Application of electron irradiation to food containers and packaging materials

International Nuclear Information System (INIS)

Ueno, Koji

2010-01-01

Problems caused by microbial contamination and hazardous chemicals have attracted much attention in the food industry. The number of systems such as hygienic management systems and Hazard Analysis Critical Control Point (HACCP) systems adopted in the manufacturing process is increasing. As manufacturing process control has become stricter, stricter control is also required for microbial control for containers and packaging materials (from disinfection to sterilization). Since safe and reliable methods for sterilizing food containers and packaging materials that leave no residue are required, electron beam sterilization used for medical equipment has attracted attention from the food industry. This paper describes an electron irradiation facility, methods for applying electron beams to food containers and packaging materials, and products irradiated with electron beams. (author)

Packaging of hazardous materials and their transport in national and international road, rail, sea and air transport. Summaries of papers. Gefahrgutverpackung und deren Befoerderung im nationalen und internationalen Strassen-, Schienen-, See- und Luftverkehr. Kurzfassungen der Referate

Energy Technology Data Exchange (ETDEWEB)

1986-01-01

The packaging and transport of hazardous goods demands a high degree of knowledge and responsibility from those involved. The symposium aims to refresh and bring up to date this knowledge with contributions about the legal fundamentals for packaging for the transport of hazardous goods; classification of materials; examination, licensing and identification of packaging; responsibilities, hability, irregularities, insurance; compatibility of filling materials; hazardous goods as additional packaging; re-use, re-conditioning, recycling, waste management, etc. (orig./HSCH).

Packaging and transportation manual. Chapter on the packaging and transportation of hazardous and radioactive waste

International Nuclear Information System (INIS)

1998-03-01

The purpose of this chapter is to outline the requirements that Los Alamos National Laboratory employees and contractors must follow when they package and ship hazardous and radioactive waste. This chapter is applied to on-site, intra-Laboratory, and off-site transportation of hazardous and radioactive waste. The chapter contains sections on definitions, responsibilities, written procedures, authorized packaging, quality assurance, documentation for waste shipments, loading and tiedown of waste shipments, on-site routing, packaging and transportation assessment and oversight program, nonconformance reporting, training of personnel, emergency response information, and incident and occurrence reporting. Appendices provide additional detail, references, and guidance on packaging for hazardous and radioactive waste, and guidance for the on-site transport of these wastes

Packaging and transportation manual. Chapter on the packaging and transportation of hazardous and radioactive waste

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-03-01

The purpose of this chapter is to outline the requirements that Los Alamos National Laboratory employees and contractors must follow when they package and ship hazardous and radioactive waste. This chapter is applied to on-site, intra-Laboratory, and off-site transportation of hazardous and radioactive waste. The chapter contains sections on definitions, responsibilities, written procedures, authorized packaging, quality assurance, documentation for waste shipments, loading and tiedown of waste shipments, on-site routing, packaging and transportation assessment and oversight program, nonconformance reporting, training of personnel, emergency response information, and incident and occurrence reporting. Appendices provide additional detail, references, and guidance on packaging for hazardous and radioactive waste, and guidance for the on-site transport of these wastes.

Regulatory and extra-regulatory testing to demonstrate radioactive material packaging safety

International Nuclear Information System (INIS)

Ammerman, D.J.

1997-01-01

Packages for the transportation of radioactive material must meet performance criteria to assure safety and environmental protection. The stringency of the performance criteria is based on the degree of hazard of the material being transported. Type B packages are used for transporting large quantities of radioisotopes (in terms of A 2 quantities). These packages have the most stringent performance criteria. Material with less than an A 2 quantity are transported in Type A packages. These packages have less stringent performance criteria. Transportation of LSA and SCO materials must be in open-quotes strong-tightclose quotes packages. The performance requirements for the latter packages are even less stringent. All of these package types provide a high level of safety for the material being transported. In this paper, regulatory tests that are used to demonstrate this safety will be described. The responses of various packages to these tests will be shown. In addition, the response of packages to extra-regulatory tests will be discussed. The results of these tests will be used to demonstrate the high level of safety provided to workers, the public, and the environment by packages used for the transportation of radioactive material

Effectiveness of Awareness Package on Occupational Health Hazards among Ragpickers of New Delhi, India.

Science.gov (United States)

Agarwalla, Rashmi; Pathak, Rambha; Singh, Mitasha; Islam, Farzana; Parashar, Mamta

2017-01-01

Ragpickers are informal workers who collect recyclable materials to earn a small wage on daily basis. They work in vulnerable conditions and awareness regarding occupational and environmental hazard is essential for them. To study the effectiveness of awareness program on various occupational health hazards among the ragpickers. This interventional study was conducted from May through October 2016 among the ragpickers living near field practice area of Department of Community Medicine and those living in slum areas around HAHC Hospital, New Delhi, India. The awareness regarding occupational and environmental health hazards was assessed using a pretested and predesigned pro forma. Snowball sampling technique was used to select the ragpickers from the various areas. Health awareness and education package was designed for the ragpickers. The package was delivered by medical officers and health workers. A posttest assessment was done 2 weeks after the awareness activity. Among 150 ragpickers, there was significant improvement in knowledge immediate post training on knowledge of occupational hazard and hygiene. Efforts should be put to develop training materials on occupation and environmental health and injury issue relating to waste management.

Radioactive material package test standards and performance requirements - public perception

International Nuclear Information System (INIS)

Pope, R.B.; Shappert, L.B.; Rawl, R.R.

1992-01-01

This paper addresses issues related to the public perception of the regulatory test standards and performance requirements for packaging and transporting radioactive material. Specifically, it addresses the adequacy of the package performance standards and testing for Type B packages, which are those packages designed for transporting the most hazardous quantities and forms of radioactive material. Type B packages are designed to withstand accident conditions in transport. To improve public perception, the public needs to better understand: (a) the regulatory standards and requirements themselves, (b) the extensive history underlying their development, and (c) the soundness of the technical foundation. The public needs to be fully informed on studies, tests, and analyses that have been carried out worldwide and form the basis of the regulatory standards and requirements. This paper provides specific information aimed at improving the public perception of packages test standards

78 FR 16044 - Hazardous Materials Packaging-Composite Cylinder Standards; Public Meeting

Science.gov (United States)

2013-03-13

... Toughiry, Engineering and Research Division, Office of Hazardous Materials Safety, Pipeline and Hazardous... the HMR, ISO 11119 Parts-1, -2 and -3, contain design, construction and testing requirements that are.../permits-approvals/special-permits . II. Public Meeting Topics During this public meeting, PHMSA will...

77 FR 24885 - Hazardous Materials; Miscellaneous Amendments (RRR)

Science.gov (United States)

2012-04-26

... special provisions, clarify the lab pack requirements for temperature-controlled materials, and revise the... in Dewar flasks. Clarify the lab pack provisions in Sec. 173.12 pertaining to temperature-controlled... shipping names, hazard classes, packing groups, special provisions, packaging authorizations, air transport...

77 FR 22504 - Hazardous Materials; Packages Intended for Transport by Aircraft

Science.gov (United States)

2012-04-16

... Convention on International Civil Aviation--also known as the Chicago Convention. Future inconsistencies with... known as the Chicago Convention. Future inconsistencies with international transport standards may... material release. Releases of hazardous materials can result in explosions or fires, while radioactive...

Expert systems for the transportation of hazardous and radioactive materials

International Nuclear Information System (INIS)

Luce, C.E.; Clover, J.C.; Ferrada, J.J.

1994-01-01

Under the supervision of the Transportation Technologies Group which is in the Chemical Technology Division at Oak Ridge National Laboratory, an expert system prototype for the transportation and packaging of hazardous and radioactive materials has been designed and developed. The development of the expert system prototype focused on using the combination of hypermedia elements and the Visual Basic trademark programming language. Hypermedia technology uses software that allows the user to interact with the computing environment through many formats: text, graphics, audio, and full-motion video. With the use of hypermedia, a user-friendly prototype has been developed to sort through numerous transportation regulations, thereby leading to the proper packaging for the materials. The expert system performs the analysis of regulations that an expert in shipping information would do; only the expert system performs the work more quickly. Currently, enhancements in a variety of categories are being made to the prototype. These include further expansion of non-radioactive materials, which includes any material that is hazardous but not radioactive; and the addition of full-motion video, which will depict regulations in terms that are easy to understand and which will show examples of how to handle the materials when packaging them

Edible packaging materials.

Science.gov (United States)

Janjarasskul, Theeranun; Krochta, John M

2010-01-01

Research groups and the food and pharmaceutical industries recognize edible packaging as a useful alternative or addition to conventional packaging to reduce waste and to create novel applications for improving product stability, quality, safety, variety, and convenience for consumers. Recent studies have explored the ability of biopolymer-based food packaging materials to carry and control-release active compounds. As diverse edible packaging materials derived from various by-products or waste from food industry are being developed, the dry thermoplastic process is advancing rapidly as a feasible commercial edible packaging manufacturing process. The employment of nanocomposite concepts to edible packaging materials promises to improve barrier and mechanical properties and facilitate effective incorporation of bioactive ingredients and other designed functions. In addition to the need for a more fundamental understanding to enable design to desired specifications, edible packaging has to overcome challenges such as regulatory requirements, consumer acceptance, and scaling-up research concepts to commercial applications.

Food Packaging Materials

Science.gov (United States)

1978-01-01

The photos show a few of the food products packaged in Alure, a metallized plastic material developed and manufactured by St. Regis Paper Company's Flexible Packaging Division, Dallas, Texas. The material incorporates a metallized film originally developed for space applications. Among the suppliers of the film to St. Regis is King-Seeley Thermos Company, Winchester, Ma'ssachusetts. Initially used by NASA as a signal-bouncing reflective coating for the Echo 1 communications satellite, the film was developed by a company later absorbed by King-Seeley. The metallized film was also used as insulating material for components of a number of other spacecraft. St. Regis developed Alure to meet a multiple packaging material need: good eye appeal, product protection for long periods and the ability to be used successfully on a wide variety of food packaging equipment. When the cost of aluminum foil skyrocketed, packagers sought substitute metallized materials but experiments with a number of them uncovered problems; some were too expensive, some did not adequately protect the product, some were difficult for the machinery to handle. Alure offers a solution. St. Regis created Alure by sandwiching the metallized film between layers of plastics. The resulting laminated metallized material has the superior eye appeal of foil but is less expensive and more easily machined. Alure effectively blocks out light, moisture and oxygen and therefore gives the packaged food long shelf life. A major packaging firm conducted its own tests of the material and confirmed the advantages of machinability and shelf life, adding that it runs faster on machines than materials used in the past and it decreases product waste; the net effect is increased productivity.

Module 13: Bulk Packaging Shipments by Highway

International Nuclear Information System (INIS)

Przybylski, J.L.

1994-07-01

The Hazardous Materials Modular Training Program provides participating United States Department of Energy (DOE) sites with a basic, yet comprehensive, hazardous materials transportation training program for use onsite. This program may be used to assist individual program entities to satisfy the general awareness, safety training, and function specific training requirements addressed in Code of Federal Regulation (CFR), Title 49, Part 172, Subpart H -- ''Training.'' Module 13 -- Bulk Packaging Shipments by Highway is a supplement to the Basic Hazardous Materials Workshop. Module 13 -- Bulk Packaging Shipments by Highway focuses on bulk shipments of hazardous materials by highway mode, which have additional or unique requirements beyond those addressed in the ten module core program. Attendance in this course of instruction should be limited to those individuals with work experience in transporting hazardous materials utilizing bulk packagings and who have completed the Basic Hazardous Materials Workshop or an equivalent. Participants will become familiar with the rules and regulations governing the transportation by highway of hazardous materials in bulk packagings and will demonstrate the application of these requirements through work projects and examination

78 FR 69745 - Safety and Security Plans for Class 3 Hazardous Materials Transported by Rail

Science.gov (United States)

2013-11-20

... material (considering the material's underlying chemical properties, corrosivity, and other characteristics) is fundamental to ensuring the selection of proper packaging and that the hazards of the materials...

Quality Assurance Program Plan for the Hazardous Materials Transportation and Packaging Program. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Calihan, T.W. III; Votaw, E.F.

1995-05-01

This QAPP covers only the implementation accomplished through Level I and II manuals. It covers the quality affecting activities identified in USDOE orders (both HQ and Richland Operations Office), US DOT, US EPA, and NRC regulations, IAEA guidelines, and the WHC manuals. It covers activities related to hazardous materials transportation performed on and off the Hanford site under the jurisdictional authority of WHC. (Hazardous materials include radioactive, hazardous waste, and mixed waste.)

Quality Assurance Program Plan for the Hazardous Materials Transportation and Packaging Program. Revision 1

International Nuclear Information System (INIS)

Calihan, T.W. III; Votaw, E.F.

1995-01-01

This QAPP covers only the implementation accomplished through Level I and II manuals. It covers the quality affecting activities identified in USDOE orders (both HQ and Richland Operations Office), US DOT, US EPA, and NRC regulations, IAEA guidelines, and the WHC manuals. It covers activities related to hazardous materials transportation performed on and off the Hanford site under the jurisdictional authority of WHC. (Hazardous materials include radioactive, hazardous waste, and mixed waste.)

Packaging based on polymeric materials

Directory of Open Access Journals (Sweden)

Jovanović Slobodan M.

2005-01-01

Full Text Available In the past two years the consumption of common in the developed countries world wide (high tonnage polymers for packaging has approached a value of 50 wt.%. In the same period more than 50% of the packaging units on the world market were made of polymeric materials despite the fact that polymeric materials present 17 wt.% of all packaging materials. The basic properties of polymeric materials and their environmental and economical advantages, providing them such a position among packaging materials, are presented in this article. Recycling methods, as well as the development trends of polymeric packaging materials are also presented.

The radioactive materials packaging handbook: Design, operations, and maintenance

International Nuclear Information System (INIS)

Shappert, L.B.; Bowman, S.M.; Arnold, E.D.

1998-01-01

As part of its required activities in 1994, the US Department of Energy (DOE) made over 500,000 shipments. Of these shipments, approximately 4% were hazardous, and of these, slightly over 1% (over 6,400 shipments) were radioactive. Because of DOE's cleanup activities, the total quantities and percentages of radioactive material (RAM) that must be moved from one site to another is expected to increase in the coming years, and these materials are likely to be different than those shipped in the past. Irradiated fuel will certainly be part of the mix as will RAM samples and waste. However, in many cases these materials will be of different shape and size and require a transport packaging having different shielding, thermal, and criticality avoidance characteristics than are currently available. This Handbook provides guidance on the design, testing, certification, and operation of packages for these materials

The radioactive materials packaging handbook: Design, operations, and maintenance

Energy Technology Data Exchange (ETDEWEB)

Shappert, L.B.; Bowman, S.M. [Oak Ridge National Lab., TN (United States); Arnold, E.D. [Lockheed Martin Energy Systems, Oak Ridge, TN (United States)] [and others

1998-08-01

As part of its required activities in 1994, the US Department of Energy (DOE) made over 500,000 shipments. Of these shipments, approximately 4% were hazardous, and of these, slightly over 1% (over 6,400 shipments) were radioactive. Because of DOE`s cleanup activities, the total quantities and percentages of radioactive material (RAM) that must be moved from one site to another is expected to increase in the coming years, and these materials are likely to be different than those shipped in the past. Irradiated fuel will certainly be part of the mix as will RAM samples and waste. However, in many cases these materials will be of different shape and size and require a transport packaging having different shielding, thermal, and criticality avoidance characteristics than are currently available. This Handbook provides guidance on the design, testing, certification, and operation of packages for these materials.

19 CFR 191.13 - Packaging materials.

Science.gov (United States)

2010-04-01

... 19 Customs Duties 2 2010-04-01 2010-04-01 false Packaging materials. 191.13 Section 191.13 Customs... (CONTINUED) DRAWBACK General Provisions § 191.13 Packaging materials. (a) Imported packaging material... packaging material when used to package or repackage merchandise or articles exported or destroyed pursuant...

75 FR 45195 - Office of Hazardous Materials Safety; Notice of Applications for Modification of Special Permit

Science.gov (United States)

2010-08-02

... permits (e.g. to provide for additional hazardous materials, packaging design changes, additional mode of... compressed oxygen without rigid outer packaging when no other means of transportation exist. 14860-M Alaska... authorizing the transportation in commerce of compressed oxygen without rigid outer packaging when no other...

Materials for advanced packaging

CERN Document Server

Wong, CP

2017-01-01

This second edition continues to be the most comprehensive review on the developments in advanced electronic packaging technologies, with a focus on materials and processing. Recognized experts in the field contribute to 22 updated and new chapters that provide comprehensive coverage on various 3D package architectures, novel bonding and joining techniques, wire bonding, wafer thinning techniques, organic substrates, and novel approaches to make electrical interconnects between integrated circuit and substrates. Various chapters also address advances in several key packaging materials, including: Lead-free solders Flip chip underfills Epoxy molding compounds Conductive adhesives Die attach adhesives/films Thermal interface materials (TIMS) Materials for fabricating embedded passives including capacitors, inductors, and resistors Materials and processing aspects on wafer-level chip scale package (CSP) and MicroElectroMechanical system (MEMS) Contributors also review new and emerging technologies such as Light ...

Alternate Materials In Design Of Radioactive Material Packages

International Nuclear Information System (INIS)

Blanton, P.; Eberl, K.

2010-01-01

This paper presents a summary of design and testing of material and composites for use in radioactive material packages. These materials provide thermal protection and provide structural integrity and energy absorption to the package during normal and hypothetical accident condition events as required by Title 10 Part 71 of the Code of Federal Regulations. Testing of packages comprising these materials is summarized.

49 CFR 173.24 - General requirements for packagings and packages.

Science.gov (United States)

2010-10-01

... identifiable (without the use of instruments) release of hazardous materials to the environment; (2) The effectiveness of the package will not be substantially reduced; for example, impact resistance, strength... significant chemical or galvanic reaction between the materials and contents of the package. (3) Plastic...

77 FR 36607 - Office of Hazardous Materials Safety Notice of Applications for Modification of Special Permit

Science.gov (United States)

2012-06-19

... modification of special permits (e.g. to provide for additional hazardous materials, packaging design changes... hazardous materials. 12102-M EQ Industrial 49 CFR 173.56(i); To modify the special Services, Inc. 173.56(b... 4.1. 13102-M Robertshaw Industrial 49 CFR 173.150(b); To modify the special Products dba 173.222(c...

Study on hazardous substances contained in radioactive waste

International Nuclear Information System (INIS)

Kuroki, Ryoichiro; Takahashi, Kuniaki

2008-01-01

It is necessary that the technical criteria is established concerning waste package for disposal of the TRU waste generated in Japan Atomic Energy Agency. And it is important to consider the criteria not only in terms of radioactivity but also in terms of chemical hazard and criticality. Therefore the environmental impact of hazardous materials and possibility of criticality were investigated to decide on technical specification of radioactive waste packages. The contents and results are as following. (1) Concerning hazardous materials included in TRU waste, regulations on disposal of industrial wastes and on environmental preservation were investigated. (2) The assessment methods for environmental impact of hazardous materials included in radioactive waste in U.K, U.S.A. and France were investigated. (3) The parameters for mass transport assessment about migration of hazardous materials in waste packages around disposal facilities were compiled. And the upper limits of amounts of hazardous materials in waste packages to satisfy the environmental standard were calculated with mass transport assessment for some disposal concepts. (4) It was suggested from criticality analysis for waste packages in disposal facility that the occurrence of criticality was almost impossible under the realistic conditions. (author)

The development of an enhanced strain measurement device to support testing of radioactive material packages

International Nuclear Information System (INIS)

Uncapkher, W.L.; Arviso, M.

1995-01-01

Radioactive material package designers use structural testing to verify and demonstrate package performance. A major part of evaluating structural response is the collection of reliable instrumentation measurement data. Over the last four decades, Sandia National Laboratories (SNL) has been actively involved in the development, testing, and evaluation of measurement devices for a broad range of applications, resulting in the commercialization of several measurement devices commonly used today. SNL maintains an ongoing program sponsored by the US Department of Energy (DOE) to develop and evaluate measurement devices to support testing of packages used to transport radioactive or hazardous materials. The development of the enhanced strain measurement device is part of this program

9 CFR 381.144 - Packaging materials.

Science.gov (United States)

2010-01-01

... to health. All packaging materials must be safe for the intended use within the meaning of section..., from the packaging supplier under whose brand name and firm name the material is marketed to the... distinguishing brand name or code designation appearing on the packaging material shipping container; must...

49 CFR 172.312 - Liquid hazardous materials in non-bulk packagings.

Science.gov (United States)

2010-10-01

... offered or intended for transportation by aircraft, packages containing flammable liquids in inner... offered or intended for transportation by aircraft, packages containing flammable liquids in inner... hermetically sealed inner packagings. (6) Packages containing liquid infectious substances in primary...

75 FR 57830 - Office of Hazardous Materials Safety; Notice of Applications for Modification of Special Permit

Science.gov (United States)

2010-09-22

... permits (e.g. to provide for additional hazardous materials, packaging design changes, additional mode of... special permit Application No. Docket No. Applicant affected thereof 7951-M ConAgra Foods, 49 CFR To... outer packaging when no other means of transportation exist. 14953-M Applied 49 CFR To modify the...

Regulatory Requirements to Combat Illicit Trafficking of Hazardous Materials

International Nuclear Information System (INIS)

Hussein, A.Z.; Zakaria, Kh.M.

2011-01-01

Since more than a decade illicit Trafficking of hazardous ( CBRNE), materials ( chemical, biological, radiological, nuclear and explosive ) has been identified as a key threat in national, regional, inter regional and international strategies. An Effective response to hazardous materials (CBRNE) risk and threat were realized to require a very high level of cooperation and coordination between various governments and their responsible organizations and authorities of regional and international partner. While improper policy of actions may easily be exploited by non- state members to (CBRNE) trafficking which may lead to develop weapon of mass destruction (WMD). Such strategy are of paramount important between all levels of the states and among regional agreements through comprehensive tailored assistance packages (e.g. export control, illicit trafficking of hazardous materials, redirection of scientist, emergency planning, crisis response safety and security culture. Capacity building, action plans and instruments for stability are necessary actions for efficient combating against illicit trafficking of hazardous materials. Regarding the needs of assessment phase, assistance must be based on data collection, analysis and prioritization of implanting the regulatory controls. Several activities have to be conducted to reduce CBRNE threat. The one- by- one approach, covering either nuclear and radioactive or chemical or biological materials has to be implanted on the country basis performance to mitigate CBRNE hazardous risk. On several consequent phases of intervention dealing with CBRNE risk mitigation the country has to establish a network of local, regional and international capabilities. Such network is setting up the mechanism for the country needs identifications, the guidelines for data collection, for data platform maintenance and update, the data assessment and the competent and operative organizations. This network will be to strengthen the long - term

Effects of mixed waste simulants on transportation packaging plastic components

International Nuclear Information System (INIS)

Nigrey, P.J.; Dickens, T.G.

1994-01-01

The purpose of hazardous and radioactive materials packaging is to, enable these materials to be transported without posing a threat to the health or property of the general public. To achieve this aim, regulations have been written establishing general design requirements for such packagings. While no regulations have been written specifically for mixed waste packaging, regulations for the constituents of mixed wastes, i.e., hazardous and radioactive substances, have been codified. The design requirements for both hazardous and radioactive materials packaging specify packaging compatibility, i.e., that the materials of the packaging and any contents be chemically compatible with each other. Furthermore, Type A and Type B packaging design requirements stipulate that there be no significant chemical, galvanic, or other reaction between the materials and contents of the package. Based on these requirements, a Chemical Compatibility Testing Program was developed in the Transportation Systems Department at Sandia National Laboratories (SNL). The program, supported by the US Department of Energy's (DOE) Transportation Management Division, EM-261 provides the means to assure any regulatory body that the issue of packaging material compatibility towards hazardous and radioactive materials has been addressed. In this paper, we describe the general elements of the testing program and the experimental results of the screening tests. The implications of the results of this testing are discussed in the general context of packaging development. Additionally, we present the results of the first phase of this experimental program. This phase involved the screening of five candidate liner and six seal materials against four simulant mixed wastes

49 CFR 173.465 - Type A packaging tests.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Type A packaging tests. 173.465 Section 173.465 Transportation Other Regulations Relating to Transportation PIPELINE AND HAZARDOUS MATERIALS SAFETY... SHIPMENTS AND PACKAGINGS Class 7 (Radioactive) Materials § 173.465 Type A packaging tests. (a) The packaging...

Mixed waste chemical compatibility: A testing program for plastic packaging components

International Nuclear Information System (INIS)

Nigrey, P.J.

1995-01-01

The purpose of hazardous and radioactive materials packaging is to enable these materials to be transported without posing a threat to the health or property of the general public. To achieve this aim, regulations in the United States have been written establishing general design requirements for such packagings. While no regulations have been written specifically for mixed waste packaging, regulations for the constituents of mixed wastes, i.e., hazardous and radioactive substances, have been codified by the US Department of Transportation (DOT, 49 CFR 173) and the US Nuclear Regulatory Commission (NRC, 10 CFR 71). The design requirements for both hazardous [49 CFR 173.24 (e)(1)] and radioactive [49 CFR 173.412 (g)] materials packaging specify packaging compatibility, i.e., that the materials of the packaging at sign d any contents be chemically compatible with each other. Furthermore, Type A [49 CFR 173.412 (g)] and Type B (10 CFR 71.43) packaging design requirements stipulate that there be no significant chemical, galvanic, or other reaction between the materials and contents of the package. Based on these requirements, a Chemical Compatibility Testing Program was developed in the Transportation Systems Department at Sandia National Laboratories (SNL). The program attempts to assure any regulatory body that the issue of packaging material compatibility towards hazardous and radioactive materials has been addressed. This program has been described in considerable detail in an internal SNL document, the Chemical Compatibility Test Plan ampersand Procedure Report (Nigrey 1993)

International performance-oriented packaging standards adopted in the united states

International Nuclear Information System (INIS)

McCall, D.L.

1993-01-01

On January 1, 1991, the U.S. Department of Transportation (DOT) initiated a transition to adopting a modified version of current international standards for packaging and transporting hazardous materials and hazardous wastes. This transition permits a 5-year phase-in period that will impact all phases of hazardous material transportation including material classification and description, packaging for shipment, and hazard communication standards. These changes are being enacted through the DOT Federal Docket HM-181, 'Performance-Oriented Packaging Standards.' These regulatory standards will have dramatic impact on nearly 5 billion tons of hazardous materials transported within the United States each year. This paper summarizes the principal elements of the new DOT regulations, the latest implementation schedule and impacts on U.S. shipping activities, and discusses outstanding issues that remain to be solved through the next 5 years. (author)

Y-12 defense programs. Nuclear Packaging Systems testing capabilities

International Nuclear Information System (INIS)

1995-06-01

The Nuclear Packaging Systems (NPS) Department can manage/accomplish any packaging task. The NPS organization is responsible for managing the design, testing, certification, procurement, operation, refurbishment, maintenance, and disposal of packaging used to transport radioactive materials, other hazardous materials, and general cargoes on public roads and within the Oak Ridge Y-12 Plant. Additionally, the NPS Department has developed a Quality Assurance plan for all packaging, design and procurement of nonweapon shipping containers for radioactive materials, and design and procurement of performance-oriented packaging for hazardous materials. Further, the NPS Department is responsible for preparation and submittal of Safety Analysis Reports for Packaging (SARP). The NPS Department coordinates shipping container procurement and safety certification activities that have lead-times of up to two years. A Packaging Testing Capabilities Table at the Oak Ridge complex is included as a table

Development directions of packaging made from polymer materials

Directory of Open Access Journals (Sweden)

Jovanović Slobodan

2011-01-01

Full Text Available World packaging market achieves turnover of about $620 billion per year with one third of this amount being associated to packaging made from polymer materials. It is expected that this kind of packaging consumption will hold at least 3% of world packaging market share in the next five years and that it will surpass the consumption of all other materials used in the packaging production. This can be contributed to product quality, low production costs as well as significant investments made in the development of polymer materials, packaging technology and packaging. This paper presents some development directions for packaging made from polymer materials, such as: packaging in the protective atmosphere, the use of active and intelligent packaging, and the use of biopolymers and recycled polymers for packaging production that come into direct contact with the packed product.

Material Efficiency in Dutch Packaging Policy

NARCIS (Netherlands)

Worrell, E.; van Sluisveld, M.A.E.

2013-01-01

Packaging materials are one of the largest contributors to municipal solid waste generation. In this paper, we evaluate the material impacts of packaging policy in The Netherlands, focusing on the role of material efficiency (or waste prevention). Since 1991, five different policies have been

75 FR 5375 - Hazardous Material; Miscellaneous Packaging Amendments

Science.gov (United States)

2010-02-02

... NPRM, we proposed to remove the maximum net mass and water capacity limits from these definitions and... a water capacity greater than 454 kg (1,000 pounds) as a receptacle for a gas are bulk packagings.... Negative comments were generally focused on issues related to record retention of closure instructions...

Test for radioactive material transport package safety

International Nuclear Information System (INIS)

Li Guoqiang; Zhao Bing; Zhang Jiangang; Wang Xuexin; Ma Anping

2012-01-01

Regulations on radioactive material transport in China were introduced. Test facilities and data acquiring instruments for radioactive material package in China Institute for Radiation Protection were also introduced in this paper, which were used in drop test and thermal test. Test facilities were constructed according to the requirements of IAEA's 'Regulations for the Safe Transport of Radioactive Material' (TS-R-l) and Chinese 'Regulations for the Safe Transport of Radioactive Material' (GB 11806-2004). Drop test facilities were used in free drop test, penetration test, mechanical test (free drop test Ⅰ, free drop test Ⅱ and free drop test Ⅲ) of type A and type B packages weighing less than thirteen tons. Thermal test of type B packages can be carried out in the thermal test facilities. Certification tests of type FCo70-YQ package, type 30A-HB-01 package, type SY-I package and type XAYT-I package according to regulations were done using these facilities. (authors)

Advances in regulation and package design for transportation or storage of radioactive materials 1991

International Nuclear Information System (INIS)

Carlson, R.W.; Fischer, L.E.; Chou, C.K.

1991-01-01

The design of packages for the transport or storage of radioactive materials, particularly spent nuclear fuel, has been evolving in three major areas. The most significant changes have been increases n the capacity of packages. Testing has received increasing importance to supplement analysis and to verify the accuracy of the computer models to represent the more complex designs. New materials have also been proposed that are capable of serving more than one function within a package which would reduce weight and offer the possibility of simplifying package design. It is the intent of the papers presented in this volume to address the impact of these developments by presenting papers that describe testing methods, materials development programs and recent package designs. Decommissioning of nuclear facilities is a field that is beginning to emerge as a major field of endeavor that spans the mechanical engineering, nuclear engineering and many other disciplines. Papers included in this publication describe efforts to understand the mechanics of decontamination of surfaces that have been exposed to radioactive materials and the application of robotics to perform tasks that would be excessively hazardous for humans. Presentation of these papers within the format of the ASME has been chosen to focus attention upon the importance of designing packages in accordance with the Boiler and Pressure Vessel Coal. The papers contained herein have been subjected to a formal review process in accordance with ASME requirements

Application of Green Environmentally Friendly Materials in Food Packaging

Directory of Open Access Journals (Sweden)

Jixia Li

2017-11-01

Full Text Available With social development, requirements on the spiritual and material life have increased. However, some environmental issues appear, for example, in food packaging. Application of environment-friendly materials in food packaging has been more and more attractive. This study analyses the characteristics of degradable food packaging material and the existing problems, proposes the manufacturing of food packaging with poly(lactic acid/nanocrystalline cellulose composite material, tests its thermal and mechanical properties, and applies it to the design of food packaging. The results demonstrate that the thermal and mechanical properties of the material could satisfy the requirements of food packaging and that the material is applicable to the design of food packaging in the future. This work provides a reference for the application of green, environment-friendly materials in the design of food packaging.

49 CFR 172.404 - Labels for mixed and consolidated packaging.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Labels for mixed and consolidated packaging. 172..., TRAINING REQUIREMENTS, AND SECURITY PLANS Labeling § 172.404 Labels for mixed and consolidated packaging. (a) Mixed packaging. When hazardous materials having different hazard classes are packed within the...

Legal analysis of information displayed on dental material packages: An exploratory research

Directory of Open Access Journals (Sweden)

Bhumika Rathore

2016-01-01

Full Text Available Introduction: Some of the dental materials possess occupational hazards, preprocedural errors, and patient allergies as suggested by evidence. With due consideration to safety of the patients and dental professionals, it is essential that the trade of these materials is in conformity with the law. Aim: To perform the legal analysis of the information displayed on the packaging of dental materials. Materials and Methods: The Bureau of Indian Standards sets guidelines for packaging and marketing of dental products in India. An exploratory cross-sectional study was performed using various search engines and websites to access the laws and regulations existing pertaining to dental materials packaging. Based on the data obtained, a unique packaging standardization checklist was developed. Dental laboratory and impression plasters, alginates, and endodontic instruments were surveyed for all the available brands. This study considered 16 brands of plasters and alginates and 42 brands of endodontic instruments for legal analysis. Legal analysis was performed using the direct observation checklist. Descriptive statistics were obtained using SPSS version 19. Results: The guidelines set by the Bureau of Indian Standards do exist but are not updated and stand as oblivious guards for marketing standards. Overall compliance to the guidelines was reported to be 18.5% by brands of alginates, 4.1% by plaster of Paris, and 11.11% by endodontic instruments. Wave One™ File reported maximum adherence with the guidelines as 66.7%. Conclusion: This study found lower rate of adherence to the guidelines, thus indicating insufficient information being disclosed to the consumers.

49 CFR 173.23 - Previously authorized packaging.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Previously authorized packaging. 173.23 Section... REQUIREMENTS FOR SHIPMENTS AND PACKAGINGS Preparation of Hazardous Materials for Transportation § 173.23 Previously authorized packaging. (a) When the regulations specify a packaging with a specification marking...

49 CFR 173.3 - Packaging and exceptions.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Packaging and exceptions. 173.3 Section 173.3... SHIPMENTS AND PACKAGINGS General § 173.3 Packaging and exceptions. (a) The packaging of hazardous materials.... standard packaging must be open to inspection by a representative of the Department. (b) The regulations...

Influence of packaging materials on Kashkaval quality

OpenAIRE

Talevski, Goce; Srbinovska, Sonja; Santa, Dushica; Mateva, Natasha

2017-01-01

This study focused on investigating the influence of 4 different packaging materials (A - the control, B - polymer emulsion, C - wax and D - polymer foil) on the quality of Kashkaval cheese. The lowest pH value had the sample protected by wax, which is most probably related to the retention of the formed organic acids and gases from the packaging material. A significant influence of the tested packaging materials (p

49 CFR 178.915 - General Large Packaging standards.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false General Large Packaging standards. 178.915 Section... PACKAGINGS Large Packagings Standards § 178.915 General Large Packaging standards. (a) Each Large Packaging.... Large Packagings intended for solid hazardous materials must be sift-proof and water-resistant. (b) All...

Waste package materials selection process

International Nuclear Information System (INIS)

Roy, A.K.; Fish, R.L.; McCright, R.D.

1994-01-01

The office of Civilian Radioactive Waste Management (OCRWM) of the United States Department of Energy (USDOE) is evaluating a site at Yucca Mountain in Southern Nevada to determine its suitability as a mined geologic disposal system (MGDS) for the disposal of high-level nuclear waste (HLW). The B ampersand W Fuel Company (BWFC), as a part of the Management and Operating (M ampersand O) team in support of the Yucca Mountain Site Characterization Project (YMP), is responsible for designing and developing the waste package for this potential repository. As part of this effort, Lawrence Livermore National Laboratory (LLNL) is responsible for testing materials and developing models for the materials to be used in the waste package. This paper is aimed at presenting the selection process for materials needed in fabricating the different components of the waste package

Radiation treatment for sterilization of packaging materials

International Nuclear Information System (INIS)

Haji-Saeid, Mohammad; Sampa, Maria Helena O.; Chmielewski, Andrzej G.

2007-01-01

Treatment with gamma and electron radiation is becoming a common process for the sterilization of packages, mostly made of natural or synthetic plastics, used in the aseptic processing of foods and pharmaceuticals. The effect of irradiation on these materials is crucial for packaging engineering to understand the effects of these new treatments. Packaging material may be irradiated either prior to or after filling. The irradiation prior to filling is usually chosen for dairy products, processed food, beverages, pharmaceutical, and medical device industries in the United States, Europe, and Canada. Radiation effects on packaging material properties still need further investigation. This paper summarizes the work done by different groups and discusses recent developments in regulations and testing procedures in the field of packaging technology

Safety Analysis Report: Packages, Pu oxide and Am oxide shipping cask: Packaging of fissile and other radioactive materials: Final report

International Nuclear Information System (INIS)

Chalfant, G.G.

1984-12-01

The PuO 2 cask or 5320-3 cask is designed for shipment of americium or plutonium by surface transportation modes. The cask design was physically tested to demonstrate that it met the criteria specified in US ERDA Manual Chapter 0529, dated 12/21/76, which invokes Title 10 Code of Federal Regulations, Part 71 (10 CFR 71) ''Packaging of Radioactive Materials for Transport,'' and Title 49 CFR Parts 171.179 ''Hazardous Materials Regulations.'' (US DOE Order 4580.1A, Chapter III, superseded manual chapter 0529 effective May 1981, but it retained the same 10 CFR 71 and 49 CFR 171-179 references

75 FR 27273 - Hazardous Materials; Packages Intended for Transport by Aircraft

Science.gov (United States)

2010-05-14

... shipments have routinely utilized multiple flight segments in the past, the proliferation of sort systems.... Today, air carriers use multiple mechanical handling systems to sort packages, and the number of... Leaks in Flexible Packaging by Bubble Emission'' or a generic test method outlined in a proposed new...

Transportation of Hazardous Materials Emergency Preparedness Hazards Assessment

Energy Technology Data Exchange (ETDEWEB)

Blanchard, A.

2000-02-28

This report documents the Emergency Preparedness Hazards Assessment (EPHA) for the Transportation of Hazardous Materials (THM) at the Department of Energy (DOE) Savannah River Site (SRS). This hazards assessment is intended to identify and analyze those transportation hazards significant enough to warrant consideration in the SRS Emergency Management Program.

Transportation of Hazardous Materials Emergency Preparedness Hazards Assessment

International Nuclear Information System (INIS)

Blanchard, A.

2000-01-01

This report documents the Emergency Preparedness Hazards Assessment (EPHA) for the Transportation of Hazardous Materials (THM) at the Department of Energy (DOE) Savannah River Site (SRS). This hazards assessment is intended to identify and analyze those transportation hazards significant enough to warrant consideration in the SRS Emergency Management Program

Transportation of hazardous materials emergency preparedness hazards assessment

International Nuclear Information System (INIS)

Blanchard, A.

2000-01-01

This report documents the Emergency Preparedness Hazards Assessment (EPHA) for the Transportation of Hazardous Materials (THM) at the Department of Energy (DOE) Savannah River Site (SRS). This hazards assessment is intended to identify and analyze those transportation hazards significant enough to warrant consideration in the SRS Emergency Management Program

The innovative application studty on eco-packaging design and materials

Directory of Open Access Journals (Sweden)

Cui Yong Min

2016-01-01

Full Text Available The paper solves the increasingly deteriorate environmental problems by positively exploring how to utilize and develop eco-packaging design reasonably. The paper explores an effective method that combines eco-packaging and environmental protection materials, hoping to define the sustainable development road of packaging design. The paper is centered on the design application of eco-packaging and environmental protection materials, applies and analyzes the method to obtain innovative design requirements and development tendency of eco-packaging design by analyzing status and significance of eco-packaging design, combining with the development and main types of eco-packaging packaging materials, and based on the achievements acquired by eco-packaging and environmental protection materials. Meanwhile, the paper also reveals mutual dependence and mutual promotion of eco-packaging design and eco-packaging materials.

Application of Green Environmentally Friendly Materials in Food Packaging

OpenAIRE

Jixia Li

2017-01-01

With social development, requirements on the spiritual and material life have increased. However, some environmental issues appear, for example, in food packaging. Application of environment-friendly materials in food packaging has been more and more attractive. This study analyses the characteristics of degradable food packaging material and the existing problems, proposes the manufacturing of food packaging with poly(lactic acid)/nanocrystalline cellulose composite material, tests its therm...

Safety analysis report for packaging (onsite) steel drum

International Nuclear Information System (INIS)

McCormick, W.A.

1998-01-01

This Safety Analysis Report for Packaging (SARP) provides the analyses and evaluations necessary to demonstrate that the steel drum packaging system meets the transportation safety requirements of HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments, for an onsite packaging containing Type B quantities of solid and liquid radioactive materials. The basic component of the steel drum packaging system is the 208 L (55-gal) steel drum

Relative consequences of transporting hazardous materials

International Nuclear Information System (INIS)

Fullwood, R.R.; Rhyne, W.R.; Simmons, J.A.; Reese, R.T.

1980-01-01

The objective of this paper is to discuss methods under study at Transportation Technology Center to develop a perspective on how technical measures of hazard and risk relate to perception of hazards, harm, and risks associated with transporting hazardous materials. This paper is concerned with two major aspects of the relative hazards problem. The first aspect is the analyses of the possible effects associated with exposure to hazardous materials as contained in the following two parts: outlines of possible problems and controversies that could be encountered in the evaluation and comparisons of hazards and risks; and description of the various measures of harm (hazards or dangers) and subsequent comparisons thereof. The second aspect of this paper leads into a presentation of the results of a study which had the following purposes: to develop analytical techniques for a consistent treatment of the phenomenology of the consequences of a release of hazardous materials; to reduce the number of variables in the consequence analyses by development of transportation accident scenarios which have the same meteorological conditions, demography, traffic and population densities, geographical features and other appropriate conditions and to develop consistent methods for presenting the results of studies and analyses that describe the phenomenology and compare hazards. The results of the study are intended to provide a bridge between analytical certainty and perception of the hazards involved. Understanding the differences in perception of hazards resulting from transport of various hazardous materials is fraught with difficulties in isolating the qualitative and quantitative features of the problem. By relating the quantitative impacts of material hazards under identical conditions, it is hoped that the perceived differences in material hazards can be delineated and evaluated

49 CFR 173.206 - Packaging requirements for chlorosilanes.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Packaging requirements for chlorosilanes. 173.206...-GENERAL REQUIREMENTS FOR SHIPMENTS AND PACKAGINGS Non-bulk Packaging for Hazardous Materials Other Than Class 1 and Class 7 § 173.206 Packaging requirements for chlorosilanes. (a) When § 172.101 of this...

Materials of Criticality Safety Concern in Waste Packages

International Nuclear Information System (INIS)

Larson, S.L.; Day, B.A.

2006-01-01

10 CFR 71.55 requires in part that the fissile material package remain subcritical when considering 'the most reactive credible configuration consistent with the chemical and physical form of the material'. As waste drums and packages may contain unlimited types of materials, determination of the appropriately bounding moderator and reflector materials to ensure compliance with 71.55 requires a comprehensive analysis. Such an analysis was performed to determine the materials or elements that produce the most reactive configuration with regards to both moderation and reflection of a Pu-239 system. The study was originally performed for the TRUPACT-II shipping package and thus the historical fissile mass limit for the package, 325 g Pu-239, was used [1]. Reactivity calculations were performed with the SCALE package to numerically assess the moderation or reflection merits of the materials [2]. Additional details and results are given in SAIC-1322-001 [3]. The development of payload controls utilizing process knowledge to determine the classification of special moderator and/or reflector materials and the associated fissile mass limit is also addressed. (authors)

49 CFR 173.29 - Empty packagings.

Science.gov (United States)

2010-10-01

... hazardous material shall be offered for transportation and transported in the same manner as when it.... (c) A non-bulk packaging containing only the residue of a hazardous material covered by Table 2 of... in Column 10a of the § 172.101 table for transportation by vessel, an empty drum or cylinder may be...

Performance-oriented packaging: A guide to identifying and designing. Identifying and designing hazardous materials packaging for compliance with post HM-181 DOT Regulations

International Nuclear Information System (INIS)

1994-08-01

With the initial publication of Docket HM-181 (hereafter referred to as HM-181), the U.S. Department of Energy (DOE), Headquarters, Transportation Management Division decided to produce guidance to help the DOE community transition to performance-oriented packagings (POP). As only a few individuals were familiar with the new requirements, elementary guidance was desirable. The decision was to prepare the guidance at a level easily understood by a novice to regulatory requirements. This document identifies design development strategies for use in obtaining performance-oriented packagings that are not readily available commercially. These design development strategies will be part of the methodologies for compliance with post HM-181 U.S. Department of Transportation (DOT) packaging regulations. This information was prepared for use by the DOE and its contractors. The document provides guidance for making decisions associated with designing performance-oriented packaging, and not for identifying specific material or fabrication design details. It does provide some specific design considerations. Having a copy of the regulations handy when reading this document is recommended to permit a fuller understanding of the requirements impacting the design effort. While this document is not written for the packaging specialist, it does contain guidance important to those not familiar with the new POP requirements

Types, production and assessment of biobased food packaging materials

Science.gov (United States)

Food packaging performs an essential function, but packaging materials can have a negative impact on the environment. This book describes the latest advances in bio-based food packaging materials. Book provides a comprehensive review on bio-based, biodegradable and recycled materials and discusses t...

Hazardous materials

Science.gov (United States)

... substances that could harm human health or the environment. Hazardous means dangerous, so these materials must be ... M. is also a founding member of Hi-Ethics and subscribes to the principles of the Health ...

49 CFR 173.428 - Empty Class 7 (radioactive) materials packaging.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Empty Class 7 (radioactive) materials packaging... SHIPPERS-GENERAL REQUIREMENTS FOR SHIPMENTS AND PACKAGINGS Class 7 (Radioactive) Materials § 173.428 Empty Class 7 (radioactive) materials packaging. A packaging which previously contained Class 7 (radioactive...

Aqueous Corrosion Rates for Waste Package Materials

Energy Technology Data Exchange (ETDEWEB)

S. Arthur

2004-10-08

The purpose of this analysis, as directed by ''Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package'' (BSC 2004 [DIRS 171583]), is to compile applicable corrosion data from the literature (journal articles, engineering documents, materials handbooks, or standards, and national laboratory reports), evaluate the quality of these data, and use these to perform statistical analyses and distributions for aqueous corrosion rates of waste package materials. The purpose of this report is not to describe the performance of engineered barriers for the TSPA-LA. Instead, the analysis provides simple statistics on aqueous corrosion rates of steels and alloys. These rates are limited by various aqueous parameters such as temperature (up to 100 C), water type (i.e., fresh versus saline), and pH. Corrosion data of materials at pH extremes (below 4 and above 9) are not included in this analysis, as materials commonly display different corrosion behaviors under these conditions. The exception is highly corrosion-resistant materials (Inconel Alloys) for which rate data from corrosion tests at a pH of approximately 3 were included. The waste package materials investigated are those from the long and short 5-DHLW waste packages, 2-MCO/2-DHLW waste package, and the 21-PWR commercial waste package. This analysis also contains rate data for some of the materials present inside the fuel canisters for the following fuel types: U-Mo (Fermi U-10%Mo), MOX (FFTF), Thorium Carbide and Th/U Carbide (Fort Saint Vrain [FSVR]), Th/U Oxide (Shippingport LWBR), U-metal (N Reactor), Intact U-Oxide (Shippingport PWR, Commercial), aluminum-based, and U-Zr-H (TRIGA). Analysis of corrosion rates for Alloy 22, spent nuclear fuel, defense high level waste (DHLW) glass, and Titanium Grade 7 can be found in other analysis or model reports.

Aqueous Corrosion Rates for Waste Package Materials

International Nuclear Information System (INIS)

Arthur, S.

2004-01-01

The purpose of this analysis, as directed by ''Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package'' (BSC 2004 [DIRS 171583]), is to compile applicable corrosion data from the literature (journal articles, engineering documents, materials handbooks, or standards, and national laboratory reports), evaluate the quality of these data, and use these to perform statistical analyses and distributions for aqueous corrosion rates of waste package materials. The purpose of this report is not to describe the performance of engineered barriers for the TSPA-LA. Instead, the analysis provides simple statistics on aqueous corrosion rates of steels and alloys. These rates are limited by various aqueous parameters such as temperature (up to 100 C), water type (i.e., fresh versus saline), and pH. Corrosion data of materials at pH extremes (below 4 and above 9) are not included in this analysis, as materials commonly display different corrosion behaviors under these conditions. The exception is highly corrosion-resistant materials (Inconel Alloys) for which rate data from corrosion tests at a pH of approximately 3 were included. The waste package materials investigated are those from the long and short 5-DHLW waste packages, 2-MCO/2-DHLW waste package, and the 21-PWR commercial waste package. This analysis also contains rate data for some of the materials present inside the fuel canisters for the following fuel types: U-Mo (Fermi U-10%Mo), MOX (FFTF), Thorium Carbide and Th/U Carbide (Fort Saint Vrain [FSVR]), Th/U Oxide (Shippingport LWBR), U-metal (N Reactor), Intact U-Oxide (Shippingport PWR, Commercial), aluminum-based, and U-Zr-H (TRIGA). Analysis of corrosion rates for Alloy 22, spent nuclear fuel, defense high level waste (DHLW) glass, and Titanium Grade 7 can be found in other analysis or model reports

Packaging material and aluminum. Hoso zairyo to aluminum

Energy Technology Data Exchange (ETDEWEB)

Itaya, T [Mitsubishi Aluminum Co. Ltd., Tokyo (Japan)

1992-02-01

The present paper introduces aluminum foil packaging materials among the relation between packing materials and aluminum. The characteristics of aluminum foil in the packaging area are in its barrier performance, non-toxicity, tastelessness and odorlessness. Its excellent functions and processibility suit best as functional materials for food, medicine and industrial material packaging. While an aluminum foil may be used as a single packing material as in foils used in homes, many of it as a packaging material are used in combination with adhesives, papers or plastic films, or coated or printed. It is used as composite materials laminated or coated with other materials according to their use for the purpose of complementing the aluminum foil as the base material. Representative method to laminate aluminum foils include the wet lamination, dry lamination, thermally dissolved lamination and extruded lamination. The most important quality requirement in lamination is the adhesion strength, which requires a close attention in selecting the kinds of adhesive, laminating conditions, and aging conditions. 8 figs., 6 tabs.

Completion of the radioactive materials packaging handbook

International Nuclear Information System (INIS)

Shappert, L.B.

1998-01-01

'The Radioactive Materials Packaging Handbook: Design, Operation and Maintenance', which will serve as a replacement for the 'Cask Designers Guide'(1970), has now been completed and submitted to the Oak Ridge National Laboratory (ORNL) electronics publishing group for layout and printing; it is scheduled to be printed in late spring 1998. The Handbook, written by experts in their particular fields, is a compilation of technical chapters that address the design aspects of a package intended for transporting radioactive material in normal commerce; it was prepared under the direction of M. E. Wangler of the US DOE and is intended to provide a wealth of technical guidance that will give designers a better understanding of the regulatory approval process, preferences of regulators on specific aspects of package design, and the types of analyses that should be considered when designing a package to carry radioactive materials. Even though the Handbook is concerned with both small and large packagings, most of the emphasis is placed on large packagings that are capable of transporting fissile, radioactive sources (e.g. spent fuels). The safety analysis reports for packagings (SARPs) must address the widest range of technical topics in order to meet United States and/or international regulations, all of which are covered in the Handbook. One of the primary goals of the Handbook is to provide information which would guide designers of radioactive materials packages to make decisions that would most likely be acceptable to regulatory agencies during the approval process of the packaging. It was therefore important to find those authors who not only were experts in one or more of the areas that are addressed in a SARP, but who also had been exposed to the regulatory process or had operational experience dealing with a wide variety of package types. Twenty-five such people have contributed their time and talents to the development of this document, mostly on a volunteer basis

Transportation package design using numerical optimization

International Nuclear Information System (INIS)

Harding, D.C.; Witkowski, W.R.

1991-01-01

The purpose of this overview is twofold: first, to outline the theory and basic elements of numerical optimization; and second, to show how numerical optimization can be applied to the transportation packaging industry and used to increase efficiency and safety of radioactive and hazardous material transportation packages. A more extensive review of numerical optimization and its applications to radioactive material transportation package design was performed previously by the authors (Witkowski and Harding 1992). A proof-of-concept Type B package design is also presented as a simplified example of potential improvements achievable using numerical optimization in the design process

Safety analysis report for packages: packaging of fissile and other radioactive materials. Final report

International Nuclear Information System (INIS)

Chalfant, G.G.

1984-01-01

The 9965, 9966, 9967, and 9968 packages are designed for surface shipment of fissile and other radioactive materials where a high degree of containment (either single or double) is required. Provisions are made to add shielding material to the packaging as required. The package was physically tested to demonstrate that it meets the criteria specified in USDOE Order No. 5480.1, chapter III, dated 5/1/81, which invokes Title 10, Code of Federal Regulations, Part 71 (10 CFR 71), Packing and Transportation of Radioactive Material, and Title 49, Code of Federal Regulations, Part 100-179, Transportation. By restricting the maximum normal operating pressure of the packages to less than 7 kg/cm 2 (gauge) (99 to 54 psig), the packages will comply with Type B(U) regulations of the International Atomic Energy Agency (IAEA) in its Regulations for the Safe Transport of Radioactive Materials, Safety Series No. 6, 1973 Revised Edition, and may be used for export and import shipments. These packages have been assessed for transport of up to 14.5 kilograms of uranium, excluding uranium-233, or 4.4 kilograms of plutonium metal, oxides, or scrap having a maximum radioactive decay energy of 30 watts. Specific maximum package contents are given. This quantity and the configuration of uranium or plutonium metal cannot be made critical by any combination of hydrogeneous reflection and moderation regardless of the condition of the package. For a uranium-233 shipment, a separate criticality evaluation for the specific package is required

Pre Conference Hazardous Materials Workshop, West/East Coast Safety Conference, held 3-4 October/31 October - 1 November 1981,

Science.gov (United States)

1981-01-01

COMPATABILITY (2) PPE (3) SOP’s 𔃼 NOTES (1) USERDA ( RADIOACTIVE MATERIALS) (2) CHEMTREC (ALL OTHER HAZARDOUS MATERIALS) 2. NAVY A. NAVY ENVIRONMENTAL HEALTH...NRC Regulations for Packaging of Radioactive Material for Transport and Transportation of Radioactive Material Under Certain Conditions (10 CFR 71) V...NAVY) I DOD Directives/Instructions--- DOD Instruction 4120.14 DOD Water and Air Polution Abatement Policy DOD 4145.19R Series Storage and Material

Completion of the Radioactive Materials Packaging Handbook

International Nuclear Information System (INIS)

Shappert, L.B.

1998-02-01

The Radioactive Materials Packaging Handbook: Design, Operation and Maintenance, which will serve as a replacement for the Cask Designers Guide (Shappert, 1970), has now been completed and submitted to the Oak Ridge National Laboratory (ORNL) electronics publishing group for layout and printing; it is scheduled to be printed in late spring 1998. The Handbook, written by experts in their particular fields, is a compilation of technical chapters that address the design aspects of a package intended for transporting radioactive material in normal commerce; it was prepared under the direction of M. E. Wangler of the US Department of Energy (DOE) and is intended to provide a wealth of technical guidance that will give designers a better understanding of the regulatory approval process, preferences of regulators on specific aspects of package design, and the types of analyses that should be considered when designing a package to carry radioactive materials

Chitosan films and blends for packaging material.

Science.gov (United States)

van den Broek, Lambertus A M; Knoop, Rutger J I; Kappen, Frans H J; Boeriu, Carmen G

2015-02-13

An increased interest for hygiene in everyday life as well as in food, feed and medical issues lead to a strong interest in films and blends to prevent the growth and accumulation of harmful bacteria. A growing trend is to use synthetic and natural antimicrobial polymers, to provide non-migratory and non-depleting protection agents for application in films, coatings and packaging. In food packaging, antimicrobial effects add up to the barrier properties of the materials, to increase the shelf life and product quality. Chitosan is a natural bioactive polysaccharide with intrinsic antimicrobial activity and, due to its exceptional physicochemical properties imparted by the polysaccharide backbone, has been recognized as a natural alternative to chemically synthesized antimicrobial polymers. This, associated with the increasing preference for biofunctional materials from renewable resources, resulted in a significant interest on the potential for application of chitosan in packaging materials. In this review we describe the latest developments of chitosan films and blends as packaging material. Copyright © 2014 Elsevier Ltd. All rights reserved.

Package Formats for Preserved Digital Material

DEFF Research Database (Denmark)

Zierau, Eld

2012-01-01

This paper presents an investigation of the best suitable package formats for long term digital preservation. The choice of a package format for preservation is crucial for future access, thus a thorough analysis of choice is important. The investigation presented here covers setting up requireme......This paper presents an investigation of the best suitable package formats for long term digital preservation. The choice of a package format for preservation is crucial for future access, thus a thorough analysis of choice is important. The investigation presented here covers setting up...... requirements for package formats used for long term preserved digital material, and using these requirements as the basis for analysing a range of package formats. The result of the concrete investigation is that the WARC format is the package format best suited for the listed requirements. Fulfilling...

Material efficiency improvement for European packaging in the period 2000-2020

Energy Technology Data Exchange (ETDEWEB)

Hekkert, M.; Joosten, L.; Worrell, E. [Department of Science, Technology and Society, Utrecht University, Utrecht (Netherlands)

1999-07-01

In this paper the current material consumption for packaging making in Europe is described. Per packaging type (food bottles, non-food bottles, boxes for primary packaging, flexible packaging, carrier bags, industrial boxes and pallets) options for improved material efficiency are described. The options are in the field of using thinner materials, using less material by changing the shape of the package, using recycled material and using refillable packages. This paper shows that many options are available to reduce the future material input for packaging and that a reduction of CO{sub 2} emissions by this sector with a factor 2 is possible. A substantial share of this reduction can be achieved without any changes in consumer behavior. 57 refs.

Hazard index for underground toxic material

International Nuclear Information System (INIS)

Smith, C.F.; Cohen, J.J.; McKone, T.E.

1980-06-01

To adequately define the problem of waste management, quantitative measures of hazard must be used. This study reviews past work in the area of hazard indices and proposes a geotoxicity hazard index for use in characterizing the hazard of toxic material buried underground. Factors included in this index are: an intrinsic toxicity factor, formulated as the volume of water required for dilution to public drinking-water levels; a persistence factor to characterize the longevity of the material, ranging from unity for stable materials to smaller values for shorter-lived materials; an availability factor that relates the transport potential for the particular material to a reference value for its naturally occurring analog; and a correction factor to accommodate the buildup of decay progeny, resulting in increased toxicity

Hazard index for underground toxic material

Energy Technology Data Exchange (ETDEWEB)

Smith, C.F.; Cohen, J.J.; McKone, T.E.

1980-06-01

To adequately define the problem of waste management, quantitative measures of hazard must be used. This study reviews past work in the area of hazard indices and proposes a geotoxicity hazard index for use in characterizing the hazard of toxic material buried underground. Factors included in this index are: an intrinsic toxicity factor, formulated as the volume of water required for dilution to public drinking-water levels; a persistence factor to characterize the longevity of the material, ranging from unity for stable materials to smaller values for shorter-lived materials; an availability factor that relates the transport potential for the particular material to a reference value for its naturally occurring analog; and a correction factor to accommodate the buildup of decay progeny, resulting in increased toxicity.

Radioactive material package seal tests

International Nuclear Information System (INIS)

Madsen, M.M.; Humphreys, D.L.; Edwards, K.R.

1990-01-01

General design or test performance requirements for radioactive materials (RAM) packages are specified in Title 10 of the US Code of Federal Regulations Part 71 (US Nuclear Regulatory Commission, 1983). The requirements for Type B packages provide a broad range of environments under which the system must contain the RAM without posing a threat to health or property. Seals that provide the containment system interface between the packaging body and the closure must function in both high- and low-temperature environments under dynamic and static conditions. A seal technology program, jointly funded by the US Department of Energy Office of Environmental Restoration and Waste Management (EM) and the Office of Civilian Radioactive Waste Management (OCRWM), was initiated at Sandia National Laboratories. Experiments were performed in this program to characterize the behavior of several static seal materials at low temperatures. Helium leak tests on face seals were used to compare the materials. Materials tested include butyl, neoprene, ethylene propylene, fluorosilicone, silicone, Eypel, Kalrez, Teflon, fluorocarbon, and Teflon/silicone composites. Because most elastomer O-ring applications are for hydraulic systems, manufacturer low-temperature ratings are based on methods that simulate this use. The seal materials tested in this program with a fixture similar to a RAM cask closure, with the exception of silicone S613-60, are not leak tight (1.0 x 10 -7 std cm 3 /s) at manufacturer low-temperature ratings. 8 refs., 3 figs., 1 tab

Food packaging materials and radiation processing of food: a brief review

International Nuclear Information System (INIS)

Chuaqui-Offermanns, N.

1989-01-01

Food is usually packaged to prevent microbial contamination and spoilage. Ionizing radiation can be applied to food-packaging materials in two ways: (i) sterilization of packaging materials for aseptic packaging, and (ii) radiation processing of prepackaged food. In aseptic packaging, a sterile package is filled with a sterile product in a microbiologically controlled environment. In irradiation of prepackaged food, the food and the packaging material are irradiated simultaneously. For both applications, the radiation stability of the packaging material is a key consideration if the technology is to be used successfully. To demonstrate the radiation stability of the packaging material, it must be shown that irradiation does not significantly alter the physical and chemical properties of the material. The irradiated material must protect the food from environmental contamination while maintaining its organoleptic and toxicological properties. Single-layer plastics cannot meet the requirements of either application. Multilayered structures produced by coextrusion would likely satisfy the demands of radiation processing prepackaged food. In aseptic packaging, the package is irradiated prior to filling, making demands on toxicological safety less stringent. Therefore, multilayered structures produced by coextrusion, lamination or co-injection moulding could satisfy the requirements. (author)

The influence of protective properties of packaging materials and ...

African Journals Online (AJOL)

The influence of protective properties of packaging materials and modified atmosphere on quality changes of dried apricot is shown in this paper. In our investigation, we used four different characteristic combinations of packaging materials with different barrier properties for packaging of dried apricot: ...

Transportation of hazardous and nuclear materials

International Nuclear Information System (INIS)

Boryczka, M.; Shaver, D.

1989-01-01

Transportation of hazardous and radioactive materials is a vital part of the nation's economy. In recent years public concern over the relative safety of transporting hazardous materials has risen sharply. The United States has a long history of transporting hazardous and radioactive material; rocket propellants, commercial spent fuel, low-level and high-level radioactive waste has been shipped for years. While the track record for shipping these materials is excellent, the knowledge that hazardous materials are passing through communities raises the ire of citizens and local governments. Public outcry over shipments containing hazardous cargo has been especially prominent when shippers have attempted to transport rocket propellants or spent nuclear fuel. Studies of recent shipments have provided insight into the difficulties of shipping in a politically charged environment, the major issues of concern to citizens, and some of the more successful methods of dealing with public concerns. This paper focuses on lessons learned from these studies which include interviews with shippers, carriers, and regulators

Anticipated development in radioactive materials packaging and transport systems

International Nuclear Information System (INIS)

Williams, L.D.; Rhoads, R.E.; Hall, R.J.

1976-07-01

Closing the light water reactor fuel cycle and the use of mixed oxide fuels will produce materials such as solidified high level waste, cladding hulls and plutonium from Pu recycle fuel that have not been transported extensively in the past. Changes in allowable gaseous emissions from fuel cycle facilities may require the collection and transportation of radioactive noble gases and tritium. Although all of these materials could be transported in existing radioactive material packaging, economic considerations will make it desirable to develop new packaging specifically designed for each material. Conceptual package designs for these materials are reviewed. Special Nuclear Material transportation safeguards are expected to have a significant impact on future fuel cycle transportation. This subject is reviewed briefly. Other factors that could affect fuel cycle transportation are also discussed. Development of new packaging for radioactive materials is not believed to require the development of new technologies. New package designs will be primarily an adaptation of existing technology to fit the changing needs of a growing nuclear power industry. 23 references

Nuclear-waste-package materials degradation modes and accelerated testing

International Nuclear Information System (INIS)

1981-09-01

This report reviews the materials degradation modes that may affect the long-term behavior of waste packages for the containment of nuclear waste. It recommends an approach to accelerated testing that can lead to the qualification of waste package materials in specific repository environments in times that are short relative to the time period over which the waste package is expected to provide containment. This report is not a testing plan but rather discusses the direction for research that might be considered in developing plans for accelerated testing of waste package materials and waste forms

Hazardous material reduction initiative

International Nuclear Information System (INIS)

Nichols, D.H.

1995-02-01

The Hazardous Material Reduction Initiative (HMRI) explores using the review of purchase requisitions to reduce both the use of hazardous materials and the generation of regulated and nonregulated wastes. Based on an 11-month program implemented at the Hanford Site, hazardous material use and waste generation was effectively reduced by using a centralized procurement control program known as HMRI. As expected, several changes to the original proposal were needed during the development/testing phase of the program to accommodate changing and actual conditions found at the Hanford Site. The current method requires a central receiving point within the Procurement Organization to review all purchase requisitions for potentially Occupational Safety and Health Administration (OSHA) hazardous products. Those requisitions (approximately 4% to 6% of the total) are then forwarded to Pollution Prevention personnel for evaluation under HMRI. The first step is to determine if the requested item can be filled by existing or surplus material. The requisitions that cannot filled by existing or surplus material are then sorted into two groups based on applicability to the HMRI project. For example, laboratory requests for analytical reagents or standards are excluded and the purchase requisitions are returned to Procurement for normal processing because, although regulated, there is little opportunity for source reduction due to the strict protocols followed. Each item is then checked to determine if it is regulated or not. Regulated items are prioritized based on hazardous contents, quantity requested, and end use. Copies of these requisitions are made and the originals are returned to Procurement within 1-hr. Since changes to the requisition can be made at later stages during procurement, the HMRI fulfills one of its original premises in that it does not slow the procurement process

Current investigations of packaging materials used for food irradiation

International Nuclear Information System (INIS)

Fiszer, W.

1996-01-01

The article reviews current investigations of packaging materials applied for food irradiation. The increasing role of various synthetic materials is described. Author reviews radiation-induced damages in these materials. The article includes the list of materials accepted for food packaging and subsequent irradiation with different doses

Compatibility of packaging components with simulant mixed waste

International Nuclear Information System (INIS)

Nigrey, P.J.; Dickens, T.G.

1996-01-01

The purpose of hazardous and radioactive materials packaging is to enable these materials to be transported without posing a threat to the health or property of the general public. To achieve this aim, regulations in the US have been written establishing general design requirements for such packagings. While no regulations have been written specifically for mixed waste packaging, regulations for the constituents of mixed wastes, i.e., hazardous and radioactive substances, have been codified by the US Department of Transportation (US DOT, 49 CFR 173) and the US Nuclear Regulatory Commission (NRC, 10 CFR 71). Based on these national requirements, a Chemical Compatibility Testing Program was developed in the Transportation Systems Department at Sandia National Laboratories (SNL). The program provides a basis to assure any regulatory body that the issue of packaging material compatibility towards hazardous and radioactive materials has been addressed. In this paper, the authors present the results of the second phase of this testing program. The first phase screened five liner materials and six seal materials towards four simulant mixed wastes. This phase involved the comprehensive testing of five candidate liner materials to an aqueous Hanford Tank simulant mixed waste. The comprehensive testing protocol involved exposing the respective materials a matrix of four gamma radiation doses (∼ 1, 3, 6, and 40 kGy), three temperatures (18, 50, and 60 C), and four exposure times (7, 14, 28, and 180 days). Following their exposure to these combinations of conditions, the materials were evaluated by measuring five material properties. These properties were specific gravity, dimensional changes, hardness, stress cracking, and mechanical properties

Effect of packaging materials on nutrients, phytochemicals and ...

African Journals Online (AJOL)

Effect of packaging materials on nutrients, phytochemicals and sensory attributes of Moinmoin. R.A. Mustapha, G.A. Ogundahunsi, O.I. Olanrewaju, O.O. Bolajoko. Abstract. Objective: The effect of packaging materials on nutrients, phytochemicals and sensory attributes of moinmoin cooked and wrapped with nylon, banana, ...

75 FR 60017 - Hazardous Materials; Miscellaneous Amendments

Science.gov (United States)

2010-09-29

... prevent shifting or significant relative motion between the packages; that the consolidation bins be... display of the hazard identity (e.g., labels instead of placards) would support a small, more flexible... direction for all or part of their journey. Dynamic forces may shift an unsecured load or cause lading to...

46 CFR 151.03-30 - Hazardous material.

Science.gov (United States)

2010-10-01

... hazardous material means a liquid material or substance that is— (a) Flammable or combustible; (b) Designated a hazardous substance under section 311(b) of the Federal Water Pollution Control Act (33 U.S.C... Agency designates hazardous substances in 40 CFR Table 116.4A. The Coast Guard designates hazardous...

Transport packages for nuclear material and waste

International Nuclear Information System (INIS)

1997-01-01

The regulations and responsibilities concerning the transport packages of nuclear materials and waste are given in the guide. The approval procedure, control of manufacturing, commissioning of the packaging and the control of use are specified. (13 refs.)

Using computer technology to identify the appropriate radioactive materials packaging

International Nuclear Information System (INIS)

Driscoll, K.L.; Conan, M.R.

1989-01-01

The Radioactive Materials Packaging (RAMPAC) database is designed to store and retrieve information on all non-classified packages certified for the transport of radioactive materials within the boundaries of the US. The information in RAMPAC is publicly available, and the database has been designed so that individuals without programming experience can search for and retrieve information using a menu-driven system. RAMPAC currently contains information on over 650 radioactive material shipping packages. Information is gathered from the US Department of Energy (DOE), the US Department of transportation (DOT), and the US Nuclear Regulatory Commission (NRC). RAMPAC is the only tool available to radioactive material shippers that contains and reports packaging information from all three Federal Agencies. The DOT information includes package listings from Canada, France, Germany, Great Britain, and Japan, which have DOT revalidations for their certificates of competent authority and are authorized for use within the US for import and export shipments only. RAMPAC was originally developed in 1981 by DOE as a research and development tool. In recent years, however, RAMPAC has proven to be highly useful to operational personnel. As packages become obsolete or materials to be transported change, shippers of radioactive materials must be able to determine if alternative packages exist before designing new packages. RAMPAC is designed to minimize the time required to make this determination, thus assisting the operational community in meeting their goals

Effects of packaging materials on storage quality of peanut kernels

Science.gov (United States)

Fu, Xiaoji; Xing, Shengping; Xiong, Huiwei; Min, Hua; Zhu, Xuejing; He, Jialin; Mu, Honglei

2018-01-01

In order to obtain optimum packaging materials for peanut kernels, the effects of four types of packaging materials on peanut storage quality (coat color, acid value, germination rate, relative damage, and prevention of aflatoxin contamination) were examined. The results showed that packaging materials had a major influence on peanut storage quality indexes. The color of the peanut seed coat packaged in the polyester/aluminum/polyamide/polyethylene (PET/AL/PA/PE) composite film bag did not change significantly during the storage period. Color deterioration was slower with polyamide/polyethylene (PA/PE) packaging materials than with polyethylene (PE) film bags and was slower in PE bags than in the woven bags. The use of PET/AL/PA/PE and PA/PE bags maintained peanut quality and freshness for more than one year and both package types resulted in better germination rates. There were significant differences between the four types of packaging materials in terms of controlling insect pests. The peanuts packaged in the highly permeable woven bags suffered serious invasion from insect pests, while both PET/AL/PA/PE and PA/PE bags effectively prevented insect infection. Peanuts stored in PET/AL/PA/PE and PA/PE bags were also better at preventing and controlling aflatoxin contamination. PMID:29518085

The transport of hazardous materials

International Nuclear Information System (INIS)

Goemmel, F.

1987-01-01

The rapid development of all kinds of transports has been leading to a continuously increasing number of accidents involving the release and escape of hazardous materials. The risks involved for men and the environment have to be realized and reduced to a minimum. Efforts in this field have meanwhile been accumulating an enormous quantity of rules, recommendations and regulations. They comprise, among others, both national and international rail transport, maritime transport, inland shipping, air and road transport regulations adding up to a total of about 5000 pages. The publication discusses the necessity and justification of the existing quantity of regulations, it deals with their possible simplification and modified user-oriented arrangement as well as with a possible international harmonization of regulations. Apart from giving a general survey of the transport of hazardous materials the author reviews the intensive efforts which are going into the safety of the transport of hazardous materials and points out technical and legal problems which have remained unsolved so far. The publication essentially contributes to clearing up the background, perspectives and prospects of the complex regulations controlling the transport of hazardous materials. (orig./HP) [de

Radiation sterilization of plastic packing materials and aseptic packaging

International Nuclear Information System (INIS)

Tokuoka, Keiko

1986-01-01

In the present day of 'satiation', quality, not quantity, is emphasized for foods, the consumers being oriented toward raw and healthy foodstuff. Aseptic Packaging is excellent means of conservation. While conventionally chemicals have been used for sterilization of packing materials for aseptic packaging, the sterilization by radiation is used in part recently. The following are described : history of aseptic packaging and its features, sterilization by radiation, γ-ray sterilization of large-sized containers, the development of an aseptic packaging system using electron rays, the occurrence of offensive odors from packing materials (comparison of odors from various materials, volatile substances occurring in irradiated polyethylene, influence of film grade upon the formation of carboxylic acid, influence of the irradiation conditions upon the occurrences of volatile substances, volatile substances occurring in the irradiation of bag-in-box packing materials), changes in properties of the packing materials. (Mori, K.)

9 CFR 317.24 - Packaging materials.

Science.gov (United States)

2010-01-01

... packaging materials must be safe for their intended use within the meaning of section 409 of the Federal... supplier under whose brand name and firm name the material is marketed to the official establishment. The... additive regulations. The guaranty must identify the material, e.g., by the distinguishing brand name or...

Packaging - Materials review

Energy Technology Data Exchange (ETDEWEB)

Herrmann, Matthias [Hoppecke Advanced Battery Technology GmbH, 08056 Zwickau (Germany)

2014-06-16

Nowadays, a large number of different electrochemical energy storage systems are known. In the last two decades the development was strongly driven by a continuously growing market of portable electronic devices (e.g. cellular phones, lap top computers, camcorders, cameras, tools). Current intensive efforts are under way to develop systems for automotive industry within the framework of electrically propelled mobility (e.g. hybrid electric vehicles, plug-in hybrid electric vehicles, full electric vehicles) and also for the energy storage market (e.g. electrical grid stability, renewable energies). Besides the different systems (cell chemistries), electrochemical cells and batteries were developed and are offered in many shapes, sizes and designs, in order to meet performance and design requirements of the widespread applications. Proper packaging is thereby one important technological step for designing optimum, reliable and safe batteries for operation. In this contribution, current packaging approaches of cells and batteries together with the corresponding materials are discussed. The focus is laid on rechargeable systems for industrial applications (i.e. alkaline systems, lithium-ion, lead-acid). In principle, four different cell types (shapes) can be identified - button, cylindrical, prismatic and pouch. Cell size can be either in accordance with international (e.g. International Electrotechnical Commission, IEC) or other standards or can meet application-specific dimensions. Since cell housing or container, terminals and, if necessary, safety installations as inactive (non-reactive) materials reduce energy density of the battery, the development of low-weight packages is a challenging task. In addition to that, other requirements have to be fulfilled: mechanical stability and durability, sealing (e.g. high permeation barrier against humidity for lithium-ion technology), high packing efficiency, possible installation of safety devices (current interrupt device

Packaging - Materials review

Science.gov (United States)

Herrmann, Matthias

2014-06-01

Nowadays, a large number of different electrochemical energy storage systems are known. In the last two decades the development was strongly driven by a continuously growing market of portable electronic devices (e.g. cellular phones, lap top computers, camcorders, cameras, tools). Current intensive efforts are under way to develop systems for automotive industry within the framework of electrically propelled mobility (e.g. hybrid electric vehicles, plug-in hybrid electric vehicles, full electric vehicles) and also for the energy storage market (e.g. electrical grid stability, renewable energies). Besides the different systems (cell chemistries), electrochemical cells and batteries were developed and are offered in many shapes, sizes and designs, in order to meet performance and design requirements of the widespread applications. Proper packaging is thereby one important technological step for designing optimum, reliable and safe batteries for operation. In this contribution, current packaging approaches of cells and batteries together with the corresponding materials are discussed. The focus is laid on rechargeable systems for industrial applications (i.e. alkaline systems, lithium-ion, lead-acid). In principle, four different cell types (shapes) can be identified - button, cylindrical, prismatic and pouch. Cell size can be either in accordance with international (e.g. International Electrotechnical Commission, IEC) or other standards or can meet application-specific dimensions. Since cell housing or container, terminals and, if necessary, safety installations as inactive (non-reactive) materials reduce energy density of the battery, the development of low-weight packages is a challenging task. In addition to that, other requirements have to be fulfilled: mechanical stability and durability, sealing (e.g. high permeation barrier against humidity for lithium-ion technology), high packing efficiency, possible installation of safety devices (current interrupt device

Packaging - Materials review

International Nuclear Information System (INIS)

Herrmann, Matthias

2014-01-01

Nowadays, a large number of different electrochemical energy storage systems are known. In the last two decades the development was strongly driven by a continuously growing market of portable electronic devices (e.g. cellular phones, lap top computers, camcorders, cameras, tools). Current intensive efforts are under way to develop systems for automotive industry within the framework of electrically propelled mobility (e.g. hybrid electric vehicles, plug-in hybrid electric vehicles, full electric vehicles) and also for the energy storage market (e.g. electrical grid stability, renewable energies). Besides the different systems (cell chemistries), electrochemical cells and batteries were developed and are offered in many shapes, sizes and designs, in order to meet performance and design requirements of the widespread applications. Proper packaging is thereby one important technological step for designing optimum, reliable and safe batteries for operation. In this contribution, current packaging approaches of cells and batteries together with the corresponding materials are discussed. The focus is laid on rechargeable systems for industrial applications (i.e. alkaline systems, lithium-ion, lead-acid). In principle, four different cell types (shapes) can be identified - button, cylindrical, prismatic and pouch. Cell size can be either in accordance with international (e.g. International Electrotechnical Commission, IEC) or other standards or can meet application-specific dimensions. Since cell housing or container, terminals and, if necessary, safety installations as inactive (non-reactive) materials reduce energy density of the battery, the development of low-weight packages is a challenging task. In addition to that, other requirements have to be fulfilled: mechanical stability and durability, sealing (e.g. high permeation barrier against humidity for lithium-ion technology), high packing efficiency, possible installation of safety devices (current interrupt device

Safety analysis report for packaging (onsite) Castor GSF cask

International Nuclear Information System (INIS)

Clements, E.P.

1997-01-01

The CASTOR GSF packaging was designed and fabricated to be a certified Type B(U) packaging and comply with the requirements of the International Atomic Energy Agency (IAEA) for transport of up to five sealed canisters of vitrified radioactive materials. This onsite Safety Analysis Report for Packaging (SARP) provides the analysis and evaluations necessary to demonstrate that the casks, with the canister payload, meet the intent of the Type B packaging regulations set forth in 10 CFR 71 and therefore meet the onsite transportation safety requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping

Applying and influence of polymer materials for packaging dairy beverages

Directory of Open Access Journals (Sweden)

Milanović Spasenija D.

2017-01-01

Full Text Available Functional food is positioned above the traditional, with the potential to improve human health. Thanks to very good physico-mechanical and barrier properties polymers became very popular in food industry as a packaging materials. Wild range of fermented dairy products could be packed in this packaging materials according to their’s inertness as well. Functional milk beverage was obtained from milk with 0,9% milk fat content by applying 10% v/v of kombucha’s inoculum cultivated on a black tea sweetened with sucrose. The beverage was packed in a different packaging materials: polyamid-polyethylen (PA/PE coextruded foil bags and polyprophylen (PP cups closed with aluminium (Al foil lids under atmospheric conditions (ATM. Beverages were storaged for 15 days at 4°C. The quality of kombucha inoculum, milk and obtained kombucha fermented milk beverage were analysed. Characterization of the packaging materials was done by investigating physico-mechanical, barrier and structural properties. The composition and changes in the headspace atmosphere, after production and during the storage, were analysed. The influence of packaging material properties and packaging conditions on the biochemical transformations of the milk’s components (the content of: lactose, L-lactic acid, D-galactose, ethanol, B1 and B2 vitamins influenced by kombucha starter were analysed as well. On the bases of the obtained results of characterisation of packaging materials, it can be concluded that PA/PE and PP materials are proper to be used for analysed beverage’s packaging. Also, there is no significant difference in content of components which were quantified, between analysed materials in correlation with the packed fermented milk beverage. [Projekat Ministarstva nauke Republike Srbije, br. III-46009

Microwave Absorbent Packaging Material from Composites Chitosan-Polyvinyl Alcohol Polymer

Directory of Open Access Journals (Sweden)

Bambang - Riyanto

2014-11-01

Full Text Available Microwave absorbent packaging materials currently tend to biomaterial. Chitosan is a dielectric biomaterial with polycationic properties. The aim of this study was to analyze characteristics of microwave absorbing packaging material made from composite chitosan-polyvinyl alcohol (PVA polymer. The ability of the packaging material to absorb microwave was determined by reflection loss measurement. Formed packaging prototype resembles as a thin transparent yellowish plastic with thickness (0.11-0.22 mm and the tensile strength (106.33±2.82-143.00±2.59 kPa. SEM analysis showed homogenous structure characterized by interaction between chitosan and PVA. Optimum absorption value was obtained from chitosan concentration of 1%, with average value of reflection loss was (-31.9289±4.0094 dB.Keywords: chitosan, material packaging, microwave, reflection loss

Microwave Absorbent Packaging Material from Composites Chitosan-Polyvinyl Alcohol Polymer

Directory of Open Access Journals (Sweden)

Bambang - Riyanto

2015-07-01

Full Text Available Microwave absorbent packaging materials currently tend to biomaterial. Chitosan is a dielectric biomaterial with polycationic properties. The aim of this study was to analyze characteristics of microwave absorbing packaging material made from composite chitosan-polyvinyl alcohol (PVA polymer. The ability of the packaging material to absorb microwave was determined by reflection loss measurement. Formed packaging prototype resembles as a thin transparent yellowish plastic with thickness (0.11-0.22 mm and the tensile strength (106.33±2.82-143.00±2.59 kPa. SEM analysis showed homogenous structure characterized by interaction between chitosan and PVA. Optimum absorption value was obtained from chitosan concentration of 1%, with average value of reflection loss was (-31.9289±4.0094 dB.Keywords: chitosan, material packaging, microwave, reflection loss

Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages

International Nuclear Information System (INIS)

1993-10-01

This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

Packaging and transportation of radioactive materials

Energy Technology Data Exchange (ETDEWEB)

None

1978-01-01

The presentations made at the Symposium on Packaging and Transportation of Radioactive Materials are included. The purpose of the meeting was for the interchange of information on the technology and politics of radioactive material transportation. Separate abstracts were prepared for individual items. (DC)

Packaging and transportation of radioactive materials

International Nuclear Information System (INIS)

1978-01-01

The presentations made at the Symposium on Packaging and Transportation of Radioactive Materials are included. The purpose of the meeting was for the interchange of information on the technology and politics of radioactive material transportation. Separate abstracts were prepared for individual items

The innovative application studty on eco-packaging design and materials

OpenAIRE

Cui Yong Min; Ren Xin Guang

2016-01-01

The paper solves the increasingly deteriorate environmental problems by positively exploring how to utilize and develop eco-packaging design reasonably. The paper explores an effective method that combines eco-packaging and environmental protection materials, hoping to define the sustainable development road of packaging design. The paper is centered on the design application of eco-packaging and environmental protection materials, applies and analyzes the method to obtain innovative design r...

Hazardous materials routing - risk management of mismanagement

International Nuclear Information System (INIS)

Glickman, T.S.

1988-01-01

Along with emergency planning and preparedness, the placement of restrictions on routing has become an increasingly popular device for managing the highway and rail risks of hazardous materials transportation. Federal studies conducted in 1985 indicate that at that time there were 513 different state and local restrictions on the routing of hazardous materials for these two modes of transportation, and that there were 136 state and local notification requirements, that is, restrictions that take the form of a statute or ordinance requiring advance warning or periodic reporting about hazardous materials shipments. Routing restrictions also take the form of prohibiting the use of road, a tunnel, or a bridge for a specified set of hazardous materials

76 FR 51324 - Hazardous Materials: Incorporating Rail Special Permits Into the Hazardous Materials Regulations

Science.gov (United States)

2011-08-18

... through use of electronic data interchange (EDI). The IVOHMA states ``differences in hazard communication... and on the possible effects EDI may have on distributing hazardous materials shipping paper... consider the use of EDI in other modes of transport in a future rulemaking. Petition No. P-1567 PHMSA...

A comprehensive approach to managing hazardous materials

International Nuclear Information System (INIS)

Donovan, A.

1990-01-01

An increased emphasis on the need for environmental protection indicates that engineers must now consider the disposition of unused hazardous materials as waste. Before specifying and ordering materials, the engineer must consider the impact of the Resource Conservation and Recovery Act (RCRA) and the Occupational Safety and Health Administration's (OSHA's) Hazard Communication Standard. Many commonly used materials such as paint, solvents, glues, and sealants fall under the requirements of these regulations. This paper presents a plant to manage hazardous materials at the US Department of Energy's (DOE's) Waste Isolation Pilot Plant (WIPP), which is managed and operated by Westinghouse Electric Corporation. The basic elements of the plan are training, hazard communication, storage and handling, tracking, and disposal. Steps to be taken to develop the plan are outlined, problems and successes are addressed, and interactions among all affected departments are identified. The benefits of an organized and comprehensive approach to managing hazardous materials are decreased worker injuries, reduction of accidental releases, minimization of waste, and compliance with federal, state, and local safety and environmental laws. In summary, the benefits of an organized program for the management of hazardous materials include compliance with the Environmental Protection Agency's (EPA's) requirements, demonstration of Westinghouse's role as a responsible corporate entity, and reduction of waste management costs

Application of United States Department of Transportation regulations to hazardous material and waste shipments on the Hanford site

International Nuclear Information System (INIS)

Burnside, M.E.

1992-01-01

All hazardous material and waste transported over roadways open to the public must be in compliance with the U.S. Department of Transportation (DOT) regulations. The DOT states that the hazardous material regulations (HMR) also apply to government-owned, contractor-operated (GOCO) transportation operations over any U.S. Department of Energy (DOE) site roadway where the public has free and unrestricted access. Hazardous material and waste in packages that do not meet DOT regulations must be transported on DOE site roadways in a manner that excludes the public and nonessential workers. At the DOE Richland Field Office (the Hanford Site), hazardous material and waste movements that do not meet DOT requirements are transported over public access roadways during off-peak hours with the roadways barricaded. These movements are accomplished using a transportation plan that involves the DOE, DOE contractors, and private utilities who operate on or near the Hanford Site. This method, which is used at the Hanford Site to comply with DOT regulations onsite, can be communicated to other DOE sites to provide a basis for achieving consistency in similar transportation operations. (author)

77 FR 49167 - Hazardous Materials: Harmonization with International Standards (RRR)

Science.gov (United States)

2012-08-15

..., but are not limited to, the authorization to allow wood as a material of package construction for... to the regulated community with respect to the material of construction authorized for such packages... amendments include, but are not limited to, the authorization to use wood as a material of package...

30 CFR 56.16004 - Containers for hazardous materials.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Containers for hazardous materials. 56.16004 Section 56.16004 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND... Storage and Handling § 56.16004 Containers for hazardous materials. Containers holding hazardous materials...

30 CFR 57.16004 - Containers for hazardous materials.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Containers for hazardous materials. 57.16004 Section 57.16004 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF LABOR METAL AND... Storage and Handling § 57.16004 Containers for hazardous materials. Containers holding hazardous materials...

Hazardous materials and waste management a guide for the professional hazards manager

CERN Document Server

Cheremisinoff, Nicholas P

1995-01-01

The management of hazardous materials and industrial wastes is complex, requiring a high degree of knowledge over very broad technical and legal subject areas. Hazardous wastes and materials are diverse, with compositions and properties that not only vary significantly between industries, but within industries, and indeed within the complexity of single facilities. Proper management not only requires an understanding of the numerous and complex regulations governing hazardous materials and waste streams, but an understanding and knowledge of the treatment, post-treatment, and waste minimizatio

HMPT: Basic Radioactive Material Transportation

Energy Technology Data Exchange (ETDEWEB)

Hypes, Philip A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-02-29

Hazardous Materials and Packaging and Transportation (HMPT): Basic Radioactive Material Transportation Live (#30462, suggested one time) and Test (#30463, required initially and every 36 months) address the Department of Transportation’s (DOT’s) function-specific [required for hazardous material (HAZMAT) handlers, packagers, and shippers] training requirements of the HMPT Los Alamos National Laboratory (LANL) Labwide training. This course meets the requirements of 49 CFR 172, Subpart H, Section 172.704(a)(ii), Function-Specific Training.

Complex-wide representation of material packaged in 3013 containers

Energy Technology Data Exchange (ETDEWEB)

Narlesky, Joshua E.; Peppers, Larry G.; Friday, Gary P.

2009-06-01

The DOE sites packaging plutonium oxide materials packaged according to Department of Energy 3013 Standard (DOE-STD-3013) are responsible for ensuring that the materials are represented by one or more samples in the Materials Identification and Surveillance (MIS) program. The sites categorized most of the materials into process groups, and the remaining materials were characterized, based on the prompt gamma analysis results. The sites issued documents to identify the relationships between the materials packaged in 3013 containers and representative materials in the MIS program. These “Represented” documents were then reviewed and concurred with by the MIS Working Group. However, these documents were developed uniquely at each site and were issued before completion of sample characterization, small-scale experiments, and prompt gamma analysis, which provided more detailed information about the chemical impurities and the behavior of the material in storage. Therefore, based on the most recent data, relationships between the materials packaged in 3013 containers and representative materials in the MIS program been revised. With the prompt gamma analysis completed for Hanford, Rocky Flats, and Savannah River Site 3013 containers, MIS items have been assigned to the 3013 containers for which representation is based on the prompt gamma analysis results. With the revised relationships and the prompt gamma analysis results, a Master “Represented” table has been compiled to document the linkages between each 3013 container packaged to date and its representative MIS items. This table provides an important link between the Integrated Surveillance Program database, which contains information about each 3013 container to the MIS items database, which contains the characterization, prompt gamma data, and storage behavior data from shelf-life experiments for the representative MIS items.

Complex-wide representation of material packaged in 3013 containers

International Nuclear Information System (INIS)

Narlesky, Joshua E.; Peppers, Larry G.; Friday, Gary P.

2009-01-01

The DOE sites packaging plutonium oxide materials packaged according to Department of Energy 3013 Standard (DOE-STD-3013) are responsible for ensuring that the materials are represented by one or more samples in the Materials Identification and Surveillance (MIS) program. The sites categorized most of the materials into process groups, and the remaining materials were characterized, based on the prompt gamma analysis results. The sites issued documents to identify the relationships between the materials packaged in 3013 containers and representative materials in the MIS program. These 'Represented' documents were then reviewed and concurred with by the MIS Working Group. However, these documents were developed uniquely at each site and were issued before completion of sample characterization, small-scale experiments, and prompt gamma analysis, which provided more detailed information about the chemical impurities and the behavior of the material in storage. Therefore, based on the most recent data, relationships between the materials packaged in 3013 containers and representative materials in the MIS program have been revised. With the prompt gamma analysis completed for Hanford, Rocky Flats, and Savannah River Site 3013 containers, MIS items have been assigned to the 3013 containers for which representation is based on the prompt gamma analysis results. With the revised relationships and the prompt gamma analysis results, a Master 'Represented' table has been compiled to document the linkages between each 3013 container packaged to date and its representative MIS items. This table provides an important link between the Integrated Surveillance Program database, which contains information about each 3013 container to the MIS items database, which contains the characterization, prompt gamma data, and storage behavior data from shelf-life experiments for the representative MIS items

A guide to the suitability of elastomeric seal materials for use in radioactive material transport packages

International Nuclear Information System (INIS)

Vince, D.J.

2004-01-01

Elastomeric seals are a frequently favoured method of sealing Radioactive Material Transport (RMT) packages. The sealing technology has been proven for many years in a wide range of industrial applications. The requirements of the RMT package applications, however, are significantly different from those commonly found in other industries. This guide outlines the Regulatory performance requirements placed on an RMT package sealing system by TS-R-1, and then summarises the material, environment and geometry characteristics of elastomeric seals relevant to RMT applications. Tables in the guide list typical material properties for a range of elastomeric materials commonly used in RMT packages

75 FR 75157 - Importation of Wood Packaging Material From Canada

Science.gov (United States)

2010-12-02

... Material From Canada AGENCY: Animal and Plant Health Inspection Service, USDA. ACTION: Proposed rule... remove the exemption that allows wood packaging material from Canada to enter the United States without... spread of pests via wood packaging material from Canada. DATES: We will consider all comments that we...

19 CFR 10.461 - Retail packaging materials and containers.

Science.gov (United States)

2010-04-01

... Free Trade Agreement Rules of Origin § 10.461 Retail packaging materials and containers. Packaging... classification set out in General Note 26(n), HTSUS. If the good is subject to a regional value content... non-originating materials, as the case may be, in calculating the regional value content of the good...

Health and safety information program for hazardous materials

International Nuclear Information System (INIS)

O'Brien, M.P.; Fallon, N.J.; Kuehner, A.V.

1979-01-01

The system is used as a management tool in several safety and health programs. It is used to: trace the use of hazardous materials and to determine monitoring needs; inform the occupational physician of the potential health problems associated with materials ordered by a given individual; inform the fire and rescue group of hazardous materials in a given building; provide waste disposal recommendations to the hazardous waste management group; assist the hazardous materials shipping coordinator in identifying materials which are regulated by the Department of Transportation; and guide management decisions in the area of recognizing and rectifying unsafe conditions. The information system has been expanded from a manual effort to provide a brief description of health hazards of chemicals used at the lab to a computerized health and safety information system which serves the needs of all personnel who may encounter the material in the course of their work. The system has been designed to provide information needed to control the potential problems associated with a hazardous material up to the time that it is consumed in a given operation or is sent to the waste disposal facility

Performance-Oriented packaging: A guide to identifying, procuring, and using

International Nuclear Information System (INIS)

O'Brien, J.H.

1992-09-01

This document guides users through the process of correctly identifying, obtaining, and using performance-oriented packaging. Almost all hazardous material shipments can be made in commercially available performance-oriented packaging. To cover the remaining shipments requiring specially designed packaging, a design guide is being developed. The design guide is scheduled to be issued 1 year after this procurement guide

Directory of certificates of compliance for radioactive materials packages; Summary Report of NRC Approved Packages

International Nuclear Information System (INIS)

1980-12-01

This directory contains a Summary Report of NRC approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the U.S. Nuclear Regulatory Commission. To assist in identifying packaging, and index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material using these packagings must be in accordance with the provisions of 49 CFR 173.393a and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure them--that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

Safety Analysis Report for Packaging, Y-12 National Security Complex, Model ES-3100 Package with Bulk HEU Contents

Energy Technology Data Exchange (ETDEWEB)

Anderson, James [Y-12 National Security Complex, Oak Ridge, TN (United States); Goins, Monty [Y-12 National Security Complex, Oak Ridge, TN (United States); Paul, Pran [Y-12 National Security Complex, Oak Ridge, TN (United States); Wilkinson, Alan [Y-12 National Security Complex, Oak Ridge, TN (United States); Wilson, David [Y-12 National Security Complex, Oak Ridge, TN (United States)

2015-09-03

This safety analysis report for packaging (SARP) presents the results of the safety analysis prepared in support of the Consolidated Nuclear Security, LLC (CNS) request for licensing of the Model ES-3100 package with bulk highly enriched uranium (HEU) contents and issuance of a Type B(U) Fissile Material Certificate of Compliance. This SARP, published in the format specified in the Nuclear Regulatory Commission (NRC) Regulatory Guide 7.9 and using information provided in UCID-21218 and NRC Regulatory Guide 7.10, demonstrates that the Y-12 National Security Complex (Y-12) ES-3100 package with bulk HEU contents meets the established NRC regulations for packaging, preparation for shipment, and transportation of radioactive materials given in Title 10, Part 71, of the Code of Federal Regulations (CFR) [10 CFR 71] as well as U.S. Department of Transportation (DOT) regulations for packaging and shipment of hazardous materials given in Title 49 CFR. To protect the health and safety of the public, shipments of adioactive materials are made in packaging that is designed, fabricated, assembled, tested, procured, used, maintained, and repaired in accordance with the provisions cited above. Safety requirements addressed by the regulations that must be met when transporting radioactive materials are containment of radioactive materials, radiation shielding, and assurance of nuclear subcriticality.

Hazardous and mixed waste transportation program

International Nuclear Information System (INIS)

Hohnstreiter, G.F.; Glass, R.E.; McAllaster, M.E.; Nigrey, P.J.; Trennel, A.J.; Yoshimura, H.R.

1993-01-01

Sandia National Laboratories (SNL) has developed a program to address the packaging needs associated with the transport of hazardous and mixed waste during the United States' Department of Energy (DOE) remediation efforts. The program addresses the technology needs associated with the transport of materials which have components that are radioactive and chemically hazardous. The mixed waste transportation activities focus on on-site specific applications of technology to the transport of hazardous and mixed wastes. These activities were identified at a series of DOE-sponsored workshops. These activities will be composed of the following: (1) packaging concepts, (2) chemical compatibility studies, and (3) systems studies. This paper will address activities in each of these areas. (J.P.N.)

Hazardous and Mixed Waste Transportation Program

International Nuclear Information System (INIS)

Hohnstreiter, G.F.; Glass, R.E.; McAllaster, M.E.; Nigrey, P.J.; Trennel, A.J.; Yoshimura, H.R.

1991-01-01

Sandia National Laboratories (SNL) has developed a program to address the packaging needs associated with the transport of hazardous and mixed waste during the United States' Department of Energy (DOE) remediation efforts. The program addresses the technology needs associated with the transport of materials which have components that are radioactive and chemically hazardous. The mixed waste transportation activities focus on on-site specific applications of technology to the transport of hazardous and mixed wastes. These activities were identified at a series of DOE-sponsored workshops. These activities will be composed of the following: (1) packaging concepts, (2) chemical compatibility studies, and (3) systems studies. This paper will address activities in each of these areas

Reuse and recycling of radioactive material packaging

International Nuclear Information System (INIS)

Gerulis, Eduardo; Zapparoli, Carlos Leonel; Barboza, Marycel Figols de

2009-01-01

Human development is directly linked to energy consumption. The political decisions (to this human development) result in economic, social and environmental aspects, whose magnitude should maintain the sustainability of every aspect for not to collapsing. The environmental aspect has been a target of research because of the excessive emission of gases which contributes to the greenhouse effect. The production processes emit gases due to the consumption of energy to get it, but it is necessary to maintain the environmental sustainability in order to minimize the contribution to the emission of greenhouse gases. The population control and the energetic efficiency are factors that contribute to the environmental sustainability. Besides them, the culture of consumption is another factor that, when applied to the reduction of emissions, also contributes to the sustainability of the environment. The reuse of materials is one of the sub-factors which contribute to the reduction of emissions. The Radiopharmacy Directory (DIRF) at IPEN-CNEN/SP, produces radiopharmaceuticals that are necessary to improve the Brazilian population's life quality. The radiopharmaceuticals are transported in packaging to the transport of radioactive material. These packages are considered non-biodegradable, because some metals, which make up these packages, pollute the environment. These packages have increased costs, in addition, because it must be approved in tests of integrity. The reuse of packaging in favorable situations to the same purpose is a way to help the environment degradation and costs reduction. The packaging reuse in unfavorable situations disobey rules or return logistics that become effective the transport back, but the consumption culture strengthening can change this situation. This paper describes IPEN's packaging, form and quantities distribution, and the packaging that comes back to be reused. (author)

Performance-oriented packaging: A guide to identifying, procuring, and using. Procurement and use of packaging using HM-181 regulations

International Nuclear Information System (INIS)

1994-09-01

This document addresses procurement of nonbulk packaging used for nonradioactive, hazardous materials that are transported by highway. The basic procedure is the same when making shipments by other modes. However, other sections of the regulations may affect the packaging requirements when shipping by other modes. The variation in requirements is extensive when air transportation is selected. A packaging engineer or transportation specialist should be contacted for guidance wen transport is by a mode other than highway

Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages

International Nuclear Information System (INIS)

1979-10-01

This directory contains a Summary Report of NRC Approved Packages for radioactive material packages effective September 14, 1979. Purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory

Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages

Energy Technology Data Exchange (ETDEWEB)

None

1979-10-01

This directory contains a Summary Report of NRC Approved Packages for radioactive material packages effective September 14, 1979. Purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory.

78 FR 24309 - Pipeline and Hazardous Materials Safety Administration

Science.gov (United States)

2013-04-24

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration List of Special Permit Applications Delayed AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA..., Pipeline and Hazardous Materials Safety Administration, U.S. Department of Transportation, East Building...

Directory of certificates of compliance for radioactive materials packages

International Nuclear Information System (INIS)

1991-10-01

This directory contains a Report of NRC Approved Packages (Volume 1) for Radioactive Materials Packages. The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

The use of dual material seals for packaging

International Nuclear Information System (INIS)

Temus, C.J.; Nichols, J.C.

2004-01-01

The use of dual material seals, metal and elastomeric for a transportation package, provides a viable option for packages requiring high temperature seal capability. Allowing the seal area to go to higher temperatures then allowed for all elastomeric seal reduce the necessity of providing thermal protection during a postulated accident condition fire. It also increases the options for impact limiting features that do not also mitigate the affects of accident thermal events. Typically, high temperature seals require the use of metal O-rings. Only one seal (typically identified as the containment seal) needs to survive the hypothetical accident conditions, including the high temperatures that may occur during the prescribed hypothetical thermal event. However, to expedite the assembly leakage rate testing of radioactive material packages, a dual O-ring seal arrangement is often used to allow creation of a relatively small volume test cavity between the seals. For any package that is being used on a frequent basis, the total cost of seals can be significantly reduced by using an elastomeric seal as the secondary seal. The elastomeric seal is not the containment boundary seal and does not need to survive the high temperature condition. To get the dual material O-ring seals to seat properly, a different approach has to be taken than with closure of a radioactive material package that does not use metallic O-ring(s). A metal O-ring requires an application of a seating force while the elastomeric package requires a certain percentage of deformation. This is further complicated when the seating force is developed using a multi-bolt closure. Because of the nature of multi-bolt closures, elastic interaction prevents the equal application of force. This paper develops the methods involved in properly closing and establishing containment when using dual material seals with a multi-bolt closure. These methods were demonstrated in two production casks requiring testing leak

76 FR 45332 - Pipeline and Hazardous Materials Safety Administration

Science.gov (United States)

2011-07-28

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration Office of... Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: List of Applications for Modification of..., 2011. ADDRESSES: Record Center, Pipeline and Hazardous Materials Safety Administration, U.S. Department...

Peer Review of the Waste Package Material Performance Interim Report

International Nuclear Information System (INIS)

J. A. Beavers; T. M. Devine, Jr.; G. S. Frankel; R. H. Jones; R. G. Kelly; R. M. Latanision; J. H. Payer

2001-01-01

At the request of the U.S. Department of Energy, Bechtel SAIC Company, LLC, formed the Waste Package Materials Performance Peer Review Panel (the Panel) to review the technical basis for evaluating the long-term performance of waste package materials in a proposed repository at Yucca Mountain, Nevada. This is the interim report of the Panel; a final report will be issued in February 2002. In its work to date, the Panel has identified important issues regarding waste package materials performance. In the remainder of its work, the Panel will address approaches and plans to resolve these issues. In its review to date, the Panel has not found a technical basis to conclude that the waste package materials are unsuitable for long-term containment at the proposed Yucca Mountain Repository. Nevertheless, significant technical issues remain unsettled and, primarily because of the extremely long life required for the waste packages, there will always be some uncertainty in the assessment. A significant base of scientific and engineering knowledge for assessing materials performance does exist and, therefore, the likelihood is great that uncertainty about the long-term performance can be substantially reduced through further experiments and analysis

Standard Guide for Packaging Materials for Foods to Be Irradiated

CERN Document Server

American Society for Testing and Materials. Philadelphia

2009-01-01

1.1 This guide provides a format to assist producers and users of food packaging materials in selecting materials that have the desirable characteristics for their intended use and comply with applicable standards or government authorizations. It outlines parameters that should be considered when selecting food-contact packaging materials intended for use during irradiation of prepackaged foods and it examines the criteria for fitness for their use. 1.2 This guide identifies known regulations and regulatory frameworks worldwide pertaining to packaging materials for holding foods during irradiation; but it does not address all regulatory issues associated with the selection and use of packaging materials for foods to be irradiated. It is the responsibility of the user of this guide to determine the pertinent regulatory issues in each country where foods are to be irradiated and where irradiated foods are distributed. 1.3 This guide does not address all of the food safety issues associated with the synergisti...

HMPT: Hazardous Waste Transportation Live 27928, Test 27929

Energy Technology Data Exchange (ETDEWEB)

Simpson, Lewis Edward [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2016-03-17

HMPT: Hazardous Waste Transportation (Live 27928, suggested one time and associated Test 27929, required initially and every 36 months) addresses the Department of Transportation (DOT) function-specific training requirements of the hazardous materials packagings and transportation (HMPT) Los Alamos National Laboratory (LANL) lab-wide training. This course addresses the requirements of the DOT that are unique to hazardous waste shipments. Appendix B provides the Title 40 Code of Federal Regulations (CFR) reference material needed for this course.

19 CFR 10.539 - Retail packaging materials and containers.

Science.gov (United States)

2010-04-01

...-Singapore Free Trade Agreement Rules of Origin § 10.539 Retail packaging materials and containers. Packaging... requirement. The United States importer of good C decides to use the build-down method, RVC=((AV−VNM)/AV... content requirement. In applying this method, the non-originating blister packages are taken into account...

Waste disposal package

Science.gov (United States)

Smith, M.J.

1985-06-19

This is a claim for a waste disposal package including an inner or primary canister for containing hazardous and/or radioactive wastes. The primary canister is encapsulated by an outer or secondary barrier formed of a porous ceramic material to control ingress of water to the canister and the release rate of wastes upon breach on the canister. 4 figs.

Management of waste from packaging of construction materials in building construction works

OpenAIRE

González Pericot, Natalia; Río Merino, Mercedes del

2011-01-01

Every material arriving at the construction site comes protected in some type of packaging, fundamentally cardboard, plastic or wood, and presently the great majority of these packagings finish in a container mixed with the rest of waste of the construction work. The increasing tendency to use prefabricated materials increases the volume of packaging necessary in product transport; in addition, the traditional materials also arrive more protected with packaging. A specific management for ...

Transportation of hazardous materials (hazmat) a literature survey

OpenAIRE

Zafer YILMAZ; Serpil EROL; Hakan Soner APLAK

2016-01-01

ransportation has a great role in logistics. Many researchers have studied on transportation and vehicle routing problems. Transportation of hazardous materials (hazmat) is a special subject for logistics. Causalities due to the accidents caused by trucks carrying hazardous materials will be intolerable. Many researchers have studied on risk assessment of hazmat transportation to find ways for reducing hazardous material transportation risks. Some researchers have studied routing of hazmat tr...

Provision of transport packaging for radioactive materials

International Nuclear Information System (INIS)

1981-04-01

The safe transport of radioactive materials is governed by various regulations based on International Atomic Energy Agency Regulations. This code of practice is a supplement to the regulations, its objects being (a) to advise designers of packaging on the technical features necessary to conform to the regulations, and (b) to outline the requirements for obtaining approval of package designs from the competent authority. (U.K.)

Navy Shipboard Hazardous Material Minimization Program

Energy Technology Data Exchange (ETDEWEB)

Bieberich, M.J. [Naval Surface Warfare Center, Annapolis, MD (United States). Carderock Div.; Robinson, P. [Life Cycle Engineering, Inc., Charleston, SC (United States); Chastain, B.

1994-12-31

The use of hazardous (and potentially hazardous) materials in shipboard cleaning applications has proliferated as new systems and equipments have entered the fleet to reside alongside existing equipments. With the growing environmental awareness (and additional, more restrictive regulations) at all levels/echelon commands of the DoD, the Navy has initiated a proactive program to undertake the minimization/elimination of these hazardous materials in order to eliminate HMs at the source. This paper will focus on the current Shipboard Hazardous Materials Minimization Program initiatives including the identification of authorized HM currently used onboard, identification of potential substitute materials for HM replacement, identification of new cleaning technologies and processes/procedures, and identification of technical documents which will require revision to eliminate the procurement of HMs into the federal supply system. Also discussed will be the anticipated path required to implement the changes into the fleet and automated decision processes (substitution algorithm) currently employed. The paper will also present the most recent technologies identified for approval or additional testing and analysis including: supercritical CO{sub 2} cleaning, high pressure blasting (H{sub 2}O + baking soda), aqueous and semi-aqueous cleaning materials and processes, solvent replacements and dedicated parts washing systems with internal filtering capabilities, automated software for solvent/cleaning process substitute selection. Along with these technological advances, data availability (from on-line databases and CDROM Database libraries) will be identified and discussed.

SOR/89-426, Transport Packaging of Radioactive Materials Regulations, amendment

International Nuclear Information System (INIS)

1989-01-01

These Regulations of 24 August 1989 amend the Transport Packaging of Radioactive Materials Regulations by clarifying the text and specifying certain requirements. In particular certain definitions have been replaced, namely those of ''Fissile Class III package'' and ''Special form radioactive material''. Also, this latter material may not be carried without a certificate attesting that it meets the requirements of the Regulations. (NEA)

Directory of certificates of compliance for radioactive materials packages: Report of NRC approved quality assurance programs for radioactive material packages

International Nuclear Information System (INIS)

1988-12-01

This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), all Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1988. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Directory of certificates of compliance for radioactive materials packages. Volume 1. Summary report of NRC approved packages

International Nuclear Information System (INIS)

1977-12-01

Purpose of this directory is to make available a convenient source of information on packagings which have been approved by the U.S. Nuclear Regulatory Commission. This volume contains a summary report of NRC-approved packages for radioactive material packages effective Nov. 30, 1977

Directory of certificates of compliance for radioactive materials packages

International Nuclear Information System (INIS)

1991-10-01

This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12., it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

Directory of certificates of compliance for radioactive materials packages: Summary report of NRC approved quality assurance programs for radioactive material packages

International Nuclear Information System (INIS)

1987-11-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1987. This directory makes available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Material flow analysis for an industry - A case study in packaging

Science.gov (United States)

Amey, E.B.; Sandgren, K.

1996-01-01

The basic materials used in packaging are glass, metals (primarily aluminum and steel), an ever-growing range of plastics, paper and paperboard, wood, textiles for bags, and miscellaneous other materials (such as glues, inks, and other supplies). They are fabricated into rigid, semi-rigid, or flexible containers. The most common forms of these containers include cans, drums, bottles, cartons, boxes, bags, pouches, and wraps. Packaging products are, for the most part, low cost, bulky products that are manufactured close to their customers. There is virtually no import or export of packaging products. A material flow analysis can be developed that looks at all inputs to an industrial sector, inventories the losses in processing, and tracks the fate of the material after its useful life. An example is presented that identifies the material inputs to the packaging industry, and addresses the ultimate fate of the materials used. ?? 1996 International Association for Mathematical Geology.

Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC approved packages

International Nuclear Information System (INIS)

1988-12-01

This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), all Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1988. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Directory of certificates of compliance for radioactive materials packages, Report of NRC approved packages

International Nuclear Information System (INIS)

1990-10-01

This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Materials Packages effective October 1, 1990. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Degradation modes of nickel-base alternate waste package overpack materials

International Nuclear Information System (INIS)

Pitman, S.G.

1988-07-01

The suitability of Ti Grade 12 for waste package overpacks has been questioned because of its observed susceptibility to crevice corrosion and hydrogen-assisted crack growth. For this reason, materials have been selected for evaluation as alternatives to Ti Grade 12 for use as waste package overpacks. These alternative materials, which are based on the nickel-chromium-molybdenum (Ni-Cr-Mo) alloy system, are Inconel 625, Hastelloy C-276, and Hastelloy C-22. The degradation modes of the Ni-base alternate materials have been examined at Pacific Northwest Laboratory to determine the suitability of these materials for waste package overpack applications in a salt repository. Degradation modes investigated included general corrosion, crevice corrosion, pitting, stress-corrosion cracking, and hydrogen embrittlement

Thermal Upgrading of 9977 Radioactive Material (Ram) Type B Package

International Nuclear Information System (INIS)

Gupta, N.; Abramczyk, G.

2012-01-01

The 9977 package is a radioactive material package that was originally certified to ship Heat Sources and RTG contents up to 19 watts and it is now being reviewed to significantly expand its contents in support of additional DOE missions. Thermal upgrading will be accomplished by employing stacked 3013 containers, a 3013 aluminum spacer and an external aluminum sleeve for enhanced heat transfer. The 7th Addendum to the original 9977 package Safety Basis Report describing these modifications is under review for the DOE certification. The analyses described in this paper show that this well-designed and conservatively analyzed package can be upgraded to carry contents with decay heat up to 38 watts with some simple design modifications. The Model 9977 package has been designed as a replacement for the Department of Transportation (DOT) Fissile Specification 6M package. The 9977 package is a very versatile Type B package which is certified to transport and store a wide spectrum of radioactive materials. The package was analyzed quite conservatively to increase its usefulness and store different payload configurations. Its versatility is evident from several daughter packages such as the 9978 and H1700, and several addendums where the payloads have been modified to suit the Shipper's needs without additional testing.

Safety Evaluation for Packaging (onsite) T Plant Canyon Items

International Nuclear Information System (INIS)

OBRIEN, J.H.

2000-01-01

This safety evaluation for packaging (SEP) evaluates and documents the ability to safely ship mostly unique inventories of miscellaneous T Plant canyon waste items (T-P Items) encountered during the canyon deck clean off campaign. In addition, this SEP addresses contaminated items and material that may be shipped in a strong tight package (STP). The shipments meet the criteria for onsite shipments as specified by Fluor Hanford in HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments

Safety Evaluation for Packaging (onsite) T Plant Canyon Items

Energy Technology Data Exchange (ETDEWEB)

OBRIEN, J.H.

2000-07-14

This safety evaluation for packaging (SEP) evaluates and documents the ability to safely ship mostly unique inventories of miscellaneous T Plant canyon waste items (T-P Items) encountered during the canyon deck clean off campaign. In addition, this SEP addresses contaminated items and material that may be shipped in a strong tight package (STP). The shipments meet the criteria for onsite shipments as specified by Fluor Hanford in HNF-PRO-154, Responsibilities and Procedures for all Hazardous Material Shipments.

Directory of certificates of compliance for radioactive materials packages

International Nuclear Information System (INIS)

1991-10-01

This directory contains Certificates of Compliance (Volume 2) for Radioactive Materials Packages. The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

Influence of factors on release of antimicrobials from antimicrobial packaging materials.

Science.gov (United States)

Wu, Yu-Mei; Wang, Zhi-Wei; Hu, Chang-Ying; Nerín, Cristina

2018-05-03

Antimicrobial packaging materials (films or coatings) (APMs) have aroused great interest among the scientists or the experts specialized in material science, food science, packaging engineering, biology and chemistry. APMs have been used to package the food, such as dairy products, poultry, meat (e.g., beef), salmon muscle, pastry dough, fresh pasta, bakery products, fruits, vegetables and beverages. Some materials have been already commercialized. The ability of APMs to extend the shelf-life of the food depends on the release rate of the antimicrobials (AMs) from the materials to the food. The optimum rate is defined as target release rate (TRR). To achieve TRR, the influencing factors of the release rate should be considered. Herein we reviewed for the first time these factors and their influence on the release. These factors mainly include the AMs, food (or food simulant), packaging materials, the interactions among them, the temperature and environmental relative humidity (RH).

44 years of testing radioactive materials packages at ORNL

Energy Technology Data Exchange (ETDEWEB)

Shappert, L.B.; Ludwig, S.B. [Oak Ridge National Lab., Oak Ridge, TN (United States)

2004-07-01

This paper briefly reviews the package testing at the Oak Ridge National Laboratory (ORNL) since 1960 and then examines the trends in the testing activities that occurred during the same period. Radioactive material shipments have been made from ORNL since the 1940s. The first fully operating reactor built at the ORNL site was patterned after the graphite pile constructed by Enrico Fermi under Stagg Field in Chicago. After serving as a test bed for future reactors, it became useful as a producer of radioactive isotopes. The Isotopes Division was established at ORNL to furnish radioactive materials used in the medical community. Often these shipments have been transported by aircraft worldwide due to the short half-lives of many of the materials. This paper touches briefly on the lighter and smaller radioisotope packages that were being shipped from ORNL in large numbers and then deals with the testing of packages designed to handle large radioactive sources, such as spent fuel, and other fissile materials.

44 years of testing radioactive materials packages at ORNL

International Nuclear Information System (INIS)

Shappert, L.B.; Ludwig, S.B.

2004-01-01

This paper briefly reviews the package testing at the Oak Ridge National Laboratory (ORNL) since 1960 and then examines the trends in the testing activities that occurred during the same period. Radioactive material shipments have been made from ORNL since the 1940s. The first fully operating reactor built at the ORNL site was patterned after the graphite pile constructed by Enrico Fermi under Stagg Field in Chicago. After serving as a test bed for future reactors, it became useful as a producer of radioactive isotopes. The Isotopes Division was established at ORNL to furnish radioactive materials used in the medical community. Often these shipments have been transported by aircraft worldwide due to the short half-lives of many of the materials. This paper touches briefly on the lighter and smaller radioisotope packages that were being shipped from ORNL in large numbers and then deals with the testing of packages designed to handle large radioactive sources, such as spent fuel, and other fissile materials

US Hazardous Materials Routes, Geographic WGS84, BTS (2006) [hazardous_material_routes_BTS_2006

Data.gov (United States)

Louisiana Geographic Information Center — The Federal Motor Carrier Safety Administration (FMCSA) Hazardous Material Routes were developed using the 2004 First Edition TIGER/Line files. The routes are...

Safety analysis report for packaging (onsite) transuranic performance demonstration program sample packaging

International Nuclear Information System (INIS)

Mccoy, J.C.

1997-01-01

The Transuranic Performance Demonstration Program (TPDP) sample packaging is used to transport highway route controlled quantities of weapons grade (WG) plutonium samples from the Plutonium Finishing Plant (PFP) to the Waste Receiving and Processing (WRAP) facility and back. The purpose of these shipments is to test the nondestructive assay equipment in the WRAP facility as part of the Nondestructive Waste Assay PDP. The PDP is part of the U. S. Department of Energy (DOE) National TRU Program managed by the U. S. Department of Energy, Carlsbad Area Office, Carlsbad, New Mexico. Details of this program are found in CAO-94-1045, Performance Demonstration Program Plan for Nondestructive Assay for the TRU Waste Characterization Program (CAO 1994); INEL-96/0129, Design of Benign Matrix Drums for the Non-Destructive Assay Performance Demonstration Program for the National TRU Program (INEL 1996a); and INEL-96/0245, Design of Phase 1 Radioactive Working Reference Materials for the Nondestructive Assay Performance Demonstration Program for the National TRU Program (INEL 1996b). Other program documentation is maintained by the national TRU program and each DOE site participating in the program. This safety analysis report for packaging (SARP) provides the analyses and evaluations necessary to demonstrate that the TRU PDP sample packaging meets the onsite transportation safety requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for an onsite Transportation Hazard Indicator (THI) 2 packaging. This SARP, however, does not include evaluation of any operations within the PFP or WRAP facilities, including handling, maintenance, storage, or operating requirements, except as they apply directly to transportation between the gate of PFP and the gate of the WRAP facility. All other activities are subject to the requirements of the facility safety analysis reports (FSAR) of the PFP or WRAP facility and requirements of the PDP

FFTF railroad tank car Safety Evaluation for Packaging

International Nuclear Information System (INIS)

Carlstrom, R.F.

1995-01-01

This Safety Evaluation for Packaging (SEP) provides evaluations considered necessary to approve transfer of the 8,000 gallon Liquid Waste Tank Car (LWTC) from Fast Flux Test Facility (FFTF) to the 200 Areas. This SEP will demonstrate that the transfer of the LWTC will provide an equivalent degree of safety as would be provided by packages meeting U.S. Department of Transportation (DOT) requirements. This fulfills onsite transportation requirements implemented in the Hazardous Material Packaging and Shipping, WHC-CM-2-14

Perceptions of the use of indigenous leaves as packaging materials ...

African Journals Online (AJOL)

Although alternative food packaging materials are available, Ghanaians still use leaves to package some ready-to-eat cornmeal products. This study examines the perceptions of a representative community sample of 70 producers, 40 sellers and 120 consumers of ready-to-eat leaves-packaged cornmeal products in ...

Towards a Generic Set of Packaging Material Key Figures

NARCIS (Netherlands)

ten Klooster, Roland; de Koeijer, Bjorn; de Lange, Jos

Many companies consider the reduction of packaging material as a relevant development direction, either required by cost savings, supply chain efficiency, sustainability or substantiated by regulations (directive 94/62/EC). This aligns with an eco-efficient redundancy perspective on packaging.

Flat-plate solar collector - installation package

Science.gov (United States)

1978-01-01

Package includes installation, operation and maintenance manual for collector, analysis of safety hazards, special handling instructions, materials list, installation drawings, and warranty and certification statement. Manual includes instructions for roof preparation and for preparing collector for installation. Several pages are devoted to major and minor repairs.

Consideration of radiation effects in the choice of packaging materials

International Nuclear Information System (INIS)

Moore, P.W.

1985-01-01

Requirements for food packaging materials include whether there is any interaction between the food and the package during or after the irradiation, and whether as a result of the irradiation, volatile or leachable substances are released from the pack into the food. The performance of cellulose-based materials and plastic films under irradiation are discussed

Metal food packaging design based on hazard analysis critical control point (HACCP system in canned food safety

Directory of Open Access Journals (Sweden)

Li Xingyi

2016-06-01

Full Text Available This study aims to design metal food packaging with hazard analysis critical control point (HACCP. First, theory of HACCP was introduced in detail. Taking empty cans provided by Wuxi Huapeng Food Packaging Company as an example, we studied migration of bisphenol compounds in coating of food can to food stimulant. Moreover, packaging design of luncheon meat can was taken as an example to confirm whether HACCP system could effectively control migration of phenolic substance. Results demonstrated that, coating of such empty were more likely to contain multiple bisphenol compounds such as bisphenol A (BPA, and bisphenol A diglycidyl ether (BADGE was considered as the leading bisphenol pollutant; food stimulant of different types, storage temperature and time could all impact migration of bisphenol compounds. HACCP system was proved to be effective in controlling hazards of phenolic substance in luncheon meat can and could reduce various phenolic substance indexes to an acceptable range. Therefore, HACCP can control migration of phenolic substance and recontamination of food and thus ensure food safety.

77 FR 60334 - New Marking Standards for Parcels Containing Hazardous Materials

Science.gov (United States)

2012-10-03

... dimension of each side must be 100 mm (3.94 inches), unless the package size requires a reduced size marking...: * * * * * 10.12 Gases (Hazard Class 2) * * * * * 10.12.2 Mailability [Revise the third and fourth sentences of...

Directory of certificates of compliance for radioactive materials packages. Volume 3, Revision 14: Report of NRC approved quality assurance programs for radioactive materials packages

International Nuclear Information System (INIS)

1994-10-01

This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

Safety evaluation for packaging (onsite) SERF cask

International Nuclear Information System (INIS)

Edwards, W.S.

1997-01-01

This safety evaluation for packaging (SEP) documents the ability of the Special Environmental Radiometallurgy Facility (SERF) Cask to meet the requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for transfer of Type B quantities (up to highway route controlled quantities) of radioactive material within the 300 Area of the Hanford Site. This document shall be used to ensure that loading, tie down, transport, and unloading of the SERF Cask are performed in accordance with WHC-CM-2-14. This SEP is valid until October 1, 1999. After this date, an update or upgrade to this document is required

Directory of Certificates of Compliance for Radioactive-Materials Packages. Summary report of NRC approved quality assurance programs for radioactive material packages

International Nuclear Information System (INIS)

1983-01-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Approved Packages (Volume I), all Certificates of Compliance (Volume 2), and Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective December 31, 1982. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the back of Volumes 1 and 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Radioanalytical method to determine contaminations due to packaging materials

International Nuclear Information System (INIS)

Figge, K.

1976-01-01

The quantitative determination of the transfer of substances in the system packaging material/foodstuff is essential for the protection of consumer and with respect to food regulations. With the help of the radio tracer techniques described it is possible to determine the migration of an individual component of the packaging material into liquid and solid foodstuffs or their simulants. Parts of the radioactive test films or sheets are brought in one- or two-sided contact with the foodstuffs or their simulants using newly developed extraction and migration cells. The extracted or migrated amounts of the packaging material component are calculated from the radioactivities migrated into the contact media under the test conditions given. As an example for the application of these radio tracer techniques, investigations into the migration behaviour of the organotin stabilizer di-n-octyltin-2-ethyl-hexyl-dithioglycolate in the system rigid PVC/edible fat or test fat respectively are described. For the determination of the total components migrating from a packaging material into foodstuffs, a radio tracer method was developed making use of a 14 C-labelled standard triglyceride mixture - the fat simulant HB 307- 14 C. The efficiency of this method is demonstrated by determinations of the global migrates of polyvinylchloride films containing different amounts of platicizers and the mean error of the single determination on the amount of global migrate is discussed. (T.G.)

Qualification test of packages for transporting radioactive materials and wastes

International Nuclear Information System (INIS)

Oliveira Santos, P. de; Miaw, S.T.W.

1990-01-01

Since 1979 the Waste Treatment Division of Nuclear Tecnology Development Center has been developed and tested packagings for transporting radioactive materials and wastes. The Division has designed facilities for testing Type A packages in accordance with the adopted regulations. The Division has tested several packages for universities, research centers, industries, INB, FURNAS, etc. (author) [pt

Application of common packaging materials in the probiotic fresh cheese production

Directory of Open Access Journals (Sweden)

Mirela Iličić

2016-03-01

Full Text Available The aim of this work was to investigate the application of common packaging materials polypropylene (PP and polystyrene (PS in the probiotic fresh cheese production packaging. Probiotic and traditional cheeses were produced from milk with standardized milk fat content of 2.3 g/100 g including the application of two cultures (probiotic and traditional. The samples were packed in the PP and PS cups and stored at 4 ºC for 30 days. The observed permeability of gases through the two applied packaging materials was significantly different. Cheese samples were analysed for microbiological properties whereby lactic acid bacteria, Bifidobacterium sp. and aerobic mesophilic bacteria (AMB were determined. Packaging materials showed no significant effect on the content of ascorbic acid which is known to be sensitive to the presence of oxygen.

Ingredient of Biomass Packaging Material and Compare Study on Cushion Properties

Directory of Open Access Journals (Sweden)

Fangyi Li

2014-01-01

Full Text Available In order to reduce the white pollution caused by nondegradable waste plastic packaging materials, the biomass cushion packaging material with straw fiber and starch as the main raw materials had been synthesized. The orthogonal experiment was used to study the impact of mass ratio of fiber to starch, content of plasticizer, active agent, and foaming agent on the compressive strength of cushion material. Infrared spectrometer and theory of water’s bridge-connection were used to study the hydroxyl groups among the fiber and starch. The results were demonstrated as follows: the mass ratio of fiber to starch had the most significant impact on compressive strength. When the contents of the plasticizer, the foaming agent, and the active agent were, respectively, 12%, 0.1%, and 0.3% and the mass ratio of fiber to starch was 2 : 5, the compressive strength was the best up to 0.94 MPa. Meanwhile, with the plasticizer content and the mass ratio of fiber to starch increasing, the cushioning coefficient of the material decreased first and then increased. Comparing the cushion and rebound performance of this material with others, the biomass cushion packaging material could be an ideal substitute of plastic packaging materials such as EPS and EPE.

Sustainable Materials Management: Non-Hazardous Materials and Waste Management Hierarchy

Science.gov (United States)

EPA developed the non-hazardous materials and waste management hierarchy in recognition that no single waste management approach is suitable for managing all materials and waste streams in all circumstances.

Emergency response packaging: A conceptual outline

International Nuclear Information System (INIS)

Luna, R.E.; McClure, J.D.; Bennett, P.C.; Wheeler, T.A.

1992-01-01

The Packaging and Transportation Needs in the 1990's (PATN) component of the Transportation Assessment and Integration (TRAIN) program (DOE Nov. 1991) was designed to survey United States Department of Energy programs, both ongoing and planned, to identify needs for packaging and transportation services over the next decade. PATN also identified transportation elements that should be developed by the DOE Office of Environmental Restoration and Waste Management (DOE EM) Transportation Management Program (TMP). As a result of the predominant involvement of the TMP in radioactive material shipment issues and DOE EM's involvement with waste management issues, the primary focus of PATN was on waste packaging issues. Pending DOE regulations will formalize federal guidelines and regulations for transportation of hazardous and radioactive materials within the boundaries of DOE reservations and facilities and reflect a growing awareness of concern regarding safety environmental responsibility activities on DOE reservations. Future practices involving the transportation of radioactive material within DOE reservations will closely parallel those used for commercial and governmental transportation across the United States. This has added to the perceived need for emergency recovery packaging and emergency response features on primary packaging, for both on-site shipments and shipments between DOE facilities (off-site). Historically, emergency response and recovery functions of packaging have not been adequately considered in packaging design and construction concepts. This paper develops the rationale for emergency response packaging, including both overpack concepts for repackaging compromised packaging and primary packaging redesign to facilitate the recovery of packages via mobile remote handling equipment. The rationale will examine concepts for determination of likely use patterns to identify types of shipments where recovery packaging may have the most favorable payoff

Digital Radiography of a Drop Tested 9975 Radioactive Materials Packaging

International Nuclear Information System (INIS)

Blanton, P.S.

2001-01-01

This paper discusses the use of radiography as a tool for evaluating damage to radioactive material packaging subjected to regulatory accident conditions. The Code of Federal Regulations, 10 CFR 71, presents the performance based requirements that must be used in the development (design, fabrication and testing) of a radioactive material packaging. The use of various non-destructive examination techniques in the fabrication of packages is common. One such technique is the use of conventional radiography in the examination of welds. Radiography is conventional in the sense that images are caught one at a time on film stock. Most recently, digital radiography has been used to characterize internal damage to a package subjected to the 30-foot hypothetical accident conditions (HAC) drop. Digital radiography allows for real time evaluation of the item being inspected. This paper presents a summary discussion of the digital radiographic technique and an example of radiographic results of a 9975 package following the HAC 30-foot drop

Packaging development needs to support environmental restoration

International Nuclear Information System (INIS)

Hummer, J.H.; Kuklinski, J.L.

1993-01-01

The U.S. Department of Energy is bringing its facilities into compliance with present environmental protection regulations. At the Hanford Site, this includes cleanup of its vast nuclear and chemical wastes. Cleanup will involve extensive collecting, consolidating, and processing of radioactive and other hazardous wastes. The Hanford Site was established by the Federal government in 1943 to produce plutonium. Natural uranium was fabricated into fuel slugs, inserted into nuclear reactors, and converted into plutonium. The irradiated slugs were then sent through plutonium extraction facilities. Process waste was discharged to the ground, stored on-site, or shipped off-site for disposal. Activities grew to include nine production reactors, five coal-fired power plants, nuclear fuel fabrication, other support facilities including underground waste storage tanks, and numerous chemical and waste processing plants. Cleanup activities will require extensive transport of radioactive and other hazardous materials. Packaging developments and research are required in the following areas to enhance environmental cleanup; (1) Packaging for Large Contaminated and Activated Components. (2) Bulk Packaging for Contaminated Solids. (3) Bulk Packaging for Contaminated Liquids. (4) Environmental Samples. (J.P.N.)

Recent advances in hazardous materials transportation research: an international exchange. State-of-the-art Report 3, addendum

International Nuclear Information System (INIS)

Hills, P.; Geysen, W.J.; Tomachevsky, E.G.; Ringot, C.; Pages, P.

1986-01-01

The 4 papers in the report deal with the following areas: the transport of non-nuclear toxic and dangerous wastes in the United Kingdom; the transport system of dangerous products as a risk factor for the future: the computer-aided information program on hazardous materials; a validation study of the INTERTRAN model for assessing risks of transportation accidents: road transport of uranium hexafluoride; modifying the regulation for small radioactive package transit through the Mont Blanc tunnel-assessment of the health and economic impact

Directory of Certificates of Compliance for Radioactive-Materials Packages. Summary report of NRC approved packages

International Nuclear Information System (INIS)

1983-01-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Approved Packages (Volume I), all Certificates of Compliance (Volume 2), and Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective December 31, 1982. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the back of Volumes 1 and 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Directory of Certificates of Compliance for Radioactive Materials Packages: Report of NRC Approved Packages

International Nuclear Information System (INIS)

1993-10-01

This directory contains a Report of NRC Approved Packages (Volume 1). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

21 CFR 178.3130 - Antistatic and/or anti-fogging agents in food-packaging materials.

Science.gov (United States)

2010-04-01

...-packaging materials. 178.3130 Section 178.3130 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT OF.../or anti-fogging agents in food-packaging materials. The substances listed in paragraph (b) of this section may be safely used as antistatic and/or antifogging agents in food-packaging materials, subject to...

21 CFR 181.22 - Certain substances employed in the manufacture of food-packaging materials.

Science.gov (United States)

2010-04-01

... food-packaging materials. 181.22 Section 181.22 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT... of food-packaging materials. Prior to the enactment of the food additives amendment to the Federal... manufacturing practice for food-packaging materials includes the restriction that the quantity of any of these...

Effects of ionizing radiation on food packaging materials and quality

International Nuclear Information System (INIS)

Welle, F.; Franz, R.

1999-01-01

Tests have shown that ionizing radiation induces a characteristic smell in the packaging laminates which also affects the simulated foods used, which however were relatively neutral in flavour, so that the tests represent the worst case. The paper explains that due to the various additives used in the production of the plastic packaging materials, the same types of polymers may react differently to the ionizing radiation, so that the results obtained from the tests are not suitable for general application. It is recommended to very carefully select the suitable packaging material for given foods and intended irradiation processes. Aspects of particular importance are discusses. (orig./CB) [de

Absorbent material for type a radioactive materials packaging containing liquids

International Nuclear Information System (INIS)

Saunders, G.A.

1989-11-01

The application of absorbent materials to the packaging and transport of liquid radioactive materials in Type A packages has not been reported in the literature. However, a significant body of research exists on absorbent materials for personal hygiene products such as diapers. Absorption capacity is dependent on both the absorbent material and the liquid being absorbed. Theoretical principles for capillary absorption in both the horizontal and the vertical plane indicate that small contact angle between the absorbent fibre and the liquid, and a small inter-fibre pore size are important. Some fluid parameters such as viscosity affect the rate of absorption but not the final absorption capacity. There appears to be little comparability between results obtained for the same absorbent and fluid using different test procedures. Test samples of materials from several classes of potential absorbents have been evaluated in this study, and shown to have a wide range of absorbent capacities. Foams, natural fibres, artificial fibres and granular materials are all potentially useful absorbents, with capacities ranging from as little as 0.86 to as much as 40.6 grams of distilled water per gram of absorbent. Two experimental procedures for evaluating the absorbent capacity of these materials have been detailed in this report, and found suitable for evaluating granular, fibrous or foam materials. Compression of the absorbent material reduces its capacity, but parameters such as relative humidity, pH, temperature, and viscosity appear to have little significant influence on capacity. When the materials were loaded to 50% of their one-minute absorbency, subsequent loss of the absorbed liquid was generally minimal. All of the absorbent materials rapidly lost their absorbed water through evaporation within twenty-four hours in still air at 21 degrees C and 50% relative humidity

Transport of radioactive material

International Nuclear Information System (INIS)

Lombard, J.

1996-01-01

This work deals with the transport of radioactive materials. The associated hazards and potential hazards are at first described and shows the necessity to define specific safety regulations. The basic principles of radiological protection and of the IAEA regulations are given. The different types of authorized packages and of package labelling are explained. The revision, updating and the monitoring of the regulations effectiveness is the subject of the last part of this conference. (O.M.)

Quality assurance requirements for packaging and transportation of radioactive materials

International Nuclear Information System (INIS)

Barker, R.F.; MacDonald, C.E.; Doda, R.J.

1978-01-01

This paper discusses the new quality assurance regulations of the Nuclear Regulatory Commission (NRC) for packaging and transportation of radioactive materials. These regulations became effective on October 18, 1977. Background information concerning these regulations and packaging and transportation history is included. The quality assurance program is described with indications of how it is composed of general (administrative) provisions which must meet the 18 quality assurance criteria and be approved by the NRC; specific provisions which appear in the DOT and NRC regulations and in the individual package design approval; and other specific procedures which are not required by regulations but which are necessary for the proper control of quality. The quality assurance program is to be developed using a graded approach for the application of pertinent criteria and optimizing the required degree of safety and control efforts involved in achieving this level of safety. The licensee-user is responsible for all phases of quality assurance for packaging activities including: design, manufacture, test, use, maintenance and repair. The package design phase is considered to be particularly important in producing adequate safety in operational activities concerning packaging and transportation of radioactive materials

Packaging strategies for printed circuit board components. Volume I, materials & thermal stresses.

Energy Technology Data Exchange (ETDEWEB)

Neilsen, Michael K. (Kansas City Plant, Kansas City, MO); Austin, Kevin N.; Adolf, Douglas Brian; Spangler, Scott W.; Neidigk, Matthew Aaron; Chambers, Robert S.

2011-09-01

Decisions on material selections for electronics packaging can be quite complicated by the need to balance the criteria to withstand severe impacts yet survive deep thermal cycles intact. Many times, material choices are based on historical precedence perhaps ignorant of whether those initial choices were carefully investigated or whether the requirements on the new component match those of previous units. The goal of this program focuses on developing both increased intuition for generic packaging guidelines and computational methodologies for optimizing packaging in specific components. Initial efforts centered on characterization of classes of materials common to packaging strategies and computational analyses of stresses generated during thermal cycling to identify strengths and weaknesses of various material choices. Future studies will analyze the same example problems incorporating the effects of curing stresses as needed and analyzing dynamic loadings to compare trends with the quasi-static conclusions.

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-08-18

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

Is radioactive mixed waste packaging and transportation really a problem

International Nuclear Information System (INIS)

McCall, D.L.; Calihan, T.W. III.

1992-01-01

Recently, there has been significant concern expressed in the nuclear community over the packaging and transportation of radioactive mixed waste under US Department of Transportation regulation. This concern has grown more intense over the last 5 to 10 years. Generators and regulators have realized that much of the waste shipped as ''low-level radioactive waste'' was in fact ''radioactive mixed waste'' and that these wastes pose unique transportation and disposal problems. Radioactive mixed wastes must, therefore, be correctly identified and classed for shipment. If must also be packaged, marked, labeled, and otherwise prepared to ensure safe transportation and meet applicable storage and disposal requirements, when established. This paper discusses regulations applicable to the packaging and transportation of radioactive mixed waste and identifies effective methods that waste shippers can adopt to meet the current transportation requirements. This paper will include a characterization and description of the waste, authorized packaging, and hazard communication requirements during transportation. Case studies will be sued to assist generators in understanding mixed waste shipment requirements and clarify the requirements necessary to establish a waste shipment program. Although management and disposal of radioactive mixed waste is clearly a critical issue, packaging and transportation of these waste materials is well defined in existing US Department of Transportation hazardous material regulations

Directory of certificates of compliance for radioactive materials packages: summary report of NRC approved quality-assurance programs for radioactive-material packages. Volume 3, Revision 3

International Nuclear Information System (INIS)

1983-09-01

This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure them in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved quality assurance programs for radioactive material packages. Volume 3, Revision 4

International Nuclear Information System (INIS)

1984-11-01

This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

Technology assessment of solar-energy systems. Materials resource and hazardous materials impacts of solar deployment

Science.gov (United States)

Schiffman, Y. M.; Tahami, J. E.

1982-04-01

The materials-resource and hazardous-materials impacts were determined by examining the type and quantity of materials used in the manufacture, construction, installation, operation and maintenance of solar systems. The materials requirements were compared with US materials supply and demand data to determine if potential problems exist in terms of future availability of domestic supply and increased dependence on foreign sources of supply. Hazardous materials were evaluated in terms of public and occupational health hazards and explosive and fire hazards. It is concluded that: although large amounts of materials would be required, the US had sufficient industrial capacity to produce those materials; (2) postulated growth in solar technology deployment during the period 1995-2000 could cause some production shortfalls in the steel and copper industry; the U.S. could increase its import reliance for certain materials such as silver, iron ore, and copper; however, shifts to other materials such as aluminum and polyvinylchloride could alleviate some of these problems.

Radioactive materials packaging standards and regulations: Making sense of it all

International Nuclear Information System (INIS)

Pope, R.B.; Rawl, R.R.

1989-01-01

Numerous regulations and standards, both national and international, apply to the packaging and transportation of radioactive material. These are legal and technical prerequisites to practically every action that a designer or user of a radioactive material transportation package will perform. The identity and applicability of these requirements and the bodies that formulate them are also not readily understood. This paper addresses the roles that various international bodies play in developing and implementing the various regulations and standards. It uses the US regulatory and standards-making bodies to illustrate how international requirements feed the domestic control of packaging and transport. It explains the scope and interactions between domestic and international regulatory and standards agencies and summarizes the status and major standards activities at the international level. The overview provided by this paper will be valuable to designers and users of radioactive material packages for better understanding and use of both standards and regulations, and for complying with regulatory requirements in the radioactive materials transportation field. 11 refs., 2 figs

Directory of certificates of compliance for radioactive materials packages. Volume 1, Revision 17: Report of NRC approved packages

International Nuclear Information System (INIS)

1994-10-01

This directory contains a Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs for Radioactive Materials Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

Directory of certificates of compliance for radioactive materials packages

International Nuclear Information System (INIS)

1992-10-01

This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3), for Radioactive Materials Packages effective October 1, 1992. The purpose of this directory is to make available a convenient source of information on packaging which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volumes 1 and 2. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The reports include a listing of all users of each package-design and approved QA programs prior to the publication date of the directory

Directory of Certificates of Compliance for Radioactive Materials Packages

International Nuclear Information System (INIS)

1992-10-01

This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3), for Radioactive Materials Packages effective October 1, 1992. The purpose of this directory is to make available a convenient source of information on packaging which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volumes 1 and 2. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The reports include a listing of all users of each package-design and approved QA programs prior to the publication date of the directory

49 CFR Appendix B to Part 173 - Procedure for Testing Chemical Compatibility and Rate of Permeation in Plastic Packaging and...

Science.gov (United States)

2010-10-01

... Rate of Permeation in Plastic Packaging and Receptacles B Appendix B to Part 173 Transportation Other... Plastic Packaging and Receptacles 1. The purpose of this procedure is to determine the chemical compatibility and permeability of liquid hazardous materials packaged in plastic packaging and receptacles...

Ammonia gas permeability of meat packaging materials.

Science.gov (United States)

Karim, Faris; Hijaz, Faraj; Kastner, Curtis L; Smith, J Scott

2011-03-01

Meat products are packaged in polymer films designed to protect the product from exterior contaminants such as light, humidity, and harmful chemicals. Unfortunately, there is almost no data on ammonia permeability of packaging films. We investigated ammonia permeability of common meat packaging films: low-density polyethylene (LDPE; 2.2 mil), multilayer polyolefin (MLP; 3 mil), and vacuum (V-PA/PE; 3 mil, 0.6 mil polyamide/2.4 mil polyethylene). The films were fabricated into 10 × 5 cm pouches and filled with 50 mL deionized water. Pouches were placed in a plexiglass enclosure in a freezer and exposed to 50, 100, 250, or 500 ppm ammonia gas for 6, 12, 24, and 48 h at -17 ± 3 °C and 21 ± 3 °C. At freezing temperatures, no ammonia residues were detected and no differences in pH were found in the water. At room temperature, ammonia levels and pH of the water increased significantly (P packaging materials have low ammonia permeability and protect meat products exposed to ammonia leaks during frozen storage.

Comparison of silicone and spin-on glass packaging materials for light-emitting diode encapsulation

Energy Technology Data Exchange (ETDEWEB)

Chang, Liann-Be; Pan, Ke-Wei; Yen, Chia-Yi [Department of Electronic Engineering and Green Technology Research Center, Chang Gung University, Taoyuan, Taiwan (China); Jeng, Ming-Jer, E-mail: mjjeng@mail.cgu.edu.tw [Department of Electronic Engineering and Green Technology Research Center, Chang Gung University, Taoyuan, Taiwan (China); Wu, Chun-Te; Hu, Sung-Cheng; Kuo, Yang-Kuao [Chemical Systems Research Division, Chung-Shan Institute of Science and Technology Armaments Bureau, MND, Taoyuan, Taiwan (China)

2014-11-03

Traditional white light light-emitting diode (LED) encapsulation is performed by mixed phosphors and silicone coating on LED die. However, this encapsulation with silicone coating incurs overheated temperatures and yellowing problem. Therefore, this work attempts to replace silicone paste by using spin-on-glass (SOG) materials. Experimental results indicate that although initial brightness of SOG-based packaging is lower than that of silicone packaging, its light attenuation is significantly lower than that of silicone for a long lighting time. After the LED power is turned on for 12 h, the brightness of LED with silicone and SOG material packaging decreases from 84 to 48 lm and 73 to 59 lm, respectively. Therefore, SOG material provides an alternative packaging solution for high power LED lighting applications. - Highlights: • Spin-on-glass (SOG) material was used to replace silicone coating for LED packaging. • Initial brightness of SOG packaging is lower than that of silicone packaging. • Over time, light attenuation in SOG is much lower than that in silicone. • Color rendering index and brightness of LED packaging was optimized by Taguchi method.

Characteristics of meat packaging materials and their environmental suitability assessment

Directory of Open Access Journals (Sweden)

Šuput Danijela Z.

2013-01-01

Full Text Available After functional phase, packaging becomes waste that is recycled or disposed of in landfills. Recently, numerus packages have been developed for assessing the packaging risk on the environment. We applied Gabi 4 Education software on polymer product packaging for meat products. The objective of first part of the paper was characterization of materials used for meat and meat products packaging in terms of mechanical and barrier properties. Results show that tested materials are able to keep protective atmosphere and contribute to the quality and sustainability of the product. Air permeability was 3.60 and 26.60 ml/m224h, and water vapor was 6.90 and 9.50 ml/m224h, respectively, for foils 1 and 2, as a result of different film composition. In second part, based on real data, Gabi 4 Education software is applied. The obtained results showed that organic compounds emissions have the highest impact on human health and the most damaging environmental impact observed was the emission of CO2.

Energy implications of recycling packaging materials

Energy Technology Data Exchange (ETDEWEB)

Gaines, L.L. [Argonne National Lab., IL (United States); Stodolsky, F. [Argonne National Lab., Washington, DC (United States)

1994-03-01

In 1992, Congress sought to rewrite the United States comprehensive solid waste legislation -- the Resource Conservation and Recovery Act (RCRA). Commodity-specific recycling rates were proposed for consumer-goods packaging materials and newsprint We compare the impacts on energy, materials use, and landfill volume of recycling at those rates to the impacts for alternative methods of material disposition to determine the optimum for each material. After products have served their intended uses, there are several alternative paths for material disposition. These include reuse, recycling to the same product, recycling to a lower-valued product, combustion for energy recovery, incineration without energy recovery, and landfill. Only options considered to be environmentally sound are Included. Both houses of Congress specifically excluded combustion for energy recovery from counting towards the recovery goats, probably because combustion is viewed as a form of disposal and is therefore assumed to waste resources and have n environmental effects. However, co-combustion in coal-fired plants or combustion in appropriately pollution-controlled waste-to-energy plants Is safe, avoids landfill costs, and can displace fossil fuels. In some cases, more fossil fuels can be displaced by combustion than by recycling. We compare the alternative life-cycle energies to the energies for producing the products from virgin materials. Results depend on the material and on the objective to be achieved. There are trade-offs among possible goals. For instance, paper packaging recycling conserves trees but may require greater fossil-fuel input than virgin production. Therefore, the objectives for proposed legislation must be examined to see whether they can most effectively be achieved by mandated recycling rates or by other methods of disposition. The optimal choices for the United States may not necessarily be the same as those for Europe and other parts of the world.

10 CFR 71.59 - Standards for arrays of fissile material packages.

Science.gov (United States)

2010-01-01

... 10 Energy 2 2010-01-01 2010-01-01 false Standards for arrays of fissile material packages. 71.59 Section 71.59 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PACKAGING AND TRANSPORTATION OF RADIOACTIVE.... The value of the CSI may be zero provided that an unlimited number of packages are subcritical, such...

Compilation of current literature on seals, closures, and leakage for radioactive material packagings

International Nuclear Information System (INIS)

Warrant, M.M.; Ottinger, C.A.

1989-01-01

This report presents an overview of the features that affect the sealing capability of radioactive material packagings currently certified by the US Nuclear Regulatory Commission. The report is based on a review of current literature on seals, closures, and leakage for radioactive material packagings. Federal regulations that relate to the sealing capability of radioactive material packagings, as well as basic equations for leakage calculations and some of the available leakage test procedures are presented. The factors which affect the sealing capability of a closure, including the properties of the sealing surfaces, the gasket material, the closure method and the contents are discussed in qualitative terms. Information on the general properties of both elastomer and metal gasket materials and some specific designs are presented. A summary of the seal material, closure method, and leakage tests for currently certified packagings with large diameter seals is provided. 18 figs., 9 tabs

An optimization model for transportation of hazardous materials

International Nuclear Information System (INIS)

Seyed-Hosseini, M.; Kheirkhah, A. S.

2005-01-01

In this paper, the optimal routing problem for transportation of hazardous materials is studied. Routing for the purpose of reducing the risk of transportation of hazardous materials has been studied and formulated by many researcher and several routing models have been presented up to now. These models can be classified into the categories: the models for routing a single movement and the models for routing multiple movements. In this paper, according to the current rules and regulations of road transportations of hazardous materials in Iran, a routing problem is designed. In this problem, the routs for several independent movements are simultaneously determined. To examine the model, the problem the transportations of two different dangerous materials in the road network of Mazandaran province in the north of Iran is formulated and solved by applying Integer programming model

The profitability drivers in packaging materials reuse for manufacturers in business to business environments

DEFF Research Database (Denmark)

Larsen, Samuel; Deleuran, Brian; Jacobsen, Peter

Purpose –The purpose of this paper is to explore the profitability drivers for a firm’s operation of a reverse supply chain (RSC) that takes back and reuses packaging materials. Results apply specifically to original equipment manufacturers (OEMs) in business to business environments. Design......’s theoretical basis is the RSC literature’s business perspective formulated by Guide and Van Wassenhove. Findings – The drivers of profitability in packaging materials reuse are 1) the amount of avoided costs of purchasing new packaging materials, 2) the firm’s ability to reduce costs of reverse logistics...... as between the drivers and their sub-level antecedents. Originality/value – The study provides exploratory insights into the economics of reusing packaging materials and identifies the drivers that are decisive for a firm’s ability to reuse packaging materials profitably....

Decontamination of food packaging using electron beam--status and prospects

Energy Technology Data Exchange (ETDEWEB)

Mittendorfer, J. E-mail: htcmitt@eunet.at; Bierbaumer, H.P.; Gratzl, F.; Kellauer, E

2002-03-01

In this paper the status of food packaging disinfection decontamination using electron beam at Mediscan GmbH is presented. The first section of the paper describes the activities at the service center, where food packaging materials, e.g. yoghurt cups are decontaminated in their final shipment containers. As important step in the hazard analysis and critical control point of food processing, microbiological uncontaminated food packaging material is of public interest and attracts a lot of attention from packaging material producers and food processors. The dose ranges for different sterility assurance levels are discussed and results from microbiological test are presented. Studies at Mediscan have demonstrated, that an electron beam treatment at a dose of 5-7 kGy is most effective against yeast and mold, which are mainly responsible for spoilage and short shelf-life of a variety of products. The second section is devoted to the field of inline decontamination of food packaging and sterilization of pharmaceutical packaging material and the research currently conducted at Mediscan. The requirements for industrial inline electron beam systems are summarized and design concepts discussed in terms of beam energy, beam current, irradiation topology, product handling and shielding.

Decontamination of food packaging using electron beam—status and prospects

Science.gov (United States)

Mittendorfer, J.; Bierbaumer, H. P.; Gratzl, F.; Kellauer, E.

2002-03-01

In this paper the status of food packaging disinfection decontamination using electron beam at Mediscan GmbH is presented. The first section of the paper describes the activities at the service center, where food packaging materials, e.g. yoghurt cups are decontaminated in their final shipment containers. As important step in the hazard analysis and critical control point of food processing, microbiological uncontaminated food packaging material is of public interest and attracts a lot of attention from packaging material producers and food processors. The dose ranges for different sterility assurance levels are discussed and results from microbiological test are presented. Studies at Mediscan have demonstrated, that an electron beam treatment at a dose of 5-7 kGy is most effective against yeast and mold, which are mainly responsible for spoilage and short shelf-life of a variety of products. The second section is devoted to the field of inline decontamination of food packaging and sterilization of pharmaceutical packaging material and the research currently conducted at Mediscan. The requirements for industrial inline electron beam systems are summarized and design concepts discussed in terms of beam energy, beam current, irradiation topology, product handling and shielding.

Decontamination of food packaging using electron beam--status and prospects

International Nuclear Information System (INIS)

Mittendorfer, J.; Bierbaumer, H.P.; Gratzl, F.; Kellauer, E.

2002-01-01

In this paper the status of food packaging disinfection decontamination using electron beam at Mediscan GmbH is presented. The first section of the paper describes the activities at the service center, where food packaging materials, e.g. yoghurt cups are decontaminated in their final shipment containers. As important step in the hazard analysis and critical control point of food processing, microbiological uncontaminated food packaging material is of public interest and attracts a lot of attention from packaging material producers and food processors. The dose ranges for different sterility assurance levels are discussed and results from microbiological test are presented. Studies at Mediscan have demonstrated, that an electron beam treatment at a dose of 5-7 kGy is most effective against yeast and mold, which are mainly responsible for spoilage and short shelf-life of a variety of products. The second section is devoted to the field of inline decontamination of food packaging and sterilization of pharmaceutical packaging material and the research currently conducted at Mediscan. The requirements for industrial inline electron beam systems are summarized and design concepts discussed in terms of beam energy, beam current, irradiation topology, product handling and shielding

Investigating the presence of hazardous materials in buildings

International Nuclear Information System (INIS)

Gustitus, D.A.; Blaisdell, P.M.

1996-01-01

Environmental hazards in buildings can be found in the air, on exposed surfaces, or hidden in roofs, walls, and systems. They can exist in buildings in solid, liquid, and gaseous states. A sound methodology for investigating the presence of environmental hazards in buildings should include several components. The first step in planning an investigation of environmental hazards in buildings is to ascertain why the investigation is to be performed. Research should be performed to review available documentation on the building. Next, a visual inspection of the building should be performed to identify and document existing conditions, and all suspect materials containing environmental hazards. Lastly, samples of suspect materials should be collected for testing. It is important to sample appropriate materials, based on the information obtained during the previous steps of the investigation. It is also important to collect the samples using standard procedures. Pollutants of concern include asbestos, lead, PCBs, and radon

Directory of certificates of compliance for radioactive materials packages. Volume 3, revision 1. Summary report of NRC approved quality assurance programs for radioactive material packages

International Nuclear Information System (INIS)

1981-12-01

The directory contains a Summary Report of NRC approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the U.S. Nuclear Regulatory Commission. To assist in identifying packaging, and index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory

Savannah River Site Eastern Transportation Hub: A Concept For a DOE Eastern Packaging, Staging and Maintenance Center - 13143

International Nuclear Information System (INIS)

England, Jeffery L.; Adams, Karen; Maxted, Maxcine; Ruff Jr, Clarence; Albenesius, Andrew; Bowers, Mark D.; Fountain, Geoffrey; Hughes, Michael; Gordon, Sydney; O'Connor, Stephen

2013-01-01

The Department of Energy (DOE) is working to de-inventory sites and consolidate hazardous materials for processing and disposal. The DOE administers a wide range of certified shipping packages for the transport of hazardous materials to include Special Nuclear Material (SNM), radioactive materials, sealed sources and radioactive wastes. A critical element to successful and safe transportation of these materials is the availability of certified shipping packages. There are over seven thousand certified packagings (i.e., Type B/Type AF) utilized within the DOE for current missions. The synergistic effects of consolidated maintenance, refurbishment, testing, certification, and costing of these services would allow for efficient management of the packagings inventory and to support anticipated future in-commerce shipping needs. The Savannah River Site (SRS) receives and ships radioactive materials (including SNM) and waste on a regular basis for critical missions such as consolidated storage, stabilization, purification, or disposition using H-Canyon and HB-Line. The Savannah River National Laboratory (SRNL) has the technical capability and equipment for all aspects of packaging management. SRS has the only active material processing facility in the DOE complex and is one of the sites of choice for nuclear material consolidation. SRS is a logical location to perform maintenance and periodic testing of the DOE fleet of certified packagings. This initiative envisions a DOE Eastern Packaging Staging and Maintenance Center (PSMC) at the SRS and a western hub at the Nevada National Security Site (NNSS), an active DOE Regional Disposal Site. The PSMC's would be the first place DOE would go to meet their radioactive packaging needs and the primary locations projects would go to disposition excess packaging for beneficial reuse. These two hubs would provide the centralized management of a packaging fleet rather than the current approach to design, procure, maintain and dispose

Application of polymer nanocomposite materials in food packaging

Directory of Open Access Journals (Sweden)

Amra Odobašić

2015-01-01

Full Text Available The term “nano” refers to nano particle size from 1 to 100 nanometers. The term "nanotechnology" was first introduced by Norio Taniguchi in 1974. Nanotechnology may be used to improve the taste and texture of food and for the production of packaging that maintain fresh product. The primary function of packaging is to maintain the quality and safety of products during transport and storage period, as well as to extend its viability by preventing unwanted effect agents such as microorganisms, chemical contaminants, oxygen, moisture and light. The aim of this paper is to point out the achievements of nanotechnology in terms of food packaging with an overview of polymers that are commonly used in food packaging, as well as strategies to improve the physical properties of polymers, including mechanical strength, thermal stability and barrier to gases. By studing of recently published literature, it was clear that nanomaterials such as nano polymers are trying to replace conventional materials in food packaging. Nanosensors can be used to prove the presence of contaminants, microtoxins and microorganisms in food.

Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved quality assurance programs for radioactive material packages. Volume 3, Revision 6

International Nuclear Information System (INIS)

1986-10-01

This directory contains a Summary Report of NRC Approved Packages (Volumes 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure them that have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use of transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

Hydrothermal carbonization of food waste and associated packaging materials for energy source generation.

Science.gov (United States)

Li, Liang; Diederick, Ryan; Flora, Joseph R V; Berge, Nicole D

2013-11-01

Hydrothermal carbonization (HTC) is a thermal conversion technique that converts food wastes and associated packaging materials to a valuable, energy-rich resource. Food waste collected from local restaurants was carbonized over time at different temperatures (225, 250 and 275°C) and solids concentrations to determine how process conditions influence carbonization product properties and composition. Experiments were also conducted to determine the influence of packaging material on food waste carbonization. Results indicate the majority of initial carbon remains integrated within the solid-phase at the solids concentrations and reaction temperatures evaluated. Initial solids concentration influences carbon distribution because of increased compound solubilization, while changes in reaction temperature imparted little change on carbon distribution. The presence of packaging materials significantly influences the energy content of the recovered solids. As the proportion of packaging materials increase, the energy content of recovered solids decreases because of the low energetic retention associated with the packaging materials. HTC results in net positive energy balances at all conditions, except at a 5% (dry wt.) solids concentration. Carbonization of food waste and associated packaging materials also results in net positive balances, but energy needs for solids post-processing are significant. Advantages associated with carbonization are not fully realized when only evaluating process energetics. A more detailed life cycle assessment is needed for a more complete comparison of processes. Copyright © 2013 Elsevier Ltd. All rights reserved.

Hazardous-materials-management system: a guide for local emergency managers

International Nuclear Information System (INIS)

Lee, M.T.; Roe, P.G.

1981-07-01

An increase in the manufacture, storage, and transportation of hazardous materials is occurring across the nation. Local jurisdictions have realized that they have the responsibility to assure a reasonable level of safety to their community members and visitors alike. Such a responsibility can be met by developing methods of preventing hazardous materials incidents; enforcing laws related to transporting and storing hazardous materials; the initiating of an appropriate first response, and activating available resources of government agencies and commercial organizations that deal with containment and cleanup. This manual has been written to help in the development of a total Hazardous Material Management System. The manual describes one approach but allows for variations as may be appropriate for the specific jurisdiction

Waste package materials testing for a salt repository: 1983 status summary report

International Nuclear Information System (INIS)

Moak, D.P.

1986-09-01

The United States plans to safely dispose of nuclear waste in deep, stable geologic formations. As part of these plans, the US Department of Energy is sponsoring research on the designing and testing of waste packages and waste package materials. This fiscal year 1983 status report summarizes recent results of waste package materials testing in a salt environment. The results from these tests will be used by waste package designers and performance assessment experts. Release characteristics data are available on two waste forms (spent fuel and waste-containing glass) that were exposed to leaching tests at various radiation levels, temperatures, pH, glass surface area to solution volume ratios, and brine solutions simulating expected salt repository conditions. Candidate materials tested for corrosion resistance and other properties include iron alloys; TI-CODE 12, the most promising titanium alloy for containment; and nickel alloys. In component interaction testing, synergistic effects have not ruled out any candidate material. 21 refs., 37 figs., 15 tabs

Surface modification of food contact materials for processing and packaging applications

Science.gov (United States)

Barish, Jeffrey A.

This body of work investigates various techniques for the surface modification of food contact materials for use in food packaging and processing applications. Nanoscale changes to the surface of polymeric food packaging materials enables changes in adhesion, wettability, printability, chemical functionality, and bioactivity, while maintaining desirable bulk properties. Polymer surface modification is used in applications such as antimicrobial or non-fouling materials, biosensors, and active packaging. Non-migratory active packagings, in which bioactive components are tethered to the package, offer the potential to reduce the need for additives in food products while maintaining safety and quality. A challenge in developing non-migratory active packaging materials is the loss of biomolecular activity that can occur when biomolecules are immobilized. Polyethylene glycol (PEG), a biocompatible polymer, is grafted from the surface of ozone treated low-density polyethylene (LDPE) resulting in a surface functionalized polyethylene to which a range of amine-terminated bioactive molecules can be immobilized. The grafting of PEG onto the surface of polymer packaging films is accomplished by free radical graft polymerization, and to covalently link an amine-terminated molecule to the PEG tether, demonstrating that amine-terminated bioactive compounds (such as peptides, enzymes, and some antimicrobials) can be immobilized onto PEG-grafted LDPE in the development of non-migratory active packaging. Fouling on food contact surfaces during food processing has a significant impact on operating efficiency and can promote biofilm development. Processing raw milk on plate heat exchangers results in significant fouling of proteins as well as minerals, and is exacerbated by the wall heating effect. An electroless nickel coating is co-deposited with polytetrafluoroethylene onto stainless steel to test its ability to resist fouling on a pilot plant scale plate heat exchanger. Further

Packaging and transportation of radioactive materials: summary program

International Nuclear Information System (INIS)

1978-01-01

This document contains summaries or abstracts of reports presented at the Symposium on Packaging and Transportation of Radioactive Materials. Separate indexing has been performed on individual items presented at this conference

REMOTE MATERIAL HANDLING IN THE YUCCA MOUNTAIN WASTE PACKAGE CLOSURE CELL AND SUPPORT AREA GLOVEBOX

International Nuclear Information System (INIS)

K.M. Croft; S.M. Allen; M.W. Borland

2005-01-01

The Yucca Mountain Waste Package Closure System (WPCS) cells provide for shielding of highly radioactive materials contained in unsealed waste packages. The purpose of the cells is to provide safe environments for package handling and sealing operations. Once sealed, the packages are placed in the Yucca Mountain Repository. Closure of a typical waste package involves a number of remote operations. Those involved typically include the placement of matched lids onto the waste package. The lids are then individually sealed to the waste package by welding. Currently, the waste package includes three lids. One lid is placed before movement of the waste package to the closure cell; the final two are placed inside the closure cell, where they are welded to the waste package. These and other important operations require considerable remote material handling within the cell environment. This paper discusses the remote material handling equipment, designs, functions, operations, and maintenance, relative to waste package closure

Directory of Certificates of Compliance for Radioactive Materials Packages. Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages. Volume 3. Revision 5

International Nuclear Information System (INIS)

1985-10-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Approved Packages (Volume I), all Certificates of Compliance (Volume 2), and Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1985. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the back of Volumes 1 and 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory. Shipments of radioactive material utilizing these packages must be in accordance with the provisions of 49 CFR Section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with a Nuclear Regulatory Commission approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR Section 71.12 does not authorize the receipt, possession, use or transfer of byproduct, source or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, or 70

49 CFR 173.33 - Hazardous materials in cargo tank motor vehicles.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Hazardous materials in cargo tank motor vehicles... Transportation § 173.33 Hazardous materials in cargo tank motor vehicles. (a) General requirements. (1) No person may offer or accept a hazardous material for transportation in a cargo tank motor vehicle except as...

Preventing method and device for underground permeation of hazardous material

International Nuclear Information System (INIS)

Funabashi, Kiyomi; Kurokawa, Hideaki; Fukazawa, Tetsuo; Yamazaki, Tadashi.

1996-01-01

In a method of preventing hazardous materials from permeating into ground by burying adsorbing materials underground, a plurality of adsorbing layers are laminated being spaced apart from each other, the concentration of the hazardous materials between each of the adsorbent layers is measured. When the concentration reaches a predetermined value, the adsorbent layers are regenerated. A suppression means for preventing hazardous materials from permeating into the ground are formed by an upper adsorbent layer and a lower adsorbent layer, and a means for measuring the concentration of hazardous materials passing through the upper adsorbent layer and a means for charging and discharging regenerated liquid are disposed. When it is detected that the poisonous materials can not be eliminated, the poisonous materials are already permeated to the adsorbent layer, and they start to inflow into underground water. In order to prevent it, an adsorbent layer is additionally disposed at the lower side of the place of detection to eliminate the poisonous materials completely thereby enabling to prevent poisonous materials from permeating into underground for a long period of time. (T.M.)

Packaging and transportation of radioactive materials: summary program

Energy Technology Data Exchange (ETDEWEB)

None

1978-01-01

This document contains summaries or abstracts of reports presented at the Symposium on Packaging and Transportation of Radioactive Materials. Separate indexing has been performed on individual items presented at this conference. (DC)

Predicting Weight Change in Gari in Two Packaging Materials ...

African Journals Online (AJOL)

An equation for predicting moisture loss or gain by gari grain packed in two types of materials was developed. From this, it may be possible to establish the storability of gari in these two packaging material. The equation took into account the permeabilities of the materials, which were determined experimentally. The validity ...

The Use of Digital Radiography in the Evaluation of Radioactive Materials. Packaging Performance Testing

International Nuclear Information System (INIS)

May, C; Lawrence Gelder, L; Boyd Howard, B

2007-01-01

New designs of radioactive material shipping packages are required to be evaluated in accordance with 10 CFR Part 71, ''Packaging and Transportation of Radioactive Material''. This paper will discuss the use of digital radiography to evaluate the effects of the tests required by 10 CFR 71.71, Normal Conditions of Transport (NCT), and 10 CFR 71.73, Hypothetical Accident Conditions (HAC). One acceptable means of evaluating packaging performance is to subject packagings to the series of NCT and HAC tests. The evaluation includes a determination of the effect on the packaging by the conditions and tests. That determination has required that packagings be cut and sectioned to learn the actual effects on internal components. Digital radiography permits the examination of internal packaging components without sectioning a package. This allows a single package to be subjected to a series of tests. After each test, the package is digitally radiographed and the effects of particular tests evaluated. Radiography reduces the number of packages required for testing and also reduces labor and materials required to section and evaluate numerous packages. This paper will include a description of the digital radiography equipment used in the testing and evaluation of the 9977 and 9978 packages at SRNL. The equipment is capable of making a single radiograph of a full-sized package in one exposure. Radiographs will be compared to sectioned packages that show actual conditions compared to radiographic images

Packaging materials for use in radiation processing of foods

International Nuclear Information System (INIS)

Dragusin, M.; Rotaru, P.R.

1999-01-01

In radiation processing of food, the product often has to be prepackaged to prevent microbial recontamination during and after irradiation. The packaging material is exposed to radiation during radiation processing and radiation stability is a key consideration in the selection of packaging materials. The effects of ionizing radiation on many food packaging materials at the dose levels recommended for food precessing can be minimized by selecting appropriate radiation resistant materials. It is important to select materials in which chemicals formed as a result of the radiation treatment do not migrate and interact with the food, affecting its organoleptic and toxicological aspects. It is also important to select materials in which the physical properties are not altered to the extent they cannot resist damage during commercial production, shipment and storage. Radiation treatment of food may be classified broadly into two categories: 1. Processes requiring doses less than 10 kGy; 2. Processes requiring doses from 25 to 40 kGy for production of commercial sterility. In radiation processing of foods, gamma radiation from radioisotopes Co-60 and Cs-137 is most widely used because of its high penetrating power. Electron beam irradiation (E<10 MeV) and X-rays (E<5 MeV) can also be used for certain speciality food and packaging to the food. Because the public acceptance of irradiated foods is a major problem in marketing such products, we have developed in our laboratory an alternative techniques. These techniques are based on applying films on the surfaces of foods. The films are edible, i.e. they are an aqueous solution based on caseine, glycerine, poly-etilene-glycol (PEG), crosslinked by radiation processing. So, our techniques implies no longer the food irradiation but instead its isolation from the environmental biological attacks by means of edible films obtained by irradiation. The protective properties of films, as special humidity, oxygen and fat barriers, are

Instrumentation for Detecting Hazardous Materials.

Science.gov (United States)

1980-06-01

equipment a detector for monitoring radioactivity . A portable device for detecting the presence of hazardous mate- rials should also be included in the...Acrylonitrile 2 Natural Gas/LNG 2 211 ----- Material Name (Cont’d.) Number of Times Listed Radioactive Materials 2 Fertilizers 1 Cellulose Nitrate 1 Acrolein...Birnbaum, and Curtis Fincher, L "Fluorescence Determination of the Atmospheric Polutant NO2 in Impact of Lasers in Spectroscopy, Vol. 49 of Proceed

Data package for the Turkey Point material interaction test capsules

International Nuclear Information System (INIS)

Krogness, J.C.; Davis, R.B.

1979-01-01

Objective of the Materials Interaction Test (MIT) is to obtain interaction information on candidate package storage materials and geologies under prototypic temperatures in gamma and low level neutron fields. Compatibility, structural properties, and chemical transformations will be studied. The multiple test samples are contained within test capsules connected end-to-end to form a test train. Only passive instrumentation has been used to monitor temperatures and record neutron fluence. The test train contains seven capsules: three to test compatibility, two for structural tests, and two for chemical transformation studies. The materials tested are potential candidates for the spent fuel package canister and repository geologies

GGVS. Ordinance on road transport of hazardous materials, including the European agreement on international road transport of hazardous materials (ADR), in their wording. Annexes A and B. Ordinances regarding exceptions from GGVS and from the ordinance on rail transport of hazardous materials, GGVE. Reasons. Selected guidelines. List of materials. 6. rev. and enlarged ed.

International Nuclear Information System (INIS)

Ridder, K.

1990-01-01

The brochure contains the following texts: (1) Ordinance on road transport of hazardous materials (GGVS), including the European agreement on international road transport of hazardous materials (ADR), as of 1990: Skeleton ordinance, annexes A and B, reasons given for the first version, and for the first amendment in 1988, execution guidelines - RS 002 (guidelines for executing the ordinance on road transport of hazardous materials, with catalogue of penalties), guidelines for drawing up written instructions for the event of accidents - RS 006, guiding principles for the training of vehicle conductors; (2) ordinance regarding exceptions from the ordinance on road transport of hazardous materials; (3) ordinance regarding exceptions from the ordinance on rail transport of hazardous materials; (4) selected guidelines: Technical guidelines TR IBC K 001, TRS 003, TRS 004, TRS 005, TRS 006; (5) listing of materials and objects governed by the ordinance on hazardous materials transport; (6) catalogue of penalties relative to road transport of hazardous materials. (orig./HP) [de

Transportation of hazardous materials (hazmat a literature survey

Directory of Open Access Journals (Sweden)

Zafer YILMAZ

2016-02-01

Full Text Available ransportation has a great role in logistics. Many researchers have studied on transportation and vehicle routing problems. Transportation of hazardous materials (hazmat is a special subject for logistics. Causalities due to the accidents caused by trucks carrying hazardous materials will be intolerable. Many researchers have studied on risk assessment of hazmat transportation to find ways for reducing hazardous material transportation risks. Some researchers have studied routing of hazmat trucks. The emergency response models and network design problems for hazmat transportation were also studied by some researchers. The transportation of hazmats can also be classified according to the mode of transport. Mainly roads are used for hazmat transportation but some shipments are intermodal. There has been a great amount of effort spent to find convenient ways for hazmat transportation. In this study, a literature survey for the articles about hazmat transportation is prepared. After pointing out the importance of hazmat transportation by the example of US hazmat transportation data, the studies on hazmat transportation since 2005 have been examined. Totally 88 articles are classified as risk, routing, routing and scheduling, emergency response, network design and accident analysis. What can be studied in future researches is pointed out.Keywords: Hazardous materials, Network design, Transportation, Routing, Risk assessment

Safety analysis report, packages. Drath and Schrader Double Lidded Drum (packaging of fissile and other radioactive materials). Final report

International Nuclear Information System (INIS)

Chalfant, G.G.

1985-07-01

The preceding Safety Analysis Report - Packages qualifies the Drath and Schrader Double Lidded Drum (see appendix E) as a Department of Transportation DOT 7A Type A packaging and/or ''Type A'' foreign made packaging. The allowable contents shall be: in solid form; non-fissile or exempt fissile material (as defined by 49 CFR 173.453); less than 700 pounds (318 kg) in weight; equal to or less than the A 1 or A 2 quantities of radioactive material as appropriate (see 49 CFR 173.435 for tables of A 1 /A 2 values); and hydrogen gas generation in radioactive waste shall be limited to a maximum of 2-1/2% and total gas pressure limited to 5 psig. Package marking shall be as specified in 49 CFR 178.350-3 or as specified by the foreign country of origin

Determination of Fire Enviroment in Stacked Cargo Containers with Radioactive Materials Packages

Energy Technology Data Exchange (ETDEWEB)

Arviso, M.; Bobbe, J.G.; Dukart, R.D.; Koski, J.A.

1999-05-01

Results from a Fire Test with a three-by-three stack of standard 6 m long International Standards Organization shipping containers containing combustible fuels and empty radioactive materials packages are reported and discussed. The stack is intended to simulate fire conditions that could occur during on-deck stowage on container cargo ships. The fire is initated by locating the container stack adjacent to a 9.8 x 6 m pool fire. Temperatures of both cargoes (empty and simulated radioactive materials packages) and containers are recorded and reported. Observations on the duration, intensity and spread of the fire are discussed. Based on the results, models for simulation of fire exposure of radioactive materials packages in such fires are suggested.

Auditors of safety in hazardous materials transportation

International Nuclear Information System (INIS)

Manas Lahoz, J.L.

1993-01-01

The author describes the methodology for safety auditory and control, prevention, risks of hazardous materials transport through ship, airplane, rail, etc. In this way, The author presents the classification of damage materials transport, characteristic damage and different transport methods

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2000 edition

International Nuclear Information System (INIS)

2000-08-01

Safety in the transport of radioactive material is dependent on packaging appropriate for the contents being shipped, rather than on operational and/or administrative actions required on the package. The grater the radiological risk posed by the material being moved, the more stringent become the performance for the packaging that can be authorised to contain it. These principles have been expanded since 1061 into a set of regulations that are responsible for safety moving the ever-growing number and complexity of radioactive material shipments throughout the world. The IAEA Regulations for the Safe Transport of Radioactive Material are incorporated into UN regulations, as well as the requirements of other international transport organizations. This is the eleventh report published by the IAEA since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Transport safety Standards Advisory Committee (TRANSSAC). Through the PACKTRAM database, the IAEA collects administrative and technical information provided by the issuing competent authority about package approval certificates

Renewable fibers and bio-based materials for packaging applications - A review of recent developments

DEFF Research Database (Denmark)

Johansson, Caisa; Bras, Julien; Mondragon, Inaki

2012-01-01

This review describes the state-of-the-art of material derived from the forest sector with respect to its potential for use in the packaging industry. Some innovative approaches are highlighted. The aim is to cover recent developments and key challenges for successful introduction of renewable...... materials in the packaging market. The covered subjects are renewable fibers and bio-based polymers for use in bioplastics or as coatings for paper-based packaging materials. Current market sizes and forecasts are also presented. Competitive mechanical, thermal, and barrier properties along with material...

Directory of Certificates of Compliance for Radioactive Materials Packages

International Nuclear Information System (INIS)

1993-10-01

This directory contains Certificates of Compliance (Volume 2), for NRC Approved Packages. The purpose of this directory is to make available a convenient source of information on Quality Assurance Programs and Packagings which have been approved by the US Nuclear Regulatory Commission. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, is applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program

Directory of certificates of compliance for radioactive materials packages. Volume 1. Summary report of NRC approved packages. Revision 6

International Nuclear Information System (INIS)

1983-09-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), all Certificates of Compliance (Volume 2), and Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective September 14, 1983

Risk methodologies for offsite hazardous materials

International Nuclear Information System (INIS)

Kot, C.A.; Eichler, T.V.; Wiedermann, A.H.

1983-01-01

A number of suggestions have been advanced in recent years concerning the risks posed to nuclear power plants by offsite hazardous materials relative to (1) the regulatory approach including considerations of minimum and safe standoff distances, exclusion distances, site acceptance ceilings and floors, screening distances and screening probabilities, plant design, etc., and (2) the analysis and evaluation procedures such as material screening criteria, plant vulnerability, standarized physical models, etc. An evaluation of current analyses and approaches indicates that this complex problem, variety of approaches, and safety concerns may be better accommodated by developing criteria and treatments along the lines of a so-called conditional risk approach. Specifically, the probability (P) of some ultimate consequence (C) occurring from an accident (A) involving hazardous materials is given as P(C) = P(C/A) x P(A). Assuming that the plant to accident site standoff distance is the fundamental independent variable of the risk methodology, certain conditional risk designations and conditions can be made and are presented

Apparatus for waste disposal of radioactive hazardous waste

International Nuclear Information System (INIS)

Burack, R.D.; Stenger, W.J.; Wolfe, C.R.

1992-01-01

This patent describes an apparatus for concentrating dissolved and solid radioactive materials carried in a waste water solution containing a hazardous chelating agent used for cleaning nuclear equipment. It comprises oxidizing chamber means, separator means coupled to the oxidizing chamber means; ion exchange means containing an ion exchange resin; dryer means for receiving the radioactive solids from the separator means and for producing dry solids; and packaging means for receiving the dry solids and spent ion exchange resins containing the removed dissolved radioactive materials and for packaging the dry solids and spent resins in solid form

Radioactive Materials Packaging (RAMPAC) Radioactive Materials Incident Report (RMIR). RAMTEMP users manual

International Nuclear Information System (INIS)

Tyron-Hopko, A.K.; Driscoll, K.L.

1985-10-01

The purpose of this document is to familiarize the potential user with RadioActive Materials PACkaging (RAMPAC), Radioactive Materials Incident Report (RMIR), and RAMTEMP databases. RAMTEMP is a minor image of RAMPAC. This reference document will enable the user to access and obtain reports from databases while in an interactive mode. This manual will be revised as necessary to reflect enhancements made to the system

Cardboard Based Packaging Materials as Renewable Thermal Insulation of Buildings: Thermal and Life Cycle Performance

OpenAIRE

Čekon, Miroslav; Struhala, Karel; Slávik, Richard

2017-01-01

Cardboard based packaging components represent a material with a significant potential of renewable exploitation in buildings. This study presents the results of thermal and environmental analysis of existing packaging materials compared with standard conventional thermal insulations. Experimental measurements were performed to identify the thermal performance of studied cardboard packaging materials. Real-size samples were experimentally tested in laboratory measurements. The thermal resi...

The effects of packaging materials on microbe population in irradiated traditional herbal medicines

International Nuclear Information System (INIS)

Bagiawati, Sri; Hilmy, Nazly

1983-01-01

Microbial population and moisture content of traditional herbal medicines contaminated with 3 kinds of aerobic microbes, packed in 5 kinds of plastic packaging materials, followed by irradiation at minimum dose of 5 kGy and stored for 6 months were investigated. The highest reduction of microbial counts during storage was observed on samples packed in polyethylene bags. All of packaging materials used were found to be impermeable to microbes and water vapour. Radiation and packaging materials used acted synergistically to inactivate microbes durind storage. The microbial counts decreased as much as 2 to 4 log cycles during storage. (author)

77 FR 60935 - Hazardous Materials: Minor Editorial Corrections and Clarifications (RRR)

Science.gov (United States)

2012-10-05

... flammable cryogenic liquid is not received by the consignee within 20 days from the date of shipment.... * * * * * Container ship * * * * * * * * Hazardous material means a substance or material that the Secretary of... transportation law (49 U.S.C. 5103). The term includes hazardous substances, hazardous wastes, marine pollutants...

Savannah River Site Eastern Transportation Hub: A Concept For a DOE Eastern Packaging, Staging and Maintenance Center - 13143

Energy Technology Data Exchange (ETDEWEB)

England, Jeffery L. [Savannah River National Laboratory, Aiken, South Carolina (United States); Adams, Karen; Maxted, Maxcine; Ruff Jr, Clarence [U.S. Department of Energy, Savannah River Site, Aiken, SC (United States); Albenesius, Andrew; Bowers, Mark D.; Fountain, Geoffrey; Hughes, Michael [Savannah River Nuclear Solutions, Aiken, SC (United States); Gordon, Sydney [National Security Technologies, LLC, Las Vegas, NV (United States); O' Connor, Stephen [U.S. Department of Energy, HQ DOE, EM-33, Germantown MD (United States)

2013-07-01

The Department of Energy (DOE) is working to de-inventory sites and consolidate hazardous materials for processing and disposal. The DOE administers a wide range of certified shipping packages for the transport of hazardous materials to include Special Nuclear Material (SNM), radioactive materials, sealed sources and radioactive wastes. A critical element to successful and safe transportation of these materials is the availability of certified shipping packages. There are over seven thousand certified packagings (i.e., Type B/Type AF) utilized within the DOE for current missions. The synergistic effects of consolidated maintenance, refurbishment, testing, certification, and costing of these services would allow for efficient management of the packagings inventory and to support anticipated future in-commerce shipping needs. The Savannah River Site (SRS) receives and ships radioactive materials (including SNM) and waste on a regular basis for critical missions such as consolidated storage, stabilization, purification, or disposition using H-Canyon and HB-Line. The Savannah River National Laboratory (SRNL) has the technical capability and equipment for all aspects of packaging management. SRS has the only active material processing facility in the DOE complex and is one of the sites of choice for nuclear material consolidation. SRS is a logical location to perform maintenance and periodic testing of the DOE fleet of certified packagings. This initiative envisions a DOE Eastern Packaging Staging and Maintenance Center (PSMC) at the SRS and a western hub at the Nevada National Security Site (NNSS), an active DOE Regional Disposal Site. The PSMC's would be the first place DOE would go to meet their radioactive packaging needs and the primary locations projects would go to disposition excess packaging for beneficial reuse. These two hubs would provide the centralized management of a packaging fleet rather than the current approach to design, procure, maintain and

Directory of Certificates of Compliance for Radioactive Materials Packages. Summary report of NRC approved packages. Volume 1, Revision 8

International Nuclear Information System (INIS)

1985-10-01

This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure them that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages. Volume 1. Revision 9

International Nuclear Information System (INIS)

1986-10-01

This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and Corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Sections 71.12, it is the responsibility of the licensees to insure them that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

Directory of certificates of compliance for radioactive materials packages. Summary report of NRC approved packages. Volume 1, Revision 7

International Nuclear Information System (INIS)

1984-11-01

This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

DEMONSTRATION OF PACKAGING MATERIALS ALTERNATIVES TO EXPANDED POLYSTYRENE

Science.gov (United States)

This report represents the second demonstration of cleaner technologies to support the goals of the 33/50 Program under the EPA Cooperative Agreement No. CR-821848. The report presents assessment results of alternative packaging materials which could potentially replace expanded...

Intelligent systems for remote decommissioning in hazardous environments

International Nuclear Information System (INIS)

Drotning, W.D.; Bennett, P.C.

1991-01-01

This paper reports on investigation of advanced handling technologies utilizing intelligent machines being supported jointly by the U.S. Department of Energy Offices of Civilian Radioactive Waste Management and Environmental Restoration and Waste Management for automation of transportation package handling operations at nuclear facilities and of nuclear waste site remediation efforts. Handling operation requirements include identification, location, and health physics operations, followed by bolting/unbolting operations and package disassembly. To accommodate these operations and the diversity of packages, fast model-based automated programming and force feedback control of a robotic control has been demonstrated for application to hazardous material cleanup. In this application, a graphical interface is used to simulate and evaluate operator-controlled motions and provide telerobotic control of the system. Remote automated handling technologies developed through these programs have the potential to decrease worker exposure and increase efficiency during decommissioning activities in hazardous environments

Effect of Spices and different Packaging Materials on acceptability ...

African Journals Online (AJOL)

Objective: The effect of spices (ginger, garlic and nutmeg) as preservatives and use of different packaging materials (aluminium foil, polythene and leaves) in preserving “moin-moin” were investigated. Subjects/Materials and Methods: The samples of the “moin-moin” were prepared with different concentrations (1,2,3)g of ...

78 FR 60755 - Hazardous Materials: Enhanced Enforcement Procedures-Resumption of Transportation

Science.gov (United States)

2013-10-02

... material,'' we envisioned etiological agents, such as biological products, infectious substances, medical... accidents or incidents involving the transportation of hazardous material. In order to achieve a uniform... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part...

Impact limiters for radioactive materials transport packagings: a methodology for assessment

International Nuclear Information System (INIS)

Mourao, Rogerio Pimenta

2002-01-01

This work aims at establishing a methodology for design assessment of a cellular material-filled impact limiter to be used as part of a radioactive material transport packaging. This methodology comprises the selection of the cellular material, its structural characterization by mechanical tests, the development of a case study in the nuclear field, preliminary determination of the best cellular material density for the case study, performance of the case and its numerical simulation using the finite element method. Among the several materials used as shock absorbers in packagings, the polyurethane foam was chosen, particularly the foam obtained from the castor oil plant (Ricinus communis), a non-polluting and renewable source. The case study carried out was the 9 m drop test of a package prototype containing radioactive wastes incorporated in a cement matrix, considered one of the most severe tests prescribed by the Brazilian and international transport standards. Prototypes with foam density pre-determined as ideal as well as prototypes using lighter and heavier foams were tested for comparison. The results obtained validate the methodology in that expectations regarding the ideal foam density were confirmed by the drop tests and the numerical simulation. (author)

Survival of Spoilage and Pathogenic Microorganisms on Cardboard and Plastic Packaging Materials

Directory of Open Access Journals (Sweden)

Lorenzo Siroli

2017-12-01

Full Text Available The aim of this work was to study the interaction of corrugated and plastic materials with pathogenic and spoiling microorganisms frequently associated to fresh produce. The effect of the two packaging materials on the survival during the storage of microorganisms belonging to the species Escherichia coli, Listeria monocytogenes, Salmonella enteritidis, Saccharomyces cerevisiae, Lactobacillus plantarum, Pseudomonas fluorescens, and Aspergillus flavus was studied through traditional plate counting and scanning electron microscopy (SEM. The results obtained showed that cardboard materials, if correctly stored, reduced the potential of packaging to cross-contaminate food due to a faster viability loss by spoilage and pathogenic microorganisms compared to the plastic ones. In fact, the cell loads of the pathogenic species considered decreased over time independently on the inoculation level and packaging material used. However, the superficial viability losses were significantly faster in cardboard compared to plastic materials. The same behavior was observed for the spoilage microorganisms considered. The SEM microphotographs indicate that the reduction of superficial contamination on cardboard surfaces was due to the entrapping of the microbial cells within the fibers and the pores of this material. In addition, SEM data showed that the entrapped cells were subjected to more or less rapid lyses, depending on the species, due to the absence of water and nutrients, with the exception of molds. The latter spoilers were able to proliferate inside the cardboard fibers only when the absorption of water was not prevented during the storage. In conclusion, the findings of this work showed the reduction of cross-contamination potential of corrugated compared to plastic packaging materials used in fruit and vegetable sector. However, the findings outlined the importance of hygiene and low humidity during cardboard storage to prevent the mold growth on

Drop Weight Device Fabrication and Tests for a Dynamic Material Property of Shock-Absorbing Material and Structure in Transportation Package

International Nuclear Information System (INIS)

Choi, Woo Seok; Jeon, Jea Eon; Han, Sang Hyeok; Lee, Sang Hoon; Seo, Ki Seok

2009-01-01

A radioactive material transportation package consists of canister and impact limiters. IAEA Safety Standard Series No. TS-R-1 recommends a drop test to evaluate the structural integrity of a transportation package under a hypothetical accident condition. The free drop test of a transportation package from 9 m height simulates one of accident conditions. The transportation package has a potential energy corresponding to 9 m drop height, and this energy changes to a kinetic energy when it impacts on the target. The energy is absorbed by a deformation of shock-absorbing material so that the minimum energy is transferred to canister. Accordingly, the shock-absorbing material is a very important part in transportation package design. Since the data for shock-absorbing material characteristics is acquired by a static test in general, it is quite different to that of dynamic characteristics. And the dynamic characteristics data is hardly found in literature. In this study, a drop weight facility was designed and fabricated which produces an impact speed like that of free drop of 9 m height. Several materials considered for an impact limiter and impact limiter structures were tested by a drop weight facility to acquire a dynamic material characteristics data

Drop Weight Device Fabrication and Tests for a Dynamic Material Property of Shock-Absorbing Material and Structure in Transportation Package

Energy Technology Data Exchange (ETDEWEB)

Choi, Woo Seok; Jeon, Jea Eon; Han, Sang Hyeok; Lee, Sang Hoon; Seo, Ki Seok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2009-05-15

A radioactive material transportation package consists of canister and impact limiters. IAEA Safety Standard Series No. TS-R-1 recommends a drop test to evaluate the structural integrity of a transportation package under a hypothetical accident condition. The free drop test of a transportation package from 9 m height simulates one of accident conditions. The transportation package has a potential energy corresponding to 9 m drop height, and this energy changes to a kinetic energy when it impacts on the target. The energy is absorbed by a deformation of shock-absorbing material so that the minimum energy is transferred to canister. Accordingly, the shock-absorbing material is a very important part in transportation package design. Since the data for shock-absorbing material characteristics is acquired by a static test in general, it is quite different to that of dynamic characteristics. And the dynamic characteristics data is hardly found in literature. In this study, a drop weight facility was designed and fabricated which produces an impact speed like that of free drop of 9 m height. Several materials considered for an impact limiter and impact limiter structures were tested by a drop weight facility to acquire a dynamic material characteristics data.

Procedures for picking up and receiving packages of radioactive material

International Nuclear Information System (INIS)

1975-05-01

This regulatory guide describes a method acceptable to the NRC staff for licensees to comply with the provisions in 10 CFR Part 20, section 20.205, with respect to arrangements for receipt, pickup, and monitoring of packages containing radioactive material and with respect to reporting of packages which, on receipt, show evidence of leakage or excessive radiation levels. (U.S.)

Safety analysis report: packages cobalt-60 shipping cask (packaging of radioactive and fissile materials)

International Nuclear Information System (INIS)

Evans, J.E.; Langhaar, J.W.

1973-07-01

Safety Analysis Report DPSPU-73-124-1 replaces DPSPU-69-124-1 and Supplement 1 to permit shipment of 350,000 curies of 60 Co (maximum) in cobalt-60 shipping casks in compliance with 10 CFR Part 71, Packaging of Radioactive Materials for Transport

19 CFR 10.601 - Retail packaging materials and containers.

Science.gov (United States)

2010-04-01

...-Central America-United States Free Trade Agreement Rules of Origin § 10.601 Retail packaging materials and...), HTSUS. (b) Effect on regional value content calculation. If the good is subject to a regional value... originating or non-originating materials, as the case may be, in calculating the regional value content of the...

Directory of certificates of compliance for radioactive materials packages

International Nuclear Information System (INIS)

1989-10-01

The purpose of this directory is to make available a convenient source of information on packaging which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory. Shipments of radioactive material utilizing these packages must be in accordance with the provisions of 49 CFR section 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure themselves that they have a copy of the current approval and conduct their transportation activities in accordance with a Nuclear Regulatory Commission approved quality assurance program

Technical and Regulatory Considerations in Using Freight Containers as Industrial Packages

Energy Technology Data Exchange (ETDEWEB)

Hawk, Mark B [ORNL; Opperman, Erich [Washington Savannah River Company; Natali, Ronald [R. B. Natali Consulting, Inc.

2008-01-01

The US Department of Energy (DOE), Office of Environmental Management (EM), is actively pursuing activities to reduce the radiological risk and clean up the environmental legacy of the nation's nuclear weapons programmes. The EM has made significant progress in recent years in the clean-up and closure of sites and is also focusing on longer term activities necessary for the completion of the clean-up programme. The packaging and transportation of contaminated demolition debris and low level waste materials in a safe and cost effective manner are essential in completing this mission. Toward this end, the US Department of Transportation's Final Rule on Hazardous Materials Regulation issued on 26 January 2004, included a new provision authorising the use of freight containers (e.g. 20 and 40 ft ISO containers) as industrial packages type 2 or 3. This paper will discuss the technical and regulatory considerations in using these newly authorised and large packages for the packaging and transportation of low level waste materials.

Analysis of energy and materials utilization for packaging liquid basic and luxury foodstuffs

Energy Technology Data Exchange (ETDEWEB)

Ebersbach, K F

1981-01-01

By the help of the product 'packaging' the quantities of the energy and materials used are demonstrated analytically within the single stages of the production and utilization of these goods. Alternatives for a better utilization of energy and materials are to be demonstrated. - A methodology for setting up analyses and alternatives is to be introduced which a) is generally accepted in investigations of this kind and b) permits controlled measures for improving the energy and materials balances. Several considerations made the authors select the packagings for beer and soft drinks as the subjects of the project. The usual packagings for these beverages are dealt with.

Program in change: shipment of hazardous materials at the INEL

International Nuclear Information System (INIS)

Reed, L.L.

1984-01-01

Positive measures such as education, control, and auditing ability should be incorporated into each hazardous material shipping program to assure compliance with regulations and the safe movement of hazardous materials. This paper discusses these and other pertinent components of a shipping program. 3 references

Environmentally sound management of hazardous waste and hazardous recyclable materials

International Nuclear Information System (INIS)

Smyth, T.

2002-01-01

Environmentally sound management or ESM has been defined under the Basel Convention as 'taking all practicable steps to ensure that hazardous wastes and other wastes are managed in a manner which will protect human health and the environment against the adverse effects which may result from such wastes'. An initiative is underway to develop and implement a Canadian Environmentally Sound Management (ESM) regime for both hazardous wastes and hazardous recyclable materials. This ESM regime aims to assure equivalent minimum environmental protection across Canada while respecting regional differences. Cooperation and coordination between the federal government, provinces and territories is essential to the development and implementation of ESM systems since waste management is a shared jurisdiction in Canada. Federally, CEPA 1999 provides an opportunity to improve Environment Canada's ability to ensure that all exports and imports are managed in an environmentally sound manner. CEPA 1999 enabled Environment Canada to establish criteria for environmentally sound management (ESM) that can be applied by importers and exporters in seeking to ensure that wastes and recyclable materials they import or export will be treated in an environmentally sound manner. The ESM regime would include the development of ESM principles, criteria and guidelines relevant to Canada and a procedure for evaluating ESM. It would be developed in full consultation with stakeholders. The timeline for the development and implementation of the ESM regime is anticipated by about 2006. (author)

Natural radioactivity and radiological hazards of building materials in Xianyang, China

International Nuclear Information System (INIS)

Lu Xinwei; Yang Guang; Ren Chunhui

2012-01-01

Common building materials collected from Xianyang, China were analyzed for the natural radioactivity of 226 Ra, 232 Th and 40 K using γ-ray spectroscopy. The average activity concentration of 226 Ra, 232 Th and 40 K in the studied building materials ranges from 13.4 to 69.9, 13.1–99.1 and 124.7–915.1 Bq kg −1 , respectively. The measured activity concentrations for these radionuclides were compared with the reported data of other countries and with the worldwide average activity of soil. To assess the radiation hazard of the natural radioactivity in all samples to the people, the radium equivalent activity, external hazard index, internal hazard index, indoor absorbed dose rate and total annual effective dose were estimated. The radium equivalent activities of the studied samples are below the internationally accepted values. The external hazard index and internal hazard index of all analyzed building materials are less than unity. The mean values of indoor absorbed dose rate for all building materials except for lime are higher than the world population-weighted average of 84 nGy h −1 and the total annual effective dose values of building materials are lower than 1 mSv y −1 except for some cyan brick samples. The study shows the measured building materials do not pose significant source of radiation hazard and are safe for use in the construction of dwellings. - Highlights: ► Natural radioactivity in building materials was determined by gamma ray spectrometry. ► The radiological hazard of studied building materials is within the recommended safety limit. ► Most of the studied building materials do not pose significant radiation risk to residents.

Unify a hazardous materials/waste program

International Nuclear Information System (INIS)

Carson, H.T.

1988-01-01

Efficiently managing a hazardous materials/waste program in a multi-facility, multi-product corporation is a major challenge. This paper describes several methods to help unify a program and gain maximum efficiency of manpower and to minimize risk

Westinghouse Hanford Company package testing capabilities

International Nuclear Information System (INIS)

Hummer, J.H.; Mercado, M.S.

1993-07-01

The Department of Energy's Hanford Site is a 1,450-km 2 (560-mi 2 ) installation located in southeastern Washington State. Established in 1943 as a plutonium production facility, Hanford's role has evolved into one of environmental restoration and remediation. Many of these environmental restoration and remediation activities involve transportation of radioactive/hazardous materials. Packagings used for the transportation of radioactive/hazardous materials must be capable of meeting certain normal transport and hypothetical accident performance criteria. Evaluations of performance to these criteria typically involve a combination of analysis and testing. Required tests may include the free drop, puncture, penetration, compression, thermal, heat, cold, vibration, water spray, water immersion, reduced pressure, and increased pressure tests. The purpose of this paper is to outline the Hanford capabilities for performing each of these tests

Type B plutonium transport package development that uses metallic filaments and composite materials

International Nuclear Information System (INIS)

Pierce, J.D.; Moya, J.L.; McClure, J.D.; Hohnstreiter, G.F.; Golliher, K.G.

1992-01-01

A new design concept for a Type B transport packaging for transporting plutonium and uranium has been developed by the Transportation Systems Department at Sandia National Laboratories (SNL). The new design came about following a review of current packagings, projected future transportation needs, and current and future regulatory requirements. United States packaging, regulations specified in Title 49, Code of Federal Regulations Parts 173.416 and 173.417 (for fissile materials) offer parallel paths under the heading of authorized Type B packages for the transport of greater than A 1 or A 2 quantities of radioactive material. These pathways are for certified Type B packagings and specification packagings. Consequently, a review was made of both type B and specification packages. A request for comment has been issued by the US Nuclear Regulatory Commission (NRC) for proposed changes to Title 10, Code of Federal Regulations Part 71. These regulations may therefore change in the near future. The principle proposed regulation change that would affect this type of package is the addition of a dynamic crush requirement for certain packagings. The US Department of Transportation (DOT) may also re-evaluate the specifications in 49 CFR that authorize the fabrication and use of specification packagings. Therefore, packaging, options were considered that will meet expected new regulations and provide shipment capability for the US Department of Energy well into the future

Technology transfer package on seismic base isolation - Volume III

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-02-14

This Technology Transfer Package provides some detailed information for the U.S. Department of Energy (DOE) and its contractors about seismic base isolation. Intended users of this three-volume package are DOE Design and Safety Engineers as well as DOE Facility Managers who are responsible for reducing the effects of natural phenomena hazards (NPH), specifically earthquakes, on their facilities. The package was developed as part of DOE's efforts to study and implement techniques for protecting lives and property from the effects of natural phenomena and to support the International Decade for Natural Disaster Reduction. Volume III contains supporting materials not included in Volumes I and II.

Implications of material selection on the design of packaging machinery.

Science.gov (United States)

Merritt, J P

2009-01-01

Material selection has significant implications on the design and cost of horizontal-form-fill-seal packaging machinery. To avoid excessive costs, machine redesigns and project delays, material selection must be reconciled early in the project and revisited throughout the construction of the machine.

Approved requirements for the packaging, labelling and carriage of radioactive material by rail

International Nuclear Information System (INIS)

1996-01-01

This document specifies the detailed provisions in the United Kingdom with respect to rail transport for packages and packaging, test procedures for radioactive materials, information concerning the preparation of radioactive materials and the operation of tanks and container wagons. The Approved Requirements came into force on 1 September 1996 and are legally binding. (UK)

Hazardous Materials Management and Emergency Response (HAMMER)

Data.gov (United States)

Federal Laboratory Consortium — The Volpentest Hazardous Materials Management and Emergency Response (HAMMER) Federal Training Center is a safety and emergency response training center that offers...

Intelligent systems for remote decommissioning in hazardous environments

International Nuclear Information System (INIS)

Drotning, W.D.; Bennett, P.C.

1991-01-01

Investigation of advanced technologies utilizing intelligent machines is being supported jointly by the US Department of Energy Offices of Civilian Radioactive Waste Management (DOE/RW) and Environmental Restoration and Waste Management (DOE/EM) for automation of transportation package handling operations at nuclear facilities and of nuclear waste site remediation efforts. Handling operation requirements include identification, location, and health physics operation, followed by bolting/unbolting operations and package disassembly. To accommodate these operations and the diversity of packages, fast model-based automated programming and force feedback control of a robotic cask handling system were developed. In addition, sensor-directed model-based robotic control has been demonstrated for application to hazardous material cleanup. In this application, a graphical interface is used to simulate and evaluate operator-controlled motions and provide telerobotic control of the system. Remote automated handling technologies developed through these programs have the potential to decrease worker exposure and increase efficiency during decommissioning activities in hazardous environments. 8 refs., 4 figs

Benefits of standard format and content for approval of packaging for radioactive material

International Nuclear Information System (INIS)

Pstrak, D.; Osgood, N.

2004-01-01

The U.S. Nuclear Regulatory Commission (NRC) uses Regulatory Guide 7.9, ''Standard Format and Content of Part 71 Applications for Approval of Packaging for Radioactive Material'' to provide recommendations on the preparation of applications for approval of Type B and fissile material packages. The purpose of this Regulatory Guide is to assist the applicant in preparing an application that demonstrates the adequacy of a package in meeting the 10 CFR Part 71 packaging requirements. NRC recently revised Regulatory Guide 7.9 to reflect current changes to the regulations in Part 71 as a result of a recent rulemaking that included changes to the structural, containment, and criticality requirements for packages. Overall, the NRC issues Regulatory Guides to describe methods that are acceptable to the NRC staff for implementing specific parts of the NRC's regulations, to explain techniques used by the NRC staff in evaluating specific problems, and to provide guidance to applicants. It is important to note the specific purpose of this Regulatory Guide. As the name indicates, this Guide sets forth a standard format for application submission that is acceptable to the NRC staff that, when used by the applicant, will accomplish several objectives. First, use of the guide provides a consistent and repeatable approach that indicates the information to be provided by the applicant. Second, the organization of the information in the application will assist the reviewer(s) in locating information. Ultimately, accomplishing these objectives will help to ensure the completeness of the information in the application as well as decrease the review time. From an international perspective, use of a standard format approach could enhance the efficiency with which Competent Authorities certify and validate packages for use in the packaging and transportation of radioactive material worldwide. This streamlined approach of preparing package applications could ultimately lead to uniform

Directory of certificates of compliance for radioactive materials packages. Certificates of compliance

International Nuclear Information System (INIS)

1979-10-01

This volume contains all Certificates of Compliance for radioactive material packages effective September 14, 1979. Purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory

9975 Shipping Package Performance Of Alternate Materials For Long-Term Storage Application

International Nuclear Information System (INIS)

Skidmore, E.; Hoffman, E.; Daugherty, W.

2010-01-01

The Model 9975 shipping package specifies the materials of construction for its various components. With the loss of availability of material for two components (cane fiberboard overpack and Viton(reg s ign) GLT O-rings), alternate materials of construction were identified and approved for use for transport (softwood fiberboard and Viton(reg s ign) GLT-S O-rings). As these shipping packages are part of a long-term storage configuration at the Savannah River Site, additional testing is in progress to verify satisfactory long-term performance of the alternate materials under storage conditions. The test results to date can be compared to comparable results on the original materials of construction to draw preliminary conclusions on the performance of the replacement materials.

Stability of flavoured phytosterol-enriched drinking yogurts during storage as affected by different packaging materials.

Science.gov (United States)

Semeniuc, Cristina Anamaria; Cardenia, Vladimiro; Mandrioli, Mara; Muste, Sevastiţa; Borsari, Andrea; Rodriguez-Estrada, Maria Teresa

2016-06-01

The aim of this study was to investigate the influence of different packaging materials on storage stability of flavoured phytosterol-enriched drinking yogurts. White vanilla (WV) and blood orange (BO) phytosterol-enriched drinking yogurts conditioned in mono-layer and triple-layer co-extruded plastic bottles were stored at +6 ± 1 °C for 35 days (under alternating 12 h light and 12 h darkness) to simulate shelf-life conditions. Samples were collected at three different storage times and subjected to determination of total sterol content (TSC), peroxide value (PV) and thiobarbituric acid reactive substances (TBARs). TSC was not significantly affected by packaging material or storage time and met the quantity declared on the label. PV was significantly influenced by yogurt type × packaging material × storage time interaction and TBARs by packaging material × storage time interaction. Between the two packaging materials, the triple-layer plastic mini bottle with black coloured and completely opaque intermediate layer offered the best protection against lipid oxidation. © 2015 Society of Chemical Industry. © 2015 Society of Chemical Industry.

Directory of certificates of compliance for radioactive materials packages: Certificates of compliance

International Nuclear Information System (INIS)

1987-11-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Certificates of Compliance (Volume 2) for Radioactive Material Packages effective October 1, 1987. This directory makes available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the back of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2003 ed

International Nuclear Information System (INIS)

2003-10-01

This is the fourteenth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Transport Safety Standards Committee (TRANSSC). It supersedes IAEA-TECDOC-1302 'Directory of National Competent Authorities' Approval Certificates for Package Design, Special Form Material and Shipment of Radioactive Material, 2002 Edition'. Through the database, the Secretariat collects administrative and technical information provided by the issuing competent authority about package approval certificates. Such data are used mainly by national competent authorities and port and customs officials to assist in regulating radioactive material movements in their country, and also by manufacturers and shippers of radioactive material. The database carries information on extant certificates and those that expired within the last complete calendar year. The PACKTRAM database only contains information that has been provided to the IAEA. The data are not complete nor guaranteed to be accurate. If detailed information is required, the original package approval certificates must be consulted. If information is required about package approval certificates that are not contained in the database, the issuing competent authority must be consulted

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 2003 ed

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-10-01

This is the fourteenth annual report being published by the Secretariat of the International Atomic Energy Agency since implementing its database on package approval certificates (PACKTRAM) at the recommendation of the Transport Safety Standards Committee (TRANSSC). It supersedes IAEA-TECDOC-1302 'Directory of National Competent Authorities' Approval Certificates for Package Design, Special Form Material and Shipment of Radioactive Material, 2002 Edition'. Through the database, the Secretariat collects administrative and technical information provided by the issuing competent authority about package approval certificates. Such data are used mainly by national competent authorities and port and customs officials to assist in regulating radioactive material movements in their country, and also by manufacturers and shippers of radioactive material. The database carries information on extant certificates and those that expired within the last complete calendar year. The PACKTRAM database only contains information that has been provided to the IAEA. The data are not complete nor guaranteed to be accurate. If detailed information is required, the original package approval certificates must be consulted. If information is required about package approval certificates that are not contained in the database, the issuing competent authority must be consulted.

Hazards assessment for the INEL Landfill Complex

International Nuclear Information System (INIS)

Knudsen, J.K.; Calley, M.B.

1994-02-01

This report documents the hazards assessment for the INEL Landfill Complex (LC) located at the Idaho National Engineering Laboratory, which is operated by EG ampersand G Idaho, Inc., for the US Department of Energy (DOE). The hazards assessment was performed to ensure that this facility complies with DOE and company requirements pertaining to emergency planning and preparedness for operational emergencies. DOE Order 5500.3A requires that a facility-specific hazards assessment be performed to provide the technical basis for facility emergency planning efforts. This hazards assessment was conducted in accordance with DOE Headquarters and the DOE Idaho Operations Office (DOE-ID) guidance to comply with DOE Order 5500.3A. The hazards assessment identifies and analyzes the hazards that are significant enough to warrant consideration in a facility's operational emergency management program. The area surrounding the LC, the buildings and structures at the LC, and the processes that are used at the LC are described in this report. All hazardous materials, both radiological and nonradiological, at the LC were identified and screened against threshold quantities according to DOE Order 5500.3A guidance. Asbestos at the Asbestos Pit was the only hazardous material that exceeded its specified threshold quantity. However, the type of asbestos received and the packaging practices used are believed to limit the potential for an airborne release of asbestos fibers. Therefore, in accordance with DOE Order 5500.3A guidance, no further hazardous material characterization or analysis was required for this hazards assessment

Hazards assessment for the INEL Landfill Complex

Energy Technology Data Exchange (ETDEWEB)

Knudsen, J.K.; Calley, M.B.

1994-02-01

This report documents the hazards assessment for the INEL Landfill Complex (LC) located at the Idaho National Engineering Laboratory, which is operated by EG&G Idaho, Inc., for the US Department of Energy (DOE). The hazards assessment was performed to ensure that this facility complies with DOE and company requirements pertaining to emergency planning and preparedness for operational emergencies. DOE Order 5500.3A requires that a facility-specific hazards assessment be performed to provide the technical basis for facility emergency planning efforts. This hazards assessment was conducted in accordance with DOE Headquarters and the DOE Idaho Operations Office (DOE-ID) guidance to comply with DOE Order 5500.3A. The hazards assessment identifies and analyzes the hazards that are significant enough to warrant consideration in a facility`s operational emergency management program. The area surrounding the LC, the buildings and structures at the LC, and the processes that are used at the LC are described in this report. All hazardous materials, both radiological and nonradiological, at the LC were identified and screened against threshold quantities according to DOE Order 5500.3A guidance. Asbestos at the Asbestos Pit was the only hazardous material that exceeded its specified threshold quantity. However, the type of asbestos received and the packaging practices used are believed to limit the potential for an airborne release of asbestos fibers. Therefore, in accordance with DOE Order 5500.3A guidance, no further hazardous material characterization or analysis was required for this hazards assessment.

Modified Hazard Ranking System/Hazard Ranking System for sites with mixed radioactive and hazardous wastes: Software documentation

Energy Technology Data Exchange (ETDEWEB)

Stenner, R.D.; Peloquin, R.A.; Hawley, K.A.

1986-11-01

The mHRS/HRS software package was developed by the Pacific Northwest Laboratory (PNL) under contract with the Department of Energy (DOE) to provide a uniform method for DOE facilities to use in performing their Conservation Environmental Response Compensation and Liability Act (CERCLA) Phase I Modified Hazard Ranking System or Hazard Ranking System evaluations. The program is designed to remove the tedium and potential for error associated with the performing of hand calculations and the interpreting of information on tables and in reference books when performing an evaluation. The software package is designed to operate on a microcomputer (IBM PC, PC/XT, or PC/AT, or a compatible system) using either a dual floppy disk drive or a hard disk storage system. It is written in the dBASE III language and operates using the dBASE III system. Although the mHRS/HRS software package was developed for use at DOE facilities, it has direct applicability to the performing of CERCLA Phase I evaluations for any facility contaminated by hazardous waste. The software can perform evaluations using either the modified hazard ranking system methodology developed by DOE/PNL, the hazard ranking system methodology developed by EPA/MITRE Corp., or a combination of the two. This document is a companion manual to the mHRS/HRS user manual. It is intended for the programmer who must maintain the software package and for those interested in the computer implementation. This manual documents the system logic, computer programs, and data files that comprise the package. Hardware and software implementation requirements are discussed. In addition, hand calculations of three sample situations (problems) with associated computer runs used for the verification of program calculations are included.

Modified Hazard Ranking System/Hazard Ranking System for sites with mixed radioactive and hazardous wastes: Software documentation

International Nuclear Information System (INIS)

Stenner, R.D.; Peloquin, R.A.; Hawley, K.A.

1986-11-01

The mHRS/HRS software package was developed by the Pacific Northwest Laboratory (PNL) under contract with the Department of Energy (DOE) to provide a uniform method for DOE facilities to use in performing their Conservation Environmental Response Compensation and Liability Act (CERCLA) Phase I Modified Hazard Ranking System or Hazard Ranking System evaluations. The program is designed to remove the tedium and potential for error associated with the performing of hand calculations and the interpreting of information on tables and in reference books when performing an evaluation. The software package is designed to operate on a microcomputer (IBM PC, PC/XT, or PC/AT, or a compatible system) using either a dual floppy disk drive or a hard disk storage system. It is written in the dBASE III language and operates using the dBASE III system. Although the mHRS/HRS software package was developed for use at DOE facilities, it has direct applicability to the performing of CERCLA Phase I evaluations for any facility contaminated by hazardous waste. The software can perform evaluations using either the modified hazard ranking system methodology developed by DOE/PNL, the hazard ranking system methodology developed by EPA/MITRE Corp., or a combination of the two. This document is a companion manual to the mHRS/HRS user manual. It is intended for the programmer who must maintain the software package and for those interested in the computer implementation. This manual documents the system logic, computer programs, and data files that comprise the package. Hardware and software implementation requirements are discussed. In addition, hand calculations of three sample situations (problems) with associated computer runs used for the verification of program calculations are included

The Influence of Aging Period, Freezing Temperature and Packaging Material on Frozen Beef Chemical Quality

Directory of Open Access Journals (Sweden)

Aris Sri Widati

2012-04-01

Full Text Available The objective of the study was to evaluate the influences of aging period, freezing temperature and packaging material on the frozen beef chemical quality. The material of the study was 2-3 years old Ongole grade beef of the Longissimus dorsi part,  and was then classified into 3 treat­ments, namely A (aging periode; 0, 12 and 24 hours, B (freezing temperature; -10°C and -20°C and C (packaging material; aluminum foil (Al, polyprophylene (PP, poly­ethylene (PE and without packaging material. The ob­served variables were water content, crude protein, fat, ash content. The data were analyzed by the Completely Randomized Design (CRD in the Factorial (3x2x4 pattern. The results indicated that the aging periode de­creased the water content, and ash content significantly (P<0.05, and decreased the crude protein but increased the fat content insignificantly. The lower freezing temperature prevented the decreases of the water content, and ash content significantly (P<0.05, but prevented the decrease of crude protein, fat content insignificantly. The packaging material could prevent the decreases of water content, ash content sig­nificantly (P<0.05, but prevent the decreases of protein, and fat content insignificantly. A significant interaction (P<0.05 occured between the freezing temperature and packaging material factors on ash content of the frozen beef. The conclusion was the frozen beef without aging has a high of water content, protein, and ash, but has a low fat content.Temperature at -200C and using aluminium foil packaging can prevent decreasing quality of frozen beef. Keywords : Aging period, freezing temperature,  packaging material

Release of powdered material from waste packages

International Nuclear Information System (INIS)

Berg, H.P.; Gruendler, D.; Peiffer, F.; Seehars, H.D.

1990-01-01

Possible incidents in the operational phase of the planned German repository KONRAD for radioactive waste with negligible heat production were investigated to assess the radiological consequences. For these investigations release fractions of the radioactive materials are required. This paper deals with the determination of the release of powdered material from waste packages under mechanical stress. These determinations were based on experiments. The experimental procedure and the process parameters chosen in accordance with the conditions in the planned repository will be described. The significance of the experimental results is discussed with respect to incidents in the planned repository. 8 figs., 3 tabs

Regional risk associated with the transport of hazardous materials

OpenAIRE

Nardini, L.; Aparicio, L.; Bandoni, A.; Tonelli, S. M.

2003-01-01

An increasing concern over the level of risk associated with hazardous materials transportation has led international efforts to focus on risk assessment at regional level. Following this trend, the aim of this work is to review the latest procedures for analysing the regional risks resulting from hazardous materials transportation by means of road and rail. In particular, two methodologies are reviewed and discussed, a method recently developed at Swiss Federal Institute of Technology [1] an...

Toward a federal/state/local partnership in hazardous materials transportation safety

International Nuclear Information System (INIS)

1982-09-01

In recognition of the federal government's responsibility for initiating a national strategy for hazardous materials transportation safety, the Materials Transportation Bureau (MTB) prepared an internal strategy paper for creating a federal/state/local partnership in hazardous materials transportation safety in August 1981. The paper outlined the scope of the hazardous materials transportation problem and established MTB's approach for creating an intergovernmental partnership for its resolution. This paper represents an update and refinement of the original plan, and is designed to chart the direction of the emerging federal/state/local relationship. The cornerstone of the plan remains the establishment of a single national set of safety regulations. It is on achievement of this objective that MTB's plan for development of enforcement, training, and emergency response capabilities at all levels of government is based. Chapter I introduces the problem with a desription of the economic importance of hazardous materials and discusses its implications for public safety. Chapter II defines the appropriate role for each level of government in the areas of rulemaking, enforcement, emergency response, and education. Chapter III demonstrates the need for uniform national safety standards and describes the economic and safety benefits of this approach. Chapter IV contains a detailed description of MTB's program for developing a successful intergovernmental partnership in hazardous materials transportation safety

Environmental risk analysis of hazardous material rail transportation

Energy Technology Data Exchange (ETDEWEB)

Saat, Mohd Rapik, E-mail: mohdsaat@illinois.edu [Department of Civil and Environmental Engineering, University of Illinois at Urbana-Champaign, 1243 Newmark Civil Engineering Laboratory, 205 North Mathews Avenue, Urbana, IL 61801 (United States); Werth, Charles J.; Schaeffer, David [Department of Civil and Environmental Engineering, University of Illinois at Urbana-Champaign, 1243 Newmark Civil Engineering Laboratory, 205 North Mathews Avenue, Urbana, IL 61801 (United States); Yoon, Hongkyu [Sandia National Laboratories, Albuquerque, NM 87123 (United States); Barkan, Christopher P.L. [Department of Civil and Environmental Engineering, University of Illinois at Urbana-Champaign, 1243 Newmark Civil Engineering Laboratory, 205 North Mathews Avenue, Urbana, IL 61801 (United States)

2014-01-15

Highlights: • Comprehensive, nationwide risk assessment of hazardous material rail transportation. • Application of a novel environmental (i.e. soil and groundwater) consequence model. • Cleanup cost and total shipment distance are the most significant risk factors. • Annual risk varies from $20,000 to $560,000 for different products. • Provides information on the risk cost associated with specific product shipments. -- Abstract: An important aspect of railroad environmental risk management involves tank car transportation of hazardous materials. This paper describes a quantitative, environmental risk analysis of rail transportation of a group of light, non-aqueous-phase liquid (LNAPL) chemicals commonly transported by rail in North America. The Hazardous Materials Transportation Environmental Consequence Model (HMTECM) was used in conjunction with a geographic information system (GIS) analysis of environmental characteristics to develop probabilistic estimates of exposure to different spill scenarios along the North American rail network. The risk analysis incorporated the estimated clean-up cost developed using the HMTECM, route-specific probability distributions of soil type and depth to groundwater, annual traffic volume, railcar accident rate, and tank car safety features, to estimate the nationwide annual risk of transporting each product. The annual risk per car-mile (car-km) and per ton-mile (ton-km) was also calculated to enable comparison between chemicals and to provide information on the risk cost associated with shipments of these products. The analysis and the methodology provide a quantitative approach that will enable more effective management of the environmental risk of transporting hazardous materials.

Environmental risk analysis of hazardous material rail transportation

International Nuclear Information System (INIS)

Saat, Mohd Rapik; Werth, Charles J.; Schaeffer, David; Yoon, Hongkyu; Barkan, Christopher P.L.

2014-01-01

Highlights: • Comprehensive, nationwide risk assessment of hazardous material rail transportation. • Application of a novel environmental (i.e. soil and groundwater) consequence model. • Cleanup cost and total shipment distance are the most significant risk factors. • Annual risk varies from $20,000 to $560,000 for different products. • Provides information on the risk cost associated with specific product shipments. -- Abstract: An important aspect of railroad environmental risk management involves tank car transportation of hazardous materials. This paper describes a quantitative, environmental risk analysis of rail transportation of a group of light, non-aqueous-phase liquid (LNAPL) chemicals commonly transported by rail in North America. The Hazardous Materials Transportation Environmental Consequence Model (HMTECM) was used in conjunction with a geographic information system (GIS) analysis of environmental characteristics to develop probabilistic estimates of exposure to different spill scenarios along the North American rail network. The risk analysis incorporated the estimated clean-up cost developed using the HMTECM, route-specific probability distributions of soil type and depth to groundwater, annual traffic volume, railcar accident rate, and tank car safety features, to estimate the nationwide annual risk of transporting each product. The annual risk per car-mile (car-km) and per ton-mile (ton-km) was also calculated to enable comparison between chemicals and to provide information on the risk cost associated with shipments of these products. The analysis and the methodology provide a quantitative approach that will enable more effective management of the environmental risk of transporting hazardous materials

Characterization of integrated circuit packaging materials

CERN Document Server

Moore, Thomas

1993-01-01

Chapters in this volume address important characteristics of IC packages. Analytical techniques appropriate for IC package characterization are demonstrated through examples of the measurement of critical performance parameters and the analysis of key technological problems of IC packages. Issues are discussed which affect a variety of package types, including plastic surface-mount packages, hermetic packages, and advanced designs such as flip-chip, chip-on-board and multi-chip models.

40 CFR 262.30 - Packaging.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 25 2010-07-01 2010-07-01 false Packaging. 262.30 Section 262.30... APPLICABLE TO GENERATORS OF HAZARDOUS WASTE Pre-Transport Requirements § 262.30 Packaging. Before... the waste in accordance with the applicable Department of Transportation regulations on packaging...

Advanced materials for thermal management of electronic packaging

CERN Document Server

Tong, Xingcun Colin

2011-01-01

The need for advanced thermal management materials in electronic packaging has been widely recognized as thermal challenges become barriers to the electronic industry's ability to provide continued improvements in device and system performance. With increased performance requirements for smaller, more capable, and more efficient electronic power devices, systems ranging from active electronically scanned radar arrays to web servers all require components that can dissipate heat efficiently. This requires that the materials have high capability of dissipating heat and maintaining compatibility

Hazardous materials sensing: An electrical metamaterial approach

Energy Technology Data Exchange (ETDEWEB)

Rawat, Vaishali; Kitture, Rohini [Department of Applied Physics, Defence Institute of Advanced Technology (DIAT), Girinagar, Pune 411025 (India); Kumari, Dimple [Department of Applied Chemistry, Defence Institute of Advanced Technology (DIAT), Girinagar, Pune 411025 (India); Rajesh, Harsh [Society for Applied Microwave Electronics Engineering and Research (SAMEER), IIT-Bombay Campus, Powai, Mumbai (India); Banerjee, Shaibal [Department of Applied Chemistry, Defence Institute of Advanced Technology (DIAT), Girinagar, Pune 411025 (India); Kale, S.N., E-mail: sangeetakale2004@gmail.com [Department of Applied Physics, Defence Institute of Advanced Technology (DIAT), Girinagar, Pune 411025 (India)

2016-10-01

Metamaterials are recently emerging materials exhibiting amazing properties such as extremely miniaturized antennas, waveguides, optical couplers, multiplexers and filters. Such structures also respond to the variation in their ambient conditions when exposed to toxic and hazardous materials, which are especially hazardous to human health. Through this manuscript, we document our studies on three different high energy materials; namely 2- bromo-2nitropropane-1,3-diol (BNP), bis (1,3-diazido prop-2-yl) malonate (AM) and bis (1,3-diazido prop-2-yl) glutarate (AG). A Complementary Split Ring Resonator has been fabricated at resonant frequency of 4.48 GHz using copper on FR4 substrate. The energetic materials were exposed to the sensor and results were monitored using Vector Network Analyzer. The volume of liquids was varied from 0.5 µL to 3 µL. Prominent and explicit shifts in the transmission resonant frequency and amplitude was seen as a signature of each energetic material. The signatures were not only sensitive to the specific toxic group in the material but also to the volume of the liquid subjected to this sensor. The results are correlated with the simulation results, basic chemistry of the materials and permittivity measurements. The ultra-fast reversibility and repeatability, with good sensitivity and specificity of these devices project their applications in sensitive locations, particularly to combat for human security and health issues.

Contribution to internal pressure and flammable gas concentration in RAM [radioactive material] transport packages

International Nuclear Information System (INIS)

Warrant, M.M.; Brown, N.

1989-01-01

Various facilities in the US generate wastes contaminated with transuranic (TRU) isotopes (such as plutonium and americium) that decay primarily by emission of alpha particles. The waste materials consist of a wide variety of commercially available plastics, paper, cloth, and rubber; concreted or sludge wastes containing water; and metals, glass, and other solid inorganic materials. TRU wastes that have surface dose rates of 200 mrem/hr or less are typically packaged in plastic bags placed inside metal drums or boxes that are vented through high efficiency particulate air (HEPA) filters. These wastes are to be transported from waste generation or storage sites to the Waste Isolation Pilot Plant (WIPP) in the TRUPACT-II, a Type B package. Radiolysis of organic wastes or packaging materials, or wastes containing water generates gas which may be flammable or simply contribute to the internal pressure of the radioactive material (RAM) transport package. This paper discusses the factors that affect the amount and composition of this gas, and summarizes maximum radiolytic G values (number of molecules produced per 100 eV absorbed energy) found in the technical literature for many common materials. These G values can be used to determine the combination of payload materials and decay heats that are safe for transport. G values are established for categories of materials, based on chemical functional groups. It is also shown using transient diffusion and quasi-equilibrium statistical mechanics methods that hydrogen, if generated, will not stratify at the top of the transport package void space. 9 refs., 1 tab

Packaging material and flexible medical tubing containing thermally exfoliated graphite oxide

Science.gov (United States)

Prud'homme, Robert K. (Inventor); Aksay, Ilhan A. (Inventor)

2011-01-01

A packaging material or flexible medical tubing containing a modified graphite oxide material, which is a thermally exfoliated graphite oxide with a surface area of from about 300 m.sup.2/g to 2600 m.sup.2/g.

Regulatory compliance in the design of packages used to transport radioactive materials

International Nuclear Information System (INIS)

Raske, D.T.

1993-01-01

Shipments of radioactive materials within the regulatory jurisdiction of the US Department of Energy (DOE) must meet the package design requirements contained in Title 10 of the Code of Federal Regulations, Part 71, and DOE Order 5480.3. These regulations do not provide design criteria requirements, but only detail the approval standards, structural performance criteria, and package integrity requirements that must be met during transport. The DOE recommended design criterion for high-level Category I radioactive packagings is Section III, Division 1, of the ASME Boiler and Pressure Vessel Code. However, alternative design criteria may be used if all the design requirements are satisfied. The purpose of this paper is to review alternatives to the Code criteria and discuss their applicability to the design of containment vessels in packages for high-level radioactive materials. Issues such as design qualification by physical testing, the use of scale models, and problems encountered using a non-ASME design approach are addressed

TECHNICAL AND REGULATORY CONSIDERATIONS IN USING FREIGHT CONTAINERS AS INDUSTRIAL PACKAGES

Energy Technology Data Exchange (ETDEWEB)

Opperman, E; Mark Hawk, M; Ron Natali, R

2007-10-16

The United States (US) Department of Energy (DOE), Office of Environmental Management (EM), is actively pursuing activities to reduce the radiological risk and clean up the environmental legacy of the nation's nuclear weapons programs. EM has made significant progress in recent years in the clean-up and closure of sites and is also focusing on longer-term activities necessary for the completion of the clean-up program. The packaging and transportation of contaminated demolition debris and low-level waste (LLW) materials in a safe and cost-effective manner are essential in completing this mission. Toward this end, the US Department of Transportation's (DOT) Final Rule on Hazardous Materials Regulation Final Rule issued January 26, 2004, included a new provision authorizing the use of Freight Containers (e.g., 20 and 40-foot ISO Containers) as Industrial Packages Type 1, 2, or 3 (IP-1, IP-2, and IP-3). This paper will discuss the technical and regulatory considerations in using these newly authorized and large packages for the packaging and transportation of LLW materials.

49 CFR 172.202 - Description of hazardous material on shipping papers.

Science.gov (United States)

2010-10-01

... papers. 172.202 Section 172.202 Transportation Other Regulations Relating to Transportation PIPELINE AND... INFORMATION, TRAINING REQUIREMENTS, AND SECURITY PLANS Shipping Papers § 172.202 Description of hazardous material on shipping papers. (a) The shipping description of a hazardous material on the shipping paper...

Mixed waste chemical compatibility with packaging components

International Nuclear Information System (INIS)

Nigrey, P.J.; Conroy, M.; Blalock, L.B.

1994-01-01

In this paper, a chemical compatibility testing program for packaging of mixed wastes at will be described. We will discuss the choice of four y-radiation doses, four time durations, four temperatures and four waste solutions to simulate the hazardous waste components of mixed wastes for testing materials compatibility of polymers. The selected simulant wastes are (1) an aqueous alkaline mixture of sodium nitrate and sodium nitrite; (2) a chlorinated hydrocarbon mixture; (3) a simulant liquid scintillation fluid; and (4) a mixture of ketones. A selection of 10 polymers with anticipated high resistance to one or more of these types of environments are proposed for testing as potential liner or seal materials. These polymers are butadiene acrylonitrile copolymer, cross-linked polyethylene, epichlorhyarin, ethylene-propylene rubber, fluorocarbon, glass-filled tetrafluoroethylene, high-density poly-ethylene, isobutylene-isoprene copolymer, polypropylene, and styrene-butadiene rubber. We will describe the elements of the testing plan along with a metric for establishing time resistance of the packaging materials to radiation and chemicals

Screening tests for hazard classification of complex waste materials – Selection of methods

International Nuclear Information System (INIS)

Weltens, R.; Vanermen, G.; Tirez, K.; Robbens, J.; Deprez, K.; Michiels, L.

2012-01-01

In this study we describe the development of an alternative methodology for hazard characterization of waste materials. Such an alternative methodology for hazard assessment of complex waste materials is urgently needed, because the lack of a validated instrument leads to arbitrary hazard classification of such complex waste materials. False classification can lead to human and environmental health risks and also has important financial consequences for the waste owner. The Hazardous Waste Directive (HWD) describes the methodology for hazard classification of waste materials. For mirror entries the HWD classification is based upon the hazardous properties (H1–15) of the waste which can be assessed from the hazardous properties of individual identified waste compounds or – if not all compounds are identified – from test results of hazard assessment tests performed on the waste material itself. For the latter the HWD recommends toxicity tests that were initially designed for risk assessment of chemicals in consumer products (pharmaceuticals, cosmetics, biocides, food, etc.). These tests (often using mammals) are not designed nor suitable for the hazard characterization of waste materials. With the present study we want to contribute to the development of an alternative and transparent test strategy for hazard assessment of complex wastes that is in line with the HWD principles for waste classification. It is necessary to cope with this important shortcoming in hazardous waste classification and to demonstrate that alternative methods are available that can be used for hazard assessment of waste materials. Next, by describing the pros and cons of the available methods, and by identifying the needs for additional or further development of test methods, we hope to stimulate research efforts and development in this direction. In this paper we describe promising techniques and argument on the test selection for the pilot study that we have performed on different

Assessing microbiologically induced corrosion of waste package materials in the Yucca Mountain repository

Energy Technology Data Exchange (ETDEWEB)

Horn, J. M., LLNL

1998-01-01

The contribution of bacterial activities to corrosion of nuclear waste package materials must be determined to predict the adequacy of containment for a potential nuclear waste repository at Yucca Mountain (YM), NV. The program to evaluate potential microbially induced corrosion (MIC) of candidate waste container materials includes characterization of bacteria in the post-construction YM environment, determination of their required growth conditions and growth rates, quantitative assessment of the biochemical contribution to metal corrosion, and evaluation of overall MIC rates on candidate waste package materials.

Drop Test Using Finite Element Method for Transport Package of Radioactive Material

International Nuclear Information System (INIS)

Xu Xiaoxiao; Zhao Bing; Zhang Jiangang; Li Gouqiang; Wang Xuexin; Tang Rongyao

2010-01-01

Mechanical test for transport package of radioactive material is one of the important tests for demonstrating package structure design. Drop test of package is a kind of destructive test. It is a common method of adopting the pre-analysis to determine drop orientation.Mechanical test of a sealed source package was calculated with finite element method (FEM) software. Based on the analysis of the calculation results, some values were obtained such as the stress, strain, acceleration and the drop orientation which causes the most severe damage, and the calculation results were compared with the results of test. (authors)

49 CFR 173.21 - Forbidden materials and packages.

Science.gov (United States)

2010-10-01

... stabilized or inhibited in a manner to preclude such evolution. The SADT may be determined by any of the test... generate a dangerous evolution of heat, unless packaged in a manner which precludes such an occurrence. (d... container, or overpack with another material, the mixing of which is likely to cause a dangerous evolution...

Development of a impact limiter for radioactive material transport packages - characterization of the polymeric material used

International Nuclear Information System (INIS)

Mourao, Rogerio Pimenta; Mattar Neto, Miguel

2000-01-01

Impact limiters are sacrificial components widely used to protect radioactive waste packages against damages arising from falls, fires and collisions with protruding objects. Several materials have been used as impact limiter filling: wood, aluminum honeycomb, and metallic or polymeric foams. Besides, hollow structures are also used as shock absorbers, either as a single shell or as a tube array. One of the most popular materials among package designers is rigid polyurethane foam, owing to its toughness, workability, low specific weight, low costs and commercial availability. In Brazil, a foam developed using the polymer extracted from the castor oil plant (Ricinus communis) is being studied as a potential impact limiter filling. For a better performance of this material, it is necessary to minimize the impact limiter dimensions without compromising the package safety. For this, a detailed knowledge of the foam physical and mechanical properties is essential. A relatively vast amount of data about regular polymeric foams can be found in the literature and in foreign manufacturers brochures, but no data has been published about the properties of the castor oil foam. This paper presents data gathered in an ongoing research program aiming at the development of a Type-B packaging. Foam samples were submitted to uniaxial static compression tests and to hydrostatic tests. The results obtained reveal that the castor oil foam has a mechanical behavior similar to that of regular foams, with good property reproducibility and homogeneity. (author)

Initial specifications for nuclear waste package external dimensions and materials

International Nuclear Information System (INIS)

Gregg, D.W.; O'Neal, W.C.

1983-09-01

Initial specifications of external dimensions and materials for waste package conceptual designs are given for Defense High Level Waste (DHLW), Commercial High Level Waste (CHLW) and Spent Fuel (SF). The designs have been developed for use in a high-level waste repository sited in a tuff media in the unsaturated zone. Drawings for reference and alternative package conceptual designs are presented for each waste form for both vertical and horizontal emplacement configurations. Four metal alloys: 304L SS, 321 SS, 316L SS and Incoloy 825 are considered for the canister or overpack; 1020 carbon steel was selected for horizontal borehole liners, and a preliminary packing material selection is either compressed tuff or compressed tuff containing iron bearing smectite clay as a binder

Degradation Behavior and Accelerated Weathering of Composite Boards Produced from Waste Tetra Pak® Packaging Materials

Science.gov (United States)

Nural Yilgor; Coskun Kose; Evren Terzi; Aysel Kanturk Figen; Rebecca Ibach; S. Nami Kartal; Sabriye Piskin

2014-01-01

Manufacturing panels from Tetra Pak® (TP) packaging material might be an alternative to conventional wood-based panels. This study evaluated some chemical and physical properties as well as biological, weathering, and fire performance of panels with and without zinc borate (ZnB) by using shredded TP packaging cartons. Such packaging material, a worldwide well-known...

DOE progress in assessing the long term performance of waste package materials

International Nuclear Information System (INIS)

Berusch, A.; Gause, E.

1987-01-01

Under the Nuclear Waste Policy Act of 1982 (NWPA)[1], the US Dept. of Energy (DOE) is conducting activities to select and characterize candidate sites suitable for the construction and operation of a geologic repository for the disposal of high-level nuclear wastes. DOE is funding three first repository projects: Basalt Waste Isolation Project, BWIP; Nevada Nuclear Waste Isolation Project, NNWSI; and Salt Repository Project Office, SRPO. It is essential in the licensing process that DOE demonstrate to the NRC that the long-term performance of the materials and design will be in compliance with the requirements of 10 CFR 60.113 on substantially complete containment within the waste packages for 300 to 1000 years and a controlled release rate from the engineered barrier system (EBS) for 10,000 years of 1 part in 10 5 per year for radionuclides present in defined quantities 100 years after permanent closure. Obviously, the time spans involved make it impractical to base the assessment of the long term performance of waste package materials on real time, prototypical testing. The assessment of performance will be implemented by the use of models that are supported by real time field and laboratory tests, monitoring, and natural analog studies. Each of the repository projects is developing a plan for demonstrating long-term waste package material performance depending on the particular materials and the package-perturbed, time-dependent environment under which the materials must function. An overview of progress in each of these activities for each of the projects is provided in the following

500 C Electronic Packaging and Dielectric Materials for High Temperature Applications

Science.gov (United States)

Chen, Liang-yu; Neudeck, Philip G.; Spry, David J.; Beheim, Glenn M.; Hunter, Gary W.

2016-01-01

High-temperature environment operable sensors and electronics are required for exploring the inner solar planets and distributed control of next generation aeronautical engines. Various silicon carbide (SiC) high temperature sensors, actuators, and electronics have been demonstrated at and above 500C. A compatible packaging system is essential for long-term testing and application of high temperature electronics and sensors. High temperature passive components are also necessary for high temperature electronic systems. This talk will discuss ceramic packaging systems developed for high temperature electronics, and related testing results of SiC circuits at 500C and silicon-on-insulator (SOI) integrated circuits at temperatures beyond commercial limit facilitated by these high temperature packaging technologies. Dielectric materials for high temperature multilayers capacitors will also be discussed. High-temperature environment operable sensors and electronics are required for probing the inner solar planets and distributed control of next generation aeronautical engines. Various silicon carbide (SiC) high temperature sensors, actuators, and electronics have been demonstrated at and above 500C. A compatible packaging system is essential for long-term testing and eventual applications of high temperature electronics and sensors. High temperature passive components are also necessary for high temperature electronic systems. This talk will discuss ceramic packaging systems developed for high electronics and related testing results of SiC circuits at 500C and silicon-on-insulator (SOI) integrated circuits at temperatures beyond commercial limit facilitated by high temperature packaging technologies. Dielectric materials for high temperature multilayers capacitors will also be discussed.

21 CFR 509.15 - Use of polychlorinated biphenyls (PCB's) in establishments manufacturing food-packaging materials.

Science.gov (United States)

2010-04-01

... establishments manufacturing food-packaging materials. 509.15 Section 509.15 Food and Drugs FOOD AND DRUG... polychlorinated biphenyls (PCB's) in establishments manufacturing food-packaging materials. (a) Polychlorinated...). These accidents in turn caused the contamination of food products intended for human consumption (meat...

21 CFR 109.15 - Use of polychlorinated biphenyls (PCB's) in establishments manufacturing food-packaging materials.

Science.gov (United States)

2010-04-01

... establishments manufacturing food-packaging materials. 109.15 Section 109.15 Food and Drugs FOOD AND DRUG... polychlorinated biphenyls (PCB's) in establishments manufacturing food-packaging materials. (a) Polychlorinated...). These accidents in turn caused the contamination of food products intended for human consumption (meat...

Packaging Evaluation Approach to Improve Cosmetic Product Safety

Directory of Open Access Journals (Sweden)

Benedetta Briasco

2016-09-01

Full Text Available In the Regulation 1223/2009, evaluation of packaging has become mandatory to assure cosmetic product safety. In fact, the safety assessment of a cosmetic product can be successfully carried out only if the hazard deriving from the use of the designed packaging for the specific product is correctly evaluated. Despite the law requirement, there is too little information about the chemical-physical characteristics of finished packaging and the possible interactions between formulation and packaging; furthermore, different from food packaging, the cosmetic packaging is not regulated and, to date, appropriate guidelines are still missing. The aim of this work was to propose a practical approach to investigate commercial polymeric containers used in cosmetic field, especially through mechanical properties’ evaluation, from a safety point of view. First of all, it is essential to obtain complete information about raw materials. Subsequently, using an appropriate full factorial experimental design, it is possible to investigate the variables, like polymeric density, treatment, or type of formulation involved in changes to packaging properties or in formulation-packaging interaction. The variation of these properties can greatly affect cosmetic safety. In particular, mechanical properties can be used as an indicator of pack performances and safety. As an example, containers made of two types of polyethylene with different density, low-density polyethylene (LDPE and high-density polyethylene (HDPE, are investigated. Regarding the substances potentially extractable from the packaging, in this work the headspace solid-phase microextraction method (HSSPME was used because this technique was reported in the literature as suitable to detect extractables from the polymeric material here employed.

49 CFR 173.7 - Government operations and materials.

Science.gov (United States)

2010-10-01

...) Determining the airworthiness and directing maintenance of the aircraft; and (3) Dispatching the aircraft... REQUIREMENTS FOR SHIPMENTS AND PACKAGINGS General § 173.7 Government operations and materials. (a) Hazardous... regulations in this subchapter or in packagings of equal or greater strength and efficiency as certified by...

Waste Package and Material Testing for the Proposed Yucca Mountain High Level Waste Repository

International Nuclear Information System (INIS)

Doering, Thomas; Pasupathi, V.

2002-01-01

Over the repository lifetime, the waste package containment barriers will perform various functions that will change with time. During the operational period, the barriers will function as vessels for handling, emplacement, and waste retrieval (if necessary). During the years following repository closure, the containment barriers will be relied upon to provide substantially complete containment, through 10,000 years and beyond. Following the substantially complete containment phase, the barriers and the waste package internal structures help minimize release of radionuclides by aqueous- and gaseous-phase transport. These requirements have lead to a defense-in-depth design philosophy. A multi-barrier design will result in a lower breach rate distributed over a longer period of time, thereby ensuring the regulatory requirements are met. The design of the Engineered Barrier System (EBS) has evolved. The initial waste package design was a thin walled package, 3/8 inch of stainless steel 304, that had very limited capacity, (3 PWR and 4 BWR assemblies) and performance characteristics, 300 to 1,000 years. This design required over 35,000 waste packages compared to today's design of just over 10,000 waste packages. The waste package designs are now based on a defense-in-depth/multi-barrier philosophy and have a capacity similar to the standard storage and rail transported spent nuclear fuel casks. Concurrent with the development of the design of the waste packages, a comprehensive waste package materials testing program has been undertaken to support the selection of containment barrier materials and to develop predictive models for the long-term behavior of these materials under expected repository conditions. The testing program includes both long-term and short-term tests and the results from these tests combination with the data published in the open literature are being used to develop models for predicting performance of the waste packages

Fire testing for package approval

International Nuclear Information System (INIS)

Burgess, M.H.; Fry, C.J.

1990-01-01

The IAEA Transport Regulations require packaging systems for radioactive material to survive transport accidents without a significant increase in hazard to members of the public. Tests used to demonstrate this include a fire or 'thermal' test which may be a practical demonstration or based on calculations. Work at Winfrith, involving the development of computer models and pool fire techniques, has given an improved understanding of physical processes. This has been used to improve computer models and pool fire techniques. The paper covers the regulatory requirements for fire testing, the basic physics of fires, practical tests, computer modelling and their applications to package design. We have confidence in our ability to predict temperatures and other conditions in accident situations and can illustrate the important features of fires with experimental evidence. (author)

Preliminary selection criteria for the Yucca Mountain Project waste package container material

International Nuclear Information System (INIS)

Halsey, W.G.

1991-01-01

The Department of Energy's Yucca Mountain Project (YMP) is evaluating a site at Yucca Mountain in Nevada for construction of a geologic repository for the storage of high-level nuclear waste. Lawrence Livermore National Laboratory's (LLNL) Nuclear Waste Management Project (NWMP) has the responsibility for design, testing, and performance analysis of the waste packages. The design is performed in an iterative manner in three sequential phases (conceptual design, advanced conceptual design, and license application design). An important input to the start of the advanced conceptual design is the selection of the material for the waste containers. The container material is referred to as the 'metal barrier' portion of the waste package, and is the responsibility of the Metal Barrier Selection and Testing task at LLNL. The selection will consist of several steps. First, preliminary, material-independent selection criteria will be established based on the performance goals for the container. Second, a variety of engineering materials will be evaluated against these criteria in a screening process to identify candidate materials. Third, information will be obtained on the performance of the candidate materials, and final selection criteria and quantitative weighting factors will be established based on the waste package design requirements. Finally, the candidate materials will be ranked against these criteria to determine whether they meet the mandated performance requirements, and to provide a comparative score to choose the material for advanced conceptual design activities. This document sets forth the preliminary container material selection criteria to be used in screening candidate materials. 5 refs

Effect of packaging materials on the quality of irradiated ground spices

International Nuclear Information System (INIS)

Saputra, T.S.; Maha, Munsiah; Purwanto, Z.I.

1985-01-01

These experiments were carried out to determine the suitable packaging materials to be used for irradiated ground spices produced in Indonesia. The materials used were white pepper (Piper album), black pepper (Piper nigrum) nutmeg (Myristica fragrans), turmeric (Curcuma domestica), and ginger (Zangiber officinale R.) packaged in transparent polypropylene bottles, in pouches made of cellophane-aluminum foil and lithopaper-polyethylene laminates. The samples were irradiated at 5 kGy, stored at ambient conditions, and then examined every 3 months from 0 up to 9 months of storage. The parameters observed were total bacterial counts, total moulds and yeast counts, water activity (Aw), moisture content, and organoleptic scores of the samples. Piperine content of white pepper and black pepper, colour of turmeric extract, and rancidity of ginger were also determined. The results showed that the packaging materials used had no significant effect on bacterial load of the samples. Prolonged storage, however, could reduce the microbial load of the ground spices. Irradiation at 5 kGy could effectively increase the hygienic condition as well as storage life of the ground spices under investigation without affecting their organoleptic properties. (author). 8 refs

Safety evaluation for packaging for 1720-DR sodium-filled tank

International Nuclear Information System (INIS)

Mercado, M.S.

1996-01-01

Preparations are under way to sell the sodium stored in the 1720-DR tank in the 1720-DR building. This will require that the tank, as well as the 1720-DR facility, be moved to the 300 Area, so that the sodium may be melted and transferred into a railroad tanker car. Because the sodium is a hazardous material and is being shipped in a nonspecification packaging, a safety evaluation for packaging (SEP) is required. This SEP approves the sodium-filled tank for a single shipment from the 105-DR area to the 300 Area

Rapid discrimination of plastic packaging materials using MIR spectroscopy coupled with independent components analysis (ICA)

International Nuclear Information System (INIS)

Kassouf, Amine; Maalouly, Jacqueline; Rutledge, Douglas N.; Chebib, Hanna; Ducruet, Violette

2014-01-01

Highlights: • An innovative technique, MIR-ICA, was applied to plastic packaging separation. • This study was carried out on PE, PP, PS, PET and PLA plastic packaging materials. • ICA was applied to discriminate plastics and 100% separation rates were obtained. • Analyses performed on two spectrometers proved the reproducibility of the method. • MIR-ICA is a simple and fast technique allowing plastic identification/classification. - Abstract: Plastic packaging wastes increased considerably in recent decades, raising a major and serious public concern on political, economical and environmental levels. Dealing with this kind of problems is generally done by landfilling and energy recovery. However, these two methods are becoming more and more expensive, hazardous to the public health and the environment. Therefore, recycling is gaining worldwide consideration as a solution to decrease the growing volume of plastic packaging wastes and simultaneously reduce the consumption of oil required to produce virgin resin. Nevertheless, a major shortage is encountered in recycling which is related to the sorting of plastic wastes. In this paper, a feasibility study was performed in order to test the potential of an innovative approach combining mid infrared (MIR) spectroscopy with independent components analysis (ICA), as a simple and fast approach which could achieve high separation rates. This approach (MIR-ICA) gave 100% discrimination rates in the separation of all studied plastics: polyethylene terephthalate (PET), polyethylene (PE), polypropylene (PP), polystyrene (PS) and polylactide (PLA). In addition, some more specific discriminations were obtained separating plastic materials belonging to the same polymer family e.g. high density polyethylene (HDPE) from low density polyethylene (LDPE). High discrimination rates were obtained despite the heterogeneity among samples especially differences in colors, thicknesses and surface textures. The reproducibility of

Rapid discrimination of plastic packaging materials using MIR spectroscopy coupled with independent components analysis (ICA)

Energy Technology Data Exchange (ETDEWEB)

Kassouf, Amine, E-mail: amine.kassouf@agroparistech.fr [ER004 “Lebanese Food Packaging”, Faculty of Sciences II, Lebanese University, 90656 Jdeideth El Matn, Fanar (Lebanon); INRA, UMR1145 Ingénierie Procédés Aliments, 1 Avenue des Olympiades, 91300 Massy (France); AgroParisTech, UMR1145 Ingénierie Procédés Aliments, 16 rue Claude Bernard, 75005 Paris (France); Maalouly, Jacqueline, E-mail: j_maalouly@hotmail.com [ER004 “Lebanese Food Packaging”, Faculty of Sciences II, Lebanese University, 90656 Jdeideth El Matn, Fanar (Lebanon); Rutledge, Douglas N., E-mail: douglas.rutledge@agroparistech.fr [INRA, UMR1145 Ingénierie Procédés Aliments, 1 Avenue des Olympiades, 91300 Massy (France); AgroParisTech, UMR1145 Ingénierie Procédés Aliments, 16 rue Claude Bernard, 75005 Paris (France); Chebib, Hanna, E-mail: hchebib@hotmail.com [ER004 “Lebanese Food Packaging”, Faculty of Sciences II, Lebanese University, 90656 Jdeideth El Matn, Fanar (Lebanon); Ducruet, Violette, E-mail: violette.ducruet@agroparistech.fr [INRA, UMR1145 Ingénierie Procédés Aliments, 1 Avenue des Olympiades, 91300 Massy (France); AgroParisTech, UMR1145 Ingénierie Procédés Aliments, 16 rue Claude Bernard, 75005 Paris (France)

2014-11-15

Highlights: • An innovative technique, MIR-ICA, was applied to plastic packaging separation. • This study was carried out on PE, PP, PS, PET and PLA plastic packaging materials. • ICA was applied to discriminate plastics and 100% separation rates were obtained. • Analyses performed on two spectrometers proved the reproducibility of the method. • MIR-ICA is a simple and fast technique allowing plastic identification/classification. - Abstract: Plastic packaging wastes increased considerably in recent decades, raising a major and serious public concern on political, economical and environmental levels. Dealing with this kind of problems is generally done by landfilling and energy recovery. However, these two methods are becoming more and more expensive, hazardous to the public health and the environment. Therefore, recycling is gaining worldwide consideration as a solution to decrease the growing volume of plastic packaging wastes and simultaneously reduce the consumption of oil required to produce virgin resin. Nevertheless, a major shortage is encountered in recycling which is related to the sorting of plastic wastes. In this paper, a feasibility study was performed in order to test the potential of an innovative approach combining mid infrared (MIR) spectroscopy with independent components analysis (ICA), as a simple and fast approach which could achieve high separation rates. This approach (MIR-ICA) gave 100% discrimination rates in the separation of all studied plastics: polyethylene terephthalate (PET), polyethylene (PE), polypropylene (PP), polystyrene (PS) and polylactide (PLA). In addition, some more specific discriminations were obtained separating plastic materials belonging to the same polymer family e.g. high density polyethylene (HDPE) from low density polyethylene (LDPE). High discrimination rates were obtained despite the heterogeneity among samples especially differences in colors, thicknesses and surface textures. The reproducibility of

Safety evaluation for packaging (onsite) for concrete-shielded RHTRU waste drum for the 327 postirradiation testing laboratory

Energy Technology Data Exchange (ETDEWEB)

Adkins, H.E.

1996-10-29

This safety evaluation for packaging authorizes onsite transport of Type B quantities of radioactive material in the Concrete- Shielded Remote-Handled Transuranic Waste (RH TRU) Drum per WHC-CM-2-14, Hazardous Material Packaging and Shipping. The drum will be used for transport of 327 Building legacy waste from the 300 Area to the Transuranic Waste Storage and Assay Facility in the 200 West Area and on to a Solid Waste Storage Facility, also in the 200 Area.

WannierTools: An open-source software package for novel topological materials

Science.gov (United States)

Wu, QuanSheng; Zhang, ShengNan; Song, Hai-Feng; Troyer, Matthias; Soluyanov, Alexey A.

2018-03-01

We present an open-source software package WannierTools, a tool for investigation of novel topological materials. This code works in the tight-binding framework, which can be generated by another software package Wannier90 (Mostofi et al., 2008). It can help to classify the topological phase of a given material by calculating the Wilson loop, and can get the surface state spectrum, which is detected by angle resolved photoemission (ARPES) and in scanning tunneling microscopy (STM) experiments. It also identifies positions of Weyl/Dirac points and nodal line structures, calculates the Berry phase around a closed momentum loop and Berry curvature in a part of the Brillouin zone (BZ).

Nupack, the new ASME code for radioactive material transportation packaging containments

International Nuclear Information System (INIS)

Turula, P.

1998-01-01

The American Society of Mechanical Engineers (ASME) has added a new division to the nuclear construction section of its Boiler and Pressure Vessel Code (B and PVC). This Division, commonly referred to as Nupack, has been written to provide a consistent set of technical requirements for containment vessels of transportation packagings for high-level radioactive materials. This paper provides an introduction to Nupack, discusses some of its technical provisions, and describes how it can be used for the design and construction of packaging components. Nupack's general provisions and design requirements are emphasized, while treatment of materials, fabrication and inspection is left for another paper

Labelling and marking of packages, for the transport of radioactive materials

International Nuclear Information System (INIS)

1977-09-01

It is the responsibility of the consignor, even when he is also the carrier, to ensure that every package of dangerous materials is correctly labelled and marked before dispatch. The purpose of this Code of Practice is to amplify the provisions, embodied in various regulations and codes for the safe transport of radioactive materials, relating to the labelling of packages of such materials, and to provide detailed instructions that will ensure fulfilment of the relevant requirements. The model regulations published by the International Atomic Energy Agency are referred to in this Code as 'the IAEA regulations'. It has been assumed that those using the Code will be familiar with the international and national transport regulations, which are based on the IAEA regulations and that they will have experience of transport procedures. (author)

Hazardous materials management and compliance training

International Nuclear Information System (INIS)

Dalton, T.F.

1991-01-01

OSHA training for hazardous waste site workers is required by the Superfund Amendments and Reauthorization Act of 1986 (SARA). In December 1986, a series of regulations was promulgated by OSHA on an interim basis calling for the training of workers engaged in hazardous waste operations. Subsequent to these interim regulations, final rules were promulgated and these final rules on hazardous waste operations and emergency response became effective on March 6, 1990. OSHA has conducted hearings on the accreditation of training programs. OSHA would like to follow the accreditation process under the AHERA regulations for asbestos, in which the model plan for accreditation of asbestos abatement training was included in Section 206 of Title 11 of the Toxic Substance Control Act (TSCA). OSHA proposed on January 26, 1990, to perform the accreditation of training programs for hazardous waste operations and that proposal suggested that they follow the model plan similar to the one used for AHERA. They did not propose to accredited training programs for workers engaged in emergency response. These new regulations pose a significant problem to the various contractors and emergency responders who deal with hazardous materials spill response, cleanup and site remediation since these programs have expanded so quickly that many people are not familiar with what particular segment of the training they are required to have and whether or not programs that have yet to be accredited are satisfactory for this type of training. Title III of SARA stipulates a training program for first responders which includes local emergency response organizations such as firemen and policemen. The purpose of this paper is to discuss the needs of workers at hazardous waste site remediation projects and workers who are dealing with hazardous substances, spill response and cleanup

Hazardous materials transportation and emergency response programs

International Nuclear Information System (INIS)

Joy, D.S.; Fore, C.S.

1983-01-01

This presentation consists of the following visual aids; (1) detailed routing capabilities of truck, rail, barge; (2) legislative data base for hazardous materials; and (3) emergency response of accident site Eddyville, Kentucky (airports in vicinity of Eddyville, KY)

Directory of national competent authorities' approval certificates for package design, special form material and shipment of radioactive material. 1991 edition

International Nuclear Information System (INIS)

1991-08-01

The format of this report is a result of recommendations made by the Standing Advisory Group on the Safe Transport of Radioactive Material (SAGSTRAM) at its 6th meeting in November 1987. The database was at that time maintained on the main frame and it was felt that adapting it for use on a personal computer would allow more flexibility in data processing and reporting. This document supersedes TECDOC-552 ''Directory of National Competent Authorities' Approval Certificates for Package Design and Shipment of Radioactive Material 1990 Edition''. Since publication of TECDOC-552, some modifications affecting the structure of the database and reporting formats were undertaken. These are fully described in ''Working Material: The PACKTRAM Database National Competent Authority Package Approval Certificates, User Guide Rev. 1'', which was released in early 1991. The present report is contained in five tables. In each of these, information is presented in alphabetical order based on the certificate number. This is composed of the issuing Member State's VRI code, followed by a slash, then a three- or four-digit number, another slash and finally a code identifying the type of package involved. ''-85'' is appended to those certificates that were approved on the basis of the 1985 Edition of Safety Series No. 6. Tables 1 to 4 present administrative data including issue and expire, dates, package identification, package serial numbers, modes for which the package/shipment is approved and the edition of Safety Series No. 6 on which the approval has been based. The technical information on package mass, authorized contents, and detailed and general description of the package are contained in Table. 5

An issue paper on the use of hydrogen getters in transportation packaging

International Nuclear Information System (INIS)

NIGREY, PAUL J.

2000-01-01

The accumulation of hydrogen is usually an undesirable occurrence because buildup in sealed systems pose explosion hazards under certain conditions. Hydrogen scavengers, or getters, can avert these problems by removing hydrogen from such environments. This paper provides a review of a number of reversible and irreversible getters that potentially could be used to reduce the buildup of hydrogen gas in containers for the transport of radioactive materials. In addition to describing getters that have already been used for such purposes, novel getters that might find application in future transport packages are also discussed. This paper also discusses getter material poisoning, the use of getters in packaging, the effects of radiation on getters, the compatibility of getters with packaging, design considerations, regulatory precedents, and makes general recommendations for the materials that have the greatest applicability in transport packaging. At this time, the Pacific Northwest National Laboratory composite getter, DEB [1,4-(phenylethylene)benzene] or similar polymer-based getters, and a manganese dioxide-based getter appear to be attractive candidates that should be further evaluated. These getters potentially can help prevent pressurization from radiolytic reactions in transportation packaging

Effect of packaging materials on shelf life and quality of banana cultivars (Musa spp.).

Science.gov (United States)

Hailu, M; Seyoum Workneh, T; Belew, D

2014-11-01

This study was carried out to evaluate the effect of packaging materials on the shelf life of three banana cultivars. Four packaging materials, namely, perforated low density polyethylene bag, perforated high density polyethylene bag, dried banana leaf, teff straw and no packaging materials (control) were used with three banana cultivars, locally known as, Poyo, Giant Cavendish and Williams I. The experiment was carried out in Randomized Complete Block Design in a factorial combination with three replications. Physical parameters including weight loss, peel colour, peel thickness, pulp thickness, pulp to peel ratio, pulp firmness, pulp dry matter, decay, loss percent of marketability were assessed every 3 days. Banana remained marketable for 36 days in the high density polyethylene and low density polyethylene bags, and for 18 days in banana leaf and teff straw packaging treatments. Unpackaged fruits remained marketable for 15 days only. Fruits that were not packaged lost their weight by 24.0 % whereas fruits packaged in banana leaf and teff straw became unmarketable with final weight loss of 19.8 % and 20.9 %, respectively. Packaged fruits remained well until 36th days of storage with final weight loss of only 8.2 % and 9.20 %, respectively. Starting from green mature stage, the colour of the banana peel changed to yellow and this process was found to be fast for unpackaged fruits. Packaging maintained the peel and the pulp thickness, firmness, dry matter and pulp to peel ratio was kept lower. Decay loss for unpackaged banana fruits was16 % at the end of date 15, whereas the decay loss of fruits packaged using high density and low density polyethylene bags were 43.0 % and 41.2 %, respectively at the end of the 36th day of the experiment. It can, thus, be concluded that packaging of banana fruits in high density and low density polyethylene bags resulted in longer shelf life and improved quality of the produce followed by packaging in dried banana leaf

Automated accountability of hazardous materials at AlliedSignal Inc., Kansas City Division

International Nuclear Information System (INIS)

Depew, P.L.

1993-12-01

The Department of Energy's (DOE) Kansas City Plant (KCP), currently operated by AlliedSignal Inc. has developed a comprehensive Hazardous Material Information System (HMIS). The purpose of this system is to provide a practical and automated method to collect, analyze and distribute hazardous material information to DOE, KCP associates, and regulatory agencies. The drivers of the HMIS are compliance with OSHA Hazard Communications, SARA reporting, pollution prevention, waste minimization, control and tracking of hazards, and emergency response. This report provides a discussion of this system

Chemical hazards from decontamination solutions in low level waste

International Nuclear Information System (INIS)

Leventhal, L.; Miller, A.; Turney, J.; Naughton, M.; IMPELL Corp., Walnut Creek, CA; Electric Power Research Inst., Palo Alto, CA)

1985-01-01

Recent regulations are focussing more attention on the non-radioactive matrix materials associated with radioactive wastes. Decontamination of operating facilities is becoming a more significant source of low-level waste. This study reviewed the chemical and biological hazards of over 50 decontamination processes. Seventeen of the most prominent hard and soft decontamination processes were examined in detail. The chemical and biological hazards of these seventeen are presented in this paper. These hazards influence the choice of radwaste processing and packaging operations and methods. Federal, state and local regulations further impact on operations and waste disposal. Hazards to personnel, in plant and off-site, resulting from the decontamination cycle are evaluated. 1 fig., 5 tabs

PATRAM '83: 7th international symposium on packaging and transportation of radioactive materials

International Nuclear Information System (INIS)

1983-01-01

Papers were presented at the following sessions: international regulations; materials, fracture toughness of ferritic steels; risk analysis techniques; storage in packagings; packaging design considerations; monolithic cast iron casks; risk analysis; facility/transportation system interface; research and development programs; UF 6 packagings; national regulations; transportation operations and traffic; containment, seals, and leakage; radiation risk experience; emergency response; structural modeling and testing; transportation system planning; institutional issues and public response; packaging systems; thermal analysis and testing; systems analysis; structural analyses; quality assurance; packaging and transportation systems; physical protection; criticality and shielding; transportation operations and experience; standards; shock absorber technology; and information and training for regulatory compliance. Individual summaries are title listed

Development on inelastic analysis acceptance criteria for radioactive material transportation packages

International Nuclear Information System (INIS)

Ammerman, D.J.; Ludwigsen, J.S.

1995-01-01

The response of radioactive material transportation packages to mechanical accident loadings can be more accurately characterized by non-linear dynamic analysis than by the ''Equivalent dynamic'' static elastic analysis typically used in the design of these packages. This more accurate characterization of the response can lead to improved package safety and design efficiency. For non-linear dynamic analysis to become the preferred method of package design analysis, an acceptance criterion must be established that achieves an equivalent level of safety as the currently used criterion defined in NRC Regulatory Guide 7.6 (NRC 1978). Sandia National Laboratories has been conducting a study of possible acceptance criteria to meet this requirement. In this paper non-linear dynamic analysis acceptance criteria based on stress, strain, and strain-energy-density will be discussed. An example package design will be compared for each of the design criteria, including the approach of NRC Regulatory Guide 7.6

The design, construction and testing of packaging[Radioactive materials

Energy Technology Data Exchange (ETDEWEB)

NONE

1976-07-01

Essentially uniform regulations, based on the IAEA Regulations for the Safe Transport of Radioactive Materials, have been adopted on a world-wide basis with the aim of ensuring safety in the transport of radioactive and fissile substances by road, rail, sea and air. The application of these regulations over a period of almost 20 years has resulted in practically complete safety in the sense that there has been no evidence of death or injury that could be attributed to the special properties of the material even when consignments were involved in serious accidents. In the regulations, reliance is placed, to the greatest extent possible, on the packaging to provide adequate shielding and containment of the contents under both normal transport and accident conditions. The Agency organized an international seminar in 1971 to consider the performance tests that have to be applied to packaging to demonstrate compliance with the regulatory requirements. The general conclusion was that the testing programme specified in the regulations was adequate for the near future, but that further consideration should be given to assessing the risks presented by the increasing volume of transport. The second international seminar, which is the subject of this report, dealt with all aspects of the design, construction and testing of packaging for the transport both of relatively small quantities of radioactive substances, which are being used to an ever increasing extent for medical and research purposes, and of the much larger quantities arising in various stages of the nuclear fuel cycle. The programme covered the general requirements for packaging; risk assessment for the transport of various radioactive and fissile substances, including plutonium; specific features of the design and construction of packaging; quality assurance; damage simulation tests, including calculational methods and scale-model testing; tests for the retention of shielding and containment after damage; and the

Potential of polymeric materials for packaging; L'impiego dei materiali polimerici nell'imballaggio

Energy Technology Data Exchange (ETDEWEB)

Lanchi, M [ENEA, Divisione Nuovi Materiali, Centro Ricerche Casaccia, Rome (Italy)

2001-07-01

Packaging preserves different kind of materials, from raw materials, and it plays an important role in the presentation of the products to the market, too. That's why packaging should be in charge of responding to marketing requirements by means of a proper design, effective colour choice and material, etc. Nowadays packaging is becoming more and more important in different fields. In Italy, it is a rapid growth of the packaging market and the companies involved are very competitive and efficient, in particular in some market segments. Concerning the application fields it can be asserted that packaging is mostly exploited in the food market which represents the 65% of the whole packaging market. Nearly all types of packaging use plastics as a part of their construction: lightness, chemical inertness, corrosion resistance, molding attitude, the good transparency to light, sound and mechanical insulation, etc. Focusing the attention to the horticultural market, growth in South of Italy in particular, examples of promising research fields to date are: developing of good barrier performance films; developing of suitable modified atmosphere packaging; developing of active plastic films, such as antimicrobic films or antioxidant films. The large amount of plastic films used for packaging create a large waste problem. This can be reduced by: optimising packaging design, avoiding the excessive use of plastics; improvising strength, moisture and heat stability per unit weight in order to reduce plastic waste volume; developing blend of plastics and bio-based polymer in order to increase the biodegradability of packaging after use. [Italian] L'imballaggio e' un prodotto adibito a contenere e a proteggere determinate merci, dalle materie prime ai prodotti finiti, a consentire la loro manipolazione e ad assicurare la loro presentazione. E' una realta' importante del mondo della produzione, delle strutture distributive e della vita quotidiana. Nell'ambito della produzione, l

Directory of certificates of compliance for radioactive materials packages, Certificates of compliance

International Nuclear Information System (INIS)

1990-10-01

This directory contains a Report of the US Nuclear Regulatory Commissions's Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Materials Packages effective October 1, 1990. The purpose of this directory is to make available a convenient source of information on packaging which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of easy package design and approved QA programs prior to the publication date of the directory

Directory of Certificates of Compliance for Radioactive Materials Packages: Certificates of Compliance

International Nuclear Information System (INIS)

1988-12-01

This directory contains a Report of the US Nuclear Regulatory Commission's Approved Packages (Volume 1), all Certificates of Compliance (Volume 2), and a Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective October 1, 1988. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the front of Volume 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Dynamic analysis to establish normal shock and vibration of radioactive material shipping packages

International Nuclear Information System (INIS)

Fields, S.R.

1980-01-01

A computer model, CARDS (Cask-Railcar Dynamic Simulator) was developed to provide input data for a broad range of radioactive material package-tiedown structural assessments. CARDS simulates the dynamic behavior of shipping packages and their transporters during normal transport conditions. The model will be used to identify parameters which significantly affect the normal shock and vibration environments which, in turn, provide the basis for determining the forces transmitted to the packages

Evaluation of Hazardous Material Management Safety in the Chemical Laboratory in BATAN

International Nuclear Information System (INIS)

Nur-Rahmah-Hidayati

2005-01-01

The management safety of the hazardous material (B3) in the chemical laboratory of BATAN was evaluated. The evaluation is necessary to be done because B3 is often used together with radioactive materials in the laboratory, but the attention to the safety aspect of B3 is not paid sufficiently in spite of its big potential hazard. The potential hazard generated from the nature of B3 could be flammable, explosive, oxidative, corrosive and poisonous. The handling of B3 could be conducted by enforcing the labelling and classification in the usage and disposal processes. Some observations of the chemical laboratory of BATAN show that the management safety of hazardous material in compliance with the government regulation no. 74 year 2001 has not been dully conducted. The management safety of B3 could be improved by, designating one who has adequate skill in hazardous material safety specially as the B3 safety officer, providing the Material Safety Data Sheet that is updated periodically to use in the laboratory and storage room, updating periodically the inventory of B3, performing training in work safety periodically, and monitoring the ventilation system intensively in laboratory and storage room. (author)

Data package for the Turkey Point material interaction test capsules

International Nuclear Information System (INIS)

Krogness, J.C.; Davis, R.B.

1980-02-01

Objective of the test is to obtain interaction information on candidate package storage materials and geologies under prototypic temperatures in gamma and low-level neutron fields. This document provides a fabrication record of the experiment

Directory of certificates of compliance for radioactive materials packages. Volume 2, Revision 6

International Nuclear Information System (INIS)

1983-09-01

This directory contains a Summary Report of NRC Approved Packages (Volume 1), Certificates of Compliance (Volume 2), and a Summary Report of NRC Approved Quality Assurance Programs for Radioactive Material Packages (Volume 3). The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance number is included at the back of each volume of the directory. The Summary Report includes a listing of all users of each package design prior to the publication date of the directory. Shipments of radioactive material utilizing these packagings must be in accordance with the provisions of 49 CFR 173.471 and 10 CFR Part 71, as applicable. In satisfying the requirements of Section 71.12, it is the responsibility of the licensees to insure them that they have a copy of the current approval and conduct their transportation activities in accordance with an NRC approved quality assurance program. Copies of the current approval may be obtained from the US Nuclear Regulatory Commission Public Document Room files (see Docket No. listed on each certificate) at 1717 H Street, Washington, DC 20555. Note that the general license of 10 CFR 71.12 does not authorize the receipt, possession, use or transfer of byproduct source, or special nuclear material; such authorization must be obtained pursuant to 10 CFR Parts 30 to 36, 40, 50, or 70

Procedures for picking up and receiving packages of radioactive material - May 1975

International Nuclear Information System (INIS)

Anon.

1976-01-01

This regulatory guide describes a method acceptable to the NRC staff for licensees to comply with the provisions in 10 CFR Part 20, Section 20.205, with respect to arrangements for receipt, pickup, and monitoring of packages containing radioactive material and with respect to reporting of packages which, on receipt, show evidence of leakage or excessive radiation levels

Safety analysis report for packaging (onsite) L3-181 N basin cask

International Nuclear Information System (INIS)

Adkins, H.E. Jr.

1996-01-01

Purpose of this Safety Analysis Report (SARP) is to authorize the onsite transfer of a Type B, Fissile Excepted, non-highway route controlled quantity in the L3-181 packaging from the N Basin to a storage/disposal facility within 200 West Area. This SARP provides the evaluation necessary to demonstrate that the L3-181 meets the requirements of the 'Hazardous Material Packaging and Shipping', WHC- CM-2-14, by meeting the applicable performance requirements for normal conditions of transport

Integrated risk reduction framework to improve railway hazardous materials transportation safety.

Science.gov (United States)

Liu, Xiang; Saat, M Rapik; Barkan, Christopher P L

2013-09-15

Rail transportation plays a critical role to safely and efficiently transport hazardous materials. A number of strategies have been implemented or are being developed to reduce the risk of hazardous materials release from train accidents. Each of these risk reduction strategies has its safety benefit and corresponding implementation cost. However, the cost effectiveness of the integration of different risk reduction strategies is not well understood. Meanwhile, there has been growing interest in the U.S. rail industry and government to best allocate resources for improving hazardous materials transportation safety. This paper presents an optimization model that considers the combination of two types of risk reduction strategies, broken rail prevention and tank car safety design enhancement. A Pareto-optimality technique is used to maximize risk reduction at a given level of investment. The framework presented in this paper can be adapted to address a broader set of risk reduction strategies and is intended to assist decision makers for local, regional and system-wide risk management of rail hazardous materials transportation. Copyright © 2013 Elsevier B.V. All rights reserved.

Microbial hazards reduction during creamy cream cheese production

Directory of Open Access Journals (Sweden)

Dorota Miarka

2015-03-01

Full Text Available The purpose of the work was to identify the hazards relevant to the production of safe food and to assess the effects of a possible infection. The paper presents the microbiological hazards that can occur throughout the production of creamy cream cheese and indicates the means to their minimization or elimination. The analysis of microbiological hazards showed that in the manufacturing process of the type of cheese mentioned, there are a few critical steps that should be specifically overseen. In order to acquire a high quality product it is important to monitor a quality of raw material, the parameters of pasteurization and souring, temperature of product packaging, storage conditions of the finished product and maintain hygiene throughout the production. The process of heat treatment, which is pasteurization, is a critical step (critical control points - CCP for the whole process. Monitoring this stage and consistent adherence to Operational Pre-Condition Programs at the thermisation and centrifuging and later packaging, guarantees a safe product and its long shelf life.

Sandia National Laboratories, California Hazardous Materials Management Program annual report.

Energy Technology Data Exchange (ETDEWEB)

Brynildson, Mark E.

2011-02-01

The annual program report provides detailed information about all aspects of the Sandia National Laboratories, California (SNL/CA) Hazardous Materials Management Program. It functions as supporting documentation to the SNL/CA Environmental Management System Program Manual. This program annual report describes the activities undertaken during the calender past year, and activities planned in future years to implement the Hazardous Materials Management Program, one of six programs that supports environmental management at SNL/CA.

Final versions of the initial package of classroom materials and guidelines

NARCIS (Netherlands)

Doorman, Michiel; Jonker, Vincent

2014-01-01

The main aim of the mascil Work Package 3 ‘classroom materials’ is to present guidelines and an online collection of teaching materials that encourage and support teachers to design their own classroom materials that connect IBL and the WoW in mathematics and science education.The collection

Assessment of Aging of Cork and TISAF Materials in the SAFKEG 3940A Package in KAMS

International Nuclear Information System (INIS)

Vormelker, P.R.

2003-01-01

This report provides an assessment of the potential for aging and degradation of the resin-bonded cork and the Thermal-Insulating, Shock-Absorbing Foam materials that are components of the SAFKEG 3940A package. This package may be used for interim storage of plutonium materials in the Savannah River Site K-Area Materials Storage

Plutonium air transportable package development using metallic filaments and composite materials

International Nuclear Information System (INIS)

Pierce, J.D.; Neilsen, M.K.

1992-01-01

A new design concept for plutonium air transport packagings has been developed by the Transportation Systems Department and modeled by the Engineering Mechanics and Material Modelinc, Department at Sandia National Laboratories (SNL). The new concept resulted from an in-depth review (Allen et al., 1989) of existing, package design philosophies and limitations. This review indicated a need for a new package which could survive combinations of impact, fire, and puncture environments, and which could be scaled up or down to meet a wide range of requirements for various contents and regulations. This new design concept uses a very robust primary containment vessel with elastomeric seals for protection and confinement of an inner containment vessel with contents. An overpack consisting of multiple layers of plastically-deformable metallic wire mesh and high-tensile strength materials is placed around the containment vessels to provide energy absorption for the primary containment vessel as well as thermal protection. The use of intermittent layers with high-tensile strength results in a limiter which remains in place during accidental impact events and can be relied upon to provide subsequent puncture and fire protection. In addition, an outer shell around the energy absorbing material is provided for handling, and weather protection

Directory of Certificates of Compliance for Radioactive-Materials Packages. Certificates of Compliance

International Nuclear Information System (INIS)

1983-01-01

This directory contains a Summary Report of the US Nuclear Regulatory Commission's Approved Packages (Volume I), all Certificates of Compliance (Volume 2), and Summary Report of NRC Approved Quality Assurance Programs (Volume 3) for Radioactive Material Packages effective December 31, 1982. The purpose of this directory is to make available a convenient source of information on packagings which have been approved by the US Nuclear Regulatory Commission. To assist in identifying packaging, an index by Model Number and corresponding Certificate of Compliance Number is included at the back of Volumes 1 and 2 of the directory. A listing by packaging types is included in the back of Volume 2. An alphabetical listing by Company name is included in the back of Volume 3 for approved QA programs. The Summary Reports include a listing of all users of each package design and approved QA programs prior to the publication date of the directory

Quality assurance of packaging used for the transport of radioactive material

International Nuclear Information System (INIS)

Oeman, S.

1987-01-01

The project is divided into four parts. This document is the final report from part 2 and 3. The aim of the project is a document called 'Proposal for quality assurance of packaging used for the transport of radioactive material' which shall act as an example for how the quality assurance should be organized for different categories of packagings. One or more specific packagings ('type packagings') in each class have been selected and studied in detail with consideration on the components which are important for the safety at transportation. Finally detailed control plans have been developed with consideration to production quality control as well as to recurring inspection. Besides it has been investigated whether there are any control methods to carry out the necessary inspections according to the control plans and report where such methods have to be developed. (author)

Nuclear waste package materials testing report: basaltic and tuffaceous environments

International Nuclear Information System (INIS)

Bradley, D.J.; Coles, D.G.; Hodges, F.N.; McVay, G.L.; Westerman, R.E.

1983-03-01

The disposal of high-level nuclear wastes in underground repositories in the continental United States requires the development of a waste package that will contain radionuclides for a time period commensurate with performance criteria, which may be up to 1000 years. This report addresses materials testing in support of a waste package for a basalt (Hanford, Washington) or a tuff (Nevada Test Site) repository. The materials investigated in this testing effort were: sodium and calcium bentonites and mixtures with sand or basalt as a backfill; iron and titanium-based alloys as structural barriers; and borosilicate waste glass PNL 76-68 as a waste form. The testing also incorporated site-specific rock media and ground waters: Reference Umtanum Entablature-1 basalt and reference basalt ground water, Bullfrog tuff and NTS J-13 well water. The results of the testing are discussed in four major categories: Backfill Materials: emphasizing water migration, radionuclide migration, physical property and long-term stability studies. Structural Barriers: emphasizing uniform corrosion, irradiation-corrosion, and environmental-mechanical testing. Waste Form Release Characteristics: emphasizing ground water, sample surface area/solution volume ratio, and gamma radiolysis effects. Component Compatibility: emphasizing solution/rock, glass/rock, glass/structural barrier, and glass/backfill interaction tests. This area also includes sensitivity testing to determine primary parameters to be studied, and the results of systems tests where more than two waste package components were combined during a single test

Nutritional response of Okra to various packaging materials and ...

African Journals Online (AJOL)

The research is focused at determining the nutritional response of Okra when pickling is carried out using different antimicrobial liquids (vinegar, olive oil, and groundnut oil) and packaging materials (glass jar, plastic and stainless steel), as well as make a comparism when spices (garlic, ginger, mixture of garlic and ginger) ...

Hazardous materials management and control program at Oak Ridge National Laboratory - environmental protection

International Nuclear Information System (INIS)

Eisenhower, B.M.; Oakes, T.W.

1982-01-01

In the Federal Register of May 19, 1980, the US Environmental Protection Agency promulgated final hazardous waste regulations according to the Resource Conservation and Recovery Act (RCRA) of 1976. The major substantive portions of these regulations went into effect on November 19, 1980, and established a federal program to provide comprehensive regulation of hazardous waste from its generation to its disposal. In an effort to comply with these regulations, a Hazardous Materials Management and Control Program was established at Oak Ridge National Laboratory. The program is administered by two Hazardous Materials Coordinators, who together with various support groups, ensure that all hazardous materials and wastes are handled in such a manner that all personnel, the general public, and the environment are adequately protected

Natural and technologic hazardous material releases during and after natural disasters: a review.

Science.gov (United States)

Young, Stacy; Balluz, Lina; Malilay, Josephine

2004-04-25

Natural disasters may be powerful and prominent mechanisms of direct and indirect hazardous material (hazmat) releases. Hazardous materials that are released as the result of a technologic malfunction precipitated by a natural event are referred to as natural-technologic or na-tech events. Na-tech events pose unique environmental and human hazards. Disaster-associated hazardous material releases are of concern, given increases in population density and accelerating industrial development in areas subject to natural disasters. These trends increase the probability of catastrophic future disasters and the potential for mass human exposure to hazardous materials released during disasters. This systematic review summarizes direct and indirect disaster-associated releases, as well as environmental contamination and adverse human health effects that have resulted from natural disaster-related hazmat incidents. Thorough examination of historic disaster-related hazmat releases can be used to identify future threats and improve mitigation and prevention efforts.

Transportation of hazardous materials in Iran: A strategic approach for decreasing accidents

Directory of Open Access Journals (Sweden)

S. Ghazinoory

2008-06-01

Full Text Available .“Hazardous materials” refer to those substances that seriously endanger human lives and/or the environment. The transportation of these materials will be inevitable in the increasingly industrialized economy of Iran. Nonetheless, numerous deadly accidents caused by the movement of these materials necessitate the design and implementation of preventive plans on several levels. This article looks into the present condition of transportation of hazardous materials in Iran and the resulting accidents. Optimal condition for the general transportation system of hazardous materials is delineated with due focus on transportation risk as the main parameter. Strategies for reaching the optimal condition are laid out and the impacts of these strategies on the reduction of accidents are analyzed.

Transportation package design using numerical optimization

International Nuclear Information System (INIS)

Harding, D.C.; Witkowski, W.R.

1992-01-01

The design of structures and engineering systems has always been an iterative process whose complexity was dependent upon the boundary conditions, constraints and available analytical tools. Transportation packaging design is no exception with structural, thermal and radiation shielding constraints based on regulatory hypothetical accident conditions. Transportation packaging design is often accomplished by a group of specialists, each designing a single component based on one or more simple criteria, pooling results with the group, evaluating the open-quotes pooledclose quotes design, and then reiterating the entire process until a satisfactory design is reached. The manual iterative methods used by the designer/analyst can be summarized in the following steps: design the part, analyze the part, interpret the analysis results, modify the part, and re-analyze the part. The inefficiency of this design practice and the frequently conservative result suggests the need for a more structured design methodology, which can simultaneously consider all of the design constraints. Numerical optimization is a structured design methodology whose maturity in development has allowed it to become a primary design tool in many industries. The purpose of this overview is twofold: first, to outline the theory and basic elements of numerical optimization; and second, to show how numerical optimization can be applied to the transportation packaging industry and used to increase efficiency and safety of radioactive and hazardous material transportation packages. A more extensive review of numerical optimization and its applications to radioactive material transportation package design was performed previously by the authors (Witkowski and Harding 1992). A proof-of-concept Type B package design is also presented as a simplified example of potential improvements achievable using numerical optimization in the design process

46 CFR 153.976 - Transfer of packaged cargo or ship's stores.

Science.gov (United States)

2010-10-01

... 46 Shipping 5 2010-10-01 2010-10-01 false Transfer of packaged cargo or ship's stores. 153.976 Section 153.976 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) CERTAIN BULK DANGEROUS CARGOES SHIPS CARRYING BULK LIQUID, LIQUEFIED GAS, OR COMPRESSED GAS HAZARDOUS MATERIALS Operations Cargo Transfer Procedures § 153.976 Transfer of...

APPLICATION OF POLYURETHANE FOAM FOR IMPACT ABSORPTION AND THERMAL INSULATION FOR RADIOACTIVE MATERIALS PACKAGINGS

International Nuclear Information System (INIS)

Smith, A; Glenn Abramczyk, G; Paul Blanton, P; Steve Bellamy, S; William Daugherty, W; Sharon Williamson, S

2007-01-01

Polyurethane foam has been widely used as an impact absorbing and thermal insulating material for large radioactive materials packages, since the 1980's. With the adoption of the regulatory crush test requirement, for smaller packages, polyurethane foam has been adopted as a replacement for cane fiberboard, because of its ability to withstand the crush test. Polyurethane foam is an engineered material whose composition is much more closely controlled than that of cane fiberboard. In addition, the properties of the foam can be controlled by controlling the density of the foam. The conditions under which the foam is formed, whether confined or unconfined have an affect on foam properties. The study reported here reviewed the application of polyurethane foam in RAM packagings and compared property values reported in the literature with published property values and test results for foam specimens taken from a prototype 9977 packaging. The study confirmed that, polyurethane foam behaves in a predictable and consistent manner and fully satisfies the functional requirements for impact absorption and thermal insulation

Metal Oxide Nanostructures in Food Applications: Quality Control and Packaging

Directory of Open Access Journals (Sweden)

Vardan Galstyan

2018-04-01

Full Text Available Metal oxide materials have been applied in different fields due to their excellent functional properties. Metal oxides nanostructuration, preparation with the various morphologies, and their coupling with other structures enhance the unique properties of the materials and open new perspectives for their application in the food industry. Chemical gas sensors that are based on semiconducting metal oxide materials can detect the presence of toxins and volatile organic compounds that are produced in food products due to their spoilage and hazardous processes that may take place during the food aging and transportation. Metal oxide nanomaterials can be used in food processing, packaging, and the preservation industry as well. Moreover, the metal oxide-based nanocomposite structures can provide many advantageous features to the final food packaging material, such as antimicrobial activity, enzyme immobilization, oxygen scavenging, mechanical strength, increasing the stability and the shelf life of food, and securing the food against humidity, temperature, and other physiological factors. In this paper, we review the most recent achievements on the synthesis of metal oxide-based nanostructures and their applications in food quality monitoring and active and intelligent packaging.

Application of Digital Image Correlation to Measurement of Packaging Material Mechanical Properties