydrogen system design, materials selection, operation, storage, and transportation, is presented. The guidelines include suggestions for safely storing, handling, and using hydrogen in gaseous (GH2), liquid (LH2), or slush (SLH2) form whether used as a propellant or non-propellant. The handbook contains 9 chapters detailing properties and hazards, facility design, design of components, materials compatibility, detection, and transportation. Chapter 10 serves as a reference and the appendices contained therein include: assessment examples; scaling laws, explosions, blast effects, and fragmentation; codes, standards, and NASA directives; and relief devices along with a list of tables and figures, abbreviations, a glossary and an index for ease of use. The intent of the handbook is to provide enough information that it can be used alone, but at the same time, reference data sources that can provide much more detail if required.

A report on the on-going researches on safe transport of radioactive materials as collected by the IAEA in 1980

International Nuclear Information System (INIS)

1981-01-01

Presented are brief reports made by Member States on research in progress in the area of safe transport of radioactive materials. Most of the research reported deals with some aspect of packaging or container design. The research contracts within the IAEA's coordinated research programme on safe transport are also outlined

Handling final storage of unreprocessed spent nuclear fuel

International Nuclear Information System (INIS)

1978-01-01

The present second report from KBS describes how the safe final storage of spent unreprocessed nuclear fuel can be implemented. According to the Swedish Stipulation Law, the owner must specify in which form the waste is to be stored, how final storage is to be effected, how the waste is to be transported and all other aspects of fuel handling and storage which must be taken into consideration in judging whether the proposed final storage method can be considered to be absolutely safe and feasible. Thus, the description must go beyond general plans and sketches. The description is therefore relatively detailed, even concerning those parts which are less essential for evaluating the safety of the waste storage method. For those parts of the handling chain which are the same for both alternatives of the Stipulation Law, the reader is referred in some cases to the first report. Both of the alternatives of the Stipulation Law may be used in the future. Handling equipment and facilities for the two storage methods are so designed that a combination in the desired proportions is practically feasible. In this first part of the report are presented: premises and data, a description of the various steps of the handling procedure, a summary of dispersal processes and a safety analysis. (author)

Influence of methane in CO2 transport and storage for CCS technology.

Science.gov (United States)

Blanco, Sofía T; Rivas, Clara; Fernández, Javier; Artal, Manuela; Velasco, Inmaculada

2012-12-04

CO(2) Capture and Storage (CCS) is a good strategy to mitigate levels of atmospheric greenhouse gases. The type and quantity of impurities influence the properties and behavior of the anthropogenic CO(2), and so must be considered in the design and operation of CCS technology facilities. Their study is necessary for CO(2) transport and storage, and to develop theoretical models for specific engineering applications to CCS technology. In this work we determined the influence of CH(4), an important impurity of anthropogenic CO(2), within different steps of CCS technology: transport, injection, and geological storage. For this, we obtained new pressure-density-temperature (PρT) and vapor-liquid equilibrium (VLE) experimental data for six CO(2) + CH(4) mixtures at compositions which represent emissions from the main sources in the European Union and United States. The P and T ranges studied are within those estimated for CO(2) pipelines and geological storage sites. From these data we evaluated the minimal pressures for transport, regarding the density and pipeline's capacity requirements, and values for the solubility parameter of the mixtures, a factor which governs the solubility of substances present in the reservoir before injection. We concluded that the presence of CH(4) reduces the storage capacity and increases the buoyancy of the CO(2) plume, which diminishes the efficiency of solubility and residual trapping of CO(2), and reduces the injectivity into geological formations.

Utilization of the organ care system as ex-vivo lung perfusion after cold storage transportation.

Science.gov (United States)

Mohite, P N; Maunz, O; Popov, A-F; Zych, B; Patil, N P; Simon, A R

2015-11-01

The Organ Care System (OCS) allows perfusion and ventilation of the donor lungs under physiological conditions. Ongoing trials to compare preservation with OCS Lung with standard cold storage do not include donor lungs with suboptimal gas exchange and donor lungs treated with OCS following cold storage transportation. We present a case of a 48-yr-old man who received such lungs after cold storage transportation treated with ex-vivo lung perfusion utilizing OCS. © The Author(s) 2015.

Interim spent-fuel storage options at commercial nuclear power plants

International Nuclear Information System (INIS)

Thakkar, A.R.; Hylko, J.M.

1991-01-01

Although spent fuel can be stored safely in waterfilled pools at reactor sites, some utilities may not possess sufficient space for life-of-plant storage capability. In-pool storage capability may be increased by reracking assemblies, rod consolidation, double tiering spent-fuel racks, and by shipping spent fuel to other utility-owned facilities. Long-term on-site storage capability for spent fuel may be provided by installing (dry-type) metal casks, storage and transportation casks, concrete casks, horizontal concrete modules, modular concrete vaults, or by constructing additional (pool-type) storage installations. Experience to date has provided valuable information regarding dry-type or pool-type installations, cask handling and staffing requirements, security features, decommissioning activities, and radiological issues

Fuel removal, transport, and storage

International Nuclear Information System (INIS)

Reno, H.W.

1986-01-01

The March 1979 accident at Unit 2 of the Three Mile Island Nuclear Power Station (TMI-2) which damaged the core of the reactor resulted in numerous scientific and technical challenges. Some of those challenges involve removing the core debris from the reactor, packaging it into canisters, loading canisters into a rail cask, and transporting the debris to the Idaho National Engineering Laboratory (INEL) for storage, examination, and preparation for final disposal. This paper highlights how some challenges were resolved, including lessons learned and benefits derived therefrom. Key to some success at TMI was designing, testing, fabricating, and licensing two rail casks, which each provide double containment of the damaged fuel. 10 refs., 12 figs

Code of Practice for the safe transport of radioactive substances 1990

International Nuclear Information System (INIS)

1990-01-01

This Federal Code revises an earlier Code on the same subject issued in 1982 and was formulated under the Environment Protection (Nuclear Codes) Act 1978. The purpose of the Code is to establish uniform safety standards, applicable throughout the Commonwealth of Australia, to provide for the protection of persons and the environment, against any dangers associated with the transport of radioactive substances. The Code uses as a basis the IAEA Regulations for the Safe Transport of Radioactive Materials. This new edition takes into account the 1985 Edition of the Regulations incorporating the 1988 Supplement and provides, furthermore, that radiation protection standards will also be subject to recommendations of the Australian National Health and Medical Research Council [fr

Regulations for safe transport of spent fuels from nuclear power plants in CMEA member countries. Part III

International Nuclear Information System (INIS)

Zizka, B.

1978-11-01

The regulations for safe transport of spent fuel from nuclear power plants in the CMEA member countries consist of general provisions, technical requirements for spent fuel transport, transport conditions, procedures for submitting reports on transport, regulations for transport and protection of radioactive material to be transported, procedures for customs clearance, technical and organizational measures for the prevention of hypothetical accidents and the elimination of their consequences. The bodies responsible for spent fuel transport in the CMEA member countries are listed. (J.B.)

Seven years of experience in storage of solid radioactive wastes of low and medium activity on the surface or in concrete ditches

International Nuclear Information System (INIS)

Bardet, G.

This experience in the transport and storage of radioactive waste leads to several reflections pertinent to large-scale nuclear installations throughout the world. The experience demonstrates that products of this kind can be centralized and confined by relatively simple processes which are safe and of reasonable cost. The necessary liaison between the producer of radioactive wastes and the group which takes charge of storage is emphasized for the choice of the waste conditioning procedure. It is a consistent part of the experience that the initial conditioning determines in large measure the handling and storage techniques. It is certain that the absence of a solution for long-term storage of radioactive wastes will lead the producers to consider and carry out conditioning which, although valuable, does not have all the same advantages for final disposition of the product. In the field of transport, the volumes and weights are important. It is desirable that a permanent storage center be near a railroad. It is stated that storage can be ensured under safe conditions and with acceptable costs of all solid wastes of low and average activity except those having more than a certain amount of alpha activity. For the latter products a solution can be found which is safe

The development of a transportable storage cask

International Nuclear Information System (INIS)

Stuart, I.F.

1991-01-01

There are a number of different technologies for implementing interim storage of spent fuel at reactor sites. It is generally accepted that, if possible, expanding the capacity of existing fuel pools through the installation of compact racks and the use of fuel rod consolidation are the most economical first steps. Once these have been carried out, other alternatives must be employed if further capacity expansion is required. It is not the purpose of this paper to discuss the relative economics of these alternatives, since under specific constraints and conditions each one can be shown to have an economic benefit. However, it is the reduction in plant operations, the minimising of radiation exposure, the inherent flexibility and corresponding overall favourable economics that have led to the development of the dual purpose storage and transport cask in the past few years. (author)

Comparison of the transportation risks for the spent fuel in Korea for different transportation scenarios

International Nuclear Information System (INIS)

Jeong, Jongtae; Cho, D.K.; Choi, H.J.; Choi, J.W.

2011-01-01

According to the long term management strategy for spent fuels in Korea, they will be transported from the spent fuel pools in each nuclear power plant to the central interim storage facility (CISF) which is to start operation in 2016. At the start of the operation of the final repository (FR), by the year 2065, transport will then take place between the CISF and the FR. Therefore, we have to determine the safe and economical logistics for the transportation of these spent fuels by considering their transportation risks and costs. In this study, we developed four transportation scenarios for a maritime transportation by considering the type of transportation casks and transport means in order to suggest safe and economical transportation logistics for the spent fuels in Korea. And, we estimated and compared the transportation risks for these four transportation scenarios. Also, we estimated and compared the transportation risks resulting from accidents during the transportation of PWR and PHWR spent fuels by road trailers from the CISF and the FR. From the results of this study, we found that risks resulting from accidents during the transportation of the spent fuels have a very low radiological risk activity with a manageable safety and health consequences. The results of this study can be used as basic data for the development of safe and economical logistics for a transportation of the spent fuels in Korea by considering the transportation costs for the four scenarios which will be needed in the near future.

Field efficacy evaluation and post-treatment contamination risk assessment of an ultraviolet disinfection and safe storage system.

Science.gov (United States)

Reygadas, Fermin; Gruber, Joshua S; Ray, Isha; Nelson, Kara L

2015-11-15

Inconsistent use of household water treatment and safe storage (HWTS) systems reduces their potential health benefits. Ultraviolet (UV) disinfection is more convenient than some existing HWTS systems, but it does not provide post-treatment residual disinfectant, which could leave drinking water vulnerable to recontamination. In this paper, using as-treated analyses, we report on the field efficacy of a UV disinfection system at improving household drinking water quality in rural Mexico. We further assess the risk of post-treatment contamination from the UV system, and develop a process-based model to better understand household risk factors for recontamination. This study was part of a larger cluster-randomized stepped wedge trial, and the results complement previously published population-level results of the intervention on diarrheal prevalence and water quality. Based on the presence of Escherichia coli (proportion of households with ≥ 1 E. coli/100 mL), we estimated a risk difference of -28.0% (95% confidence interval (CI): -33.9%, -22.1%) when comparing intervention to control households; -38.6% (CI: -48.9%, -28.2%) when comparing post- and pre-intervention results; and -37.1% (CI: -45.2%, -28.9%) when comparing UV disinfected water to alternatives within the household. We found substantial increases in post-treatment E. coli contamination when comparing samples from the UV system effluent (5.0%) to samples taken from the storage container (21.1%) and drinking glasses (26.0%). We found that improved household infrastructure, additional extractions from the storage container, additional time from when the storage container was filled, and increased experience of the UV system operator were associated with reductions in post-treatment contamination. Our results suggest that the UV system is efficacious at improving household water quality when used as intended. Promoting safe storage habits is essential for an effective UV system dissemination. The drinking

21 CFR 864.3250 - Specimen transport and storage container.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Specimen transport and storage container. 864.3250 Section 864.3250 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF HEALTH AND HUMAN SERVICES (CONTINUED) MEDICAL DEVICES HEMATOLOGY AND PATHOLOGY DEVICES Pathology Instrumentation and Accessories § 864...

Vacuum technologies developed for at-400A Type B transportation and storage package

International Nuclear Information System (INIS)

Franklin, K.W.; Cockrell, G.D.

1995-01-01

The AT-400A TYPE B transportation and storage container will be used at Pantex Plant for the transportation and interim storage of plutonium pits. The AT-400A was designed by a joint effort between Sandia National Labs, Los Alamos National Labs, Lawrence Livermore National Laboratory, and Mason and Hanger-Silas Mason Co., Inc. In order to meet the requirements for transportation and storage, five different vacuum technologies had to be developed. The goals of the various vacuum technologies were to verify the plutonium pit was sealed, perform the assembly verification leak check in accordance with ANSI N-14.5 and to provide a final inert gas backfill in the containment vessel. This paper will discuss the following five vacuum technologies: (1) Pit Leak Testing, (2) Containment Vessel Purge and Backfill with tracer gas, (3) Containment Vessel Leak Testing, (4) Containment Vessel Purge and Final Backfill, and (5) Leak Testing of the Containment Vessel Gas Transfer tube

Status of Philippine regulatory infrastructure for the safe transport of radioactive materials

International Nuclear Information System (INIS)

Parami, V.K.; De Jesus, T.G.

2004-01-01

This paper presents some regulatory practices and experiences of the Philippine Nuclear Research Institute (PNRI) in ensuring safe transport of radioactive materials. The regulation and licensing the use of radioactive materials started in 1958. The number of packages containing radioactive materials transported into and within the country has increased with the increase number of licensees. During the period 2000-2002, the total number of licensees is 293, 311 and 311 respectively. The PNRI issues certificates of release and certificate of transport/authority to transport. Based on the data of certificates, the topmost sealed source shipments from abroad, mostly in type A package, are 192 Ir and 125 I for brachytherapy. For unsealed sources, also mostly in type A package, the topmost radioactive materials are 99m Tc (generators), 131 I, 201 Tl mainly for medical diagnosis. From the data on certificates of transport, the total number of packages inspected for the period 2000-2002 is 464, 577 and 747 respectively. The experiences in the enforcement of the transport regulations and the implication of issuing certificates of release and transport are discussed and recommendations are presented. (Authors)

Development of a National System to Regulate Safe Transport of Radioactive Materials in Ukraine

International Nuclear Information System (INIS)

Gashev, M.; Kutuzova, T.; Sakalo, V.

2016-01-01

The paper provides brief information on development of the legislative framework and regulatory requirements in transport of radioactive materials in Ukraine. The application of IAEA documents is demonstrated and their contribution to the improvement of the national regulatory control system and processes of its harmonization with international safety requirements is underlined. Proposals for coordination and interaction enhancement in order to improve safety in safe transport of radioactive materials are defined in the conclusion. (author)

Transport, handling, and interim storage of intermediate-level transuranic waste at the INEL

International Nuclear Information System (INIS)

Metzger, J.C.; Snyder, A.M.

1977-09-01

The Idaho National Engineering Laboratory stores transuranic (TRU)-contaminated waste emitting significant amounts of beta-gamma radiation. This material is referred to as intermediate-level TRU waste. The Energy Research and Development Administration requires that this waste be stored retrievably during the interim before a Federal repository becomes operational. Waste form and packaging criteria for the eventual storage of this waste at a Federal repository, i.e., the Waste Isolation Pilot Plant (WIPP), have been tentatively established. The packaging and storage techniques now in use at the Idaho National Engineering Laboratory are compatible with these criteria and also meet the requirement that the waste containers remain in a readily-retrievable, contamination-free condition during the interim storage period. The Intermediate Level Transuranic Storage Facility (ILTSF) provides below-grade storage in steel pipe vaults for intermediate-level TRU waste prior to shipment to the WIPP. Designated waste generating facilities, operated for the Energy Research and Development Administration, use a variety of packaging and transportation methods to deliver this waste to the ILTSF. Transfer of the waste containers to the ILTSF storage vaults is accomplished using handling methods compatible with these waste packaging and transport methods

Advisory material for the IAEA regulations for the safe transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2008-01-01

Since the first edition in 1961, the Regulations for the Safe Transport of Radioactive Material of the IAEA (IAEA Regulations) have served as the basis of safety for the transport of radioactive material worldwide. In the discussions leading to the first edition of the IAEA Regulations, it was realized that there was need for a publication to supplement the Regulations which could give information of individual provisions as to their purpose, their scientific background and how to apply them in practice. In response, the Agency published Safety Series No. 7, entitled, in its first edition in 1961, 'Notes on Certain Aspects of the Regulations'. An additional source of information on the Regulations, providing advice on 'how' the user should comply with them which could be augmented from time to time in the light of latest experience, was provided by the Agency, initially in relation to the 1973 edition of the Regulations. This was entitled 'Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material' and designated Safety Series No. 37. This document is the result of combining the two Safety Series in a single publication. Thus the primary purpose of this publication is to provide guidance to users on proven and acceptable ways of complying with the Regulations. This Advisory Material is not a stand-alone text and it only has significance when used as a companion to the IAEA Safety Standards Series No. ST-1, Regulations for the Safe Transport of Radioactive Material (1996 edition)

Transport and Storage Economics of CCS Networks in the Netherlands

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-04-15

A team from the Rotterdam Climate Initiative, CATO-2 (the Dutch national R and D programme on CCS) and the Clinton Climate Initiative, developed a financial model to assess the economics of alternative CO2 transport and storage options in the North Sea, based on common user infrastructure. The purpose of the financial model is to introduce a simple planning tool relating to the transport and storage components of an integrated CCS project using readily available, non-confidential data. A steering group of major emitters with advanced plans for CCS projects in the Netherlands and Belgium guided the project. Although the report focusses on potential projects in the Netherlands (Rotterdam and Eemshaven) and Belgium (Antwerp) in the short to medium term, the analysis and lessons could be useful to other regions considering CO2 network solutions.

Next nuclear gamble: transportation and storage of nuclear waste

International Nuclear Information System (INIS)

Resnikoff, M.

1983-01-01

Accidents during transport of nuclear waste are more threatening - though less likely - than a reactor meltdown because transportation accidents could occur in the middle of a populous city, affecting more people and property than a plant accident, according to the Council on Economic Priorities, a non-profit public service research organization. Transportation, as presently practiced, is unsafe. Shipping containers, called casks, are poorly designed and constructed, CEP says. The problem needs attention because the number of casks filled with nuclear waste on the nation's highways could increase a hundred times during the next 15 years under the Nuclear Waste Policy Act of 1982, which calls for storage areas. Recommendations, both technical and regulatory, for reducing the risks are presented

SUBTASK 2.19 – OPERATIONAL FLEXIBILITY OF CO2 TRANSPORT AND STORAGE

Energy Technology Data Exchange (ETDEWEB)

Jensen, Melanie; Schlasner, Steven; Sorensen, James; Hamling, John

2014-12-31

Carbon dioxide (CO2) is produced in large quantities during electricity generation and by industrial processes. These CO2 streams vary in terms of both composition and mass flow rate, sometimes substantially. The impact of a varying CO2 stream on pipeline and storage operation is not fully understood in terms of either operability or infrastructure robustness. This study was performed to summarize basic background from the literature on the topic of operational flexibility of CO2 transport and storage, but the primary focus was on compiling real-world lessons learned about flexible operation of CO2 pipelines and storage from both large-scale field demonstrations and commercial operating experience. Modeling and pilot-scale results of research in this area were included to illustrate some of the questions that exist relative to operation of carbon capture and storage (CCS) projects with variable CO2 streams. It is hoped that this report’s real-world findings provide readers with useful information on the topic of transport and storage of variable CO2 streams. The real-world results were obtained from two sources. The first source consisted of five full-scale, commercial transport–storage projects: Sleipner, Snøhvit, In Salah, Weyburn, and Illinois Basin–Decatur. These scenarios were reviewed to determine the information that is available about CO2 stream variability/intermittency on these demonstration-scale projects. The five projects all experienced mass flow variability or an interruption in flow. In each case, pipeline and/or injection engineers were able to accommodate any issues that arose. Significant variability in composition has not been an issue at these five sites. The second source of real- world results was telephone interviews conducted with experts in CO2 pipeline transport, injection, and storage during which commercial anecdotal information was acquired to augment that found during the literature search of the five full-scale projects. The

Effect of sunlight, transport and storage vessels on drinking water ...

African Journals Online (AJOL)

Effect of sunlight, transport and storage vessels on drinking water quality in rural Ghana. ... on drinking water quality in rural Ghana. K Obiri-Danso, E Amevor, LA Andoh, K Jones ... Full Text: EMAIL FREE FULL TEXT EMAIL FREE FULL TEXT

Explanatory material for the IAEA regulations for the safe transport of radioactive material (1985 edition). 2. ed

International Nuclear Information System (INIS)

1987-01-01

This document pertains to Safety Series No. 7 of the IAEA, which is to explain the provisions of the IAEA Safety Series No. 6 in order to help comprehension of the regulatory standards and to promote compliance, public acceptance and further development of the Regulations. The document also reflects corrections and changes implemented by the 1986 Supplement to the Regulations for the Safe Transport of Radioactive Material. The intent of the document is to show why certain provisions of Safety Series No. 6 exist, why they are so formed (including any relevant history) and the rationale behind the provisions. Definitions are presented, basic principles established, activity and fissile material limits as well as computational techniques are presented. The detailed requirements (the latter sections are built on this information) concern: shipping and storage, material packagings and packages which govern design. Test requirements are provided. Approval and administrative requirements are stated. Heavy emphasis is placed on providing safety through design. It contains the cornerstone of the basic requirements for packagings, packages and material-related aspects.

The risk assesment in storage and transportation of dangerous substances - preoccupations and perspectives

International Nuclear Information System (INIS)

Lazar, Roxana Elena; Dumitrescu, Maria; Stefanescu, Ioan

2001-01-01

The paper presents a risk assessment model for dangerous substance storage and transportation. It will combine also qualitative and quantitative evaluation methods, the results being referred to the lethal risk at individual and social level. The model includes the main tasks to classify the risks and to achieve a scale of priorities. To achieve a proper analysis of a regional risk the following steps should be observed: a list of dangerous substances; the classification of storage and transportation activities in the area; the selection of those activities that can be included in the study; establishing the category of effects ; the estimation of consequences to the environment and people; the calculation of major accidents frequency; the risk level classification. Generally, in the global risk assessment in industrial sector one neglects the risk induced by the transport of dangerous substances. Because of that the decision process in the risk management field can be seriously affected and the initiatives to reduce the risk and to decrease the consequences of potential accidents can be reduced, too. The model will be applied to evaluate the risk due major accidents occurring in the storage of dangerous substances and their transportation on roads, railway or by pipes. It represents a prime action plan at national level to evaluate and analyze the transportation risk. (authors)

Regulations concerning marine transport and storage of dangerous things (abridged)

International Nuclear Information System (INIS)

1987-01-01

This report shows the Ordinances No.84 (1967) and No.30 (1957) of the Ministry of transport. The Ordinance No.84 has been published in detail elsewhere. The provisions concerning shipping transport and storage of dangerous substances deal with isolation of each dangerous substance, method for loading (cleaning of container, etc.), certificate for ship for transporting dangerous substances, renewal of certificate for ship for transporting dangerous substances, return of certificate, fee (for renewal and reissue of certificate), definition of terms, type of radioactive cargo (L-type cargo, A-type cargo, BM-type cargo, BU type cargo), transport of radioactive substances, type of fissionable cargo (Type I, Type II and Type III), confirmation of safety concerning radioactive cargo (conformity to standards, inspection, approval, etc.), limit of cargo volume, transport index, marking (type of cargo), confirmation of safety of transport, inspection of contamination, notice of transport, special measures, inspection of cargo (radioactive substances), requirements for container and package, etc. (Nogami, K.)

Transportation impacts on the Tennessee highway system proposed monitored retrievable storage. Final report

Energy Technology Data Exchange (ETDEWEB)

Cobble, C.

1985-12-12

The issue of the transport of spent fuels to the proposed monitored retrievable storage facility in Tennessee is discussed. Relevant issues include the ability of the roads and bridges on the transport routes to handle the weight of the trucks. (CBS)

Safe and Secure Transportation of Radioactive Materials in Pakistan and Future Challenges

International Nuclear Information System (INIS)

Muneer, Muhammad; Ejaz, Asad

2016-01-01

PNRA is the sole organization in the country responsible to regulate all matters pertaining to ionizing radiations. For the safety of transport of radioactive material in the country, PNRA has adopted IAEA TS-R-1 as a national regulation. To cover the security aspects and emergency situations, if any, during the transportation of radioactive material, PNRA has issued the regulatory guide on ‘Transportation of Radioactive Material by Road in Pakistan’. In Pakistan, low to medium activity radioactive sources are transported from one place to another by road for the purpose of industrial radiography, well logging, medical application, etc. According to national policy, sealed radioactive sources of half life greater than 1 year and with initial activity of 100 GBq or more imported in the country are required to be returned to country of origin (exported) after its use. Although the activities related to transport of radioactive material remained safe and secure and no major accident/incident has been reported so far, however, the improvement/enhancement in the regulatory infrastructure is a continuous process. In future, more challenges are expected to be faced in the safety of transport packages. This paper will describe the steps taken by PNRA for the safety and security of transport of radioactive material in the country and future challenges. (author)

Gas adsorption during storage of plutonium dioxide powders

International Nuclear Information System (INIS)

Cuillerdier, C.; Cossonnet, C.; Germain, M.

1984-10-01

Adsorption phenomena occuring in plutonium dioxide containers are studied for the determination of safe conditions for storage and transportation of plutonium dioxide powders. Adsorption on dried PuO 2 of air individual gases, influence of powder isotopic composition, chemisorption, effect of moisture are determined. Adsorption of dry air obeys an Elovich's law for its kinetics it is greatly exchange by α radiolysis. Pressure in the container can be reduced by storage under dry inert gas (Ar), decreasing the PuO 2 load and using powder containing preadsorbed water or wet air then radiolysis may occur (H 2 formation)

MRS [monitored retrievable storage] to transportation system interfaces

International Nuclear Information System (INIS)

Row, T.H.; Croff, A.G.

1987-01-01

In March 1987, the US Department of Energy presented to Congress the proposal to construct and operate a facility for the monitored retrievable storage (MRS) of spent fuel at a site on the Clinch River in the Roane County portions of Oak Ridge. In discussing the MRS to Transportation System Interfaces, the authors provide a blending of the technical and institutional issues, for they do not believe the solutions to success of this enterprise lie wholly in one area. The authors cover: early chronology of the MRS; comparison of total-system life cycle cost estimates of the authorized system and improved-performance system (i.e., the system that includes a facility for MRS); transportation costs resulting from shipping, security and cask; assumptions for dedicated rail transport from MRS to repository; and significant results from the Total System Life Cycle Cost (TSLCC) analysis of the improved performance system. (AT)

Safe Minimum Internal Temperature Chart

Science.gov (United States)

... Internal Temperature Chart Safe steps in food handling, cooking, and storage are essential in preventing foodborne illness. You can't see, smell, or taste harmful bacteria that may cause illness. In every step of food preparation, follow the four guidelines to keep food safe: ...

Regulations for the Safe Transport of Radioactive Materials. 1964 Revised Edition

International Nuclear Information System (INIS)

1965-01-01

In 1961 the International Atomic Energy Agency, within the framework of its statutory functions and in accordance with recommendations made by its Preparatory Commission and by the Economic and Social Council of the United Nations, published safety regulations which could be applied to the national and international transport of radio active materials by all means of transport. At the same time, the Director General of the Agency indicated that these regulations would be revised at appropriate intervals in consultation with Member States and the organizations concerned and invited suggestions for their improvement in the light of experience and increased knowledge. In preparing the revised regulations presented in this document, the Agency has received considerable support from its Member States and the organizations concerned, which have made extensive studies and suggestions in order to assist in its work. The Agency also convened several meetings of experts from its Member States and of representatives of a number of international organizations, and has been represented in several meetings convened by those organizations. In publishing the revised transport regulations which result from that co-ordinated effort, the Agency aims at proposing a lasting framework of principles and rules, complemented by appropriate technical data, acceptable for the safe transport of radio active materials by air, land and water. In particular, the developments which have been introduced concerning the packaging requirements, the nuclear safety criteria for the transport of fissile materials and the methods for testing packages should facilitate the international acceptance of packages by the authorities concerned. The Board of Governors of the Agency approved the revised regulations in June and September 1964. It authorized the Director General to apply them, as appropriate, to Agency operations and Agency assisted operations and to recommend to Member States and to the

The experience of the Republic of Belarus in the field of safe and secure transport of radioactive material

International Nuclear Information System (INIS)

Astashka, R.; Kronava, Z.; Prykhodzka, A.; Tkachonak, I.

2016-01-01

The experience of the safe and secure transport of radioactive material of the Republic of Belarus includes domestic and international movements. Transit is a substantial part of international movements taking into account the location of the country. Legislative and regulatory requirements on safety and security of radioactive material transport being in force in the country include the demands making by such state structures as the Department on Nuclear and Radiation Safety, the Department on supervision for the safe industrial activities, the Ministry of Health of the Republic of Belarus. At the same time response to accidents and security events belongs to the scope of activity of special subdivisions of the Ministry for Emergency Situations and the Ministry of Internal Affairs of the Republic of Belarus. For safety purposes all the above-mentioned structures are executing their duties in close collaboration with each other and are following the IAEA safety and security recommendations. The regulatory infrastructure concerning the safe and secure transport of radioactive material of the Republic of Belarus is the subject of the contributed paper. (author)

Storage and transport casks combine to bring benefits

International Nuclear Information System (INIS)

Thorup, C.

1988-01-01

The Nuclear Assurance Corporation is currently preparing a safety report on its new spent fuel storage/transport casks. The report is due to be submitted to the NRC in 1989, together with an application for a licence. The aim of the combined casks is to simplify the process of dealing with spent fuel, whilst keeping costs down. The design of the casks is described, together with questions relating to the licensing of the casks. (author)

Uranium retrieval support, storage, and marketing

International Nuclear Information System (INIS)

Jackson, J.D.; Marshall, E.M.

2001-01-01

The United States Department of Energy is implementing a stewardship approach to management of uranium assets. This life-cycle approach to managing uranium addresses current needs in the context of a long-term strategy. In June 1998, the United States Department of Energy established the Uranium Management Group. The mission of the UMG is to safely collect and store commercially viable uranium from various DOE facilities at a central location. The Oak Ridge Operations Office, in Oak Ridge, Tennessee, was given the task to establish a facility for the storage of these uranium materials. Materials collected are non-waste uranium and packaged to allow transport and long-term storage. Coordination of uranium management under the Uranium Management Group offers significant opportunities for sayings through improved planning and efficiency and creates an environmentally sound approach for the storage and reuse of excess uranium. (author)

Uranium retrieval support, storage, and marketing

Energy Technology Data Exchange (ETDEWEB)

Jackson, J.D.; Marshall, E.M. [U.S. Department of Energy, Oak Ridge, Tennessee (United States)

2001-07-01

The United States Department of Energy is implementing a stewardship approach to management of uranium assets. This life-cycle approach to managing uranium addresses current needs in the context of a long-term strategy. In June 1998, the United States Department of Energy established the Uranium Management Group. The mission of the UMG is to safely collect and store commercially viable uranium from various DOE facilities at a central location. The Oak Ridge Operations Office, in Oak Ridge, Tennessee, was given the task to establish a facility for the storage of these uranium materials. Materials collected are non-waste uranium and packaged to allow transport and long-term storage. Coordination of uranium management under the Uranium Management Group offers significant opportunities for sayings through improved planning and efficiency and creates an environmentally sound approach for the storage and reuse of excess uranium. (author)

Structure-function relationships in sapwood water transport and storage.

Science.gov (United States)

Barbara L. Gartner; Frederick C. Meinzer

2005-01-01

Primary production by plants requires the loss of substantial quantities of water when the stomata are open for carbon assimilation. The delivery of that water to the leaves occurs through the xylem. The structure, condition, and quantity of the xylem control not only the transport efficiency but also the release of water from storage. For example, if there is high...

CASTORR 1000/19: Development and Design of a New Transport and Storage Cask

International Nuclear Information System (INIS)

Funke, Th.; Henig, Ch.

2008-01-01

The design of the new transport and storage cask type CASTOR R 1000/19 is presented in this paper. This cask was developed for the dry interim storage of spent VVER1000 fuel assemblies concerning the requirements of the Temelin NPP, Czech Republic. While the cask body is based on well-known ductile cast iron cask types with in-wall moderator, the basket follows a new concept. The basket is able to carry 19 fuel assemblies with a total decay heat power up to approximately 17 kW. The cask fulfils all requirements for a type B(U)F package. The main nuclear, mechanical and thermal properties of the cask are illustrated for normal conditions and for hypothetical accident scenarios during transport and storage. The main steps of the handling procedure such as loading the cask, drying the cavity and mounting the double lid system for tightness during interim storage are shown in principle. For this handling, boundary conditions at the NPP site such as dimensions, weight and the loading machine interface are considered. (authors)

Experimental and theoretical approach to the assessment of stability criteria for safe transport of ammonium nitrate based emulsions

NARCIS (Netherlands)

Fabiano, B.; Kersten, R.J.A.; Barbucci, A.; Boers, M.N.

2013-01-01

The safety issues connected to storage and transportation of ammonium nitrate and ammonium nitrate emulsions are to be considered of primary importance, as demonstrated by the Tolouse explosion and various handling and storage accidents in different countries. This paper is focused on the assessment

Behind the wheel: community consultation informs adaptation of safe-transport program for older drivers.

Science.gov (United States)

Coxon, Kristy; Keay, Lisa

2015-12-09

Safe-transport is important to well-being in later life but balancing safety and independence for older drivers can be challenging. While self-regulation is a promising tool to promote road safety, more research is required to optimise programs. Qualitative research was used to inform the choice and adaptation of a safe-transport education program for older drivers. Three focus groups were conducted with older drivers living in northwest Sydney to explore four key areas related to driving in later life including aged-based licensing, stopping or limiting driving, barriers to driving cessation and alternative modes of transportation. Data were analysed using content analysis. Four categories emerged from the data; bad press for older drivers, COMPETENCE not age, call for fairness in licensing regulations, and hanging up the keys: It's complicated! Two key issues being (1) older drivers wanted to drive for as long as possible but (2) were not prepared for driving cessation; guided the choice and adaption of the Knowledge Enhances Your Safety (KEYS) program. This program was adapted for the Australian context and focus group findings raised the need for practical solutions, including transport alternatives, to be added. Targeted messages were developed from the data using the Precaution Adoption Process Model (PAPM), allowing the education to be tailored to the individual's stage of behaviour change. Adapting our program based on insights gained from community consultation should ensure the program is sensitive to the needs, skills and preferences of older drivers.

Comparison of three media for transport and storage of the samples collected for detection of avian influenza virus.

Science.gov (United States)

Zhang, Xiao-Chun; Liu, Shuo; Hou, Guang-Yu; Zhuang, Qing-Ye; Wang, Kai-Cheng; Jiang, Wen-Ming; Wang, Su-Chun; Li, Jin-Ping; Yu, Jian-Min; Du, Xiang; Huang, Bao-Xu; Chen, Ji-Ming

2015-09-15

Detection of avian influenza viruses (AIVs) is important for diagnosis, surveillance and control of avian influenza which is of great economic and public health significance. Proper transport and storage of samples is critical for the detection when the samples cannot be detected immediately. As recommended by some international or national authoritative entities and some publications, phosphate buffered saline (PBS), PBS-glycerol and brain heart infusion broth (BHIB) are frequently used for transport and storage of the samples collected for detection of AIVs worldwide. In this study, we compared these three media for transport and storage of simulated and authentic swab and feces samples collected for detection of AIVs using virus isolation and reverse transcription-PCR. The results suggest that PBS-glycerol is superior to PBS and BHIB as the sample transport and storage media. The results also suggest that the samples collected for detection of AIVs should be detected as soon as possible because the virus concentration of the samples may decline rapidly during storage within days at 4 or -20°C. Copyright © 2015 Elsevier B.V. All rights reserved.

Handling of spent nuclear fuel and final storage of vitrified high level reprocessing waste

International Nuclear Information System (INIS)

1978-01-01

The report gives a general summary of the Swedish KBS-project on management and disposal of vitrified reprocessed waste. Its final aim is to demostrate that the means of processing and managing power reactor waste in an absolutely safe way, as stipulated in the Swedish so called Conditions Act, already exist. Chapters on Storage facility for spent fuel, Intermidiate storage of reprocessed waste, Geology, Final repository, Transportation, Protection, and Siting. (L.E.)

Rigorous Screening Technology for Identifying Suitable CO2 Storage Sites II

Energy Technology Data Exchange (ETDEWEB)

George J. Koperna Jr.; Vello A. Kuuskraa; David E. Riestenberg; Aiysha Sultana; Tyler Van Leeuwen

2009-06-01

This report serves as the final technical report and users manual for the 'Rigorous Screening Technology for Identifying Suitable CO2 Storage Sites II SBIR project. Advanced Resources International has developed a screening tool by which users can technically screen, assess the storage capacity and quantify the costs of CO2 storage in four types of CO2 storage reservoirs. These include CO2-enhanced oil recovery reservoirs, depleted oil and gas fields (non-enhanced oil recovery candidates), deep coal seems that are amenable to CO2-enhanced methane recovery, and saline reservoirs. The screening function assessed whether the reservoir could likely serve as a safe, long-term CO2 storage reservoir. The storage capacity assessment uses rigorous reservoir simulation models to determine the timing, ultimate storage capacity, and potential for enhanced hydrocarbon recovery. Finally, the economic assessment function determines both the field-level and pipeline (transportation) costs for CO2 sequestration in a given reservoir. The screening tool has been peer reviewed at an Electrical Power Research Institute (EPRI) technical meeting in March 2009. A number of useful observations and recommendations emerged from the Workshop on the costs of CO2 transport and storage that could be readily incorporated into a commercial version of the Screening Tool in a Phase III SBIR.

Transport and storage of spent nuclear fuel

International Nuclear Information System (INIS)

Lung, M.; Lenail, B.

1987-01-01

From a safety standpoint, spent fuel is clearly not ideal for permanent disposal and reprocessing is the best method of preparing wastes for long-term storage in a repository. Furthermore, the future may demonstrate that some fission products recovered in reprocessing have economic applications. Many countries have in fact reached the point at which the recycling of plutonium and uranium from spent fuel is economical in LWR's. Even in countries where this is not yet evident, (i.e., the United States), the French example shows that the day will come when spent fuel will be retrieved for reprocessing and recycle. It is highly questionable whether spent fuel will ever be considered and treated as waste in the same sense as fission products and processed as such, i.e., packaged in a waste form for permanent disposal. Even when recycled fuel material can no longer be reused in LWR's because of poor reactivity, it will be usable in FBR's. Based on the considerable experience gained by SGN and Cogema, this paper has provided practical discussion and illustrations of spent fuel transport and storage of a very important step in the nuclear fuel management process. The best of spent fuel storage depends on technical, economic and policy considerations. Each design has a role to play and we hope that the above discussion will help clarify certain issues

Development of Self-Remediating Packaging for Safe and Secure Transport of Infectious Substances.

Energy Technology Data Exchange (ETDEWEB)

Guilinger, Terry Rae; Gaudioso, Jennifer M; Aceto, Donato Gonzalo; Lowe, Kathleen M.; Tucker, Mark D; Salerno, Reynolds Mathewson; Souza, Caroline Ann

2006-11-01

As George W. Bush recognized in November 2001, "Infectious diseases make no distinctions among people and recognize no borders." By their very nature, infectious diseases of natural or intentional (bioterrorist) origins are capable of threatening regional health systems and economies. The best mechanism for minimizing the spread and impact of infectious disease is rapid disease detection and diagnosis. For rapid diagnosis to occur, infectious substances (IS) must be transported very quickly to appropriate laboratories, sometimes located across the world. Shipment of IS is problematic since many carriers, concerned about leaking packages, refuse to ship this material. The current packaging does not have any ability to neutralize or kill leaking IS. The technology described here was developed by Sandia National Laboratories to provide a fail-safe packaging system for shipment of IS that will increase the likelihood that critical material can be shipped to appropriate laboratories following a bioterrorism event or the outbreak of an infectious disease. This safe and secure packaging method contains a novel decontaminating material that will kill or neutralize any leaking infectious organisms; this feature will decrease the risk associated with shipping IS, making transport more efficient. 3 DRAFT4

Transport Mechanisms for CO2-CH4 Exchange and Safe CO2 Storage in Hydrate-Bearing Sandstone

Directory of Open Access Journals (Sweden)

Knut Arne Birkedal

2015-05-01

Full Text Available CO2 injection in hydrate-bearing sediments induces methane (CH4 production while benefitting from CO2 storage, as demonstrated in both core and field scale studies. CH4 hydrates have been formed repeatedly in partially water saturated Bentheim sandstones. Magnetic Resonance Imaging (MRI and CH4 consumption from pump logs have been used to verify final CH4 hydrate saturation. Gas Chromatography (GC in combination with a Mass Flow Meter was used to quantify CH4 recovery during CO2 injection. The overall aim has been to study the impact of CO2 in fractured and non-fractured samples to determine the performance of CO2-induced CH4 hydrate production. Previous efforts focused on diffusion-driven exchange from a fracture volume. This approach was limited by gas dilution, where free and produced CH4 reduced the CO2 concentration and subsequent driving force for both diffusion and exchange. This limitation was targeted by performing experiments where CO2 was injected continuously into the spacer volume to maintain a high driving force. To evaluate the effect of diffusion length multi-fractured core samples were used, which demonstrated that length was not the dominating effect on core scale. An additional set of experiments is presented on non-fractured samples, where diffusion-limited transportation was assisted by continuous CO2 injection and CH4 displacement. Loss of permeability was addressed through binary gas (N2/CO2 injection, which regained injectivity and sustained CO2-CH4 exchange.

Financial assistance to States and tribes to support emergency preparedness and response and the safe transportation of hazardous shipments

International Nuclear Information System (INIS)

Bradbury, J.A.; Jones, M.L.

1995-01-01

This report identifies and summarizes existing sources of financial assistance to States and Indian tribes in preparing and responding to transportation emergencies and ensuring the safe transportation of hazardous shipments through their jurisdictions. The report has been prepared as an information resource for the US Department of Energy's Office of Environmental Restoration and Waste Management, Office of Transportation, Emergency Management and Analytical Services. The report discusses funding programs administered by the following Federal agencies: Federal Emergency Management Agency; Department of Transportation; the Environmental Protection Agency; and the Department of Energy. Also included is a summary of fees assessed by some States on carriers of hazardous materials and hazardous waste. The discussion of programs is supplemented by an Appendix that provides a series of tables summarizing funding sources and amounts. The report includes several conclusions concerning the level of funding provided to Indian tribes, the relative ranking of funding sources and the variation among States in overall revenues for emergency response and safe transportation

Safe havens in Europe

DEFF Research Database (Denmark)

Paldam, Martin

2013-01-01

Eleven safe havens exist in Europe providing offshore banking and low taxes. Ten of these states are very small while Switzerland is moderately small. All 11 countries are richer than their large neighbors. It is shown that causality is from small to safe haven to wealth, and that theoretically...... equilibriums are likely to exist where a certain regulation is substantially lower in a small country than in its big neighbor. This generates a large capital inflow to the safe havens. The pool of funds that may reach the safe havens is shown to be huge. It is far in excess of the absorptive capacity...... of the safe havens, but it still explains, why they are rich. Microstates offer a veil of anonymity to funds passing through, and Switzerland offers safe storage of funds....

Assessment of the Electrical Power Requirements for Continued Safe Storage and Waste Feed Delivery Phase One

International Nuclear Information System (INIS)

MAY, T.H.

2000-01-01

This study evaluated the ability of the electrical distribution system to support safe storage as well as the first phase of the Waste Feed Delivery. Several recommendations are made to improve the electrical system. The ability to assure adequate Waste Feed Delivery (WFD) to the Privatization Contractor's vitrification facility is a key element in the overall Hanford cleanup schedule. An important aspect of this WFD is the availability of sufficient and appropriate electrical power in the single- and double-shell tank farms. The methodology for performing this review and the results are described

Recommendations on the proposed Monitored Retrievable Storage Facility

Energy Technology Data Exchange (ETDEWEB)

1985-10-01

Following the Department of Energy's announcement in April 1985 that three Tennessee sites were to be considered for the Monitored Retrievable Storage facility, Governor Lamar Alexander initiated a review of the proposal to be coordinated by his Safe Growth Team. Roane County and the City of Oak Ridge, the local governments sharing jurisdiction over DOE's primary and secondary sites, were invited to participate in the state's review of the MRS proposal. Many issues related to the proposed MRS are being considered by the Governor's Safe Growth Team. The primary objective of the Clinch River MRS Task Force has been to determine whether the proposed Monitored Retrievable Storage facility should be accepted by the local governments, and if so, under what conditions. The Clinch River MRS Task Force is organized into an Executive Committee cochaired by the Roane County Executive and Mayor of Oak Ridge and three Study Groups focusing on environmental (including health and safety), socioeconomic, and transportation issues.

Recommendations on the proposed Monitored Retrievable Storage Facility

Energy Technology Data Exchange (ETDEWEB)

1985-10-01

Following the Department of Energy`s announcement in April 1985 that three Tennessee sites were to be considered for the Monitored Retrievable Storage facility, Governor Lamar Alexander initiated a review of the proposal to be coordinated by his Safe Growth Team. Roane County and the City of Oak Ridge, the local governments sharing jurisdiction over DOE`s primary and secondary sites, were invited to participate in the state`s review of the MRS proposal. Many issues related to the proposed MRS are being considered by the Governor`s Safe Growth Team. The primary objective of the Clinch River MRS Task Force has been to determine whether the proposed Monitored Retrievable Storage facility should be accepted by the local governments, and if so, under what conditions. The Clinch River MRS Task Force is organized into an Executive Committee cochaired by the Roane County Executive and Mayor of Oak Ridge and three Study Groups focusing on environmental (including health and safety), socioeconomic, and transportation issues.

Thermally responsive polymer electrolytes for inherently safe electrochemical energy storage

Science.gov (United States)

Kelly, Jesse C.

-off" ratio in electrochemical activity at elevated temperatures. Overall, solution pH and conductivity were altered by an order of magnitude and device performance (ability to store charge) decreased by over 70%. After demonstration of a model responsive electrolyte in an aqueous system, ionic liquid (IL) based electrolytes were developed as a means of controlling the electrochemical performance in the non-aqueous environments that batteries, specifically Li-ion, require. Here, two systems were developed: (1) an electrolyte comprising poly(ethylene oxide) (PEO), the IL, [EMIM][BF4], and a lithium salt and (2) an electrolyte comprising poly(benzyl methacrylate) (PBzMA), the IL, [EMIM][TFSI], and a lithium salt. In each system, the polymer-IL phase separation inhibited device operation at elevated temperatures. For the PEO/IL electrolyte, the thermally induced liquid-liquid phase separation was shown to decrease the ionic conductivity, thereby affecting the concentration of ions at the electrode. Additionally, an increasing charge transfer resistance associated with the phase separated polymer coating the porous electrode was shown to limit electrochemical activity significantly. For the PBzMA/IL electrolyte, the solid-liquid phase separation did not show a change in conductivity, but did cause a drastic increase in charge transfer resistance, effectively shutting off Li-ion battery operation at high temperatures. Such responsive mixtures provide a transformative approach to regulating electrochemical processes, which is necessary to achieve inherently safe operation in large format energy storage with EDLCs, supercapacitors and Li-ion batteries.

Performance of CASTOR{sup R} HAW Cask Cold Trials for Loading, Transport and Storage of HAW canisters

Energy Technology Data Exchange (ETDEWEB)

Wilmsmeier, Marco; Vossnacke, Andre [GNS Gesellschaft fuer Nuklear-Service mbH, Hollestrasse 7A, D-45127 Essen (Germany)

2008-07-01

On the basis of reprocessing contracts, concluded between the German Nuclear Utilities (GNUs) and the reprocessing companies in France (AREVA NC) and the UK (Nuclear Decommissioning Authority), GNS has the task to return the resulting residues to Germany. The high active waste (HAW) residuals from nuclear fuel reprocessing are vitrified and filled into steel cans, the HAW canisters. According to reprocessing contracts the equivalent number of HAW canisters to heavy metals delivered has to be returned to the country of origin and stored at an interim storage facility where applicable. The GNS' CASTOR{sup R} HAW casks are designed and licensed to fulfil the requirements for transport and long-term storage of HAW canisters. The new cask type CASTOR{sup R} HAW28M is capable of storing 28 HAW canisters with a maximum thermal power of 56 kW in total. Prior to the first active cask loading at a reprocessing facility it is required to demonstrate all important handling steps with the CASTOR{sup R} HAW28M cask according to a specific and approved sequence plan (MAP). These cold trials have to be carried out at the cask loading plant and at the reception area of an interim storage facility in Gorleben (TBL-G), witnessed by the licensing authorities and their independent experts. At transhipment stations GNS performs internal trials to demonstrate safe handling. A brand-new, empty CASTOR{sup R} HAW28M cask has been shipped from the GNS cask assembly facility in Muelheim to the TBL-G for cold trials. With this cask, GNS has to demonstrate the transhipment of casks at the Dannenberg transfer station from rail to road, transport to and reception at the TBL-G as well as incoming dose rate and contamination measurements and preparation for storage. After removal of all shock absorbers with a cask specific handling frame, tilting operation and assembly of the secondary lid with a pressure sensor, the helium leak tightness and 'Block-mass' tests have to be carried out

The transports of nuclear fuel cycle: An essential activity, safely managed

International Nuclear Information System (INIS)

Lenail, B.; Savornin, B.; Curtis, H.W.

1989-01-01

Transports associated with the nuclear fuel cycle normally use public means of transport by rail, road, sea and air and it might therefore be expected that they would be the Achilles heel of the cycle from a safety point of view. In fact, despite a few minor accidents, no radioactive releases resulting in a significant exposure of the public or the environment have occurred. On the other hand, during the last quarter, the news media have reported major spillages of crude oil and chemicals of high toxicity which have jeopardized the environment, the explosion of gas tankers with dozens of fatalities, and even the sinking of a nuclear submarine. All reports show that the radiation exposure to the public resulting from transports is negligible, i.e., far below 1% of that due to the whole nuclear industry. Similarly, the radiation exposure of transport workers has been lower than anticipated over several decades. The demonstrations and attacks by opponents of the nuclear industry against transports have been limited and have been used as an attempt to freeze the activity of different plants or disposal sites, and to focus public attention on the nuclear issue, rather than to question the fuel cycle transports themselves or the safety principles ruling them. When looking for explanations of such a favorable situation, which they should endeavour to perpetuate, without being surprised if any incident occurs, one finds two major reasons: First, the awareness by the fuel cycle operators, of the vital importance of a safe and reliable implementation of the necessary transports. Secondly, the results of assessments of safety conducted by international organizations and most countries, which have resulted in detailed international recommendations, as well as uniform national and modal regulations, thus establishing the necessary link between the basic rules for radioprotection and the needs of the Transport Industry

Royal Decree 1749/1984 of 1 August approving the national regulations on the safe transport of dangerous goods by air together with technical instructions for the safe transport of dangerous goods by air

International Nuclear Information System (INIS)

1984-01-01

This Royal Decree approves the national Regulations on the safe transport of dangerous goods by air. The Regulations as well as the attached detailed technical instructions are based on the 1981 revised text of the Annex concerning dangerous goods of the Chicago Convention on International Civil Aviation. It also covers radioactive materials. (NEA) [fr

A multi-purpose unit concept to integrate storage, transportation, and the engineered barrier system

International Nuclear Information System (INIS)

Hollaway, W.R.; Rozier, R.; Nitti, D.A.; Williams, J.R.

1993-01-01

The Multi-Purpose Unit (MPU) is a new concept for standardizing and integrating the waste management functions of spent fuel storage, transportation, and geologic disposal. The MPU concept would use one unit, composed of a relatively thick-walled inner canister with a multi-purpose overpack, to meet the requirements for storage in 10 CFR 72, transportation in 10 CFR 71, and the engineered barrier system in 10 CFR 60. The MPU concept differs from the recently proposed Multi-Purpose Canister (MPC) concept in that the MPU concept uses a single multi-purpose overpack for storage, transportation, and geologic disposal, while the MPC concept uses separate and unique overpacks for each of these system functions. A design concept for the MPU is presented along with an estimate of unit costs. An initial evaluation of overall system cost showed that the MPU concept could be economically competitive with the current reference system. The MPU concept provides the potential for significant reduction, simplification, and standardization of Civilian Radioactive Waste Management (CRWMS) facilities and operations, including those at the utilities, during waste acceptance and transportation, and at the Monitored Retrievable Storage (MRS) facility and the repository. The primary issues for the MPU concept relate to uncertainties with respect to licensing, and the programmatic risks associated with implementing the MPU concept before the repository design is finalized. The strong potential exhibited by the MPU concept demonstrates that this option merits additional development and should be considered in the next phase of work on multi-purpose concepts for the CRWMS

Assembly for transport and storage of radioactive nuclear fuel elements

International Nuclear Information System (INIS)

Myers, G.

1978-01-01

The invention concerns the self-control of coolant deficiencies on the transport of spent fuel elements from nuclear reactors. It guarantees that drying out of the fuel elements is prevented in case of a change of volume of the fluid contained in storage tanks and accumulators and serving as coolant and shielding medium. (TK) [de

Transportation over long distance and thermal energy storage, coupling with energetic valuation processes from waste. State of art. Extended abstract

International Nuclear Information System (INIS)

Megret, O.; Bequet, L.; Manificat, A.; Weber, C.

2011-12-01

This study aims, on one hand, to realize a state of art about over long distance transport and heat energy storage and, on the other hand, to examine their coupling with waste valuation systems. After reminding the adequate context of development with those solutions and too showing the importance of the stake linked to the current work, we first expose the introductive elements in terms of storage and heat energy transport. The second chapter deals with the description of some materials, equipment and systems concerning heat storage energy. Afterward, the over long distance heat transport systems are detailed in the third chapter. In the fourth chapter, it is about waste valuation techniques and heat energy potentials users. The fifth chapter sums up the different techniques of storage and heat transport that are applicable to waste field according to the appropriate sector. Finally, the sixth chapter goes about 3 case-works in 3 fields: housing/commercial, industrial laundry and high temperature industry (steel industry). The purpose is to determine the implementation feasibility of the different techniques of storage and waste heat transport. (authors)

Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington

Energy Technology Data Exchange (ETDEWEB)

1994-07-01

This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ``Safety Measures for Waste Tanks at Hanford Nuclear Reservation,`` of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues.

Safe interim storage of Hanford tank wastes, draft environmental impact statement, Hanford Site, Richland, Washington

International Nuclear Information System (INIS)

1994-07-01

This Draft EIS is prepared pursuant to the National Environmental Policy Act (NEPA) and the Washington State Environmental Policy Act (SEPA). DOE and Ecology have identified the need to resolve near-term tank safety issues associated with Watchlist tanks as identified pursuant to Public Law (P.L.) 101-510, Section 3137, ''Safety Measures for Waste Tanks at Hanford Nuclear Reservation,'' of the National Defense Authorization Act for Fiscal Year 1991, while continuing to provide safe storage for other Hanford wastes. This would be an interim action pending other actions that could be taken to convert waste to a more stable form based on decisions resulting from the Tank Waste Remediation System (TWRS) EIS. The purpose for this action is to resolve safety issues concerning the generation of unacceptable levels of hydrogen in two Watchlist tanks, 101-SY and 103-SY. Retrieving waste in dilute form from Tanks 101-SY and 103-SY, hydrogen-generating Watchlist double shell tanks (DSTs) in the 200 West Area, and storage in new tanks is the preferred alternative for resolution of the hydrogen safety issues

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

International Nuclear Information System (INIS)

1976-05-01

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

Fiscal 1975 Sunshine Project research report. Research on refining, transport and storage systems for hydrogen, and their safety technologies (Research on measurement/control system for safety management in low-temperature storage and refining processes of hydrogen); 1975 nendo suiso no seisei, yuso, chozo system oyobi hoan gijutsu ni kansuru kenkyu seika hokokusho. Suiso no teion chozo, seisei dankai no anzen no tame no keisoku seigyo system ni kansuru kenkyu chosa

Energy Technology Data Exchange (ETDEWEB)

NONE

1976-05-28

The following were selected as themes necessary and important for the safety of the forthcoming hydrogen energy system, based on the fiscal 1974 document survey result, and the fiscal 1975 research results. First as for low- temperature storage of hydrogen, since safe discharge of hydrogen gas generated in a storage tank is important, gas motor discharging usually used for such transport tanks as tank lorry, and burn bond discharging suitable for discharge of a large amount of hydrogen were selected as test items. Next as for storage and transport of low-temperature hydrogen such as liquid hydrogen, a low-temperature control valve to control the amount of liquid hydrogen for transport was selected as a test item. Under the assumption of the model tests on the above 3 items in fiscal 1976, various studies and trial designs were made on concrete test equipment. The test plans were also prepared for some ones among them. (NEDO)

Essentials of energy technology sources, transport, storage, conservation

CERN Document Server

Fricke, Jochen

2013-01-01

An in-depth understanding of energy technology, sources, conversion, storage, transport and conservation is crucial for developing a sustainable and economically viable energy infrastructure. This need, for example, is addressed in university courses with a special focus on the energy mix of renewable and depletable energy resources. Energy makes our lives comfortable, and the existence of amenities such as heaters, cars, warm water, household appliances and electrical light is characteristic for a developed economy. Supplying the industrial or individual energy consumer with energy 24 hours

Awareness of the need for safe storage of Methadone at home is not improved by the use of protocols on recording information giving

Directory of Open Access Journals (Sweden)

Crome Ilana B

2008-04-01

Full Text Available Abstract Background Methadone is a synthetic, narcotic analgesic used in the treatment of drug misuse. Tragedies involving children being poisoned by the accidental ingestion of methadone are no longer a rare occurrence. Following an audit of the effectiveness of the provision and recall of information to patients attending an NHS Methadone Clinic a protocol was introduced to ensure that staff documented the provision of such information and patients gave a written confirmation that they had received the information. Methods The study was undertaken in the setting of an NHS methadone clinic with the aim of re- auditing the storage of methadone at home following the introduction of the new protocols. 174 patients completed an anonymous questionnaire regarding where they store methadone at home and whether they recall being given advice about safe storage. Community pharmacists were contacted by telephone to assess the level of advice given to methadone patients regarding safety. Results Only 49 (28.2% patients recalled being given advice about safe storage, 24 (13.8% recalled that information was provided by clinic staff. 170 (97.7% patients regard methadone as being dangerous. (28.2%. Methadone is most commonly stored in a cupboard (37.9%. All methadone is dispensed in a bottle with a child resistant cap on it. All patients reported they stored their methadone in the original bottle provided by the pharmacist. Conclusion Recall of information on safety issues is very poor. Provision of written as well as verbal information is needed. The use of printed safety information cards which patients can take away for future reference may be of use. It is the responsibility of health professionals to ensure they provide information and advice to methadone users on the safe storage of their methadone at home.

Solute transport and storage mechanisms in wetlands of the Everglades, south Florida

Science.gov (United States)

Harvey, Judson W.; Saiers, James E.; Newlin, Jessica T.

2005-01-01

Solute transport and storage processes in wetlands play an important role in biogeochemical cycling and in wetland water quality functions. In the wetlands of the Everglades, there are few data or guidelines to characterize transport through the heterogeneous flow environment. Our goal was to conduct a tracer study to help quantify solute exchange between the relatively fast flowing water in the open part of the water column and much more slowly moving water in thick floating vegetation and in the pore water of the underlying peat. We performed a tracer experiment that consisted of a constant‐rate injection of a sodium bromide (NaBr) solution for 22 hours into a 3 m wide, open‐ended flume channel in Everglades National Park. Arrival of the bromide tracer was monitored at an array of surface water and subsurface samplers for 48 hours at a distance of 6.8 m downstream of the injection. A one‐dimensional transport model was used in combination with an optimization code to identify the values of transport parameters that best explained the tracer observations. Parameters included dimensions and mass transfer coefficients describing exchange with both short (hours) and longer (tens of hours) storage zones as well as the average rates of advection and longitudinal dispersion in the open part of the water column (referred to as the “main flow zone”). Comparison with a more detailed set of tracer measurements tested how well the model's storage zones approximated the average characteristics of tracer movement into and out of the layer of thick floating vegetation and the pore water in the underlying peat. The rate at which the relatively fast moving water in the open water column was exchanged with slowly moving water in the layer of floating vegetation and in sediment pore water amounted to 50 and 3% h−1, respectively. Storage processes decreased the depth‐averaged velocity of surface water by 50% relative to the water velocity in the open part of the water

Report of consultants to the IAEA on requirements for the safe transport of low hazard radioactive materials

International Nuclear Information System (INIS)

Collin, W.; Grenier, M.; Hopkins, D.

1982-01-01

In the present paper changes are recommmended to certain definitions given in the 2nd draft revision of the IAEA 'regulations for the safe transport of radioactive materials (safety series no. 6)'. (orig./RW)

Transport container storage. Pt. 2

International Nuclear Information System (INIS)

Guenther, B.; Kuehn, H.D.; Schulz, E.

1987-01-01

In connection with mandatory licensing procedures and in the framework of quality control for serially produced containers from spheroidal graphite cast iron of quality grade GGG 40, destined to be used in the transport and storage of radioactive materials, each prototype and each production sample of a design is subjected to comprehensive destructive and non-destructive material tests. The data obtained are needed on the one hand to check whether specified, representative material characteristics are observed; on the other hand they are systematically evaluated to update knowledge and technical standards. The Federal Institute of Materials Research and Testing (BAM) has so far examined 528 individual containers (513 production samples and 15 prototypes) of wall thicknesses from 80 millimetres to 500 millimetres in this connection. It has turned out that the measures for quality assurance and quality control as substantiated by a concept of expertise definitely confirm the validity of component test results for production samples. (orig.) [de

Silica desiccant packets for storage and transport of Streptococcus pneumoniae and other clinically relevant species.

Directory of Open Access Journals (Sweden)

Casey L Pell

Full Text Available Bacterial isolates are often transported between laboratories for research and diagnostic purposes. Silica desiccant packets (SDPs, which are inexpensive and do not require freezing, were evaluated for storage and recovery of bacterial isolates. Conditions such as inoculum size, swab type and temperature of storage were investigated using ten Streptococcus pneumoniae isolates. The optimized protocol was then tested using 49 additional S. pneumoniae isolates representing 40 serogroups. Overall, S. pneumoniae growth was considered satisfactory (>100 colony forming units for 98/109 (89.9% and 20/20 (100% swabs after 14 days at room temperature or 28 days at 4° C, respectively. Storage in SDPs did not impact on the ability of S. pneumoniae isolates to be subsequently serotyped. When the survival of nine other clinically relevant bacterial species was tested, seven were viable after 28 days at room temperature, the exceptions being Neisseria gonorrhoeae and Haemophilus influenzae. SDPs are suitable for transport and short-term storage of bacterial species including S. pneumoniae.

Microencapsulated Phase-Change Materials For Storage Of Heat

Science.gov (United States)

Colvin, David P.

1989-01-01

Report describes research on engineering issues related to storage and transport of heat in slurries containing phase-change materials in microscopic capsules. Specific goal of project to develop lightweight, compact, heat-management systems used safely in inhabited areas of spacecraft. Further development of obvious potential of technology expected to lead to commercialization and use in aircraft, electronic equipment, machinery, industrial processes, and other sytems in which requirements for management of heat compete with severe restrictions on weight or volume.

Operation and maintenance of spent fuel storage and transportation casks/containers

International Nuclear Information System (INIS)

2007-01-01

Member States have a growing need for casks for spent fuel storage and transportation. A variety of casks has been developed and is in use at an increasing number of sites. This has resulted in an accumulation of experience that will provide valuable information for other projects in spent fuel management. This publication provides a comprehensive review of information on the cask operation and maintenance associated with spent fuel storage. It draws upon generic knowledge from industrial experience and applications and is intended to serve as a basis for better planning and implementation in future projects

Towards Safe Food Free From Pesticides Residues: Biochemical Changes of Selected Vitamins, Trace Elements and Genotoxicity of Irradiated Dates During Storage

International Nuclear Information System (INIS)

Farag, S.E.A.; Elsawy, KH.M.; Elgammal, M.H.; Hammoud, G.M.; Youssef, M.S.H.

2012-01-01

Decreasing quality of semi-dry dates due to infestation during storage is recorded by many researchers. Low gamma irradiation doses could be considered safe alternative of human toxic chemicals and pesticides. In the present study, semi-dry dates irradiated with different doses of 1, 3, 5 kGy beside non-irradiated samples were stored at 20 degree C and at -18 degree C for nine months. Vitamins E, A and trace elements were determined to check the genotoxicity effect of irradiation at high doses (1, 3, 5, 20 and 30 kGy). Results of high pressure liquid chromatography (HPLC) proved that semi-dry dates contain vitamins A (β-carotene) and E (α-tocopherol) in amounts of 98.78 μg/100 g and 1.818 mg/100 g, respectively, in raw non-irradiated fruits. Degradation of vitamins either naturally during storage or by irradiation was manifested. However, the lowest losses of vitamins were detected at low doses of irradiation (1-3 kGy). Also, trace elements and metals were determined by inductively coupled plasma (ICP) technique. Six trace elements; selenium (Se), zinc (Zn), cupper (Cu), cobalt (Co), chromium (Cr) and nickel (Ni), which are responsible for immunity system were detected in dates with considerable concentrations. Two contaminants heavy metals, lead (Pb) and cadmium (Cd), were detected. All the trace elements were in safe levels and have negligible changes under stress of irradiation and during long storage conditions. The genotoxicity test proved that the increased toxicity of irradiated dates was dose dependant, therefore, the irradiated samples at 1 kGy were safe (near control samples). Consequently, the irradiation at 1 kGy was preferable to be used as an alternative of pesticides in spite of some losses in some bioactive content.

Contribution to fissile materials transportation in transit storage

International Nuclear Information System (INIS)

Silva, Teresinha de Moraes da

2005-01-01

The national and international standards for the transportation of fissile materials establish two indexes: Transport Index (Tl) and Criticality Safety Index (ISC). Besides, in non-exclusive transit, the largest of these indexes cannot overtake the value 50. Considering several groups to be transported, the sum of the transportation indexes cannot overtake 200 and the distance between them should be 6 meters This work aimed, as a primary target, to verify when an index is superior to another, in relation to the fissile materials studied, i.e., uranium oxides UO 2 , U 3 O 8 and uranium silicide U 3 Si 2 , taking into account the different enrichment grades. The result found is that the criticality safety index is always greater. As a second goal, it was tried to verify if there is any alteration in the case of these compounds aging process, i.e., alteration in transport index (Tl) due to gamma radiation of daughters radioisotopes in secular equilibrium. No alteration, was verified as the daughters contribution although considerable related to the transport index is very small concerning the criticality safety index. As a third target, it was tried to justify a distance equal to 6 meters, between each group of fissile material. The result showed that, in air media, the distance of 1 meter is sufficient, except for the UO 2 compound at 100% of enrichment, which reaches 2 meter while in the water means the distance of 40cm is enough for the compounds studied. This fact is of great importance when the cost of the necessary area in the transportation and storage is taken into consideration. (author)

European Model Code of safe practice in the storage and handling of petroleum products. Part I. Operations

Energy Technology Data Exchange (ETDEWEB)

1973-01-01

This safe practice code was prepared by a working group consisting of experts from 10 Western European countries. It consists of short guidelines and technical advice on general precautions, injuries and medical services, permits to work, fire prevention and fighting, jetties, pipework, storage tanks, static electricity, electrical equipment, road vehicles, tank cars, handling of bitumen products, liquefied petroleum gases, packed products and training of personnel. The code is supplemented by 10 appendices, including a suggested syllabus for a 2-day course on fire prevention and emergency action for managers of oil installations.

Effects of Transport and Storage Conditions on Gene Expression in Blood Samples.

Science.gov (United States)

Malentacchi, Francesca; Pizzamiglio, Sara; Wyrich, Ralf; Verderio, Paolo; Ciniselli, Chiara; Pazzagli, Mario; Gelmini, Stefania

2016-04-01

Inappropriate handling of blood samples might induce or repress gene expression and/or lead to RNA degradation affecting downstream analysis. In particular, sample transport is a critical step for biobanking or multicenter studies because of uncontrolled variables (i.e., unstable temperature). We report the results of a pilot study implemented within the EC funded SPIDIA project, aimed to investigate the role of transport and storage of blood samples containing and not containing an RNA stabilizer. Blood was collected from a single donor both in EDTA and in PAXgene Blood RNA tubes. Half of the samples were sent to a second laboratory both at room temperature and at 4°C, whereas the remaining samples were stored at room temperature and at 4°C. Gene expression of selected genes (c-FOS, IL-1β, IL-8, and GAPDH) known to be induced or repressed by ex vivo blood handling and of blood-mRNA quality biomarkers identified and validated within the SPIDIA project, which allow for monitoring changes in unstabilized blood samples after collection and during transport and storage, were analyzed by RT-qPCR. If the shipment of blood in tubes not containing RNA stabilizer is not performed under a stable condition, gene profile studies can be affected by the effects of transport. Moreover, also controlled temperature shipment (4°C) can influence the expression of specific genes if blood is collected in tubes not containing a stabilizer. The use of dedicated biomarkers or time course experiments should be performed in order to verify potential bias on gene expression analysis due to sample shipment and storage conditions. Alternatively, the use of RNA stabilizer containing tubes can represent a reliable option to avoid ex vivo RNA changes.

Certifying the TN-BRP and TN-REG transportable storage demonstration casks

International Nuclear Information System (INIS)

Abbott, D.G.; Nolan, D.J.; Yoshimura, H.R.

1991-01-01

The US DOE has obtained US NRC certification to transport two transportable storage casks for a demonstration project. Because the casks had been built before the decision was made to obtain NRC certification, only limited modifications could be made to the casks. NRC's review resulted in several technical concerns that were subsequently resolved by design modifications, testing, and further analysis. Certification activities included qualifying the ferritic steel body material, modifying the borated stainless steel basket design, and extensive impact limiter testing. Recommendations for certifying future casks are presented based on experience with these casks

Maximum overpressure in gastight containers of the storage and transport of dangerous liquids

International Nuclear Information System (INIS)

Steen, H.

1977-11-01

For a design of containers suitable under safety aspects for the transport and storage of dangerous liquids the maximum overpressure to be expected is an important value. The fundamentals for the determination of the internal pressure are pointed out for the simplified model of a rigid (i.e. not elastically or plastically deforming) and gastight container. By assuming of extreme storage and transport conditions (e.g. for the maximum liquid temperatures due to sun radiation) the figures of the maximum overpressure are calculated for about hundred liquids being of practical interest. The results show a significant influence of the compression of air in the ullage space caused by liquid expansion due to temperature rise (compression effect), particularly for liquids with a higher boiling point. The influence of the solubility of air in the liquid on the internal pressure can be neglected under the assumed transport conditions. The estimation of the volume increase of the container due to the effect of the internal pressure leads to the limitation, that the assumption of a rigid container is only justified for cylindrical and spherical steel tanks. The enlargement of the container volume due to a heating of the container shell does play no significant roll for all metal containers under the assumed conditions of storage and transport. The results obtained bear out essentially the stipulations for the test pressure and the filling limits laid down in the older German regulations for the transport of dangerous liquids in rail tank waggons and road tank vehicles without pressure relief valves. For the recently fixed and internationally harmonized regulations for tankcontainers the considerations and the results pointed out in this paper give rise to a review. (orig.) [de

Advanced surveillance technologies for used fuel long-term storage and transportation - 59032

International Nuclear Information System (INIS)

Tsai, Hanchung; Liu, Yung Y.; Nutt, Mark; Shuler, James

2012-01-01

Utilities worldwide are using dry-cask storage systems to handle the ever-increasing number of discharged fuel assemblies from nuclear power plants. In the United States and possibly elsewhere, this trend will continue until an acceptable disposal path is established. The recent Fukushima nuclear power plant accident, specifically the events with the storage pools, may accelerate the drive to relocate more of the used fuel assemblies from pools into dry casks. Many of the newer cask systems incorporate dual-purpose (storage and transport) or multiple-purpose (storage, transport, and disposal) canister technologies. With the prospect looming for very long term storage - possibly over multiple decades - and deferred transport, condition- and performance-based aging management of cask structures and components is now a necessity that requires immediate attention. From the standpoint of consequences, one of the greatest concerns is the rupture of a substantial number of fuel rods that would affect fuel retrievability. Used fuel cladding may become susceptible to rupture due to radial-hydride-induced embrittlement caused by water-side corrosion during the reactor operation and subsequent drying/transfer process, through early stage of storage in a dry cask, especially for high burnup fuels. Radio frequency identification (RFID) is an automated data capture and remote-sensing technology ideally suited for monitoring sensitive assets on a long-term, continuous basis. One such system, called ARG-US, has been developed by Argonne National Laboratory for the U.S. Department of Energy's Packaging Certification Program for tracking and monitoring drums containing sensitive nuclear and radioactive materials. The ARG-US RFID system is versatile and can be readily adapted for dry-cask monitoring applications. The current built-in sensor suite consists of seal, temperature, humidity, shock, and radiation sensors. With the universal asynchronous receiver/transmitter interface in

Code of practice for the control and safe handling of radioactive sources used for therapeutic purposes (1988)

International Nuclear Information System (INIS)

1988-01-01

This Code is intended as a guide to safe practices in the use of sealed and unsealed radioactive sources and in the management of patients being treated with them. It covers the procedures for the handling, preparation and use of radioactive sources, precautions to be taken for patients undergoing treatment, storage and transport of radioactive sources within a hospital or clinic, and routine testing of sealed sources [fr

Iron transport and storage in the coccolithophore: Emiliania huxleyi.

Science.gov (United States)

Hartnett, Andrej; Böttger, Lars H; Matzanke, Berthold F; Carrano, Carl J

2012-11-01

Iron is an essential element for all living organisms due to its ubiquitous role in redox and other enzymes, especially in the context of respiration and photosynthesis. The iron uptake and storage systems of terrestrial/higher plants are now reasonably well understood with two basic strategies for iron uptake being distinguished: strategy I plants use a mechanism involving soil acidification and induction of Fe(III)-chelate reductase (ferrireductase) and Fe(II) transporter proteins while strategy II plants have evolved sophisticated systems based on high-affinity, iron specific, binding compounds called phytosiderophores. In contrast, there is little knowledge about the corresponding systems in marine plant-like lineages. Herein we report a study of the iron uptake and storage mechanisms in the coccolithophore Emiliania huxleyi. Short term radio-iron uptake studies indicate that iron is taken up by Emiliania in a time and concentration dependent manner consistent with an active transport process. Based on inhibitor studies it appears that iron is taken up directly as Fe(iii). However if a reductive step is involved the Fe(II) must not be accessible to the external environment. Upon long term exposure to (57)Fe we have been able, using a combination of Mössbauer and XAS spectroscopies, to identify a single metabolite which displays spectral features similar to the phosphorus-rich mineral core of bacterial and plant ferritins.

Reserpine-induced reduction in norepinephrine transporter function requires catecholamine storage vesicles.

Science.gov (United States)

Mandela, Prashant; Chandley, Michelle; Xu, Yao-Yu; Zhu, Meng-Yang; Ordway, Gregory A

2010-01-01

Treatment of rats with reserpine, an inhibitor of the vesicular monoamine transporter (VMAT), depletes norepinephrine (NE) and regulates NE transporter (NET) expression. The present study examined the molecular mechanisms involved in regulation of the NET by reserpine using cultured cells. Exposure of rat PC12 cells to reserpine for a period as short as 5min decreased [(3)H]NE uptake capacity, an effect characterized by a robust decrease in the V(max) of the transport of [(3)H]NE. As expected, reserpine did not displace the binding of [(3)H]nisoxetine from the NET in membrane homogenates. The potency of reserpine for reducing [(3)H]NE uptake was dramatically lower in SK-N-SH cells that have reduced storage capacity for catecholamines. Reserpine had no effect on [(3)H]NE uptake in HEK-293 cells transfected with the rat NET (293-hNET), cells that lack catecholamine storage vesicles. NET regulation by reserpine was independent of trafficking of the NET from the cell surface. Pre-exposure of cells to inhibitors of several intracellular signaling cascades known to regulate the NET, including Ca(2+)/Ca(2+)-calmodulin dependent kinase and protein kinases A, C and G, did not affect the ability of reserpine to reduce [(3)H]NE uptake. Treatment of PC12 cells with the catecholamine depleting agent, alpha-methyl-p-tyrosine, increased [(3)H]NE uptake and eliminated the inhibitory effects of reserpine on [(3)H]NE uptake. Reserpine non-competitively inhibits NET activity through a Ca(2+)-independent process that requires catecholamine storage vesicles, revealing a novel pharmacological method to modify NET function. Further characterization of the molecular nature of reserpine's action could lead to the development of alternative therapeutic strategies for treating disorders known to be benefitted by treatment with traditional competitive NET inhibitors. Copyright 2010 Elsevier Ltd. All rights reserved.

A Historical Review of the Safe Transport of Spent Nuclear Fuel, Rev. 1

Energy Technology Data Exchange (ETDEWEB)

Connolly, Kevin J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Pope, Ronald [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-09-01

This report is a revision to M3 milestone M3FT-16OR090402028 for the former Nuclear Fuels Storage and Transportation Planning Project (NFST), “Safety Record of SNF Shipments.” The US Department of Energy (DOE) has since established the Office of Integrated Waste Management (IWM), which builds on the work begun by NFST, to develop an integrated waste management system for spent nuclear fuel (SNF), including the developm

Financial assistance to states and tribes to support emergency preparedness and response and the safe transportation of hazardous shipments: 1996 Update

Energy Technology Data Exchange (ETDEWEB)

Bradbury, J.A.; Leyson, J.; Lester, M.K.

1996-07-01

This report revises and updates the 1995 report Financial Assistance to States and Tribes to Support Emergency Preparedness and Response and the Safe Transportation of Hazardous Shipments, PNL-10260 (UC-620). The presentation of data and some of the data reported have been changed; these data supersede those presented in the earlier publication. All data have been updated to fiscal year 1995, with the exception of FEMA data that are updated to fiscal year 1994 only. The report identifies and summarizes existing sources of financial assistance to States and Tribes in preparing and responding to transportation emergencies and ensuring the safe transportation of hazardous shipments through their jurisdictions. It is intended for use as an information resource for the U.S. Department of Energy`s Office of Environmental Management (EM), Office of Transportation, Emergency Management, and Analytical Services (EM-76).

Financial assistance to states and tribes to support emergency preparedness and response and the safe transportation of hazardous shipments: 1996 Update

International Nuclear Information System (INIS)

Bradbury, J.A.; Leyson, J.; Lester, M.K.

1996-07-01

This report revises and updates the 1995 report Financial Assistance to States and Tribes to Support Emergency Preparedness and Response and the Safe Transportation of Hazardous Shipments, PNL-10260 (UC-620). The presentation of data and some of the data reported have been changed; these data supersede those presented in the earlier publication. All data have been updated to fiscal year 1995, with the exception of FEMA data that are updated to fiscal year 1994 only. The report identifies and summarizes existing sources of financial assistance to States and Tribes in preparing and responding to transportation emergencies and ensuring the safe transportation of hazardous shipments through their jurisdictions. It is intended for use as an information resource for the U.S. Department of Energy's Office of Environmental Management (EM), Office of Transportation, Emergency Management, and Analytical Services (EM-76)

Performance of Four Transport and Storage Systems for Molecular Detection of Multidrug-Resistant Tuberculosis

Science.gov (United States)

Rabodoarivelo, Marie Sylvianne; Imperiale, Bélen; andrianiavomikotroka, Rina; Brandao, Angela; Kumar, Parveen; Singh, Sarman; Ferrazoli, Lucilaine; Morcillo, Nora; Rasolofo, Voahangy; Palomino, Juan Carlos; Vandamme, Peter; Martin, Anandi

2015-01-01

Background Detection of drug-resistant tuberculosis is essential for the control of the disease but it is often hampered by the limitation of transport and storage of samples from remote locations to the reference laboratory. We performed a retrospective field study to evaluate the performance of four supports enabling the transport and storage of samples to be used for molecular detection of drug resistance using the GenoType MTBDRplus. Methods Two hundred Mycobacterium tuberculosis strains were selected and spotted on slides, FTA cards, GenoCards, and in ethanol. GenoType MTBDRplus was subsequently performed with the DNA extracted from these supports. Sensitivity and specificity were calculated and compared to the results obtained by drug susceptibility testing. Results For all supports, the overall sensitivity and specificity for detection of resistance to RIF was between 95% and 100%, and for INH between 95% and 98%. Conclusion The four transport and storage supports showed a good sensitivity and specificity for the detection of resistance to RIF and INH in M. tuberculosis strains using the GenoType MTBDRplus. These supports can be maintained at room temperature and could represent an important alternative cost-effective method useful for rapid molecular detection of drug-resistant TB in low-resource settings. PMID:26431352

Office of Storage and Transportation Systems quality assurance directive

International Nuclear Information System (INIS)

1986-10-01

This Directive provides policy guidance, defines organizational authorities and responsibilities for quality assurance (QA) and establishes minimum acceptable requirements for assuring the quality of all programs under the overall direction of the OSTS. This directive provides guidance for preparation of subordinate QA documents (e.g., QA plans, procedures) for the major Office of Storage and Transportation Systems programs that support DOE licensing and/or certification objectives. In turn, those highly specific QA documents will amplify the general guidance presented in this Directive

CASTOR{sup R} 1000/19: Development and Design of a New Transport and Storage Cask

Energy Technology Data Exchange (ETDEWEB)

Funke, Th.; Henig, Ch. [GNS mbH, Hollestrasse 7A, 45127 Essen (Germany)

2008-07-01

The design of the new transport and storage cask type CASTOR{sup R} 1000/19 is presented in this paper. This cask was developed for the dry interim storage of spent VVER1000 fuel assemblies concerning the requirements of the Temelin NPP, Czech Republic. While the cask body is based on well-known ductile cast iron cask types with in-wall moderator, the basket follows a new concept. The basket is able to carry 19 fuel assemblies with a total decay heat power up to approximately 17 kW. The cask fulfils all requirements for a type B(U)F package. The main nuclear, mechanical and thermal properties of the cask are illustrated for normal conditions and for hypothetical accident scenarios during transport and storage. The main steps of the handling procedure such as loading the cask, drying the cavity and mounting the double lid system for tightness during interim storage are shown in principle. For this handling, boundary conditions at the NPP site such as dimensions, weight and the loading machine interface are considered. (authors)

A comparison of radiation doses and risks between spent fuel transport/storage and selected non-nuclear activities

International Nuclear Information System (INIS)

Pennington, C.W.

2003-01-01

Spent fuel transport and storage have achieved an exemplary safety record over four decades within both the United States (US) and the global community at large. This paper offers an assessment demonstrating the safety of spent fuel transport and storage packagings relative to currently accepted but unregulated non-nuclear activities and practices within society. Over the last quarter of a century, several spent fuel transport and storage packaging test programmes have produced data that allow calculation of potential releases and population doses resulting from a terrorist attack. The US Department of Energy (DOE) has used this information to develop projected worst-case, low probability population exposures as part of the Final Environmental Impact Statement (FEIS) for the Yucca Mountain repository. The paper discusses potential population exposures from these packagings based on analysis and testing under beyond-design-basis (BDB) events, including missile attacks, and then defines and defends an acceptance criterion for the bounding outcomes of these events, based upon current accepted activities within society that produce high radiation doses to the general public. These activities involve unregulated technologies and practices within society that yield population doses significantly exceeding those that would result from such hypothetical and highly improbable events as a terrorist missile attack on a spent fuel transport or storage packaging. In particular, technologically enhanced natural radiation (TENR) exposures from building materials, farming, and masonry construction are highlighted. Recent landmark work by the US National Academy of Sciences (NAS) and by the United Nations Scientific Committee on the Effects of Atomic Radiation (UNSCEAR) are cited in support of this assessment, along with work from the US Environmental Protection Agency (EPA). From this compelling evidence, it is concluded that spent fuel transport and storage represent a low

Changes in chemical quality indices during long-term storage of palm-olein oil under heated storage and transport-type conditions

CSIR Research Space (South Africa)

Van der Merwe, GH

2004-01-15

Full Text Available of Food and Agriculture J Sci Food Agric 84:52?58 (online: 2003) DOI: 10.1002/jsfa.1609 Changes in chemical quality indices during long-term storage of palm-olein oil under heated storage and transport-type conditions Gretel H van der Merwe,1asteriskmath... Lourens M du Plessis1 and John RN Taylor2 1CSIR Bio/Chemtek, PO Box 395, Pretoria 0001, South Africa 2Department of Food Science, University of Pretoria, Pretoria 0002, South Africa Abstract: Six quality indices, namely free fatty acids (FFA), peroxide...

Sustainable Solutions for Nuclear used Fuels Interim Storage

International Nuclear Information System (INIS)

Arslan, Marc; Favet, Dominique; Issard, Herve; Le Jemtel, Amaury; Drevon, Caroline

2014-01-01

AREVA has a unique experience in providing sustainable solutions for used fuel management, fitted with the needs of different customers in the world and with regulation in different countries. These solutions entail both recycling and interim storage technologies. In a first part, we will describe the various types of solutions for Interim Storage of UNF that have been implemented around the world for interim storage at reactor or centralized Pad solution in canisters dry storage, vault type storages for dry storage, dry storage of transportation casks (dual purpose) pools for wet storage, The experience for all these different families of interim storages in which AREVA is involved is extensive and will be discussed with respect to the new challenges: increase of the duration of the interim storage (long term interim storage) increase of burn up of the fuels In a second part of the presentation, special recycling features will be presented. In that case, interim storage of the used fuels is ensured in pools. This provides in the long term good conditions for the behaviour of the fuel and its retrievability. With recycling, the final waste (Universal Canister of vitrified fission products and compacted hulls and end pieces): is stable and licensed in many countries for the final disposal (France, UK, Belgium, NL, Switzerland, Germany, Japan, upcoming: Spain, Australia, Italy). Presents neither safety criticality risks nor proliferation risks (AREVA conditioned HLW and LL-ILW are free of IAEA safeguard constraints thanks to AREVA process high recovery and purification yields). It can therefore be safely stored in interim storage for more than 100 years before final disposal. Some economic considerations will also be discussed. In particular, in the case of long term interim storage of used fuels, there are growing uncertainties regarding the future needs of repackaging and transportation, which can result in future cost overruns. Meanwhile, in the recycling policy

Survey of experience with dry storage of spent nuclear fuel and update of wet storage experience

International Nuclear Information System (INIS)

1988-01-01

Spent fuel storage is an important part of spent fuel management. At present about 45,000 t of spent water reactor fuel have been discharged worldwide. Only a small fraction of this fuel (approximately 7%) has been reprocessed. The amount of spent fuel arisings will increase significantly in the next 15 years. Estimates indicate that up to the year 2000 about 200,000 t HM of spent fuel could be accumulated. In view of the large quantities of spent fuel discharged from nuclear power plants and future expected discharges, many countries are involved in the construction of facilities for the storage of spent fuel and in the development of effective methods for spent fuel surveillance and monitoring to ensure that reliable and safe operation of storage facilities is achievable until the time when the final disposal of spent fuel or high level wastes is feasible. The first demonstrations of final disposal are not expected before the years 2000-2020. This is why the long term storage of spent fuel and HLW is a vital problem for all countries with nuclear power programmes. The present survey contains data on dry storage and recent information on wet storage, transportation, rod consolidation, etc. The main aim is to provide spent fuel management policy making organizations, designers, scientists and spent fuel storage facility operators with the latest information on spent fuel storage technology under dry and wet conditions and on innovations in this field. Refs, figs and tabs

Computational Search for Improved Ammonia Storage Materials

DEFF Research Database (Denmark)

Jensen, Peter Bjerre; Lysgaard, Steen; Vegge, Tejs

Metal halide ammines, e.g. Mg(NH3)6Cl2 and Sr(NH3)8Cl2, can reversibly store ammonia, with high volumetric hydrogen storage capacities. The storage in the halide ammines is very safe, and the salts are therefore highly relevant as a carbon-free energy carrier in future transportation infrastructure...... selection. The GA is evolving from an initial (random) population and selecting those with highest fitness, a function based on e.g. stability, release temperature, storage capacity and the price of the elements. The search space includes all alkaline earth, 3d and 4d metals in combination with chloride......, bromide or iodide, and mixtures thereof. In total the search space consists of thousands of combinations, which makes a GA ideal, to reduce the number of necessary calculations. We are screening for a one step release from either a hexa or octa ammine, and we have found promising candidates, which...

Dynamics of water transport and storage in conifers studied with deuterium and heat tracing techniques.

Science.gov (United States)

F.C. Meinzer; J.R. Brooks; J.-C. Domec; B.L. Gartner; J.M. Warren; D.R. Woodruff; K. Bible; D.C. Shaw

2006-01-01

The volume and complexity of their vascular systems make the dynamics of tong-distance water transport in large trees difficult to study. We used heat and deuterated water (D20) as tracers to characterize whole-tree water transport and storage properties in individual trees belonging to the coniferous species Pseudotsuga menziesii...

IAEA mode-related research in the safe transport of radioactive material

Energy Technology Data Exchange (ETDEWEB)

Blalock, L.G.; Rawl, R.R. [International Atomic Energy Agency, IAEA, Vienna (Austria)

1998-07-01

The International Atomic Energy Agency sponsors Co-ordinated Research Programmes (CRP) in the safe transport of radioactive material. The CRPs are intended to encourage research by Member States in identified areas and to facilitate co-ordination of exchange of information and resources to reach a common understanding of the problem and alternative solutions. Two of these programmes are: Accident Severity at Sea During the Transport of Radioactive Material and Accident Severity During the Air Transport of Radioactive Material. This paper will discuss these two programmes and their relationship to the continuing regulatory revision process and interfaces with the International Maritime Organization (IMO) and the International Civil Aviation Organization (ICAO). Some Member States and non-governmental organizations in IMO meetings expressed concerns that accidents on board ships may be more severe than the IAEA regulatory tests account for, and that package failure with subsequent release of radioactive material may occur. The CRP on accident severity at sea was established to develop further quantitative information on potential accident severities during the transport of radioactive material by ships. The primary objective of this programme is to collect and evaluate statistical data of marine accidents, perform analyses of potential accident conditions and evaluate the risks resulting from such shipments. The CRP on air transport was established to make a major international effort to collect relevant frequency and severity data and to analyze it so the accident forces to which a packages of radioactive material might be subjected to in a severe air accident can be more confidently quantified. Several countries have ongoing data collection activities related to aircraft accidents and severity and other sources of statistics for in-flight aircraft accidents will be explored. The International Civil Aviation Organization informed the IAEA of their plans to improve

IAEA mode-related research in the safe transport of radioactive material

International Nuclear Information System (INIS)

Blalock, L.G.; Rawl, R.R.

1998-01-01

The International Atomic Energy Agency sponsors Co-ordinated Research Programmes (CRP) in the safe transport of radioactive material. The CRPs are intended to encourage research by Member States in identified areas and to facilitate co-ordination of exchange of information and resources to reach a common understanding of the problem and alternative solutions. Two of these programmes are: Accident Severity at Sea During the Transport of Radioactive Material and Accident Severity During the Air Transport of Radioactive Material. This paper will discuss these two programmes and their relationship to the continuing regulatory revision process and interfaces with the International Maritime Organization (IMO) and the International Civil Aviation Organization (ICAO). Some Member States and non-governmental organizations in IMO meetings expressed concerns that accidents on board ships may be more severe than the IAEA regulatory tests account for, and that package failure with subsequent release of radioactive material may occur. The CRP on accident severity at sea was established to develop further quantitative information on potential accident severities during the transport of radioactive material by ships. The primary objective of this programme is to collect and evaluate statistical data of marine accidents, perform analyses of potential accident conditions and evaluate the risks resulting from such shipments. The CRP on air transport was established to make a major international effort to collect relevant frequency and severity data and to analyze it so the accident forces to which a packages of radioactive material might be subjected to in a severe air accident can be more confidently quantified. Several countries have ongoing data collection activities related to aircraft accidents and severity and other sources of statistics for in-flight aircraft accidents will be explored. The International Civil Aviation Organization informed the IAEA of their plans to improve

Safe transport of radioactive materials

Energy Technology Data Exchange (ETDEWEB)

NONE

1977-12-31

The film shows the widespread use of radioactive materials in industry, medicine and research and explains the need for transporting nuclear material from producer to user. It shows the way in which packages containing radioactive materials are handled during transport and explains the most important provisions of the IAEA transport regulations, safety series no. 6, such as packaging design criteria and testing requirements, illustrated by various tests carried out, specimen packages and package and freight container labelling. Also illustrated are practical measures to be taken in case of an accident

Struggle against violations of the rules for radioactive materials storage, utilization, accounting and transport

International Nuclear Information System (INIS)

Iojrysh, A.I.

1986-01-01

Criminal punishments for violation of the rules of radioactive materials accounting, storage, utilization and transport or those for illegimate sending of these materials presupposed by the RSFSR criminal code are considered

Transporting fuel debris from TMI-2 to INEL

International Nuclear Information System (INIS)

Quinn, G.J.; Burton, H.M.; Bixby, W.W.; McIntosh, T.W.; McGoff, O.J.; Barkonic, R.J.; Henrie, J.O.

1986-06-01

Transportation of the damaged fuel from Unit 2 of Three Mile Island (TMI-2) presented noteworthy technical challenges involving complex institutional issues. The program resulted from both a need to package and remove the accident debris and also the opportunity to receive and study damaged core components. These combined to establish the safe transport of the TMI-2 fuel debris as a high priority for many diverse organizations. The capability of the sending and receiving facilities to handle spent fuel transport casks in the most cost-effective manner was assessed and resulted in the development by Nuclear Packaging Inc. (NuPac) of the NuPac 125-B rail cask. This paper reviews the technical challenges in preparation of the TMI-2 core debris for transport from TMI-2 to the Idaho National Engineering Laboratory (INEL) and receipt and storage of that material at INEL. Challenges discussed include design and testing of fuel debris canisters; design, fabrication and licensing of a new rail cask for spent fuel transport; cask loading operations, equipment and facilities at TMI-2; transportation logistics; and, receipt, storage and core examination operations at INEL. 10 refs

Transportation and storage studies on irradiated Alphonso mangoes

International Nuclear Information System (INIS)

Farkas, J.; Dharkar, S.D.; Sreenivasan, A.

1972-01-01

Control as well as skin coated (6% ''Myvacet'') and/or irradiated (25 to 35 krad) mangoes were packed in baskets in dry paddy straw and shipped by rail. After a storage at a temperature of 25 to 32 0 C for a period of 8 days, the baskets were shipped back. After receipt in the laboratory the fruits were kept under observation for 5 more days and then scored for ripening and marketability as assessed by appearance, skin gloss and typical flavour. 100 per cent of fruits skin-coated and irradiated were marketable at the end of the experiment. None of the unirradiated control fruits were saleable by this time, while 66%, of the irradiated fruits were in acceptable condition. In further experiments one dozen mangoes each from control, irradiated and skin-coated and irradiated groups were wrapped individually in tissue paper and packed tightly in a plyweed box. This consignment was air-lifted from Bombay to Budapest, a distance of about 5600 kilometers. The time interval between irradiation and their receipt in Hungary was 4 days. The mangoes were assessed for their storage characteristics by various parameters that included physiological loss in weight, puncture resistance of the skin, pulp texture, carotenoids, acidity and organoleptic attributes, at various periods during storage. It was found that ripening and senescence are strikingly delayed in mangoes by skin-coating and radiation treatment. The treated mangoes retained their skin-resistance while the disappearance of chlorophyl and formation of carotenoids were substantially delayed. Weight loss in storage was lower and reduction of acidity and formation of sugars in the fruit flesh took place later. Organoleptically, the fruits subjected to the combination treatment were good. These studies point to the feasibility of the combination treatment in prolonging the shelf life of fruits significantly to enable their transport to distant countries. (F.G.)

Safe handling of radiation sources

International Nuclear Information System (INIS)

Abd Nasir Ibrahim; Azali Muhammad; Ab Razak Hamzah; Abd Aziz Mohamed; Mohammad Pauzi Ismail

2004-01-01

This chapter discussed the subjects related to the safe handling of radiation sources: type of radiation sources, method of use: transport within premises, transport outside premises; Disposal of Gamma Sources

The safe home project.

Science.gov (United States)

Arphorn, Sara; Jiraniratisai, Sopaphan; Rungtakul, Rungsri; Phutta, Nikom

2011-12-01

The Thai Health Promotion Foundation supported the Improvement of Quality of Life of Informal Workers project in Ban Luang District, Amphur Photaram, Ratchaburi Province. There were many informal workers in Ban Luang District. Sweet-crispy fish producers in Ban Luang were the largest group among the sweet-crispy fish producers in Thailand. This project was aimed at improving living and working conditions of informal workers, with a focus on the sweet-crispy fish group. Good practices of improved living and working conditions were used to help informal workers build safe, healthy and productive work environments. These informal workers often worked in substandard conditions and were exposed to various hazards in the working area. These hazards included risk of exposure to hot work environment, ergonomics-related injuries, chemical hazards, electrical hazards etc. Ergonomics problems were commonly in the sweet-crispy fish group. Unnatural postures such as prolonged sitting were performed dominantly. One hundred and fifty informal workers participated in this project. Occupational health volunteers were selected to encourage occupational health and safety in four groups of informal workers in 2009. The occupational health volunteers trained in 2008 were farmers, beauty salon workers and doll makers. The occupational health and safety knowledge is extended to a new informal worker group: sweet-crispy fish producer, in 2009. The occupational health and safety training for sweet-crispy fish group is conducted by occupational health volunteers. The occupational health volunteers increased their skills and knowledge assist in to make safe home and safe community through participatory oriented training. The improvement of living and working condition is conducted by using a modified WISH, Work Improvement for Safe Home, checklist. The plans of improvement were recorded. The informal workers showed improvement mostly on material handling and storage. The safe uses and safe

Long-term storage and safe retrieval of human papillomavirus DNA using FTA elute cards.

Science.gov (United States)

Barth, Heidi; Morel, Adrien; Mougin, Christiane; Averous, Gerlinde; Legrain, Michèle; Fender, Muriel; Risch, Simone; Fafi-Kremer, Samira; Velten, Michel; Oudet, Pierre; Baldauf, Jean-Jacques; Stoll-Keller, Françoise

2016-03-01

Biobanking or collection and storage of specimens for future research purposes have become an essential tool in many fields of biomedical research and aims to provide a better understanding of disease mechanisms as well as the identification of disease-specific biomarkers that can navigate in complex diseases. In this study, we assessed the use of Flinders Technology Associates (FTA) cards as a long-term storage device for cervical specimens with suspected human papillomavirus (HPV) infections. HPV detection and genotyping results in liquid-based transport media were compared to HPV results from FTA cards. The overall agreement for the presence of any HPV infection between liquid-based medium and FTA cards stored for 1 year at ambient temperature was 100%. Reproducibility analysis of HPV detection and genotyping from FTA cards demonstrated that FTA cards are a reliable medium to store and preserve viral nucleic acids. Biobanking of cervical cells on FTA cards may provide a key resource for epidemiological and retrospective HPV studies. Copyright © 2015 Elsevier B.V. All rights reserved.

A comparative study on uranium and ZrCo for the storage of tritium

Energy Technology Data Exchange (ETDEWEB)

Kim, Summi; Paek, Seungwoo; Lee, Minsoo; Kim, Kwangrag; Ahn, Dohee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Sohn, Soonhwan; Song, Kyumin [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

2007-07-01

Safe handling, transport, and storage of tritium requires several condition: very low equilibrium pressures over the tritide at room temperature, high dissociation pressure at moderate temperatures, existence of plateau regions in the loading/deloading isotherms, fast adsorption/desorption kinetics, no disproportionation, low reactivity of the metal/tritide system towards air and the major contaminants, low pyrophoricity, and low aging effects caused by the accumulated of He-3.

A comparative study on uranium and ZrCo for the storage of tritium

International Nuclear Information System (INIS)

Kim, Summi; Paek, Seungwoo; Lee, Minsoo; Kim, Kwangrag; Ahn, Dohee; Sohn, Soonhwan; Song, Kyumin

2007-01-01

Safe handling, transport, and storage of tritium requires several condition: very low equilibrium pressures over the tritide at room temperature, high dissociation pressure at moderate temperatures, existence of plateau regions in the loading/deloading isotherms, fast adsorption/desorption kinetics, no disproportionation, low reactivity of the metal/tritide system towards air and the major contaminants, low pyrophoricity, and low aging effects caused by the accumulated of He-3

Spatial and intertemporal arbitrage in the California natural gas transportation and storage network

Science.gov (United States)

Uria Martinez, Rocio

Intertemporal and spatial price differentials should provide the necessary signals to allocate a commodity efficiently inside a network. This dissertation investigates the extent to which decisions in the California natural gas transportation and storage system are taken with an eye on arbitrage opportunities. Daily data about flows into and out of storage facilities in California over 2002-2006 and daily spreads on the NYMEX futures market are used to investigate whether the injection profile is consistent with the "supply-of-storage" curve first observed by Working for wheat. Spatial price differentials between California and producing regions fluctuate throughout the year, even though spot prices at trading hubs across North America are highly correlated. In an analysis of "residual supply", gas volumes directed to California are examined for the influence of those fluctuations in locational differentials. Daily storage decisions in California do seem to be influenced by a daily price signal that combines the intertemporal spread and the locational basis between California and the Henry Hub, in addition to strong seasonal and weekly cycles. The timing and magnitude of the response differs across storage facilities depending on the regulatory requirements they face and the type of customers they serve. In contrast, deviations in spatial price differentials from the levels dictated by relative seasonality in California versus competing regions do not trigger significant reallocations of flows into California. Available data for estimation of both the supply-of-storage and residual-supply curves aggregate the behavior of many individuals whose motivations and attentiveness to prices vary. The resulting inventory and flow profiles differ from those that a social planner would choose to minimize operating costs throughout the network. Such optimal allocation is deduced from a quadratic programming model, calibrated to 2004-2005, that acknowledges relative seasonality

Monitored retrievable storage design

International Nuclear Information System (INIS)

Woods, W.D.

1985-01-01

The Nuclear Waste Policy Act of 1982 (NWPA) established a national policy for the safe storage and disposal of spent nuclear fuel and high-level radioactive waste. The NWPA requires that DOE... ''submit a proposal to Congress on the need for and feasibility of one or more Monitored Retrievable Storage (MRS) Facilities''... In subsequent evaluations of the commercial nuclear waste management system, DOE has identified important advantages in providing an MRS Facility as an integral part of the total system. The integral MRS Facility serves as an independent, centralized spent nuclear fuel and high-level waste handling and packaging facility with a safe temporary storage capacity

Peak cladding temperature in a spent fuel storage or transportation cask

International Nuclear Information System (INIS)

Li, J.; Murakami, H.; Liu, Y.; Gomez, P.E.A.; Gudipati, M.; Greiner, M.

2007-01-01

From reactor discharge to eventual disposition, spent nuclear fuel assemblies from a commercial light water reactor are typically exposed to a variety of environments under which the peak cladding temperature (PCT) is an important parameter that can affect the characteristics and behavior of the cladding and, thus, the functions of the spent fuel during storage, transportation, and disposal. Three models have been identified to calculate the peak cladding temperature of spent fuel assemblies in a storage or transportation cask: a coupled effective thermal conductivity and edge conductance model developed by Manteufel and Todreas, an effective thermal conductivity model developed by Bahney and Lotz, and a computational fluid dynamics model. These models were used to estimate the PCT for spent fuel assemblies for light water reactors under helium, nitrogen, and vacuum environments with varying decay heat loads and temperature boundary conditions. The results show that the vacuum environment is more challening than the other gas environments in that the PCT limit is exceeded at a lower boundary temperature for a given decay heat load of the spent fuel assembly. This paper will highlight the PCT calculations, including a comparison of the PCTs obtained by different models.

Japanese perspectives and research on packaging, transport and storage of spent fuel

International Nuclear Information System (INIS)

Saegusa, T.; Ito, C.; Yamakawa, H.; Shirai, K.

2004-01-01

The Japanese policy on spent fuel is reprocessing. Until, reprocessed, spent fuel shall be stored properly. This paper overviews current status of transport and storage of spent fuel with related research in Japan. The research was partly carried out under a contract of Ministry of Economy, Trade and Industry of the Japanese government

Process-based reactive transport model to quantify arsenic mobility during aquifer storage and recovery of potable water.

Science.gov (United States)

Wallis, Ilka; Prommer, Henning; Pichler, Thomas; Post, Vincent; Norton, Stuart B; Annable, Michael D; Simmons, Craig T

2011-08-15

Aquifer storage and recovery (ASR) is an aquifer recharge technique in which water is injected in an aquifer during periods of surplus and withdrawn from the same well during periods of deficit. It is a critical component of the long-term water supply plan in various regions, including Florida, USA. Here, the viability of ASR as a safe and cost-effective water resource is currently being tested at a number of sites due to elevated arsenic concentrations detected during groundwater recovery. In this study, we developed a process-based reactive transport model of the coupled physical and geochemical mechanisms controlling the fate of arsenic during ASR. We analyzed multicycle hydrochemical data from a well-documented affected southwest Floridan site and evaluated a conceptual/numerical model in which (i) arsenic is initially released during pyrite oxidation triggered by the injection of oxygenated water (ii) then largely complexes to neo-formed hydrous ferric oxides before (iii) being remobilized during recovery as a result of both dissolution of hydrous ferric oxides and displacement from sorption sites by competing anions.

Selection of exception limits for all actinide nuclides based on revised criteria for safe international transport

International Nuclear Information System (INIS)

Lavarenne, C.; Rouyer, V.; Sert, G.; Mennerdahl, D.; Dean, C.; Barton, N.; Jean, F.

2003-01-01

Since 1998, there have been some speculations about future transport of significant quantities and concentrations of other actinide nuclides than the four currently listed in the regulation for the safe transport of the radioactive material. Therefore, it raised a need to specify exception limits for such actinides. Additionally, the total fissile nuclide mass per consignment of excepted packages was limited in the 1996 edition of the regulations (a conveyance limit is preliminary supported in the 2003 revision). The proposed changes of the rules have to take this new control into account. The European Community (DGTREN) decided to fund a project related to this subject. In order to define credible exception limits, it was necessary to have reasonably accurate data for all actinide nuclides. Then the authors of the study decided to perform calculations with different codes (MONK, MCNP, CRISTAL, SCALE) and different cross-section libraries (JEF2.2, ENDFB, JENDL, etc.). This article presents the work achieved and gives propositions of modification for the IAEA requirements for the Safe Transport of Radioactive Material related to, firstly, the list of the fissile materials, and secondly, the rule to determine the quantities of actinide nuclides that can be excepted from the requirements for the packages containing fissile materials. The participants acknowledge the DGTREN who made this work possible due to its support. (author)

MRS systems study, Task F: Transportation impacts of a monitored retrievable storage facility

Energy Technology Data Exchange (ETDEWEB)

Brentlinger, L.A.; Gupta, S.; Plummer, A.M.; Smith, L.A.; Tzemos, S.

1989-05-01

The passage of the Nuclear Waste Policy Amendments Act of 1987 (NWPAA) modified the basis from which the Office of Civilian Radioactive Waste Management (OCRWM) had derived and developed the configuration of major elements of the waste system (repository, monitored retrievable storage, and transportation). While the key aspects of the Nuclear Waste Policy Act of 1982 remain unaltered, NWPAA provisions focusing site characterization solely at Yucca Mountain, authorizing a monitored retrievable storage (MRS) facility with specific linkages to the repository, and establishing an MRS Review Commission make it prudent for OCRWM to update its analysis of the role of the MRS in the overall waste system configuration. This report documents the differences in transportation costs and radiological dose under alternative scenarios pertaining to a nuclear waste management system with and without an MRS, to include the effect of various MRS packaging functions and locations. The analysis is limited to the impacts of activities related directly to the hauling of high-level radioactive waste (HLW), including the capital purchase and maintenance costs of the transportation cask system. Loading and unloading impacts are not included in this study because they are treated as facility costs in the other task reports. Transportation costs are based on shipments of 63,000 metric tons of uranium (MTU) of spent nuclear fuel and 7,000 MTU equivalent of HLW. 10 refs., 41 tabs.

Performance of CASTOR {sup registered} HAW cask cold trials for loading, Transport and storage of HAW canisters

Energy Technology Data Exchange (ETDEWEB)

Wilmsmeier, Marco; Horn, Thomas; Graf, Wilhelm [GNS Gesellschaft fuer Nuklear-Service mbH (Germany)

2009-07-01

With over 30 years of experience in the design, manufacturing, assembly and loading of CASTOR {sup registered} casks, GNS is one of the worldwide leading suppliers of casks for the transport and storage of spent fuel assemblies as well as for canisters with vitrified high active wastes (meanwhile over 1.000 casks loaded and stored and more than 1.500 ordered). GNS's products are used at around 30 sites worldwide for a wide range of inventories from pressurised and boiling water reactor fuels (PWR, VVER and BWR, RBMK), thorium high-temperature reactor fuels (THTR) and research reactor fuels (MTR) to vitrified high active wastes (HAW) from reprocessing plants. GNS is responsible for all nuclear wastes resulting from German Nuclear Power Plants and assists and/or performs in the loading and dispatch of CASTOR {sup registered} casks as well as their transport to and storage at central interim storage facilities and local interim storage areas. (orig.)

Experimental insights into organic carbon oxidation potential during fluvial transport without floodplain storage

Science.gov (United States)

Scheingross, J. S.; Hovius, N.; Sachse, D.; Vieth-Hillebrand, A.; Turowski, J. M.; Hilton, R. G.

2016-12-01

Over geologic timescales, the exchange of organic carbon (OC) between the atmosphere, rock, and biosphere is thought to be a major control on global climate. CO2 flux estimates from oxidation of rock-derived OC and sequestration of biospheric OC during fluvial transit from source to sink are approximately the same order of magnitude or larger than those from silicate weathering. Despite field data showing loss of OC moving downstream in lowland rivers, it is unclear if losses occur primarily during active fluvial transport within the river, where OC is in continual motion within an aerated environment, or during longer periods when OC is temporarily stored in river floodplains which may be anoxic. This represents a major knowledge gap, as the unknown location of OC oxidation (i.e., river vs. floodplain) limits our ability to develop process-based models that can be employed to predict OC losses, constrain carbon budgets, and unravel links between climate, tectonics, and erosion. To fill this gap, we investigated the potential for OC oxidation in laboratory experiments simulating fluvial transport without floodplain storage. Mixtures of OC-rich and siliciclastic sediment were transported for distances of 2000 km in annular flumes while making time-series measurements of sediment TOC and water DOC concentrations. Initial results for transport of OC-rich soil show increasing DOC with transport distance to levels that represent a transfer of 2% of the total OC from the solid to the dissolved phase; however, we observed no detectable change in the solid-phase TOC. Similar results were obtained in a control experiment with identical sediment in still water. These preliminary results suggest minimal OC oxidation within our experiment, and, to the extent that such experiments represent natural transport through river systems, are consistent with the hypothesis that OC losses may occur primarily during floodplain storage rather than fluvial transport.

Heat in the Barents Sea: transport, storage, and surface fluxes

Directory of Open Access Journals (Sweden)

L. H. Smedsrud

2010-02-01

Full Text Available A column model is set up for the Barents Sea to explore sensitivity of surface fluxes and heat storage from varying ocean heat transport. Mean monthly ocean transport and atmospheric forcing are synthesised and force the simulations. Results show that by using updated ocean transports of heat and freshwater the vertical mean hydrographic seasonal cycle can be reproduced fairly well.

Our results indicate that the ~70 TW of heat transported to the Barents Sea by ocean currents is lost in the southern Barents Sea as latent, sensible, and long wave radiation, each contributing 23–39 TW to the total heat loss. Solar radiation adds 26 TW in the south, as there is no significant ice production.

The northern Barents Sea receives little ocean heat transport. This leads to a mixed layer at the freezing point during winter and significant ice production. There is little net surface heat loss annually in the north. The balance is achieved by a heat loss through long wave radiation all year, removing most of the summer solar heating.

During the last decade the Barents Sea has experienced an atmospheric warming and an increased ocean heat transport. The Barents Sea responds to such large changes by adjusting temperature and heat loss. Decreasing the ocean heat transport below 50 TW starts a transition towards Arctic conditions. The heat loss in the Barents Sea depend on the effective area for cooling, and an increased heat transport leads to a spreading of warm water further north.

Fuel Behaviour in Transport after Dry Storage: a Key Issue for the Management of used Nuclear Fuel

International Nuclear Information System (INIS)

Issard, Herve

2014-01-01

Interim used fuel dry storage has been developed in many countries providing an intermediate solution while waiting for evaluation and decisions concerning future use (such as recycling) or disposal sites. There is an important industrial experience feedback and excellent safety records. It appears that the duration of interim storage may become longer than initially expected. At the start of storage operations 40 years was considered sufficiently long to make a decision on either recycling or direct disposal of used nuclear fuel. Now it is said that storage time may have to be extended. Whatever the choice for the management of used fuel, it will finally have to be transported from the storage facility to another location, for recycling or final disposal. Bearing in mind the important principle that radioactive waste shall be managed in such a way that undue burdens will not be imposed on future generations, there is no guarantee that the fuel characteristics can be maintained in perpetuity. On the other hand, transport accident conditions from applicable regulation (IAEA SSR-6) are very severe for irradiated materials. Therefore, in compliance with transport regulations, the safety analysis of the fuel in transport after storage is mandatory. This paper will give an overview of the current situation related to the used fuel behaviour in transport after dry storage. On this matter there are some elements of information already available as well as some gaps of knowledge. Several national R and D programs and international teams are presently addressing these gaps. A lot of R and D work has already been done. An objective of these R and D projects is to aid decision makers. It is important to fix a limit and not to multiply intermediate operations because it means higher costs and more uncertainties. The identified gaps concern the following issues especially for high burn-up (HBU) fuels: thermal model for casks, degradation process of fuel material, cladding creep

Status of the Regulation for safe and secure transport of radioactive materials in Madagascar

International Nuclear Information System (INIS)

Raoelina Andriambololona; Zafimanjato, J.L.R.; Solofoarisina, W.C.; Randriantseheno, H.F.

2011-01-01

Radioactive sources are widely used in medicine, in industrial exploration and development, as well as in basic scientific research and education in Madagascar. The ability to use such radioactive materials in these sectors depends on their safe and secure transport both within and between countries. Transport safety of radioactive materials within the country is regulated. The law No. 97-041 on radiation protection and radioactive waste management in Madagascar promulgated in January 1998 and the decree No.2735/94 dealing the transport of radioactive materials promulgated in June 1994 govern all activities related to the transport of radioactive material. This law was established to meet the requirements of the International Basic Safety Standards (BSS, IAEA Safety Series 115). It is not fully consistent with current international standards (GS-R-1). Indeed, in order to enhance the security of radioactive sources, Madagascar has implemented the Code of Conduct and the Guidance on the Import and Export of Radioactive Sources. Faced with delays and denials of shipment of radioactive materials issues, the National Focal Point has been appointed to work with ISC members and the regional networks on the global basis.

Status of the regulation for safe and secure transport of radioactive materials in Madagascar

International Nuclear Information System (INIS)

Andriambololona, Raoelina; Zafimanjato, J.L.R.; Solofoarisina, W.C.; Randriantseheno, H.F.

2016-01-01

Radioactive sources are widely used in medicine, in industrial exploration and development, as well as in basic scientific research and education in Madagascar. The ability to use such radioactive materials in these sectors depends on their safe and secure transport both within and between countries. Transport safety of radioactive materials within the country is regulated. The law n° 97-041 on radiation protection and radioactive waste management in Madagascar promulgated in January 1998 and the decree n° 2735/94 dealing the transport of radioactive materials promulgated in June 1994 govern all activities related to the transport of radioactive material. This law was established to meet the requirements of the International Basic Safety Standards (BSS, IAEA Safety Series 115). It is not fully consistent with current international standards (GS-R-1). Indeed, in order to enhance the security of radioactive sources, Madagascar has implemented the Code of Conduct and the Guidance on the Import and Export of Radioactive Sources. Faced with delays and denials of shipment of radioactive materials issues, the National Focal Point has been appointed to work with ISC members and the regional networks on the global basis. (author)

Recovery Act: 'Carbonsheds' as a Framework for Optimizing United States Carbon Capture and Storage (CCS) Pipeline Transport on a Regional to National Scale

Energy Technology Data Exchange (ETDEWEB)

Pratson, Lincoln

2012-11-30

Carbonsheds are regions in which the estimated cost of transporting CO{sub 2} from any (plant) location in the region to the storage site it encompasses is cheaper than piping the CO{sub 2} to a storage site outside the region. We use carbonsheds to analyze the cost of transport and storage of CO{sub 2} in deploying CCS on land and offshore of the continental U.S. We find that onshore the average cost of transport and storage within carbonsheds is roughly $10/t when sources cooperate to reduce transport costs, with the costs increasing as storage options are depleted over time. Offshore transport and storage costs by comparison are found to be roughly twice as expensive but t may still be attractive because of easier access to property rights for sub-seafloor storage as well as a simpler regulatory system, and possibly lower MMV requirements, at least in the deep-ocean where pressures and temperatures would keep the CO{sub 2} negatively buoyant. Agent-based modeling of CCS deployment within carbonsheds under various policy scenarios suggests that the most cost-effective strategy at this point in time is to focus detailed geology characterization of storage potential on only the largest onshore reservoirs where the potential for mitigating emissions is greatest and the cost of storage appears that it will be among the cheapest.

Midwestern High-Level Radioactive Waste Transportation Project

International Nuclear Information System (INIS)

Sattler, L.R.

1992-02-01

In addition to arranging for storage and disposal of radioactive waste, the US Department of Energy (DOE) must develop a safe and efficient transportation system in order to deliver the material that has accumulated at various sites throughout the country. The ability to transport radioactive waste safely has been demonstrated during the past 20 years: DOE has made over 2,000 shipments of spent fuel and other wastes without any fatalities or environmental damage related to the radioactive nature of the cargo. To guarantee the efficiency of the transportation system, DOE must determine the optimal combination of rail transport (which allows greater payloads but requires special facilities) and truck transport Utilizing trucks, in turn, calls for decisions as to when to use legal weight trucks or, if feasible, overweight trucks for fewer but larger shipments. As part of the transportation system, the Facility Interface Capability Assessment (FICA) study contributes to DOE's development of transportation plans for specific facilities. This study evaluates the ability of different facilities to receive, load and ship the special casks in which radioactive materials will be housed during transport In addition, the DOE's Near-Site Transportation Infrastructure (NSTI) study (forthcoming) will evaluate the rail, road and barge access to 76 reactor sites from which DOE is obligated to begin accepting spent fuel in 1998. The NSTI study will also assess the existing capabilities of each transportation mode and route, including the potential for upgrade

Safety aspects of long-term dry interim storage of type-B spent fuel and HLW transport casks

International Nuclear Information System (INIS)

Wolff, D.; Probst, U.; Voelzke, H.; Droste, B.; Roedel, R.

2004-01-01

Based on the German decision to minimise transports of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities several on-site storage facilities have been licensed till the end of 2003. Because of the large amount of type-B transport casks which are going to be used for long-term interim storage the question of time limited type-B license maintenance during the storage period of up to 40 years has been discussed under different aspects. This paper describes present technical aspects of the discussion. A main aspect of transport cask qualification for interim storage is the long-term behaviour of the metallic seal lid system. Concerning this results from current experimental long-term tests with metallic ''Helicoflex''-seals in which pool water is enclosed are presented. The test series has been performed by the Federal Institute for Materials Research and Testing (BAM) on behalf of the Federal Office for Radiation Protection (BfS) since 2001. Finally, the paper presents a German concept for an authorities' and technical experts' exchange of experience, know-how and state of the art referring to cask dispatch in nuclear facilities. BAM has taken over a central role in this so-called ''co-ordinating institution for cask dispatching information'' (''KOBAF'') which contains an online data base and a technical working group meeting twice a year. The goal is to keep comparable technical standards for all nuclear sites and storage facilities which are going to load and dispatch casks of the same or similar types under the responsibility of different German state governments for the next decades

Ammonia Storage as Complex Compounds for a Safe and Compact Hydrogen Storage

National Research Council Canada - National Science Library

Sarkisian, Paul

2003-01-01

.... Design software suitable to the evaluation of the complex compounds for this particular application was developed that would determine the size and weight of the complex compound sorber to be used for ammonia storage...

Experience with the transport and storage casks CASTOR (registered) MTR 2 for spent nuclear fuel assemblies from research reactors

Energy Technology Data Exchange (ETDEWEB)

Jack, Allen; Rettenbacher, Katharina; Skrzyppek, Juergen [GNS Gesellschaft fuer Nuklear-Service mbH, Essen (Germany)

2011-07-01

The CASTOR (registered) MTR 2 cask was designed and manufactured by the company GNS during the 1990's for the transport and interim storage of spent nuclear fuel assemblies from various types of research reactors. Casks of this type have been used at the VKTA Research Centre in Rossendorf near Dresden, Germany as well as at the European Commission's Joint Research Centre at Petten and at the HOR reactor at Delft in the Netherlands. A total of 24 units have been used for the functions of transport and storage with various spent fuel types (VVER, HFR-HEU, and HOR-HEU) for more than ten years now. This type of packaging for radioactive material is a member of the CASTOR (registered) family of spent nuclear fuel casks used worldwide. Over 1000 units are loaded and in storage in Europe, Asia, Africa and North America. This paper presents the experience from the use of the casks for transport and storage in the past, as well as the prospects for the future. (author)

On the development and benchmarking of an approach to model gas transport in fractured media with immobile water storage

Science.gov (United States)

Harp, D. R.; Ortiz, J. P.; Pandey, S.; Karra, S.; Viswanathan, H. S.; Stauffer, P. H.; Anderson, D. N.; Bradley, C. R.

2017-12-01

In unsaturated fractured media, the rate of gas transport is much greater than liquid transport in many applications (e.g., soil vapor extraction operations, methane leaks from hydraulic fracking, shallow CO2 transport from geologic sequestration operations, and later-time radionuclide gas transport from underground nuclear explosions). However, the relatively immobile pore water can inhibit or promote gas transport for soluble constituents by providing storage. In scenarios with constant pressure gradients, the gas transport will be retarded. In scenarios with reversing pressure gradients (i.e. barometric pressure variations) pore water storage can enhance gas transport by providing a ratcheting mechanism. Recognizing the computational efficiency that can be gained using a single-phase model and the necessity of considering pore water storage, we develop a Richard's solution approach that includes kinetic dissolution/volatilization of constituents. Henry's Law governs the equilibrium gaseous/aqueous phase partitioning in the approach. The approach is implemented in a development branch of the PFLOTRAN simulator. We verify the approach with analytical solutions of: (1) 1D gas diffusion, (2) 1D gas advection, (3) sinusoidal barometric pumping of a fracture, and (4) gas transport along a fracture with uniform flow and diffusive walls. We demonstrate the retardation of gas transport in cases with constant pressure gradients and the enhancement of gas transport with reversing pressure gradients. The figure presents the verification of our approach to the analytical solution of barometric pumping of a fracture from Nilson et al (1991) where the x-axis "Horizontal axis" is the distance into the matrix block from the fracture.

Fracture mechanics aspects in the safe design of ductile iron shipping and storage containers

International Nuclear Information System (INIS)

Sappok, M.; Bounin, D.

1996-01-01

Containers made of ductile cast iron provide a safe method for transport of radioactive material. Contrary to widespread opinion ductile cast iron is a very tough material and can be manufactured in heavy sections. The containers are designed to withstand the very high impact loads of accidents like free drops onto unyielding targets. The design is based on postulated undetected crack-like flaws at the highest stressed location. Design must show that applied stress intensities are smaller than fracture toughness and no crack initiation and therefore also no crack propagation can occur. The design procedure followed in this paper is given in a new guideline still being drafted by the International Atomic Energy Agency

CASTOR THTR transport/storage casks

International Nuclear Information System (INIS)

Laug, R.W.; Spilker, H.; Sappok, M.

1998-01-01

For the management of spent fuel from nuclear power plants, two possibilities are available in Germany. One possibility is the reprocessing of the spent fuel and the realization of a so called closed nuclear fuel cycle, the other is the direct disposal after a period of interim storage, without reprocessing. For the German GCR plants ''THTR 300'' and ''AVR'', only the way of direct disposal is available to date for managing the spent fuel (pebble-bed fuel). For the period of interim storage, dry storage in casks was selected. (author)

The safe transport of radioactive materials

International Nuclear Information System (INIS)

Swindell, G.E.

1975-01-01

In the course of transport by road, rail, sea and air, consignments of radioactive material are in close proximity to ordinary members of the public and in most cases they are loaded and unloaded by transport workers who have no special training or experience in the handling of radioactive substances. The materials being transported cover a wide variety - ranging from small batches of short-lived radionuclides used in medical practice which can be transported in small sealed lead pots in cardboard boxes, to large, extremely radioactive consignments of irradiated nuclear fuel in flasks weighing many tons. With the growing development of nuclear power programmes the transport of irradiated fuel is likely to increase markedly. It is clear that unless adequate regulations concerning the design and assembly of the packages containing these materials are precisely set down and strictly carried out, there would be a high probability that some of the radioactive contents would be released, leading to contamination of other transported goods and the general environment, and to the delivery of a radiation dose to the transport workers and the public. An additional requirement is that the transport should proceed smoothly and without delay. This is particularly important for radioactive materials of short half-life, which would lose significant amounts of their total activity in unnecessary delays at international boundaries. Therefore, it is essential that the regulations are also enforced, to ensure that the radioactive material is contained and the surrounding radiation level reduced to a value which poses no threat to other sensitive goods such as photographic film, or to transport workers and other passengers. These regulations should be as uniform as possible on an international basis, so that consignments can move freely from one country to another with as little delay as possible at the frontiers. (author)

The incorporation of boron in fissile transport packages for the transport and interim storage of irradiated light water reactor fuels

International Nuclear Information System (INIS)

Hunter, I.J.

1998-01-01

Boron is widely used in the nuclear industry for capturing neutrons and it is particularly useful in the criticality control of packages for the transport and interim storage of irradiated light water reactor fuels. Such fuels are typically located in an internal frame of stainless steel or aluminium, referred to as a basket, which locates the fuel assemblies in channels. Transnucleaire has designed and supplied more than 100 baskets of varying types during the past 30 years. Boron has been incorporated in many forms. Early designs of baskets used boron in specific zones to contribute to the control of criticality. Later developments in new materials dispersed boron throughout the basket and gave designers more options for the basic forms which make up the channels. New basket concepts have been developed by Transnucleaire to meet the changing market needs for transport and interim storage and boron continues to play an important role as an efficient thermal neutron absorber. (author)

Standard casks for the transport of LWR spent fuel. Storage/transport casks for long cooled spent fuel

International Nuclear Information System (INIS)

Blum, P.; Sert, G.; Gagnon, R.

1983-01-01

During the past decade, TRANSNUCLEAIRE has developed, licensed and marketed a family of standard casks for the transport of spent fuel from LWR reactors to reprocessing plants and the ancillary equipments necessary for their operation and transport. A large number of these casks are presently used for European and intercontinental transports and manufactured under TRANSNUCLEAIRE supervision in different countries. The main advantages of these casks are: - large payload for considered modes of transport, - moderate cost, - reliability due to the large experience gained by TRANSNUCLEAIRE as concerns fabrication and operation problems, - standardization faciliting fabrication, operation and spare part supply. Recently, TRANSNUCLEAIRE also developed a new generation of casks for the dry storage and occasional transport of LWR spent fuel which has been cooled for 5 years or 7 years in case of consolidated fuel rods. These casks have an optimum payload which takes into account the shielding requirements and the weight limitations at most sites. This paper deals more particularly with the TN 24 model which exists in 4 versions among which one for 24 PWR 900 fuel assemblies and another one for the consolidated fuel rods from 48 of same fuel assemblies

Transportation and Aging: An Updated Research Agenda for Advancing Safe Mobility.

Science.gov (United States)

Dickerson, Anne E; Molnar, Lisa; Bedard, Michel; Eby, David W; Classen, Sherrilene; Polgar, Janice

2017-10-01

This article discusses what is currently known about three important topics related to older driver safety and mobility: screening and evaluation, education and training interventions, and in-vehicle technology. Progress is being made to improve the safe mobility of older adults in these key areas; however, significant research gaps remain. This article advances the state of knowledge by identifying these gaps, and proposing further research topics will improve the lives of older adults. In addition, we discuss several themes that emerged from the review, including the need for multidisciplinary, community-wide solutions; large-scale, longitudinal studies; improved education/training for both older adults themselves and the variety of stakeholders involved in older adult transportation; and programs and interventions that are flexible and responsive to individual needs and differences.

Preparation and characterization of nano-sized phase change emulsions as thermal energy storage and transport media

International Nuclear Information System (INIS)

Chen, J.; Zhang, P.

2017-01-01

Highlights: • The nano-sized phase change emulsions are prepared by using D-phase method. • The thermo-physical and transport properties are experimentally investigated. • The influence of surfactant on the melting temperature and latent heat of water is clarified. • The phase change emulsion can be used as the heat transfer fluid in a thermal energy storage system. - Abstract: Phase change emulsion (PCE) is a kind of two-phase heat transfer fluid with phase change material (PCM) dispersed in carrier fluid. It has received intensive attractions in recent years due to the fact that it can be used as both the thermal energy storage material and transport medium simultaneously in a thermal energy storage system. In the present study, nano-sized PCEs are prepared by the D-phase method with n-hexadecane and n-octadecane as PCMs. The thermo-physical and transport properties are characterized to facilitate the applications. The droplet size distribution of the PCE is measured by a Photon Correlation Spectroscopy, and the results show that the droplet size distributions are similar at different mass fractions. The rheological behavior and viscosity of the PCE are measured by a rheometer, which shows that the PCEs at mass fractions below 30.0 wt% are Newtonian fluids, and the viscosities are dependent on both the mass fraction and temperature. The differential scanning calorimetry (DSC) is employed to analyze the phase change characteristics of the PCE, and the results indicate large supercooling degree of water and PCM in the PCE. The melting temperature and latent heat of water in the PCE are much smaller than those of pure water. The thermal conductivities of the PCE with different mass fractions at different temperatures are measured by the transient hot-wire method. Furthermore, the energy transport characteristics of the PCEs are evaluated on the basis of the measured thermo-physical and transport properties. The results suggest that the PCEs show a drastic

Double container system for the transport and storage of radioactive materials

International Nuclear Information System (INIS)

Popp, F.W.; Pontani, B.; Ernst, E.

1987-01-01

The double container system consists of an inner storage container made of steel for the gastight inclusion of the radioactive material to be stored and an outer shielding container which ensures the necessary shielding and mechanical safety in handling and transport. A neutron moderator layer of material containing hydrogen, preferably polyethylene, is present in the annular gap between the outer shielding container and the inner storage container. In order to achieve good shielding with simultaneous very good heat conduction from the inside to the outside, the moderator layer consists of individual polyethylene rings stacked above one another. There is an H profile ring made of heat conducting metal material between each two polyethylene rings. The legs of the H profile ring surround the sides of the two polyethylene rings for fixing it. (orig.) [de

Advisory material for the IAEA regulations for the safe transport of radioactive material (1985 edition). 3. ed.

International Nuclear Information System (INIS)

1990-01-01

The IAEA Regulations for the Safe Transport of Radioactive Material provide standards for ensuring a high level of safety of people, property and the environment against radiation and criticality hazards as well as thermal effects associated with the transport of radioactive material. The basic requirements to be met are: Effective containment of radioactive material; Effective control of radiation emitted from the package; A subcritical condition for any fissile material; and Adequate dissipation of any heat generated within the package. Effective quality assurance and compliance assurance programmes are required, for example: (a) Appropriate and sound packages are used; (b) The activity of radioactive material in each package does not exceed the regulatory activity limit for that material and that package type; (c) The radiation levels external to, and the contamination levels on, surfaces of packages do not exceed the appropriate limits; (d) Packages are properly marked and labelled and transport documents are completed; (e) the number of packages containing radioactive material in a conveyance is within the regulatory limits; (f) Packages of radioactive material are stowed in conveyances and are stored at a safe distance from persons and photosensitive materials; (g) Only those transport and lifting devices which have been tested are used in loading, conveying and unloading packages of radioactive material; and (h) Packages of radioactive material are properly secured for transport. The control of the transport of radioactive materials may be necessary also for other reasons, e.g. safeguards control and physical protection of nuclear materials and control of a property. For radioactive materials having other dangerous properties, the regulations of Member States, modal conventions and agreements, and other relevant documents of international organizations need to be applied. A Member State may require in its national regulations that an additional approval be

Regulations for the safe transport of radioactive material. 1996 edition (revised)

International Nuclear Information System (INIS)

2000-01-01

Following a comprehensive review by panels of experts convened by the IAEA starting in 1991, a revised version of the IAEA Regulations for the Safe Transport of Radioactive Material (formerly Safety Series No. 6) was approved by the Board of Governors in September 1996. This publication supersedes all editions of the Regulations issued under Safety Series No. 6. By 1969, the Regulations had been adopted by almost all international organizations concerned with transport and used by many Member States for their own regulations. Through the worldwide adoption of the IAEA Regulations for all modes of transport, a very high standard of safety in transport has been achieved. In the revisions since the first edition, attempts have been made to find a balance between the need to take account of technical advances and operational experience, and the desirability of providing a stable framework of regulatory requirements. One of the aims of this approach is to allow packages designed to previous versions of the Regulations to continue to be used for a reasonable period of time. It is recognized that not all regulatory changes can be implemented simultaneously; Member States and international organizations are therefore invited, in adopting this revision, to provide for use of both the 'old' requirements and the 'new' ones during a period of transition that may last for a few years. It is further recommended that adoption of these revised Regulations occur within a period of five years from publication to achieve worldwide harmonization of their application. In implementing the provisions of these Regulations, it may be necessary for Member States to issue complementary national regulations. Except as necessary for solely domestic purposes, such national regulations should not conflict with these Regulations. For convenience, the requirements to be met for the transport of specified types of consignments are included in an abbreviated form as Schedules in this publication

Regulations for the safe transport of radioactive material. 1996 edition (revised)

International Nuclear Information System (INIS)

2002-01-01

Following a comprehensive review by panels of experts convened by the IAEA starting in 1991, a revised version of the IAEA Regulations for the Safe Transport of Radioactive Material (formerly Safety Series No. 6) was approved by the Board of Governors in September 1996. This publication supersedes all editions of the Regulations issued under Safety Series No. 6. By 1969, the Regulations had been adopted by almost all international organizations concerned with transport and used by many Member States for their own regulations. Through the worldwide adoption of the IAEA Regulations for all modes of transport, a very high standard of safety in transport has been achieved. In the revisions since the first edition, attempts have been made to find a balance between the need to take account of technical advances and operational experience, and the desirability of providing a stable framework of regulatory requirements. One of the aims of this approach is to allow packages designed to previous versions of the Regulations to continue to be used for a reasonable period of time. It is recognized that not all regulatory changes can be implemented simultaneously. Member States and international organizations are therefore invited, in adopting this revision, to provide for use of both the 'old' requirements and the 'new' ones during a period of transition that may last for a few years. It is further recommended that adoption of these revised Regulations occur within a period of five years from publication to achieve worldwide harmonization of their application. In implementing the provisions of these Regulations, it may be necessary for Member States to issue complementary national regulations. Except as necessary for solely domestic purposes, such national regulations should not conflict with these Regulations. For convenience, the requirements to be met for the transport of specified types of consignments are included in an abbreviated form as Schedules in this publication

CarbonSAFE Illinois - Macon County

Energy Technology Data Exchange (ETDEWEB)

Whittaker, Steve [University of Illinois; Illinois State Geological Survey

2017-08-03

CarbonSAFE Illinois is a a Feasibility study to develop an established geologic storage complex in Macon County, Illinois, for commercial-scale storage of industrially sourced CO2. Feasibility activities are focused on the Mt. Simon Storage Complex; a step-out well will be drilled near existing storage sites (i.e., the Midwest Geological Sequestration Consortium’s Illinois Basin – Decatur Project and the Illinois Industrial Carbon Capture and Storage Project) to further establish commercial viability of this complex and to evaluate EOR potential in a co-located oil-field trend. The Archer Daniels Midland facility (ethanol plant), City Water, Light, and Power in Springfield, Illinois (coal-fired power station), and other regional industries are potential sources of anthropogenic CO2 for storage at this complex. Site feasibility will be evaluated through drilling results, static and dynamic modeling, and quantitative risk assessment. Both studies will entail stakeholder engagement, consideration of infrastructure requirements, existing policy, and business models. Project data will help calibrate the National Risk Assessment Partnership (NRAP) Toolkit to better understand the risks of commercial-scale carbon storage.

Modification Of Carry-Blair Transport Media For Storage Salmonella typhi

Directory of Open Access Journals (Sweden)

Yati Supriatin

2016-09-01

Full Text Available The aim of this study was to determine transport media modification as alternative media to replace Carry Blair. One type of transport media that often use to carry faeces specimens suspected to contain Salmonella typhi is Carry-Blair media. Studies have been conducted experimentally by storing Salmonella typhi on alternative transport media with Peptone composition, disodium Phosphate, Sodium chloride, Calcium chloride, which is made using a semi-solid and Carry-Blair as a control. Three variety of storage was done (0 hour,6 hours,9 hours at a temperature 4⁰-8⁰C and then Salmonella typhi was inoculated in Salmonella Shigella Agar using spread plate technique incubated during 24 hours at 37⁰C, counted the number of colonies by the plate count method using the colony counter. The results of ANOVA could be concluded that modification media could be use as alternative media replace Carry-Blair at 6 hours. Based on regression correlation test was assumed that the Salmonella typhi bacteria still life at less than 11 hours 54 minutes.

The management system for the safe transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2008-01-01

The purpose of this Safety Guide is to provide information to organizations that are developing, implementing or assessing a management system for activities relating to the transport of radioactive material. Such activities include, but are not limited to, design, fabrication, inspection and testing, maintenance, transport and disposal of radioactive material packaging. This publication is intended to assist those establishing or improving a management system to integrate safety, health, environmental, security, quality and economic elements to ensure that safety is properly taken into account in all activities of the organization. Contents: 1. Introduction; 2. Management system; 3. Management responsibility; 4. Resource management; 5. Process implementation; 6. Measurement, assessment and improvement; Appendix: Graded approach for management systems for the safe transport of radioactive materials; Annex I: Two examples of management systems; Annex II: Examples of management system standards; Annex III: Example of a documented management system (or quality assurance programme) for an infrequent consignor; Annex IV: Example of a documented management system (or quality assurance programme) description for an infrequent carrier; Annex V: Example of a procedure for control of records; Annex VI: Example of a procedure for handling packages containing radioactive materials, including receipt and dispatch; Annex VII: Example of a packaging maintenance procedure in a complex organization; Annex VIII: Example of an internal audit procedure in a small organization; Annex IX: Example of a corrective and preventive action procedure

Nickel-hydrogen battery design for the Transporter Energy Storage Subsystem (TESS)

Science.gov (United States)

Lapinski, John R.; Bourland, Deborah S.

1992-01-01

Information is given in viewgraph form on nickel hydrogen battery design for the transporter energy storage subsystem (TESS). Information is given on use in the Space Station Freedom, the launch configuration, use in the Mobile Servicing Center, battery design requirements, TESS subassembley design, proof of principle testing of a 6-cell battery, possible downsizing of TESS to support the Mobile Rocket Servicer Base System (MBS) redesign, TESS output capacity, and cell testing.

High density fuel storage racks

International Nuclear Information System (INIS)

Groves, M.D.

1978-01-01

An apparatus is described for the safe and compact storage of nuclear fuel assemblies in an array of discrete open-ended neutron absorbing shields for which the theoretical minimum safe separation distance and cell pitch are known. Open-ended stainless steel end fittings are welded to each end of each shield and the end fittings are welded to each other in side-by-side relation, thereby reducing the cell pitch tolerance due to fabrication uncertainties. In addition, a multiplicity of ridges on the sides of each shield having a height equal to one half the theoretical minimum safe separation distance further reduce shield bowing tolerances. The net tolerance reduction permits a significant increase in the number of fuel assemblies that can be safely contained in a storage area of fixed size

Energy Storage Publications | Transportation Research | NREL

Science.gov (United States)

, California. 23 pp.; NREL Report No. PR-5400-60290. Optimal Sizing of Energy Storage and Photovoltaic Power (11) 2017 pp. 1095-1118. Life Prediction Model for Grid-Connected Li-ion Battery Energy Storage System Prediction Model for Grid-Connected Li-ion Battery Energy Storage System - Preprint Paper Source: Smith

European experience in transport/storage cask for vitrified residues

International Nuclear Information System (INIS)

Otton, Camille; Sicard, Damien

2007-01-01

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

Spent fuel storage and transport cask decontamination and modification. An overview of management requirements and applications based on practical experience

International Nuclear Information System (INIS)

1999-04-01

A large increase in the number of casks required for transport and/or storage of spent fuel is forecast into the next century. The principal requirement will be for increased number of storage and dual purpose (transport/storage) casks for interim storage of spent fuel prior to reprocessing or permanent disposal in both on-site and off-site storage facilities. Through contact with radioactive materials spent fuel casks will be contaminated on both internal and external surfaces. In broad terms, cask contamination management can be defined by three components: minimisation, prevention and decontamination. This publication is a compilation of international experience with cask contamination problems and decontamination practices. The objective is to present current knowledge and experience as well as developments, trends and potential for new applications in this field. Furthermore, the report may assist in new design or modification of existing casks, cask handling systems and decontamination equipment

Order No. 20558 of 6 May 1964 - Adoption of the IAEA rules for the safe transport of radioactive materials

International Nuclear Information System (INIS)

1964-01-01

This Order adopts the IAEA Regulations for the Safe Transport of radioactive Materials in Portugal, together with any subsequent modifications made to the Regulations pending the publication of regulations to be elaborated by the Commission for protection against ionizing radiation. (NEA) [fr

Long-Term Dry Storage of High Burn-Up Spent Pressurized Water Reactor (PWR) Fuel in TAD (Transportation, Aging, and Disposal) Containers

International Nuclear Information System (INIS)

Hwang, Yong Soo

2008-12-01

A TAD canister, in conjunction with specially-designed over-packs can accomplish the functions of transportation, aging, and disposal (TAD) in the management of spent nuclear fuel (SNF). Industrial dry cask systems currently available for SNF are licensed for storage-only or for dual-purpose (i.e., storage and transportation). By extending the function to include the indefinite storage and perhaps, eventual geologic disposal, the TAD canister would have to be designed to enhance, among others, corrosion resistance, thermal stability, and criticality-safety control. This investigative paper introduces the use of these advanced iron-based, corrosion-resistant materials for SNF transportation, aging, and disposal.The objective of this investigative project is to explore the interest that KAERI would research and develop its specific SAM coating materials for the TAD canisters to satisfy the requirements of corrosion-resistance, thermal stability, and criticality-controls for long-term dry storage of high burn-up spent PWR fuel

Safe management of waste from health-care activities

International Nuclear Information System (INIS)

Pruess, A.; Giroult, E.; Rushbrook, P.

1999-01-01

The waste produced in the course of health-care activities, from contaminated needles to radioactive isotopes, carries a greater potential for causing infection and injury than any other type of waste, and inadequate or inappropriate management is likely to have serious public health consequences and deleterious effects on the environment. This handbook - the result of extensive international consultation and collaboration - provides comprehensive guidance on safe, efficient, and environmentally sound methods for the handling and disposal of health-care wastes. The various categories of waste are clearly defined and the particular hazards that each poses are described. Considerable prominence is given to the careful planning that is essential for the success of waste management; workable means of minimizing waste production are outlined and the role of reuse and recycling of waste is discussed. Most of the text, however, is devoted to the collection, segregation, storage, transport, and disposal of wastes. Details of containers for each category of waste, labelling of waste packages, and storage conditions are provided, and the various technologies for treatment of waste and disposal of final residues are discussed at length. Advice is given on occupational safety for all personnel involved with waste handling, and a separate chapter is devoted to the closely related topic of hospital hygiene and infection control. The handbook pays particular attention to basic processes and technologies that are not only safe but also affordable, sustainable, and culturally appropriate. For health-care settings in which resources are severely limited there is a separate chapter on minimal programmes; this summarizes all the simplest and least costly techniques that can be employed for the safe management of health-care wastes. The guide is aimed at public health managers and policy-makers, hospital managers, environmental health professionals, and all administrators with an

Schedules of Provisions of the IAEA Regulations for the Safe Transport of Radioactive Material (2009 Ed.). Safety Guide

International Nuclear Information System (INIS)

2014-01-01

This Safety Guide is issued in support of Regulations for the Safe Transport of Radioactive Material (IAEA Safety Standards Series No. TS-R-1, 2009 Edition). It lists the paragraph numbers of the Transport Regulations that are relevant for specified types of consignment, classified according to their UN numbers. It does not provide additional recommendations. The intended users are consignors and consignees, carriers, shippers, regulators, and end users involved in the transport of radioactive material. A person or organization intending to transport a particular type of consignment of radioactive material must meet requirements in all sections of the Transport Regulations. This Safety Guide aids users by providing a listing of the relevant requirements of the Transport Regulations for each type of radioactive material, package or shipment. Once a consignor has classified the radioactive material to be shipped, the appropriate UN number can be assigned and the paragraph numbers of the requirements that apply for the shipment can be found in the corresponding schedule

Safety aspects of long-term dry interim storage of Type B spent fuel and high-level transport casks

International Nuclear Information System (INIS)

Wolff, D.; Probst, U.; Voelzke, H.; Droste, B.; Roedel, R.

2004-01-01

Based on the German decision to minimise transport of spent fuel casks between nuclear power plants, reprocessing plants and central storage facilities several on-site storage facilities were licensed until the end of 2003. Because of the large amount of Type B(U) transport casks which are going to be used for long-term interim storage the question of time-limited Type B(U) licence maintenance during the storage period of up to 40 years has been discussed under different aspects. This paper describes present technical aspects of the discussion. A main aspect of qualification of transport casks for interim storage is the long-term behaviour of the metallic seal-lid system. Here we present results from current long-term experimental tests with metallic 'Helicoflex' seals in which pool water is enclosed. This series of tests has been performed by the Federal Institute for Materials Research and Testing (BAM) on behalf of the Federal Office for Radiation Protection (BfS) since 2001. Finally, the paper presents a German concept for an exchange of experience, know-how and state-of-the-art between authorities and technical experts with regard to cask dispatch in nuclear facilities. BAM has taken over a central role in this so-called 'coordinating institution for cask dispatching information' ('KOBAF') which entails management of an online database of cask-specific documents and a technical working group meeting twice a year. The goal is to keep comparable technical standards for all nuclear sites and storage facilities which are going to load and dispatch casks of the same or similar types under the responsibility of different German state governments for the coming decades. (author)

Validation of CFD-methods to predict heat transfer and temperatures during the transport and storage of casks under a cover

International Nuclear Information System (INIS)

Leber, A.; Graf, W.; Hueggenberg, R.

2004-01-01

With respect to the transport of casks for radioactive material, the proof of the safe heat removal can be accomplished by validated calculation methods. The boundary conditions for thermal tests for type B packages are specified in the ADR based on the regulations defined by the International Atomic Energy Agency. The varying boundary conditions under transport or storage conditions are based on the varying thermal conditions true for different cask types. In most cases the cask will be transported in lying position under a cover (e.g. canopy or tarpaulin) and stored in standing position in an array with other casks. The main heat transport mechanisms are natural convection and thermal radiation. The cover or the storage building are furnished with vents that create an air flow, which will improve the natural convection. Depending on the thermal boundary conditions, the cask design and the heat power, about 50 - 95% of the heat power will be removed from the finned cask surface by natural convection. Consequently the convection by air flow is the main heat transport mechanism. The air flow can be approximated with analytical methods by solving the integral heat and flow balances for the domain. In a stationary state the overpressure due the buoyancy and the pressure loss in the flow resistances are equal. Based on the air flow, the relevant temperatures of the cask can be calculated in an iterative process. Due to the fast development of numerical calculation methods and computer hardware, the use of Computational- Fluid-Dynamics(CFD) calculations plays an important role. CFD-calculations are based on solving the equations of conservation (Navier-Stokes equations) using a finite element mesh or a finite volume mesh of the model. For a finned cask lying under a cover, where the main contributing element for heat removal is natural convection in combination with the thermal radiation, a CFD-calculation can be the most appropriate method. Common CFD-Codes are FLUENT

Safe storage of pesticides in Sri Lanka - identifying important design features influencing community acceptance and use of safe storage devices

DEFF Research Database (Denmark)

Weerasinghe, Manjula; Pieris, Ravi; Eddleston, Michael

2008-01-01

BACKGROUND: Self-poisoning with pesticides is the cause of an estimated 300,000 deaths annually in rural Asia. The great majority of these deaths are from impulsive acts of self-harm using pesticides that are readily available in the home. The secure storage of pesticides under lock has been...

Safety And Promotion in the Federal Aviation Administration- Enabling Safe and Successful Commercial Space Transportation

Science.gov (United States)

Repcheck, Randall J.

2010-09-01

The United States Federal Aviation Administration’s Office of Commercial Space Transportation(AST) authorizes the launch and reentry of expendable and reusable launch vehicles and the operation of launch and reentry sites by United States citizens or within the United States. It authorizes these activities consistent with public health and safety, the safety of property, and the national security and foreign policy interests of the United States. In addition to its safety role, AST has the role to encourage, facilitate, and promote commercial space launches and reentries by the private sector. AST’s promotional role includes, among other things, the development of information of interest to industry, the sharing of information of interest through a variety of methods, and serving as an advocate for Commercial Space Transportation within the United States government. This dual safety and promotion role is viewed by some as conflicting. AST views these two roles as complementary, and important for the current state of commercial space transportation. This paper discusses how maintaining a sound safety decision-making process, maintaining a strong safety culture, and taking steps to avoid complacency can together enable safe and successful commercial space transportation.

The medicines refrigerator and the importance of the cold chain in the safe storage of medicines.

Science.gov (United States)

Hatchett, Richard

2017-10-04

The medicines refrigerator is a common piece of equipment found in clinical areas. It is used to ensure specific medicines are safely stored within a narrow temperature range in line with manufacturers' instructions; this is usually between +2˚C and +8˚C, and ideally +5˚C. Drugs stored in the medicines refrigerator include: vaccines; insulin; chemotherapy drugs; topical preparations, such as some types of eye drops; and other treatments such as glucagon, which is used to manage severe hypoglycaemia. This article reviews the function of the medicines refrigerator and the checks required by healthcare practitioners to ensure that medicines remain safely stored and their effectiveness is maintained. It also outlines the medicines refrigeration procedure known as the 'cold chain', which includes the use of cold boxes or vaccine carriers to maintain the required temperature of medicines during transport from the manufacturer to user, or between healthcare departments. ©2012 RCN Publishing Company Ltd. All rights reserved. Not to be copied, transmitted or recorded in any way, in whole or part, without prior permission of the publishers.

Explanatory material for the IAEA regulations for the safe transport of radioactive material (1985 edition). 2. ed. (as amended 1990)

International Nuclear Information System (INIS)

1990-01-01

This publication is an updated version of the Second Edition of the Explanatory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (1985 Edition) and replaces all previous versions of Safety Series No. 7. This publication includes the changes to Safety Series No. 7 contained in the Regulations for the Safe Transport of Radioactive Material, 1985 Edition, Supplement 1988, as well as modifications adopted by the Review Panel that was convened in Vienna, 10-14 July 1989. For the convenience of the user, the old Safety Series style adopted in the original publication has been retained, although the old style has now been superseded by a new one, affecting the structure, the format and the cover of the Safety Series. It should be noted, however, that future editions will be published in the new style.

BWR - Spent Fuel Transport and Storage with the TNTM9/4 and TNTM24BH Casks

International Nuclear Information System (INIS)

Wattez, L.; Marguerat, Y.; Hoesli, C.

2006-01-01

The Swiss Nuclear Utilities have started in 2001 to store spent fuel in dry metallic dual-purpose casks at ZWILAG, the Swiss interim storage facility. BKW FMB Energy Ltd., the Muehleberg Nuclear Power Plant owner, is involved in this process and has elected to store its BWR spent fuel in a new high capacity dual-purpose cask, the TNeTeM24BH from the COGEMA Logistics/TRANSNUCLEAR TN TM 24 family. The Muehleberg BWR spent fuels are transported by road in a medium size shuttle transport cask and then transferred to a heavy transport/storage cask (dry transfer) in the hot cell of ZWILAG site. For that purpose, COGEMA Logistics designed and supplied: - Two shuttle casks, TN TM 9/4, mainly devoted to transport of spent fuel from Muehleberg NPP to ZWILAG. Licensed according to IAEA 1996, the TN TM 9/4 is a 40 ton transport cask, for 7 BWR high bum-up spent fuel assemblies. - A series of new high capacity dual-purpose casks, TN TM 24BH, holding 69 BWR spent fuels. Two transport campaigns took place in 2003 and 2004. For each campaign, ten TN TM 9/4 round trips are performed, and one TN TM 24BH is loaded. 5 additional TN TM 24BH are being manufactured for BKW, and the next transport campaigns are scheduled from 2006. The TN TM 24BH high capacity dual purpose cask and the TN TM 9/4 transport cask characteristics and capabilities will then be detailed. (authors)

Technology for the storage of radioactive materials packagings during maritime transport. Phase 1

International Nuclear Information System (INIS)

Ringot, C.; Chevalier, G.; Tomachevski, E.G.

1989-01-01

Following the accident of the M/S Mont Louis on August 25, 1984 carrying UF 6 cylinders, this report is a preliminary study of bibliographic data to help to define recommendations on packaging stowing for sea transport. Data on acceleration to take into account for normal or accidental transport conditions, safe areas on board that should be reserved for radioactive materials and accidents statistics are collected. Main information concerns: number of serious casualities or total losses to ships in European waters, accident causes, collision probability in function of mean distance between ships in the British Channel, selection of 8 reference accidents for future studies

Advisory material for the IAEA Regulations for the safe transport of radioactive material (1985 Edition). 3. ed.

International Nuclear Information System (INIS)

1987-01-01

The purpose of this document is to provide advice on the application of the provisions of the 1985 Edition of Safety Series No. 6 (concerning the IAEA Regulations for the Safe Transport of Radioactive Material) in order to help achieve compliance with the regulatory standards. This document also reflects the corrections and changes implemented by the 1986 Supplement to the Regulations for the Safe Transport of Radioactive Material. Its intent is to describe methods, techniques and practices (citing any appropriate national and international standards) which can be considered a means of satisfying certain requirements. It should always be read as offering 'a way' or 'ways' rather than 'the unique way' of achieving compliance. The information provided is to be considered purely advisory and never mandatory, except where a competent authority may require use of any part or parts of the text. This document provides information about the technical requirements of the Regulations and about the methods and technology which may be employed to satisfy them, for the benefit of designers and manufacturers of packagings, consignors, carriers, competent authorities and others, i.e. it provides 'how' information

Integrated management platform of nuclear fuel storage and transportation based on RFID

International Nuclear Information System (INIS)

Song Yafeng; Ma Yanqin; Chen Liyu; Jiang Yong; Wu Jianlei; Yang Haibo; Zhang Haiyan

2012-01-01

This paper describes integrated system model to improve work efficiency and optimize control measures of nuclear fuel storage and transportation, RFID and information integration technology is introduced, traditional management processes are innovated in data acquisition and monitoring fields as well, system solutions and design model are given by emphasizing on the following key technologies: cascade protection of information system, security protocol of RFID information, algorithm of collision. (authors)

Center for Electrocatalysis, Transport Phenomena, and Materials (CETM) for Innovative Energy Storage - Final Report

Energy Technology Data Exchange (ETDEWEB)

Soloveichik, Grigorii [GE Global Research, Niskayuna, New York (United States)

2015-11-30

EFRC vision. The direct use of organic hydrides in fuel cells as virtual hydrogen carriers that generate stable organic molecules, protons, and electrons upon electro-oxidation and can be electrochemically charged by re-hydrogenating the oxidized carrier was the major focus of the Center for Electrocatalysis, Transport Phenomena and Materials for Innovative Energy Storage (EFRC-ETM). Compared to a hydrogen-on-demand design that includes thermal decomposition of organic hydrides in a catalytic reactor, the proposed approach is much simpler and does not require additional dehydrogenation catalysts or heat exchangers. Further, this approach utilizes the advantages of a flow battery (i.e., separation of power and energy, ease of transport and storage of liquid fuels) with fuels that have system energy densities similar to current hydrogen PEM fuel cells. EFRC challenges. Two major EFRC challenges were electrocatalysis and transport phenomena. The electrocatalysis challenge addresses fundamental processes which occur at a single molecular catalyst (microscopic level) and involve electron and proton transfer between the hydrogen rich and hydrogen depleted forms of organic liquid fuel and the catalyst. To form stable, non-radical dehydrogenation products from the organic liquid fuel, it is necessary to ensure fast transport of at least two electrons and two protons (per double bond formation). The same is true for the reverse hydrogenation reaction. The transport phenomena challenge addresses transport of electrons to/from the electrocatalyst and the current collector as well as protons across the polymer membrane. Additionally it addresses prevention of organic liquid fuel, water and oxygen transport through the PEM. In this challenge, the transport of protons or molecules involves multiple sites or a continuum (macroscopic level) and water serves as a proton conducting medium for the majority of known sulfonic acid based PEMs. Proton transfer in the presence of

Organization and costs of repurchasing, transportation, warehousing and storage of raspberry fruit

Directory of Open Access Journals (Sweden)

Kalanović-Bulatović Branka

2015-01-01

Full Text Available Due to its characteristic, apart from nutritive and medical significance, raspberry is particularly important for our country in social and economic terms, since its export attracts foreign currency inflow. Since the quality of raspberry decreases rapidly after picking, it is utterly important that the whole process, from picking to cold storage of fruit, should be rationally organized, thus finally reducing the costs and increasing the production value. For these reasons precisely the research deals with organization of the entire process, from repurchase to cold storage of raspberry fruits, as well as the analysis of pertaining costs. Necessary information for the preparation of the paper has been obtained from cold storage plants engaged in raspberry storage and preservation. Necessary information has been gathered using several methods, viz: observation, interview and content analysis methods. Furthermore, analysis, comparison and calculation methods have also been used in the preparation of the paper. The raspberry fruit repurchase, transport and storage costs range from 1,6 to 1,8 EUR per kg, exclusive of storage (store-housing. To this one should add store-housing costs ranging from 0,009 to 0,013 EUR per kg on a monthly basis. Modern organization of production and communication between producers, repurchasers, processors and exporters is essential in order to decrease fluctuations in repurchase and sales price of fresh raspberry and its products and the improvement of overall financial effect of all links within the chain of this economy activity. Cold storage plants, even if of minor capacities, are beneficial not only for the immediate participants in the producer-buyer chain, but it also makes an important stimulating factor for rural development and economy of the country.

Interim and final storage casks

International Nuclear Information System (INIS)

Stumpfrock, L.; Kockelmann, H.

2012-01-01

The disposal of radioactive waste is a huge social challenge in Germany and all over the world. As is well known the search for a site for a final repository for high-level waste in Germany is not complete. Therefore, interim storage facilities for radioactive waste were built at plant sites in Germany. The waste is stored in these storage facilities in appropriate storage and transport casks until the transport in a final repository can be carried out. Licensing of the storage and transport casks aimed for use in the public space is done according to the traffic laws and for handling in the storage facility according to nuclear law. Taking into account the activity of the waste to be stored, different containers are in use, so that experience is available from the licensing and operation in interim storage facilities. The large volume of radioactive waste to be disposed of after the shut-down of power generation in nuclear power stations makes it necessary for large quantities of licensed storage and transport casks to be provided soon.

Greater-Than-Class C Low-Level Radioactive Waste Transportation Strategy report and institutional plan

Energy Technology Data Exchange (ETDEWEB)

Schmitt, R.C.; Tyacke, M.J.

1995-01-01

This document contains two parts. Part I, Greater-Than-Class-C Low-Level Radioactive Waste Transportation Strategy, addresses the requirements, responsibilities, and strategy to transport and receive these wastes. The strategy covers (a) transportation packaging, which includes shipping casks and waste containers; (b) transportation operations relating to the five facilities involved in transportation, i.e., waste originator, interim storage, dedicated storage, treatment, and disposal; (c) system safety and risk analysis; (d) routes; (e) emergency preparedness and response; and (o safeguards and security. A summary of strategic actions is provided at the conclusion of Part 1. Part II, Institutional Plan for Greater-Than-Class C Low-Level Radioactive Waste Packaging and Transportation, addresses the assumptions, requirements, and institutional plan elements and actions. As documented in the Strategy and Institutional Plan, the most challenging issues facing the GTCC LLW Program shipping campaign are institutional issues closely related to the strategy. How the Program addresses those issues and demonstrates to the states, local governments, and private citizens that the shipments can and will be made safely will strongly affect the success or failure of the campaign.

Greater-Than-Class C Low-Level Radioactive Waste Transportation Strategy report and institutional plan

International Nuclear Information System (INIS)

Schmitt, R.C.; Tyacke, M.J.

1995-01-01

This document contains two parts. Part I, Greater-Than-Class-C Low-Level Radioactive Waste Transportation Strategy, addresses the requirements, responsibilities, and strategy to transport and receive these wastes. The strategy covers (a) transportation packaging, which includes shipping casks and waste containers; (b) transportation operations relating to the five facilities involved in transportation, i.e., waste originator, interim storage, dedicated storage, treatment, and disposal; (c) system safety and risk analysis; (d) routes; (e) emergency preparedness and response; and (o safeguards and security. A summary of strategic actions is provided at the conclusion of Part 1. Part II, Institutional Plan for Greater-Than-Class C Low-Level Radioactive Waste Packaging and Transportation, addresses the assumptions, requirements, and institutional plan elements and actions. As documented in the Strategy and Institutional Plan, the most challenging issues facing the GTCC LLW Program shipping campaign are institutional issues closely related to the strategy. How the Program addresses those issues and demonstrates to the states, local governments, and private citizens that the shipments can and will be made safely will strongly affect the success or failure of the campaign

The ICRP 60 and the agency's regulations for the safe transport of radioactive material

International Nuclear Information System (INIS)

Biaggio, A.L.; Novo, R.G.

1993-01-01

The International Commission on Radiological Protection (ICRP) has adopted its new '1990 Recommendations of the International Commission on Radiological Protection' in November 1990, they were published in 1991 as 'ICRP Publication 60.' Two main scenarios are considered by the new ICRP's recommendations: a) Protection in proposed and continuing practices (further subdivided as protection against actual exposures and protection against potential exposures); and b) Protection by intervention. Although intervention means any activity in order to decrease the overall exposure, removing existing sources, modifying pathways or reducing the number of exposed individuals, in relation to the transport of radioactive materials, protection by intervention is related mainly to emergency planning, while protection against actual and potential exposures can be considered as the subject of most of the requirements of the 'Regulations for the Safe Transport of Radioactive Material', of the International Atomic Energy Agency (IAEA). The on-going revision of the IAEA Safety Series No. 9, which is aimed at putting this publication in line with the new ICRP recommendations will, for the first time, provide a convalidated radiological framework for the 1996 revision of the Agency Transport Regulations. However, to adapt to the transport area the radiological principles and criteria will require a significant effort and a carefully evaluation of the overall impact of each change proposed. (J.P.N.)

Ultimate storage of spent fuel elements from the AVR experimental nuclear power plant in the Asse Salt Mine

Energy Technology Data Exchange (ETDEWEB)

Wolf, J.

1975-02-15

The present paper is intended to serve as the basis for the licensing procedures both in respect of the transport and storage techniques and also for the ultimate storage itself. In regard to the technique it will be shown on the basis of design drawings and calculations that the handling, transport and storage of the fuel elements can be safely carried out in accordance with the regulations in force. In regard to the ultimate storage itself, since no highly radioactive wastes with a long-lived actinide content have yet been stored, it will be necessary to show that an unacceptable contamination of the biosphere will be avoided even in the long term under all anticipated conditions. It will further be necessary to show by calculations and suitable tests, in view of the radioactive gas and fissile material content, that no danger due to gas release from the fuel elements will arise during the operating life of the mine and that a nuclear criticality risk can be excluded for all time.

The IAEA regulations for the safe transport of radioactive material; new strategies for the future

International Nuclear Information System (INIS)

Selling, H.A.; Brittinger, M.T.M.

1993-01-01

This paper presents a historic review of 30 years experience with the IAEA's Regulations for the Safe Transport of Radioactive Material as the basis for regulatory control of those materials worldwide. It is demonstrated that the underlying principles and fundamental philosophy have proven their validity and have been the main reason for the excellent safety record of transport operations. The IAEA Regulations are currently halfway a comprehensive revision process aiming at the publication of a new edition by 1996. Although the main principles are likely to be maintained in the next edition of the Regulations, some developments in this area will undoubtedly have an effect on their structure. The main new developments are: the air transport of large quantities of radioactive material, requiring that a risk basis be established which is comparable with other modes of transport, transport of uranium hexafluoride requiring provisions which include the associated chemical hazards, the transport of large volumes of radioactive waste originating from decommissioning of nuclear power stations, and the influence of the new risk estimates for exposure to ionizing radiation and consequently the lower dose limits as recommended by ICRP. This paper will make an attempt to identify the problems associated with those developments, to outline its programme of activities intended to address the problems and to suggest possible solutions as recommended by the IAEA senior advisory group in this subject area. (J.P.N.)

Advisory group for the comprehensive review of the Agency's regulations for the safe transport of radioactive materials. Vienna, 1-12 September 1980

International Nuclear Information System (INIS)

Rawl, R.R.

1981-05-01

The discussions and recommendations for the revision of the IAEA regulations for the safe transport of radioactive materials are reported. The last revision of the regulations was published in 1973. The regulations have been adopted by all international bodies concerned with transport and by almost all individual Member States. In view of the developments in the means of transport, the volume of traffic and the nature of materials transported, Member States and international organizations rely on the Agency for advice and guidance. Hence the regulations are to be reviewed by 1983

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

International Nuclear Information System (INIS)

Powell, F.P.

1995-04-01

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

Safety and security considerations for the transport of spent teletherapy units

International Nuclear Information System (INIS)

Mallaupoma, Mario; Paez, Jose; Huatay, Luis; Cruz, Walter

2008-01-01

Among the applications of nuclear technology, a practice widely used and generates many benefits to society are teletherapy applications. Many of the teletherapy units used contain a source of cobalt-60 and after their useful life they have to be dismantled and transported to a safe place. In this case were transported two units with an activity of more than 75 TBq . This paper presents safety and security considerations for the transport of the teletherapy units according to the recommendations of actual state of art. It is described all facets of safe transport by means of a set of technical and administrative safety requirements and controls, including the actions required by the consignor and carrier. The main emphasis was put on the stages of transport operations that give rise to exposure to radiation like packing, preparation, loading, handling, storage in transit and movement of packages of radioactive material. On the other side some security actions were considered in order to prevent theft, sabotage or other malicious acts during the transport of the packages. As a conclusion it must be mentioned that both safety and security considerations are very important aspects that must be taking in account for the transport of high activity radioactive material. (author)

CO2 storage in Sweden

International Nuclear Information System (INIS)

Ekstroem, Clas; Andersson, Annika; Kling, Aasa; Bernstone, Christian; Carlsson, Anders; Liljemark, Stefan; Wall, Caroline; Erstedt, Thomas; Lindroth, Maria; Tengborg, Per; Edstroem, Mikael

2004-07-01

with the expansions of natural gas networks for Sweden should be looked for. Issues that need more deep studies are how the injection infrastructures for aquifers need to be modified compared to those used for oil fields, successively improved validation of CO 2 handling costs for Europe and Sweden, regarding i.a. ship transport and industrial compression and cooling of large CO 2 flows in connection to CO 2 capture. It is likely that the local environment would be affected by a possible leakage. Many organisms and ecosystems are sensitive to small changes in the CO 2 concentration. Knowledge exists on how humans, animals and plants would be affected by enhanced contents of carbon dioxide in their immediate surroundings, and on how the physical part of soils and water would be influenced by higher CO 2 concentrations. How individual ecosystems would be affected will have to be assessed based on the conditions in each specific system. Further studies are needed on consequences for ecosystems, especially for ecosystems in the ground, particularly those deep in the ground. Severe environmental damages (large short-term emissions that would damage the surrounding environment, i.e. concentrations around 25 % CO 2 ) would be limited to a few tens of meters from the plant and will therefore not need to be considered. No calculations have been performed for any transport means besides pipelines. Two parallels to CO 2 transport and storage are geothermic projects and natural gas pipelines. For geothermic projects there is a basic positive attitude already before the project start and the operations take place deep in the ground, i.e. at a safe distance from those concerned, and no threatening picture has been felt. No overall legal framework applicable to CO 2 transport and storage exist today, neither within the national Swedish law nor within international/European law. There are however adjacent legal frameworks mainly regarding transport. Providing that the construction of

Natural Gas Hydrate as a Storage Mechanism for Safe, Sustainable and Economical Production from Offshore Petroleum Reserves

Directory of Open Access Journals (Sweden)

Michael T. Kezirian

2017-06-01

Full Text Available Century Fathom presents an innovative process to utilize clathrate hydrates for the production, storage and transportation of natural gas from off-shore energy reserves in deep ocean environments. The production scheme was developed by considering the preferred state of natural gas in the deep ocean and addressing the hazards associated with conventional techniques to transport natural gas. It also is designed to mitigate the significant shipping cost inherent with all methods. The resulting proposed scheme restrains transport in the hydrate form to the ocean and does not attempt to supply energy to the residential consumer. Instead; the target recipients are industrial operations. The resulting operational concept is intrinsically safer by design; environmentally sustainable and significantly cost-effective compared with currently proposed schemes for the use of natural gas hydrates and has the potential to be the optimal solution for new production of reserves; depending on the distance to shore and capacity of the petroleum reserve. A potential additional benefit is the byproduct of desalinated water.

Cement-Based Materials for Nuclear Waste Storage

CERN Document Server

Cau-di-Coumes, Céline; Frizon, Fabien; Lorente, Sylvie

2013-01-01

As the re-emergence of nuclear power as an acceptable energy source on an international basis continues, the need for safe and reliable ways to dispose of radioactive waste becomes ever more critical. The ultimate goal for designing a predisposal waste-management system depends on producing waste containers suitable for storage, transportation and permanent disposal. Cement-Based Materials for Nuclear-Waste Storage provides a roadmap for the use of cementation as an applied technique for the treatment of low- and intermediate-level radioactive wastes.Coverage includes, but is not limited to, a comparison of cementation with other solidification techniques, advantages of calcium-silicate cements over other materials and a discussion of the long-term suitability and safety of waste packages as well as cement barriers. This book also: Discusses the formulation and production of cement waste forms for storing radioactive material Assesses the potential of emerging binders to improve the conditioning of problemati...

[The design of heat dissipation of the field low temperature box for storage and transportation].

Science.gov (United States)

Wei, Jiancang; Suin, Jianjun; Wu, Jian

2013-02-01

Because of the compact structure of the field low temperature box for storage and transportation, which is due to the same small space where the compressor, the condenser, the control circuit, the battery and the power supply device are all placed in, the design for heat dissipation and ventilation is of critical importance for the stability and reliability of the box. Several design schemes of the heat dissipation design of the box were simulated using the FLOEFD hot fluid analysis software in this study. Different distributions of the temperature field in every design scheme were constructed intimately in the present study. It is well concluded that according to the result of the simulation analysis, the optimal heat dissipation design is decent for the field low temperature box for storage and transportation, and the box can operate smoothly for a long time using the results of the design.

Implementation of the 1996 edition of the IAEA regulations for the safe transport of radioactive material

International Nuclear Information System (INIS)

Rawl, R.R.; Kervella, O.

1998-01-01

The International Atomic Energy Agency (IAEA) completed a 10 year and revision of its 'Regulations for the Safe Transport of Radioactive Material' with approval of the amendments by its Board of Governors in September 1996. The revised edition contains some important changes in the regulations, including: type C package requirements; provisions for low dispersible material; uranium hexafluoride packaging; exemption value specifications; operational requirements, including the creation of a criticality safety index and new proper shipping names/UN numbers. The 1996 edition of the IAEA regulations has been published and corresponding revisions now being considered by the international transport safety organizations and Member States. In particular, the United Nations Committee of Experts on the Transport of Dangerous Goods, International Civil Aviation Organization and International Maritime Organization and preparing revisions to take into account the revised Class 7 requirements. An effective date of 1 January 2001 has been recommended so that international and domestic requirements might come into force simultaneously, thereby avoiding disruptive out-of-phase implementation. (authors)

Environmental and thermodynamic evaluation of CO2 capture, transport and storage with and without enhanced resource recovery

International Nuclear Information System (INIS)

Iribarren, Diego; Petrakopoulou, Fontina; Dufour, Javier

2013-01-01

This study evaluates the environmental and thermodynamic performance of six coal-fired power plants with CO 2 capture and storage. The technologies examined are post-combustion capture using monoethanolamine, membrane separation, cryogenic fractionation and pressure swing adsorption, pre-combustion capture through coal gasification, and capture performing conventional oxy-fuel combustion. The incorporation of CO 2 capture is evaluated both on its own and in combination with CO 2 transport and geological storage, with and without beneficial use. Overall, we find that pre-combustion CO 2 capture and post-combustion through membrane separation present relatively low life-cycle environmental impacts and high exergetic efficiencies. When accounting for transport and storage, the environmental impacts increase and the efficiencies decrease. However, a better environmental performance can be achieved for CO 2 capture, transport and storage when incorporating beneficial use through enhanced oil recovery. The performance with enhanced coal-bed methane recovery, on the other hand, depends on the impact categories evaluated. The incorporation of methane recovery results in a better thermodynamic performance, when compared to the incorporation of oil recovery. The cumulative energy demand shows that the integration of enhanced resource recovery strategies is necessary to attain favourable life-cycle energy balances. - Highlights: ► Evaluation of six different CO 2 capture technologies for coal-fired power plants. ► Calculation of life-cycle environmental impacts and exergetic efficiencies. ► Suitability of post-combustion capture with membrane separation. ► Suitability of pre-combustion capture through coal gasification. ► Improved performance when incorporating enhanced resource recovery

Transport, acceptance, storage and handling of the itens of nuclear power plants

International Nuclear Information System (INIS)

1989-01-01

The norm aiming to establish the requirements applied to workers or organizations which participate of the activities of transport, acceptance, storage and handling of important itens for safety of nuclear power plants, is presented. The established requirements treat of protection and control necessary to assure that the quality of important itens for safety be it preserved from the end of fabrication until their incorporation to nuclear power plant. (M.C.K.) [pt

Liquefied natural gas (LNG) : production, storage and handling. 7. ed.

Energy Technology Data Exchange (ETDEWEB)

Kalra, S; Jaron, K; Adragna, M; Coyle, S; Foley, C; Hawryn, S; Martin, A; McConnell, J [eds.

2003-07-01

This Canadian Standard on the production, storage and handling of liquefied natural gas (LNG) was prepared by the Technical Committee on Liquefied Natural Gas under the jurisdiction of the Steering Committee on Oil and Gas Industry Systems and Materials. It establishes the necessary requirements for the design, installation and safe operation of LNG facilities. The Standard applies to the design, location, construction, operation and maintenance of facilities at any location of the liquefaction of natural gas and for the storage, vaporization, transfer, handling and truck transport of LNG. The training of personnel involved is also included as well as containers for LNG storage, including insulated vacuum systems. It includes non-mandatory guidelines for small LNG facilities but does not apply to the transportation of refrigerants, LNG by rail, marine vessel or pipeline. This latest edition contains changes in working of seismic design requirements and minor editorial changes to several clauses to bring the Standard closer to the US National Fire Protection Association's Committee on Liquefied Natural Gas Standard while maintaining Canadian regulatory requirements. The document is divided into 12 sections including: general requirements; plant site provisions; process equipment; stationary LNG storage containers; vaporization facilities; piping system and components; instrumentation and electrical services; transfer of LNG and refrigerants; fire protection, safety and security; and, operating, maintenance and personnel training. This Standard, like all Canadian Standards, was subject to periodic review and was most recently reaffirmed in 2003. 6 tabs., 6 figs., 3 apps.

Analysis and Design of Cryogenic Pressure Vessels for Automotive Hydrogen Storage

Science.gov (United States)

Espinosa-Loza, Francisco Javier

demonstrated a methodology for computationally efficient detailed modeling of cryogenic pressure vessels. The work continues with support of the US Department of Energy to demonstrate a new generation of cryogenic vessels anticipated to improve on the hydrogen storage performance figures previously imposed in this project. The author looks forward to further contributing to a future of long-range, inexpensive, and safe zero emissions transportation.

Hydrogeological problems in the ultimate storage of radioactive wastes

International Nuclear Information System (INIS)

Uerpmann, E.P.

1980-01-01

The following work shows how one can achieve the safe closure of ultimate-stored radioactive wastes by connecting a series of various barriers to the biosphere. The propagation of radionuclides by ground water is considered to be the most important long-term transport mechanism. Salt occurences in the Federal Republic of Germany are considered to be the best form suitable for end storage formations for known reasons. When not observing mining and hydrogeological knowledge, the danger of uncontrollable water flow in the end storage can arise from the water solubility of the salt rocks. Therefore the filling of salt mines and the subsequent procedures are dealt with in detail. The leading of radioactive nuclides is influenced by the properties of the ultimately stored wastes and by the quality of the remaining filling of the caves. These problems are dealt with in detail. A series of barriers to the closure of the underground caves are suggested and discussed. The most important barriers consist of the stability of the corresponding selected end storage structure. Possible arrangements of the storage cave are given which even after storage must maintain a high stability. Proposals are made on how the ultimately stored wastes can protect themselves against contact with free water or salt solutions. (orig.) [de

Gas Hydrate Storage of Natural Gas

Energy Technology Data Exchange (ETDEWEB)

Rudy Rogers; John Etheridge

2006-03-31

lower heat transfer rate in the internal heat exchanger than was designed. It is believed that the fins on the heat-exchanger tubes did not make proper contact with the tubes transporting the chilled glycol, and pairs of fins were too close for interior areas of fins to serve as hydrate collection sites. A correction of the fabrication fault in the heat exchanger fin attachments could be easily made to provide faster formation rates. The storage success with the POC process provides valuable information for making the process an economically viable process for safe, aboveground natural-gas storage.

Preliminary Study of RFID System for the LILW Transportation

International Nuclear Information System (INIS)

Kim, Dohyung; Lee, Unjang; Choi, Kyusup

2008-01-01

Radio-Frequency Identification (RFID) is an automatic identification method, relying on storing and remotely retrieving data using devices called RFID tags or transponders. In Korea, Low-to-Intermediate Level Radioactive Wastes (LILW) are planed to be disposed at Kyeonju disposal repository, and 100,000 LILW drums will be disposed for the first 10 years of disposal. Tracking of these LILW drums is one of the important parts for safe transportation. To track the LILW drums during the transport as well as storage and disposal, RFID can be the prospective method for tracking the LILW drums. In this report, RFID system is introduced to the LILW transport from the generation site to disposal site, and one possible RFID system is suggested as a preliminary study

Heat and Moisture Transport and Storage Parameters of Bricks Affected by the Environment

Science.gov (United States)

Kočí, Václav; Čáchová, Monika; Koňáková, Dana; Vejmelková, Eva; Jerman, Miloš; Keppert, Martin; Maděra, Jiří; Černý, Robert

2018-05-01

The effect of external environment on heat and moisture transport and storage properties of the traditional fired clay brick, sand-lime brick and highly perforated ceramic block commonly used in the Czech Republic and on their hygrothermal performance in building envelopes is analyzed by a combination of experimental and computational techniques. The experimental measurements of thermal, hygric and basic physical parameters are carried out in the reference state and after a 3-year exposure of the bricks to real climatic conditions of the city of Prague. The obtained results showed that after 3 years of weathering the porosity of the analyzed bricks increased up to five percentage points which led to an increase in liquid and gaseous moisture transport parameters and a decrease in thermal conductivity. Computational modeling of hygrothermal performance of building envelopes made of the studied bricks was done using both reference and weather-affected data. The simulated results indicated an improvement in the annual energy balances and a decrease in the time-of-wetness functions as a result of the use of data obtained after the 3-year exposure to the environment. The effects of weathering on both heat and moisture transport and storage parameters of the analyzed bricks and on their hygrothermal performance were found significant despite the occurrence of warm winters in the time period of 2012-2015 when the brick specimens were exposed to the environment.

Pipelines, inexpensive and safe mode of transport

Energy Technology Data Exchange (ETDEWEB)

Grover, D D

1979-01-01

Pipelines are the leading bulk commodity transporter and should play an even more important role in the future of energy transportation and distribution. As fossil fuel and low-cost uranium resources become depleted, it will be economical to produce hydrogen by electrolysis and transport it through underground pipelines to points of consumption. The cost would be only two to three times that of transporting natural gas per unit of heat energy and substantially less than the cost of transporting electric energy in overhead, extra-high-voltage transmission lines. Pipeline design, including economic pipe diameter; pipe material; operation by remote control and automation; cathodic protection; pipeline construction; and pipeline maintenance, particularly as regards the 1157 km long Oil India Pipeline, are discussed.

Midwestern High-Level Radioactive Waste Transportation Project. Highway infrastructure report

Energy Technology Data Exchange (ETDEWEB)

Sattler, L.R.

1992-02-01

In addition to arranging for storage and disposal of radioactive waste, the US Department of Energy (DOE) must develop a safe and efficient transportation system in order to deliver the material that has accumulated at various sites throughout the country. The ability to transport radioactive waste safely has been demonstrated during the past 20 years: DOE has made over 2,000 shipments of spent fuel and other wastes without any fatalities or environmental damage related to the radioactive nature of the cargo. To guarantee the efficiency of the transportation system, DOE must determine the optimal combination of rail transport (which allows greater payloads but requires special facilities) and truck transport Utilizing trucks, in turn, calls for decisions as to when to use legal weight trucks or, if feasible, overweight trucks for fewer but larger shipments. As part of the transportation system, the Facility Interface Capability Assessment (FICA) study contributes to DOE`s development of transportation plans for specific facilities. This study evaluates the ability of different facilities to receive, load and ship the special casks in which radioactive materials will be housed during transport In addition, the DOE`s Near-Site Transportation Infrastructure (NSTI) study (forthcoming) will evaluate the rail, road and barge access to 76 reactor sites from which DOE is obligated to begin accepting spent fuel in 1998. The NSTI study will also assess the existing capabilities of each transportation mode and route, including the potential for upgrade.

Storage, handling and internal transport of radioactive materials (fuel elements excepted) in nuclear power plants

International Nuclear Information System (INIS)

1983-06-01

The rule applies to storage and handling as well as to transport within the plant and to the exchange of - solid radioactive wastes, - liquid radioactive wastes, except for those covered by the rule KTA 3603, - radioactive components and parts which are planned to be mounted and dismounted until shutdown of the plant, - radioactive-contaminated tools and appliances, - radioactive preparations. The rule is to be applied within the fenced-in sites of stationary nuclear power plants with LWR or HTR including their transport load halls, as fas as these are situated so as to be approachable from the nuclear power station by local transport systems. (orig./HP) [de

The safe removal of frozen air from the annulus of an LH2 storage tank

Science.gov (United States)

Krenn, A.; Starr, S.; Youngquist, R.; Nurge, M.; Sass, J.; Fesmire, J.; Cariker, C.; Bhattacharya, A.

2015-12-01

Large Liquid Hydrogen (LH2) storage tanks are vital infrastructure for NASA. Eventually, air may leak into the evacuated and perlite filled annular region of these tanks. Although the vacuum level is monitored in this region, the extremely cold temperature causes all but the helium and neon constituents of air to freeze. A small, often unnoticeable pressure rise is the result. As the leak persists, the quantity of frozen air increases, as does the thermal conductivity of the insulation system. Consequently, a notable increase in commodity boil-off is often the first indicator of an air leak. Severe damage can result from normal draining of the tank. The warming air will sublimate which will cause a pressure rise in the annulus. When the pressure increases above the triple point, the frozen air will begin to melt and migrate downward. Collection of liquid air on the carbon steel outer shell may chill it below its ductility range, resulting in fracture. In order to avoid a structural failure, as described above, a method for the safe removal of frozen air is needed. A thermal model of the storage tank has been created using SINDA/FLUINT modelling software. Experimental work is progressing in an attempt to characterize the thermal conductivity of a perlite/frozen nitrogen mixture. A statistical mechanics model is being developed in parallel for comparison to experimental work. The thermal model will be updated using the experimental/statistical mechanical data, and used to simulate potential removal scenarios. This paper will address methodologies and analysis techniques for evaluation of two proposed air removal methods.

Results of ultrasonic testing evaluations on UF6 storage cylinders

International Nuclear Information System (INIS)

Lykins, M.L.

1997-02-01

The three site cylinder management program is responsible for the safe storage of the DOE owned UF 6 storage cylinders at PORTS, PGDP and at the K-25 site. To ensure the safe storage of the UF 6 in the cylinders, the structural integrity of the cylinders must be evaluated. This report represents the latest cylinder integrity investigation that utilized wall thickness evaluations to identify thinning due to atmospheric exposure

Guide to the design, testing and use of packaging for the safe transport of radioactive materials

International Nuclear Information System (INIS)

1976-01-01

This guide gives to designers, manufacturers and users of packaging, advice supplementary to, or in amplification of, the recommendations made by the International Atomic Energy Agency for the safe transport of radioactive materials as given in IAEA Safety Series No. 6 (1973) and the advisory material given in IAEA Safety Series No. 37 (1973). This guide should be read and used in conjunction with these recommendations, the appropriate national regulations and any applicable regulations or requirements of the carriers concerned. (author)

Spent fuel transport and storage system for NOK: The TN52L, TN97L, TN24 BHL and TN24 GB casks

International Nuclear Information System (INIS)

Wattez, L.; Verdier, A.; Monsigny, P.-A.

2007-01-01

NOK nuclear power plants in Switzerland, LEIBSTADT (KKL) BWR nuclear power plant and BEZNAU (KKB) PWR nuclear power plant have opted to ship spent fuel to a central facility called ZWILAG for interim storage. In the mid-nineties, COGEMA LOGISTICS was contracted by KKL for the supply of the TN52L and TN97L transport and storage casks for BWR fuel types. In 2003, KKL also ordered from COGEMA LOGISTICS the supply of six TN24 BHL transport and storage casks. This paper shows how all the three cask designs have responded to the KKL needs to ship and store BWR spent fuel. In addition, it highlights the already significant operational feedback of the TN52L and TN97L casks by the KKL and ZWILAG operators. In 2004, NOK also ordered three TN24 GB transport and storage casks for PWR fuel types. These casks are presently being manufactured. (author)

Contributions to optimization of storage and transporting industrial goods

Science.gov (United States)

Babanatsas, T.; Babanatis Merce, R. M.; Glăvan, D. O.; Glăvan, A.

2018-01-01

Optimization of storage and transporting industrial goods in a factory either from a constructive, functional, or technological point of view is a determinant parameter in programming the manufacturing process, the performance of the whole process being determined by the correlation realized taking in consideration those two factors (optimization and programming the process). It is imperative to take into consideration each type of production program (range), to restrain as much as possible the area that we are using and to minimize the times of execution, all of these in order to satisfy the client’s needs, to try to classify them in order to be able to define a global software (with general rules) that is expected to fulfil each client’s needs.

Quality assurance requirements in the testing of packages to be used for safe transportation of RAM

International Nuclear Information System (INIS)

Vieru, Gheorghe; Nistor, Viorica; Mihaiu, Ramona

2010-01-01

The quality of the Type A, B or C packages used for transport and storage of Radioactive Material (RAM) has to be proved by performing qualification tests in accordance with the Transport Regulations, within the Reliability and Testing Laboratory, Institute for Nuclear Research (INR) Pitesti, where has designed and developed a new Romanian Testing Facility. The qualifications testing are performed under a strict quality assurance programme based on the specific procedures prior approved by the Romanian Nuclear Regulatory Body CNCAN (National Commission for Nuclear Activity Control). This paper describe the quality assurance programme in accordance with the quality management system developed in order to meet the requirements provided by the national regulations as well as to the requirements of the IAEA's safety standard TS-R-1 related to testing of packages to be used for transport of RAM and also provides an overview of the new Romanian Testing Facilities for RAM Packages, developed by the INR's Reliability and Testing Laboratory within an Excellence Scientific Contract. (authors)

Evaluation and analysis method for natural gas hydrate storage and transportation processes

International Nuclear Information System (INIS)

Hao Wenfeng; Wang Jinqu; Fan Shuanshi; Hao Wenbin

2008-01-01

An evaluation and analysis method is presented to investigate an approach to scale-up a hydration reactor and to solve some economic problems by looking at the natural gas hydrate storage and transportation process as a whole. Experiments with the methane hydration process are used to evaluate the whole natural gas hydrate storage and transportation process. The specific contents and conclusions are as follows: first, batch stirring effects and load coefficients are studied in a semi-continuous stirred-tank reactor. Results indicate that batch stirring and appropriate load coefficients are effective in improving hydrate storage capacity. In the experiments, appropriate values for stirring velocity, stirring time and load coefficient were found to be 320 rpm, 30 min and 0.289, respectively. Second, throughput and energy consumption of the reactor for producing methane hydrates are calculated by mass and energy balance. Results show that throughput of this is 1.06 kg/d, with a product containing 12.4% methane gas. Energy consumption is 0.19 kJ, while methane hydrates containing 1 kJ heat are produced. Third, an energy consumption evaluation parameter is introduced to provide a single energy consumption evaluation rule for different hydration reactors. Parameter analyses indicate that process simplicity or process integration can decrease energy consumption. If experimental gas comes from a small-scale natural gas field and the energy consumption is 0.02 kJ when methane hydrates containing 1 kJ heat are produced, then the decrease is 87.9%. Moreover, the energy consumption evaluation parameter used as an economic criterion is converted into a process evaluation parameter. Analyses indicate that the process evaluation parameter is relevant to technology level and resource consumption for a system, which can make it applicable to economic analysis and venture forecasting for optimal capital utilization

Development of safety-relevant components for the transport and handling of final storage casks for waste from decommissioning

International Nuclear Information System (INIS)

Bruening, D.; Geiser, H.; Kloeckner, F.; Rittscher, D.; Schlesinger, H.J.

1992-10-01

The aim of the study was the development, construction and testing of a transportation system that is able to transport cylindrical waste containers as well as containers from the deliverer to the 'KONRAD' final repository. A transport palette has been developed that can carry two cylindrical waste containers with type B requirement or classification II. An Open-All-Container for the transport of palettes and 'KONRAD' containers has been developed. A storage of cylindrical waste containers and containers in the final repository is possible with the newly developed transportation system. Safety specifications of the transportation system have been passed successfully. (orig.). 30 refs., 8 tabs., 74 figs [de

Organic n-type materials for charge transport and charge storage applications.

Science.gov (United States)

Stolar, Monika; Baumgartner, Thomas

2013-06-21

Conjugated materials have attracted much attention toward applications in organic electronics in recent years. These organic species offer many advantages as potential replacement for conventional materials (i.e., silicon and metals) in terms of cheap fabrication and environmentally benign devices. While p-type (electron-donating or hole-conducting) materials have been extensively reviewed and researched, their counterpart n-type (electron-accepting or electron-conducting) materials have seen much less popularity despite the greater need for improvement. In addition to developing efficient charge transport materials, it is equally important to provide a means of charge storage, where energy can be used on an on-demand basis. This perspective is focused on discussing a selection of representative n-type materials and the efforts toward improving their charge-transport efficiencies. Additionally, this perspective will also highlight recent organic materials for battery components and the efforts that have been made to improve their environmental appeal.

Experimental Studies of Phase Change and Microencapsulated Phase Change Materials in a Cold Storage/Transportation System with Solar Driven Cooling Cycle

Directory of Open Access Journals (Sweden)

Lin Zheng

2017-11-01

Full Text Available The paper presents the different properties of phase change material (PCM and Microencapsulated phase change material (MEPCM employed to cold storage/transportation system with a solar-driven cooling cycle. Differential Scanning Calorimeter (DSC tests have been performed to analyze the materials enthalpy, melting temperature range, and temperature range of solidification. KD2 Pro is used to test the thermal conductivities of phase change materials slurry and the results were used to compare the materials heat transfer performance. The slurry flow characteristics of MEPCM slurry also have been tested. Furthermore, in order to analyze the improvement effect on stability, the stability of MEPCM slurry with different surfactants have been tested. The researches of the PCM and MEPCM thermal properties revealed a more prospective application for phase change materials in energy storage/transportation systems. The study aims to find the most suitable chilling medium to further optimize the design of the cold storage/transportation systems with solar driven cooling cycles.

Safety guide of safe use of industrial radiography

International Nuclear Information System (INIS)

1994-01-01

The objective of this guidance is to present general regulations for the safe use and radiation protection of industrial radiography. Storage and inspection of apparatus, personal instructions for working in radiography facilities are offered

The SERI solar energy storage program

Science.gov (United States)

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

1980-01-01

In support of the DOE thermal and chemical energy storage program, the solar energy storage program (SERI) provides research on advanced technologies, systems analyses, and assessments of thermal energy storage for solar applications in support of the Thermal and Chemical Energy Storage Program of the DOE Division of Energy Storage Systems. Currently, research is in progress on direct contact latent heat storage and thermochemical energy storage and transport. Systems analyses are being performed of thermal energy storage for solar thermal applications, and surveys and assessments are being prepared of thermal energy storage in solar applications. A ranking methodology for comparing thermal storage systems (performance and cost) is presented. Research in latent heat storage and thermochemical storage and transport is reported.

Recommended Practices for the Safe Design and Operation of Flywheels

Energy Technology Data Exchange (ETDEWEB)

Bender, Donald Arthur [Sandia National Lab. (SNL-CA), Livermore, CA (United States); Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2015-12-01

Flywheel energy storage systems are in use globally in increasing numbers . No codes pertaining specifically to flywheel energy storage exist. A number of industrial incidents have occurred. This protocol recommends a technical basis for safe flywheel de sign and operation for consideration by flywheel developers, users of flywheel systems and standards setting organizations.

Safe transport of irradiated fuel by sea

International Nuclear Information System (INIS)

Miller, M.L.

1997-01-01

The development is described of a transport system dedicated to the sea transport of irradiated nuclear fuel. The background is reviewed of why shipments were required and the establishment of a specialist shipping company, Pacific Nuclear Transport Limited. A description of the ships, flasks and other equipment utilised is provided, together with details of key procedures implemented to ensure safety and customer satisfaction. (Author)

Qualification testing facility for type A, B and C packages to be used for transport and storage of radioactive materials

International Nuclear Information System (INIS)

Vieru, G.; Nistor, V.; Vasile, A.; Cojocaru, V.

2009-01-01

In accordance with the Economic Commission for Europe-Committee on inland transport (ADR- European Agreement-concerning the international carriage of dangerous goods by road, 2007 Edition) the Safety and Security of the dangerous goods class No. 7 - Radioactive Materials during transport in all different modes - by road, by rail, by sea, by inland rivers or by air - have to be ensured at a very high level. The radioactive materials (RAM) packaging have to comply to all transport conditions, routine or in accident conditions, possibly to occur during transportation operations. It is well known that the safety in the transport of RAM is dependent on packaging appropriate for the contents being shipped rather than on operational and/or administrative actions required for the package. The quality of these packages - type A, B or C has to be proved by performing qualification tests in accordance with the Romanian nuclear regulation conditions provided by CNCAN Order no. 357/22.12.2005- N orms for a Safe Transport of Radioactive Material , the IAEA Vienna Recommendation (1, 2) stipulated in the Safety standard TS-R-1- Regulation for the Safe Transport of Radioactive Material, 2005 Edition, and other applicable international recommendations. The paper will describe the components of the designed testing facilities, and the qualification testing to be performed for all type A, B and C packages subjected to the testing Quality assurance and quality controls measures taken in order to meet technical specification provided by the design are also presented and commented. The paper concludes that the new Romanian Testing Facilities for RAM packages will comply with the national safe standards as well as with the IAEA applicable recommendation provided by the TS-R-1 safety standard. (authors)

Design assessment for transport and storage casks

International Nuclear Information System (INIS)

Janberg, K.; Diersch, R.; Spilker, H.; Dreier, G.

1995-01-01

The design assessment concerning the mechanical behaviour of transport and storage casks for radioactive material to fulfil nuclear safety criteria has to be based on two essential considerations: (1) Effective analysis of the stress-strain state of the cask components under both normal operational and test conditions including hypothetical accident scenarios with suitable accepted methods. (2) Economic estimation of the required properties and the structural state of the cask components with sufficient exactness. In an overview of the codes which are available at GNS/GNB for cask impact strength analyses (ANSYS, ADINA, VDI Codes), procedures and aspects of benchmarking and validation of calculation codes are described. The results of experimental full size cask drop test programs (CASTOR, POLLUX) and corresponding pre-test calculational analyses show the suitability of the codes used. The influence of dynamic effects on the mechanical properties of material (ductile cast iron, wood) has been investigated experimentally. By consideration of these dynamic values in strength analyses of casks at impact a good agreement between experimental and calculational results has been achieved. (author)

Constor steel concrete sandwich cask concept for transport and storage of spent nuclear fuel

International Nuclear Information System (INIS)

Diersch, R.; Dreier, G.; Gluschke, K.; Zubkov, A.; Danilin, B.; Fromzel, V.

1998-01-01

A spent nuclear fuel transport and storage sandwich cask concept has been developed together with the Russian company CKTI. Special consideration was given to an economical and effective way of manufacturing by using conventional mechanical engineering technologies and common materials. The main objective of this development was to fabricate these casks in countries not having highly specialized industries. Nevertheless, this sandwich cask concept fulfills both the internationally valid IAEA criteria for transportation and the German criteria for long-term intermediate storage. The basic cask concept has been designed for adaptation to different spent fuel specifications as well as handling conditions in the NPP. Recently, adaptations have been made for spent fuel from the RBMK and VVER reactors, and also for BWR spent fuel. The analyses of nuclear and thermal behaviour as well as of strength according to IAEA examination requirements (9-m-drop, 1-m-pin drop, 800 deg. C-fire test) and of the behaviour during accident scenarios at the storage site (drop, fire, gas cloud explosion, side impact) were carried out by means of recognized calculation methods and programmes. In a special experimental programme, the mechanical and thermodynamic properties of heavy concrete were examined and the reference values required for safety analyses were determined. The results of the safety analysis after drop tests according to IAEA-regulations as well as after 1 m-drops at the storage site were confirmed by means of a test programme using a scale model. The fabrication technology has been tested with help of a half scale cask model. The model has been prefabricated in Russia and completed in Germany. It has been shown that the CONSTOR cask can be fabricated in an effective and economic way. (authors)

Transport of Spent Nuclear Fuels, High and Intermediate Level Wastes: A Continuous Challenge

International Nuclear Information System (INIS)

Otton, C.; Blachet, L.

2009-01-01

For more than 45 years TN International has been involved in the radioactive materials transportation field. Since the beginning the used nuclear fuel transportation has been its core business. During all these years TN International, now part of AREVA, has been able to anticipate and fulfil the needs for new transport or storage casks design to fit the nuclear industry evolutions. A whole fleet of casks able to transport all the materials of the nuclear fuel cycle has been developed. In this presentation we will focus on the casks for the spent fuel, high level waste and intermediate level waste transportation. Answering to the constant evolution of the nuclear industry transport needs is a challenge that TN International faces routinely. Concerning the spent nuclear fuel transportation, TN International has developed in the early 80's a fleet of TN12 type casks fitted with several types of baskets able to safely transport all the spent fuel from the nuclear power plant or the research laboratories to AREVA La Hague plant. The current challenge is the design of a new transport cask generation taking into account the needs of the industry for the next 30 years. The replacement of the TN12 cask generation is to be scheduled as the regulations have changed and the fuel characteristics have evolved. The new generation of casks will take into account all the technical evolutions made during the TN12 thirty years of use. MOX spent fuel has now its dedicated cask: the TN112 which certificate of approval has been obtained in July 2008. This cask is able to transport 12 MOX spent fuel elements with a short cooling time. The first loading of the cask has been performed in 2008 in the EDF nuclear power plant of Saint-Laurent-des-Eaux. Concerning the high level waste such as the La Hague vitrified residues a whole fleet of casks has been developed such as the TN 28 VT dedicated to transport, the TN81 and TN85 dedicated to transport and storage. These casks have permitted the

Regulations of safe transport of radioactive material

International Nuclear Information System (INIS)

Patel, R.J.; Sumathi, E.

2017-01-01

BARC is a multi-disciplinary nuclear research organisation with facilities located at various parts of the country. The nuclear and radiological facilities in BARC include fuel fabrication facilities, nuclear research reactors, radiological laboratories, nuclear recycle facilities, waste management facilities and other associated facilities. RAdioactive Material (RAM) such as fresh nuclear fuel, irradiated fuel, radioactive sources, vitrified high level wastes, special nuclear material etc., are transported between these facilities either within the controlled premises or in public domain. In BARC the regulatory approval for the packages used for transport of RAM is issued by BARC Safety Council (BSC). Competent Authority for issuing the design approval for the BARC packages in public domain is Director, BARC. In this aspect BSC is assisted by Safety Review Committee-Transport of Radioactive Material (SRC-TRM) constituted by BSC entrusted with the mandate to ensure the packages are designed, manufactured and transported in accordance with the current regulations. This article summarizes the regulatory requirements for transport of RAM and experience in BARC facilities

Experience Of Using Metal-and-Concrete Cask TUK-108/1 For Storage And Transportation Of Spent Nuclear Fuel Of Decommissioned NPS

Energy Technology Data Exchange (ETDEWEB)

Barnes, E.; Dyer, R. [Environmental Protection Agency, Ronald Reagan Bldg. 3rd Floor 1200 Pennsylvania Av., NW Washington, D.C. 20024 (United States); Snipes, R. [Oak Ridge National Laboratories, VA (United States); Dolbenkov, V.G.; Guskov, V.D.; Korotkov, G.V. [Joint Stock Company ' KBSM' , 64 Lesnoy Av., St.Petersburg 194100 (Russian Federation); Makarchuk, T.F. [Joint Stock Company ' Atomstroyexport' , Potapovskiy str. 5, bld. 4, Moscow, 101990 (Russian Federation); Zakharchev, A.A. [State Corporation ' Rosatom' , 24-26 Ordinka St., Moscow, 100000 (Russian Federation)

2009-06-15

In past 10 years in Russia an intensive development of a new technology of management of spent nuclear fuel (SNF) has taken place. This technology is based on the concept of using a shielded cask which provides safety of its content (SNF) and meeting all other safety requirements to storage and transportation of SNF. Radiation protection against emission and non-propagation of activity outside the cask is ensured by the physical barriers such as all-metal or composite body, face work, inner structures to accommodate spent fuel assemblies (SFA), lids with sealing systems. Residual heat buildup is off-taken to the environment by natural way: emission and convection of surrounding air. The necessity in development of the cask technology of SNF management was conditioned by the situation at hand with defueling of Russian decommissioned nuclear-powered submarines (NPS) as the existed transport infrastructure and enterprises involved in fuel processing could not meet the demand for transportation and processing of SNF neither from reactors of all dismantled NPS, nor from reactors of NPS waiting for decommissioning. The US and Norway actively participated in the trilateral joint project with the Russian Federation aimed at creation of a cask prototype for interim storage and transportation of SNF of dismantled NPS. The 1.1 Project is a part of the Arctic Military Environmental Cooperation (AMEC) Program. In December 2000 the project was successfully completed by issuance of the certificate-permit for design and transportation of NP Submarine SNF. It was a first certified dual-purpose TUK from the MMC family. In these years 106 TUK-108/1 casks have been manufactured and supplied to PO Mayak, JSC CS Zvezda, JSC CS Zvezdochka and FSUE DalRAO. The storage pads for interim storage of TUK-108/1 have been built and currently are in operation on sites of SNF unloading from submarine reactors and SNF cask-loading such as JSC CS Zvezda, JSC CS Zvezdochka and FSUE DalRAO. In

Impact of downslope soil transport on carbon storage and fate in permafrost dominated landscapes

Science.gov (United States)

Shelef, E.; Rowland, J. C.; Wilson, C. J.; Altmann, G.; Hilley, G. E.

2014-12-01

A large fraction of high latitude permafrost-dominated landscapes are covered by soil mantled hillslopes. In these landscapes, soil organic carbon (SOC) accumulates and is lost through lateral transport processes. At present, these processes are not included in regional or global landsurface climate models. We present preliminary results of a soil transport and storage model over a permafrost dominated hillslope. In this model soil carbon is transported downslope within a mobile layer that thaws every summer. The model tracks soil transport and its subsequent storage at the hillslope's base. In a scenario where a carbon poor subsurface is blanketed by a carbon-rich surface layer, the progressive downslope soil transport can result in net carbon sequestration. This sequestration occurs because SOC is carried from the hilllsope's near-surface layer, where it is produced by plants and is capable of decomposing, into depositional sites at the hillslope's base where it is stored in frozen deposits such that it's decomposition rate is effectively zero. We use the model to evaluate the quantities of carbon stored in depositional settings during the Holocene, and to predict changes in sequestration rate in response to thaw depth thickening expected to occur within the next century due to climate-change. At the Holocene time scale, we show that a large amount of SOC is likely stored in depositional sites that comprise only a small fraction of arctic landscapes. The convergent topography of these sites makes them susceptible to fluvial erosion and suggests that increased fluvial incision in response to climate-change-induced thawing has the potential to release significant amounts of carbon to the river system, and potentially to the atmosphere. At the time scale of the next century, increased thaw depth may increase soil-transport rates on hillslopes and therefore increase SOC sequestration rates at a magnitude that may partly compensate for the carbon release expected from

Safe havens in Europe: Switzerland and the ten dwarfs

Directory of Open Access Journals (Sweden)

Martin Paldam

2013-12-01

Full Text Available Eleven safe havens exist in Europe providing offshore banking and low taxes. Ten of these states are very small while Switzerland is moderately small. All 11countries are richer than their large neighbors. It is shown that causality is from small to safe haven towealth, and that theoretically equilibriums are likely to exist where a certain regulation is substantially lower in a small country than in its big neighbor. This generates a large capital inflow to the safe havens. The pool of funds that may reach the safe havens is shown to be huge. It is far in excess of the absorptive capacity of the safe havens, but it still explains, why they are rich. Microstates offer a veil of anonymity to funds passing through, and Switzerland offers safe storage of funds.

BWR spent fuel transport and storage system for KKL: TN trademark 52L, TN trademark 97L, TN trademark 24 BHL

International Nuclear Information System (INIS)

Sicard, D.; Verdier, A.; Monsigny, P.A.

2004-01-01

The LEIBSTADT (KKL) nuclear power plant in Switzerland has opted to ship spent fuel to a central facility called ZWILAG for interim storage. In the mid-nineties, COGEMA LOGISTICS was contracted by KKL for the supply of the TN trademark a52L and TN trademark 97L transport and storage casks for BWR fuel types. In 2003, KKL also ordered from COGEMA LOGISTICS the supply of six TNae24 BHL transport and storage casks. This paper shows how all the three cask designs have responded to the KKL needs to ship and store BWR spent fuel. In addition, it highlights the already significant operational feedback of the TN trademark 52L and TN trademark 97L casks by the KKL and ZWILAG operators

Axial and radial water transport and internal water storage in tropical forest canopy trees.

Science.gov (United States)

Shelley A. James; Frederick C. Meinzer; Guillermo Goldstein; David Woodruff; Timothy Jones; Teresa Restom; Monica Mejia; Michael Clearwater; Paula. Campanello

2003-01-01

Heat and stable isotope tracers were used to study axial and radial water transport in relation to sapwood anatomical characteristics and internal water storage in four canopy tree species of a seasonally dry tropical forest in Panama. Anatomical characteristics of the wood and radial profiles of sap flow were measured at the base, upper trunk, and crown of a single...

Safety aspects of radioactive waste transportation and storage in the Republic of Moldova

International Nuclear Information System (INIS)

Gasca, Iu.

2009-01-01

A special attention continues to be given to the management of radioactive wastes. The National Department of Radioactive Waste Management is a unique institute in Moldova that deals with reception, transportation and storage of radioactive wastes. It collaborates with International Atomic Energy Agency. The management of low- and intermediate-level waste has remained permanently focused at the IAEA work. In 2003 IAEA supported the construction and technique of low-level and intermediate-level radioactive waste repository in Moldova. During 2003-2005 the US Department of Energy supported financing of planning and building of the underground storage for keeping the installations with high-level radioactive sources with all safety systems (signalization, video-monitoring). In 2008 the construction of radioactive wastes conditioning station was initiated with support of the US Embassy's Bureau for military cooperation

Design, construction and mounting of a container for transportation and storage of a closed plutonium glove box

International Nuclear Information System (INIS)

Aparicio, G.; Insegna, M.A.; Mathot, S.R.; Munoz, C.; Orlando, O.S.; Salguero, D.

1990-01-01

With the aim of confining a closed chemistry glove box (with reference to papers: 'Closure of an analytical chemistry glove box in alpha Laboratory' and 'Disconnection and transportation of a closed plutonium glove box to a controlled zone'), it was necessary to design and construct a container to assure transportation from its location (a controlled zone) up to a definitive storage place capable of supporting its posterior confinement. (Author) [es

A Multi-function Cask for At-Reactor Storage of Short-Cooled Spent Fuel, Transport, and Disposal

International Nuclear Information System (INIS)

Forsberg, C.W.

2004-01-01

The spent nuclear fuel (SNF) system in the United States was designed with the assumptions that SNF would be stored for several years in an at-reactor pool and then transported to reprocessing plants for recovery of fissile materials, that security would not be a major issue, and that the SNF burnups would be low. The system has evolved into a once-through fuel cycle with high-burnup SNF, long-term storage at the reactor sites, and major requirements for safeguards and security. An alternative system is proposed to better meet these current requirements. The SNF is placed in multi-function casks with the casks used for at-reactor storage, transport, and repository disposal. The cask is the handling package, provides radiation shielding, and protects the SNF against accidents and assault. SNF assemblies are handled only once to minimize accident risks, maximize security and safeguards by minimizing access to SNF, and reduce costs. To maximize physical protection, the cask body is constructed of a cermet (oxide particles embedded in steel, the same class of materials used in tank armor) and contains no cooling channels or other penetrations that allow access to the SNF. To minimize pool storage of SNF, the cask is designed to accept short-cooled SNF. To maximize the capability of the cask to reject decay heat and to limit SNF temperatures from short-cooled SNF, the cask uses (1) natural circulation of inert gas mixtures inside the cask to transfer heat from the SNF to the cask body and (2) an overpack with external natural-circulation, liquid-cooled fins to transfer heat from the cask body to the atmosphere. This approach utilizes the entire cask body area for heat transfer to maximize heat removal rates-without any penetrations through the cask body that would reduce the physical protection capabilities of the cask body. After the SNF has cooled, the cooling overpack is removed. At the repository, the cask is placed in a corrosion-resistant overpack before disposal

Plutonium safe handling

International Nuclear Information System (INIS)

Tvehlov, Yu.

2000-01-01

The abstract, prepared on the basis of materials of the IAEA new leadership on the plutonium safe handling and its storage (the publication no. 9 in the Safety Reports Series), aimed at presenting internationally acknowledged criteria on the radiation danger evaluation and summarizing the experience in the safe management of great quantities of plutonium, accumulated in the nuclear states, is presented. The data on the weapon-class and civil plutonium, the degree of its danger, the measures for provision of its safety, including the data on accident radiation consequences with the fission number 10 18 , are presented. The recommendations, making it possible to eliminate the super- criticality danger, as well as ignition and explosion, to maintain the tightness of the facility, aimed at excluding the radioactive contamination and the possibility of internal irradiation, to provide for the plutonium security, physical protection and to reduce irradiation are given [ru

BEAM TRANSPORT AND STORAGE WITH COLD NEUTRAL ATOMS AND MOLECULES

Energy Technology Data Exchange (ETDEWEB)

Walstrom, Peter L. [Los Alamos National Laboratory

2012-05-15

A large class of cold neutral atoms and molecules is subject to magnetic field-gradient forces. In the presence of a field, hyperfine atomic states are split into several Zeeman levels. The slopes of these curves vs. field are the effective magnetic moments. By means of optical pumping in a field, Zeeman states of neutral lithium atoms and CaH molecules with effective magnetic moments of nearly {+-} one Bohr magneton can be selected. Particles in Zeeman states for which the energy increases with field are repelled by increasing fields; particles in states for which the energy decreases with field are attracted to increasing fields. For stable magnetic confinement, field-repelled states are required. Neutral-particle velocities in the present study are on the order of tens to hundreds of m/s and the magnetic fields needed for transport and injection are on the order of in the range of 0.01-1T. Many of the general concepts of charged-particle beam transport carry over into neutral particle spin-force optics, but with important differences. In general, the role of bending dipoles in charged particle optics is played by quadrupoles in neutral particle optics; the role of quadrupoles is played by sextupoles. The neutralparticle analog of charge-exchange injection into storage rings is the use of lasers to flip the state of particles from field-seeking to field-repelled. Preliminary tracking results for two neutral atom/molecule storage ring configurations are presented. It was found that orbit instabilities limit the confinment time in a racetrack-shaped ring with discrete magnetic elements with drift spaces between them; stable behavior was observed in a toroidal ring with a continuous sextupole field. An alternative concept using a linear sextupole or octupole channel with solenoids on the ends is presently being considered.

TNTM85 and TNTM81 transports / storage flasks: An optimized solution for vitrified residues

International Nuclear Information System (INIS)

Sicard, D.; Verdier, A.; Dyck, P.

2006-01-01

By analyzing the evolution of burnup of spent fuel to be reprocessed, the high activity vitrified residues would not be transported in the existing flask designs. Therefore COGEMA LOGISTICS decided in the late nineties to develop a design with optimized capacity able to store and transport the most active and hottest canisters. The TN TM 85 flask shall permit in the near future in Germany the storage and the transport of the highest vitrified residues defining a thermal power of 56 kW. The challenge for the TN TM 85 flask design was that the geometry entry data were very restrictive and were combined with a fairly wide range set by COGEMA Specification 300AQ16 relative to vitrified residue canister. In addition, the cask had to fit as much as possible in the existing procedures for the TN TM 28 cask and TS 28 V cask, all along the logistics chain of loading, unloading, transport and maintenance. (authors)

A community-based cluster randomised trial of safe storage to reduce pesticide self-poisoning in rural Sri Lanka

DEFF Research Database (Denmark)

Pearson, Melissa; Konradsen, Flemming; Gunnell, David

2011-01-01

. One approach to reducing access to pesticides is for households to store pesticides in lockable "safe-storage" containers. However, before this approach can be promoted, evidence is required on its effectiveness and safety. Methods/Design A community-based cluster randomised controlled trial has been...... at the 5% significance level. Secondary outcomes will include the incidence of all pesticide poisoning and total self-harm. Discussion This paper describes a large effectiveness study of a community intervention to reduce the burden of intentional poisoning in rural Sri Lanka. The study builds on a strong...... partnership between provincial health services, local and international researchers, and local communities. We discuss issues in relation to randomisation and contamination, engaging control villages, the intervention, and strategies to improve adherence. Trial Registritation The trial is registered...

Neutron storage

International Nuclear Information System (INIS)

Strelkov, A.V.

2004-01-01

The report is devoted to neutron storage (NS) and describes the history of experiments on the NS development. Great attention is paid to ultracold neutron (UCN) storage. The experiments on the UCN generation, transport, spectroscopy, storage and detection are described. Experiments on searching the UCN electric-dipole moment and electric charge are continued. Possible using of UCN for studying the nanoparticles is discussed [ru

Storage and transport containers for radioactive medical materials

International Nuclear Information System (INIS)

Suthanthiran, K.

1989-01-01

This patent describes a storage and transport container for small-diameter ribbon-like lengths of material including radioactive substances for use in medical treatments, comprising: an exterior shell for radiation shielding metal having top and bottom members of radiation shielding metal integral therewith; radiation shielding metal extending downward from the top of the container and forming a central cavity, the central cavity being separate from the exterior shell material of the container and extending downwardly a distance less than the height of the container; a plurality of small diameter carrier tubes located within the interior of the container and having one end of each tube opening through one side of the container and the other end of such tube opening through the opposite lateral side of the container with the central portion of each tube passing under the central cavity; and a plug of radiation shielding metal removably located in the top the central cavity for shielding the radiation from radiation sources located within the container

Strategic planning for transportation under the NWPA

International Nuclear Information System (INIS)

Larson, D.; Miernyk, J.

1992-01-01

This paper reports that the western states have found strategic planning to be an effective approach for identifying activities, and the appropriate sequencing of activities, that should be undertaken in the development of a transportation system for shipping high-level waste and spent nuclear fuel to a repository or monitored retrievable storage (MRS) facility. The Western Interstate Energy Board's High-Level Radioactive Waste Committee works with the U.S. Department of Energy pursuant to a cooperative agreement on the development of a safe, publicly-acceptable transportation system. The Committee has developed a Strategic Plan and Schedule which: guides the scheduling and prioritization of the Committee's work; enhances understanding of the complex and interrelated activities that states believe should be undertaken in developing a transportation system for high-level radioactive materials; and provides states with an appropriate structure for evaluating DOE's responsiveness to state needs

Water transport in desert alluvial soil

International Nuclear Information System (INIS)

Kearl, P.M.

1982-04-01

Safe storage of radioactive waste buried in an arid alluvial soil requires extensive site characterization of the physical process influencing moisture movement which could act as a transport medium for the migration of radionuclides. The field portion of this study included an infiltration plot instrumented with thermocouple psychrometers and neturon moisture probe access holes. Baseline information shows a zone of higher moisture content at approximately 1.5 m (5 ft) in depth. A sprinkler system simulated a 500-year precipitation event. Results revealed water penetrated the soil to 0.9 m (2.9 ft). Due to the low moisture content, vapor transport was primarily responsible for water movement at this depth. Temperature gradients are substantially responsible for vapor transport by preferentially sorting water-vapor molecules from the surrounding air by using the soil as a molecular sieve. Adsorbed and capillary water vapor pressure increases in response to a temperature increase and releases additional water to the soil pore atmosphere to be diffused away

Regulations for the safe transport of radioactive materials

International Nuclear Information System (INIS)

Kgogo, Obonye

2016-04-01

The report provides insight and investigates whether Transport Regulations in Botswana follow international standards for transport of radioactive material. Radioactive materials are very useful in most of our activities and are manufactured in different countries, therefore end up traversing from one country to another and being transported in national roads .The IAEA regulation for the Transport of radioactive material is used as the reference guideline in this study. The current Regulations for Transport of radioactive material in Botswana do not cover all factors which need to be considered when transporting radioactive although they refer to IAEA regulations. Basing on an inadequacy of the regulations and category of radioactive materials in the country recommendations were made concerning security, packaging and worker training's. The regulations for the Transport of radioactive material in Botswana need to be reviewed and updated so that they can relate to international standard. (au)

US Department of Energy, Westinghouse Hanford Company ARECO cesium transportation plan

Energy Technology Data Exchange (ETDEWEB)

Clements, E.P., Westinghouse Hanford

1996-07-15

The U.S. Department of Energy (DOE) is committed to the safe, efficient, and cost-effective transportation of all materials that support its various programs and activities. DOE strives to ensure that hazardous materials (particularly radioactive),hazardous substances, and hazardous mixed waste are handled and transported in compliance with all applicable federal, state,tribal, and local rules and regulations. This plan outlines the activities and responsibilities of DOE and other agencies that will be followed to conclude a significant movement of radioactive cesium (Cs) chloride capsules in a safe and uneventful manner. DOE-Headquarters (DOE-HQ) has directed that Cs capsules manufactured at the Waste Encapsulation and Storage Facility (WESF) be returned to WESF, located at DOE`s Hanford Site in southeast Washington State. Currently, there are 25 Cs capsules at the Applied Radiant Energy Corporation (ARECO)facility utilized for the polymerization of wood products in Lynchburg, Virginia, that requires removal as part of the overall Cs capsule return effort. This plan has been prepared in cooperation with member states of the Western Governors` Association (WGA) and the Southern States Energy Board (SSEB);the Council of State Governments Midwestern Office; and the Confederated Tribes of the Umatilla Indian Reservations, through whose jurisdictions these shipments will pass, and is an example of DOE-HQ`s commitment to early coordination and substantive involvement in its decision-making processes. This transportation plan identifies responsibilities, requirements,and procedures to ensure the success of the capsule return program. The plan summarizes transportation activities,organizational responsibilities, emergency preparedness guidelines, and other methods for achieving safe transport.

Doses of the staff during the spent fuel assemblies transportation and storage in Nuhmos 56V concrete system

International Nuclear Information System (INIS)

Atoyan, V.; Muradyan, A.

2003-01-01

The NUHMOS 56V concrete system provides long-term interim storage (50 years) for spent fuel assemblies, which have been out of the reactor for a sufficient period of time. It consists from horizontal storage modules. The fuel assemblies are confined in a helium atmosphere by a canister containment pressure vessel. The canister is protected and shielded by a massive reinforced concrete module. Decay heat is removed from the canister and concrete module by a passive natural draft convection ventilation system. The project of storage does not foresee the radiation monitoring inside of building and around it. But we provided and realize the radiation monitoring program around storage, it includes tree phases: - determination the zero background around the building before storage put in exploiting; - monitoring of the radioactive particles in air (additional aspiration plant); dose rate monitoring by portable dosimeters and soil monitoring during the process of the fuel storage; - constantly after the completion the fuel storage process - monitoring of the radioactive particles in air (additional aspiration plant); dose rate monitoring by portable dosimeters, and soil monitoring. Also designed the dose rate monitoring by the dosimeter RME 3 with the transfer of data by radio channel to central monitor. The canistered spent fuel assemblies are transferred from the plant's spent fuel pool to the concrete storage modules in a transfer cask. The cask is aligned with the storage module and the canister and inserted into the module by means of a hydraulic ram. The system is a totally passive installation that is designed to provide shielding and safe confinement of spent fuel for a range of postulated accident conditions and natural phenomena. (authors)

Happy Trails: Transporting Children Safely.

Science.gov (United States)

Alexander, Nancy P.

1995-01-01

Given that state laws requiring child passenger restraints are often weak or poorly enforced and that misuse of child restraint systems is common among many adults, offers advice for educating parents, children, and caregivers about transportation safety. Discusses the selection and proper use of car seats, and stresses the importance of…

Combining computation and experiment to accelerate the discovery of new hydrogen storage materials

Science.gov (United States)

Siegel, Donald

2009-03-01

The potential of emerging technologies such as fuel cells (FCs) and photovoltaics for environmentally-benign power generation has sparked renewed interest in the development of novel materials for high density energy storage. For applications in the transportation sector, the demands placed upon energy storage media are especially stringent, as a potential replacement for fossil-fuel-powered internal combustion engines -- namely, the proton exchange membrane FC -- utilizes hydrogen as a fuel. Although hydrogen has about three times the energy density of gasoline by weight, its volumetric energy density (even at 700 bar) is roughly a factor of six smaller. Consequently, the safe and efficient storage of hydrogen has been identified as one of the key materials-based challenges to realizing a transition to FC vehicles. This talk will present an overview of recent efforts at Ford aimed at developing new materials for reversible, solid state hydrogen storage. A tight coupling between first-principles modeling and experiments has greatly accelerated our efforts, and several examples illustrating the benefits of this approach will be presented.

Health and Safety Aspects of Solid Biomass Storage, Transportation and Feeding

Energy Technology Data Exchange (ETDEWEB)

Koppejan, J. [Procede Biomass, Enschede (Netherlands); Loennermark, A.; Persson, H.; Larsson, I.; Blomqvist, P. [SP Technical Research Institute of Sweden, Boraas (Sweden); Arshadi, M.; Valencia-Reyes, E. [Swedish University of Agricultural Sciences, Uppsala (Sweden); Melin, S. [University of British Columbia, Vancouver, BC (Canada); Howes, Pat [AEA Group, London (United Kingdom); Wheeler, P. [Lend Lease, Sydney (Australia); Baxter, D. [Joint Research Institute JRC, European Commission EC, Brussels (Belgium); Nikolaisen, L. [Danish Technological Institute, Taastrup (Denmark)

2013-05-15

This publication focuses on the health and safety issues of the supply chain of solid biofuels with the objective to highlight commonly used mitigation methodologies to promote a better working environment when dealing with solid biofuels. It has been compiled as a joint effort by experts active in Tasks 32, 36, 37 and 40 of the IEA Bioenergy Agreement, with their own specific fields of expertise. Only through this cooperation, it was possible to touch upon the full range of issues in one publication that one may come across when developing projects in which solid biomass fuels are produced, traded or used. The properties of a biomass material and the intended use determine how the material should be safely transported and stored. Selfheating, off-gassing and dust explosions are significant challenges for the industry that have already resulted in significant losses of capital investments and even tragic loss of life. Likewise, exposure to biologically active material, such as moulds and spores may form a serious hazard for the health of workers involved. With the growth of the bioenergy sector, it is important not only that opportunities for bioenergy are implemented in an efficient and economic manner, but also safely.

Assessing the management system to demonstrate the safe of transport of radioactive material

Energy Technology Data Exchange (ETDEWEB)

Bruno, Natanael C.; Mattar, Patricia M.; Pontes, Andre T., E-mail: nbruno@cnen.gov.br, E-mail: pmattar@cnen.gov.br, E-mail: atpontes@id.uff.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil)

2017-11-01

Radioactive materials are used for medical purposes, to avoid greenhouse gas effect in energy production plants, food and other products sterilization, research and sophisticated measurement technologies. Transport of radioactive material involves a range of actors each one having specific responsibilities for safety. Through Management System, consignors and carriers fulfil objective evidences that safety requirements are met in practice, while compliance assurance programs allow regulatory bodies and/or competent authorities to demonstrate to society that public, workers and environment are protected. According to the International Atomic Energy Agency (IAEA), safety has to be achieved and maintained through an effective management system. This system should integrate all elements of management so that requirements for safety are established and applied consistently with other requirements, including those related to human performance, quality and security, and that safety is not compromised by other requirements or demands. Comissao Nacional de Energia Nuclear (CNEN), the Brazilian Regulatory Body for the safe transport of radioactive materials, adopt international standards to establish safety requirements deemed relevant for protection of health and minimization of danger to life and property, and to provide for the application of these standards. Seeking for continuous improvement, the adherence of the practices adopted by CNEN's Transport Safety Unit (TSU) against the recommendations from the IAEA was assessed. This assessment led to the elaboration of proposals for improvement as well as the identification of good practices. The methodology used to perform this assessment was the SARIS methodology, developed by the IAEA. This paper will describe the most relevant findings of this study. (author)

Assessing the management system to demonstrate the safe of transport of radioactive material

International Nuclear Information System (INIS)

Bruno, Natanael C.; Mattar, Patricia M.; Pontes, Andre T.

2017-01-01

Radioactive materials are used for medical purposes, to avoid greenhouse gas effect in energy production plants, food and other products sterilization, research and sophisticated measurement technologies. Transport of radioactive material involves a range of actors each one having specific responsibilities for safety. Through Management System, consignors and carriers fulfil objective evidences that safety requirements are met in practice, while compliance assurance programs allow regulatory bodies and/or competent authorities to demonstrate to society that public, workers and environment are protected. According to the International Atomic Energy Agency (IAEA), safety has to be achieved and maintained through an effective management system. This system should integrate all elements of management so that requirements for safety are established and applied consistently with other requirements, including those related to human performance, quality and security, and that safety is not compromised by other requirements or demands. Comissao Nacional de Energia Nuclear (CNEN), the Brazilian Regulatory Body for the safe transport of radioactive materials, adopt international standards to establish safety requirements deemed relevant for protection of health and minimization of danger to life and property, and to provide for the application of these standards. Seeking for continuous improvement, the adherence of the practices adopted by CNEN's Transport Safety Unit (TSU) against the recommendations from the IAEA was assessed. This assessment led to the elaboration of proposals for improvement as well as the identification of good practices. The methodology used to perform this assessment was the SARIS methodology, developed by the IAEA. This paper will describe the most relevant findings of this study. (author)

Efficacy of an anaerobic swab transport system to maintain aerobic and anaerobic microorganism viability after storage at -80 degrees C.

Science.gov (United States)

Musser, Jeffrey M B; Gonzalez, Rosa

2011-01-01

An Amies agar gel swab transport system was evaluated for its ability to maintain bacterial viability and relative quantity after freezing at -80°C. Nine American Type Culture Collection (ATCC) bacterial strains were used: 3 anaerobic strains (Propionibacterium acnes, Peptostreptococcus anaerobius, and Clostridium sporogenes) and 6 facultative or strict aerobic bacterial strains (Stenotrophomonas maltophilia, Escherichia coli ([ATCC 25922 and ATCC 11775], Salmonella enterica subsp. enterica serovar Typhimurium, Staphylococcus saprophyticus, and Lactobacillus casei). The bacterial species were chosen because they corresponded to bacteria identified in psittacine feces and cloacal samples. There were no significant differences between growth scores at baseline and after storage at -80°C for 40 days for any of the bacteria examined after 48 and 72 hr of incubation, with the exception of P. anaerobius. For P. anaerobius, there was a significant reduction (P < 0.001) in the growth score after storage at -80°C for 40 days from that of the baseline; however, the bacteria were still viable. The tested swab transport system may be useful when lengthy storage and transport times necessitate freezing samples prior to culture.

Transportation of high-level waste and spent fuel

International Nuclear Information System (INIS)

Carlson, J.H.; Lake, W.H.; Thompson, J.H.

1993-01-01

The Office of Civilian Radioactive Waste Management (OCRWM) transportation program is a multifaceted undertaking to transport spent nuclear fuel from commercial reactors to temporary and permanent storage facilities commencing in 1998. One of the significant ingredients necessary to achieving this goal is the development and acquisition of shipping casks. Efforts to design and acquire high capacity casks is ongoing, as are efforts to purchase casks that can be made available using current technology. By designing casks that are optimized to the specifications of the older cooler spent fuel that will be shipped, and by designing to current NRC requirements, OCRWM's new generation of spent fuel casks will be more efficient and at least as safe as current cask designs. (J.P.N.)

A present status for dry storage of spent nuclear fuel

Energy Technology Data Exchange (ETDEWEB)

Bang, K. S.; Lee, J. C.; Park, H. Y.; Seo, K. S

2003-04-01

National policy for management of a spent nuclear fuel does not establish in Korea yet. A storage capacity of a storage pool that is to store the spent nuclear fuel will be exceeded an amount of accumulation from the first Woljin nuclear power plant in 2007. Therefore it is necessary that dry storage facility is secured to store safely the spent nuclear fuel on site of the nuclear power plant until national policy for a back-end spent nuclear fuel cycle is established. In order to store safely spent nuclear fuel, it is important that the present status and technology on dry storage of spent nuclear fuel is looked over. Therefore, the present status on dry storage of spent nuclear fuel was analyzed so as to develop dry storage system and choose a proper dry storage method domestic.

Safe Detection System for Hydrogen Leaks

Energy Technology Data Exchange (ETDEWEB)

Lieberman, Robert A. [Intelligent Optical Systems, Inc., Torrance, CA (United States); Beshay, Manal [Intelligent Optical Systems, Inc., Torrance, CA (United States)

2012-02-29

Hydrogen is an "environmentally friendly" fuel for future transportation and other applications, since it produces only pure ("distilled") water when it is consumed. Thus, hydrogen-powered vehicles are beginning to proliferate, with the total number of such vehicles expected to rise to nearly 100,000 within the next few years. However, hydrogen is also an odorless, colorless, highly flammable gas. Because of this, there is an important need for hydrogen safety monitors that can warn of hazardous conditions in vehicles, storage facilities, and hydrogen production plants. To address this need, IOS has developed a unique intrinsically safe optical hydrogen sensing technology, and has embodied it in detector systems specifically developed for safety applications. The challenge of using light to detect a colorless substance was met by creating chemically-sensitized optical materials whose color changes in the presence of hydrogen. This reversible reaction provides a sensitive, reliable, way of detecting hydrogen and measuring its concentration using light from low-cost LEDs. Hydrogen sensors based on this material were developed in three completely different optical formats: point sensors ("optrodes"), integrated optic sensors ("optical chips"), and optical fibers ("distributed sensors") whose entire length responds to hydrogen. After comparing performance, cost, time-to-market, and relative market need for these sensor types, the project focused on designing a compact optrode-based single-point hydrogen safety monitor. The project ended with the fabrication of fifteen prototype units, and the selection of two specific markets: fuel cell enclosure monitoring, and refueling/storage safety. Final testing and development of control software for these markets await future support.

SQA of finite element method (FEM) codes used for analyses of pit storage/transport packages

Energy Technology Data Exchange (ETDEWEB)

Russel, E. [Lawrence Livermore National Lab., CA (United States)

1997-11-01

This report contains viewgraphs on the software quality assurance of finite element method codes used for analyses of pit storage and transport projects. This methodology utilizes the ISO 9000-3: Guideline for application of 9001 to the development, supply, and maintenance of software, for establishing well-defined software engineering processes to consistently maintain high quality management approaches.

Study of hydrogen vehicle storage in enclosed parking facilities

Energy Technology Data Exchange (ETDEWEB)

Belzile, M A [Transport Canada, Ottawa, ON (Canada). ecoTECHNOLOGY for Vehicles; Cook, S [Canadian Hydrogen and Fuel Cell Association, Vancouver, BC (Canada)

2009-07-01

This paper reported on a coordinated research program between Transport Canada and Hydrogen and Fuel Cells Canada that examines issues of hydrogen vehicle storage. The ecoTECHNOLOGY for Vehicles (eTV) program focuses on the safety issues of operating and storing hydrogen fuelled vehicles in enclosed parking facilities. The aim of the program is to review existing research, current building standards applied in Canada, standards applied to natural gas vehicles, and standards and recommended practices for the design of fuel cell vehicles. Any potential gaps in safety will be considered in the design of CFD modeling scenarios. Considerations that extend beyond previously performed studies include the effect of Canadian climate on vehicle safety and leak detection equipment, fail-safe mechanism performance, as well as analyses of the frequency of hydrogen leak occurrences and the probability of ignition. The results of the study will facilitate policy makers and authorities in making decisions regarding the storage of hydrogen fuelled vehicles as they become more popular.

Nuclear hydrogen production and its safe handling

International Nuclear Information System (INIS)

Chung, Hongsuk; Paek, Seungwoo; Kim, Kwang-Rag; Ahn, Do-Hee; Lee, Minsoo; Chang, Jong Hwa

2003-01-01

An overview of the hydrogen related research presently undertaken at the Korea Atomic Energy Research Institute are presented. These encompass nuclear hydrogen production, hydrogen storage, and the safe handling of hydrogen, High temperature gas-cooled reactors can play a significant role, with respect to large-scale hydrogen production, if used as the provider of high temperature heat in fossil fuel conversion or thermochemical cycles. A variety of potential hydrogen production methods for high temperature gas-cooled reactors were analyzed. They are steam reforming of natural gas, thermochemical cycles, etc. The produced hydrogen should be stored safely. Titanium metal was tested primarily because its hydride has very low dissociation pressures at normal storage temperatures and a high capacity for hydrogen, it is easy to prepare and is non-reactive with air in the expected storage conditions. There could be a number of potential sources of hydrogen evolution risk in a nuclear hydrogen production facility. In order to reduce the deflagration detonation it is necessary to develop hydrogen control methods that are capable of dealing with the hydrogen release rate. A series of experiments were conducted to assess the catalytic recombination characteristics of hydrogen in an air stream using palladium catalysts. (author)

Low-cost concepts for dry transfer of spent fuel and waste between storage and transportation casks

International Nuclear Information System (INIS)

Schneider, K.L.

1984-01-01

The federal government may provide interim storage for spent fuel from commercial nuclear power reactors that have used up their available storage capacity. One of the leading candidate concepts for this interim storage is to place spent fuel in large metal shielding casks. The Federal Interim Storage (FIS) site may not have the capability to transfer spent fuel from transportation casks to storage casks and vice versa. Thus, there may be an incentive to construct a relatively inexpensive but reliable intercask transfer system for use at an FIS site. This report documents the results of a preliminary 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 betwee 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). Information derived for each of the concepts is operating, capital and relocation costs; implementation and relocation time requirements; and overall characteristics

Why Do Parents with Toddlers Store Poisonous Products Safely?

Directory of Open Access Journals (Sweden)

Tinneke M. J. Beirens

2010-01-01

Full Text Available Unintentional poisoning is a major cause of nonfatal injuries in children aged 0–24 months. Associations between self-reported habits on the child safe storage of medication and cleaning products and family, and psychosocial factors were assessed, using a model based on the Protection Motivation Theory. By identifying correlates of safety behavior in this manner, more insight in factors which influence this behavior is obtained. Health promotion activities in order to promote safety behavior should address these factors in order to increase the effectiveness of the health message. Data were gathered from a cross-sectional survey using self-administered questionnaires, mailed to a population sample of 2470 parents with toddlers. The results indicate that the promotion of safe storage of medication and cleaning products should address the family situation, personal cognitive factors as well as social factors. Interventions should particularly focus on parents' self-efficacy of storing poisonous products in a child safe manner and on the vulnerability of their child in their home concerning an unintentional poisoning incident.

Influence of forest and rangeland management on anadromous fish habitat in Western North America: water transportation and storage of logs.

Science.gov (United States)

J.R. Sedell; W.S. Duval

1985-01-01

Environmental effects of water transportation of logs in western North America include the historical driving of logs in rivers and streams, and the current dumping, sorting, transportation, and storage of logs in rivers and estuaries in British Columbia and southeastern Alaska. The historical discussion focuses on habitat losses and volumes of...

Burnup credit for storage and transportation casks

International Nuclear Information System (INIS)

Wells, A.H.

1988-01-01

The application of burnup credit to storage and transportation cask licensing results in a significant improvement in cask capacity and an associated reduction of the cost per kilogram of uranium in the cask contents. The issues for licensing with burnup credit deal primarily with the treatment of fission product poisons and methods of verification of burnup during cask operations. Other issues include benchmarking of cross-section sets and codes and the effect of spatial variation of burnup within an assembly. The licensing of burnup credit for casks will be complex, although the criticality calculations are not themselves difficult. Attention should be directed to the use of fission product poisons and the uncertainties that they introduce. Verification of burnup by measurements will remove some of the concerns for criticality safety. Calculations for burnup credit casks should consider rod-to-rod and axial variations of burnup, as well as variability of burnable poisons it they are used in the assembly. In spite of the complexity of cask burnup credit licensing issues, these issues appear to be resolvable within the current state of the art of criticality safety

Concerning the order of the Ministry of Transport for the amendment to part of the Rules for the Vehicle Transportation of Nuclear Fuel, the Rules for Ship Transportation and Storage of Dangerous Objects, and the Rules for the Enforcement of the Aviation Act

International Nuclear Information System (INIS)