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Note: This page contains sample records for the topic "accident prevention provisions" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
they are not comprehensive nor are they the most current set.
We encourage you to perform a real-time search of NLEBeta
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1

Severe accident approach - final report. Evaluation of design measures for severe accident prevention and consequence mitigation.  

Science Conference Proceedings (OSTI)

An important goal of the US DOE reactor development program is to conceptualize advanced safety design features for a demonstration Sodium Fast Reactor (SFR). The treatment of severe accidents is one of the key safety issues in the design approach for advanced SFR systems. It is necessary to develop an in-depth understanding of the risk of severe accidents for the SFR so that appropriate risk management measures can be implemented early in the design process. This report presents the results of a review of the SFR features and phenomena that directly influence the sequence of events during a postulated severe accident. The report identifies the safety features used or proposed for various SFR designs in the US and worldwide for the prevention and/or mitigation of Core Disruptive Accidents (CDA). The report provides an overview of the current SFR safety approaches and the role of severe accidents. Mutual understanding of these design features and safety approaches is necessary for future collaborations between the US and its international partners as part of the GEN IV program. The report also reviews the basis for an integrated safety approach to severe accidents for the SFR that reflects the safety design knowledge gained in the US during the Advanced Liquid Metal Reactor (ALMR) and Integral Fast Reactor (IFR) programs. This approach relies on inherent reactor and plant safety performance characteristics to provide additional safety margins. The goal of this approach is to prevent development of severe accident conditions, even in the event of initiators with safety system failures previously recognized to lead directly to reactor damage.

Tentner, A. M.; Parma, E.; Wei, T.; Wigeland, R.; Nuclear Engineering Division; SNL; INL

2010-03-01T23:59:59.000Z

2

Accidents  

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

Health Risks » Accidents Health Risks » Accidents DUF6 Health Risks line line Accidents Storage Conversion Manufacturing Disposal Transportation Accidents A discussion of accidents involving depleted UF6 storage cylinders, including possible health effects, accident risk, and accident history. Potential Health Effects from Cylinder Accidents Accidents involving depleted UF6 storage cylinders are a concern because they could result in an uncontrolled release of UF6 to the environment, which could potentially affect the health of workers and members of the public living downwind of the accident site. Accidental release of UF6 from storage cylinders or during processing activities could result in injuries or fatalities. The most immediate hazard after a release would be from inhalation of hydrogen fluoride (HF), a highly corrosive gas formed when

3

Inherent Prevention and Mitigation of Severe Accident Consequences in Sodium-Cooled Fast Reactors  

SciTech Connect

Safety challenges for sodium-cooled fast reactors include maintaining core temperatures within design limits and assuring the geometry and integrity of the reactor core. Due to the high power density in the reactor core, heat removal requirements encourage the use of high-heat-transfer coolants such as liquid sodium. The variation of power across the core requires ducted assemblies to control fuel and coolant temperatures, which are also used to constrain core geometry. In a fast reactor, the fuel is not in the most neutronically reactive configuration during normal operation. Accidents leading to fuel melting, fuel pin failure, and fuel relocation can result in positive reactivity, increasing power, and possibly resulting in severe accident consequences including recriticalities that could threaten reactor and containment integrity. Inherent safety concepts, including favorable reactivity feedback, natural circulation cooling, and design choices resulting in favorable dispersive characteristics for failed fuel, can be used to increase the level of safety to the point where it is highly unlikely, or perhaps even not credible, for such severe accident consequences to occur.

Roald A. Wigeland; James E. Cahalan

2011-04-01T23:59:59.000Z

4

Evaluation of Alternative Control for Prevention and or Mitigation of HEPA Filter Failure Accidents at Tank Farm Facilities  

SciTech Connect

This study evaluates the adequacy and benefit of use of HEPA filter differential pressure limiting setpoints to initiate exhauster shut down as an alternative safety control for postulated accidents that might result in filtration failure and subsequent unfiltered release from Tank Farm primary tank ventilators.

GUSTAVSON, R.D.

2000-01-28T23:59:59.000Z

5

Chernobyl Nuclear Accident | National Nuclear Security Administration  

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

Chernobyl Nuclear Accident | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response...

6

Accident Investigation Handbook  

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

SENSI NOT MEAS UREMENT TIVE D DOE-HDBK-1 1208-2012 July 2012 DOE E HA ANDBOOK K Ac ccide ent and d Op pera ational Sa afety y An naly ysis Volume e I: Ac ccide ent A Analy ysis Tec chniq ques U.S. Depar rtmen nt of En nergy Was shingto on, D.C C. 205 85 DOE-HDBK-1208-2012 INTRODUCTION - HANDBOOK APPLICATION AND SCOPE Accident Investigations (AI) and Operational Safety Reviews (OSR) are valuable for evaluating technical issues, safety management systems and human performance and environmental conditions to prevent accidents, through a process of continuous organizational learning. This Handbook brings together the strengths of the experiences gained in conducting Department of Energy (DOE) accident investigations over the past many years. That experience encourages us

7

Small Business Solicitation Provision  

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

Solicitation Provision Solicitation Provision The Department of Energy has many exceptionally complex projects and programs involving the environmental remediation of its sites, and because of this complexity, are beyond the capabilities of small business in terms of a small business acting as the prime contractor. However, there are many opportunities within these projects in which small businesses can take part. It is the Department of Energy's policy to promote the participation of small business in all of its programs and projects. As such, the following solicitation provision, and evaluation criteria, will be included by the Department of Energy in environmental remediation acquisitions which are not set aside for small business. In addition, a contract clause will also be included in the resulting contract, providing

8

Nuclear Reactor Accidents  

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

Reactor Accidents The accidents at the Three Mile Island (TMI) and Chernobyl nuclear reactors have triggered particularly intense concern about radiation hazards. The TMI accident,...

9

Sec. Herrington Leads Delegation in Response to Chernobyl Accident...  

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

Sec. Herrington Leads Delegation in Response to Chernobyl Accident | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering...

10

RECENT LASER ACCIDENTS AT DEPARTMENT OF ENERGY LABORATORIES  

SciTech Connect

Recent laser accidents and incidents at research laboratories across the Department of Energy complex are reviewed in this paper. Factors that contributed to the accidents are examined. Conclusions drawn from the accident reports are summarized and compared. Control measures that could have been implemented to prevent the accidents will be summarized and compared. Recommendations for improving laser safety programs are outlined and progress toward achieving them are summarized.

ODOM, CONNON R. [Los Alamos National Laboratory

2007-02-02T23:59:59.000Z

11

Accident Investigation Handbook  

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

Improvement (HPI). The recommended techniques apply equally well to DOE Federal-led accident investigations conducted under DOE Order (O) 225.1B, Accident Investigations,...

12

SRS - SRNS General Provisions and Related Documents  

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

SRNS General Provisions and Related Documents General ProvisionsTerms and Conditions Documents Certifications SolicitationSubcontract Documents Focused Observation Safety...

13

DOE Accident Prevention and Investigation Program  

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

The Office of Health, Safety and Security HSS Logo Department of Energy Seal Left Tab SEARCH Right Tab TOOLS Right Tab Left Tab HOME Right Tab Left Tab ABOUT US Right Tab Left Tab...

14

General Provisions on Air Pollution Control (Ohio) | Department of Energy  

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

General Provisions on Air Pollution Control (Ohio) General Provisions on Air Pollution Control (Ohio) General Provisions on Air Pollution Control (Ohio) < Back Eligibility Agricultural Construction Fuel Distributor Industrial Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative State/Provincial Govt Transportation Tribal Government Utility Program Info State Ohio Program Type Environmental Regulations Provider Ohio Environmental Protection Agency This chapter of the law that establishes the Ohio Environmental Protection Agency outlines the air pollution rules to secure and maintain levels of air quality that are consistent with the protection of health and the prevention of injury to plant, animal life, and property in the state of Ohio, and to provide for the comfortable enjoyment of the natural

15

EPR Severe Accident Threats and Mitigation  

SciTech Connect

Despite the extremely low EPR core melt frequency, an improved defence-in-depth approach is applied in order to comply with the EPR safety target: no stringent countermeasures should be necessary outside the immediate plant vicinity like evacuation, relocation or food control other than the first harvest in case of a severe accident. Design provisions eliminate energetic events and maintain the containment integrity and leak-tightness during the entire course of the accident. Based on scenarios that cover a broad range of physical phenomena and which provide a sound envelope of boundary conditions associated with each containment challenge, a selection of representative loads has been done, for which mitigation measures have to cope with. This paper presents the main critical threats and the approach used to mitigate those threats. (authors)

Azarian, G. [Framatome ANP SAS, Tour Areva, Place de la Coupole 92084 Paris la Defense (France); Kursawe, H.M.; Nie, M.; Fischer, M.; Eyink, J. [Framatome ANP GmbH, Freyeslebenstrasse, 1, D-91058 Erlangen (Germany); Stoudt, R.H. [Framatome ANP Inc. - 3315 Old Forest Rd, Lynchburgh, VA 24501 (United States)

2004-07-01T23:59:59.000Z

16

Failsafe : living with man-made disaster and accident  

E-Print Network (OSTI)

"There is no progress with out progress of the catastrophe." Virilio. This thesis project proposes that technological solutions in the design of our systems are not enough to prevent 'man-made' accident. Social, organisational ...

Higgins, Saoirse, 1966-

2004-01-01T23:59:59.000Z

17

2003 Edition NEHRP RECOMMENDED PROVISIONS FOR ...  

Science Conference Proceedings (OSTI)

Page 1. Program on Improved Seismic Safety Provisions of the National Institute of Building Sciences 2003 Edition NEHRP ...

2007-03-01T23:59:59.000Z

18

Nuclear criticality accidents  

SciTech Connect

Criticality occurs when a sufficient quantity of fissionable material is accumulated, and it results in the liberation of nuclear energy. All process accidents have involved plutonium or highly enriched uranium, as have most of the critical experiment accidents. Slightly enriched uranium systems require much larger quantities of material to achieve criticality. An appreciation of criticality accidents should be based on an understanding of factors that influence criticality, which are discussed in this article. 11 references.

Smith, D.R. (Los Alamos National Laboratory, New Mexico (Unites States))

1991-10-01T23:59:59.000Z

19

A framework for the assessment of severe accident management strategies  

SciTech Connect

Severe accident management can be defined as the use of existing and/or altemative resources, systems and actors to prevent or mitigate a core-melt accident. For each accident sequence and each combination of severe accident management strategies, there may be several options available to the operator, and each involves phenomenological and operational considerations regarding uncertainty. Operational uncertainties include operator, system and instrumentation behavior during an accident. A framework based on decision trees and influence diagrams has been developed which incorporates such criteria as feasibility, effectiveness, and adverse effects, for evaluating potential severe accident management strategies. The framework is also capable of propagating both data and model uncertainty. It is applied to several potential strategies including PWR cavity flooding, BWR drywell flooding, PWR depressurization and PWR feed and bleed.

Kastenberg, W.E. [ed.; Apostolakis, G.; Dhir, V.K. [California Univ., Los Angeles, CA (United States). Dept. of Mechanical, Aerospace and Nuclear Engineering] [and others

1993-09-01T23:59:59.000Z

20

Aggressive Datacenter Power Provisioning with Batteries  

Science Conference Proceedings (OSTI)

Datacenters spend $10--25 per watt in provisioning their power infrastructure, regardless of the watts actually consumed. Since peak power needs arise rarely, provisioning power infrastructure for them can be expensive. One can, thus, aggressively underprovision ... Keywords: Datacenters, UPS, batteries, cap-ex, peak power, peak shaving, provisioning, stored energy

Sriram Govindan; Di Wang; Anand Sivasubramaniam; Bhuvan Urgaonkar

2013-02-01T23:59:59.000Z

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


21

Severe Accident Studies | Department of Energy  

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

Severe Accident Studies Severe Accident Studies Powerpoint discussing studies and conclusions on transportation accidents and safety. Severe Accident Studies More Documents &...

22

DOE Challenge Home Recommended Quality Management Provisions  

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

Recommended Quality Recommended Quality Management Provisions RECOMMENDED QUALITY MANAGEMENT PROVISIONS QM Provision Builder Documentation & Verification Requirements Rater/Verifier Requirements QM #1: Project Documentation Complete construction documents shall be qualified as Designed to Earn ENERGY STAR and document all additional provisions and specifications required for DOE Challenge Home including mandatory provisions: 2012 IECC envelope insulation levels, ENERGY STAR windows, duct work in conditioned space, hot water distribution requirements requirements for indoor fixtures, EPA Indoor airPLUS checklist, and Renewable Energy Ready Home Checklists. Develop and store construction documents which, at a minimum, shall include all content required to consistently implement

23

Severe Accident Studies  

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

Severe Accident Studies Severe Accident Studies Christopher S. Bajwa Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards USNRC 2012 U.S. DOE National Transportation Stakeholders Forum (NTSF) May 15 - 17, 2012 Knoxville, TN * Going The Distance? - The Safe Transport of Spent Nuclear Fuel and High-Level Radioactive Waste in the United States * Released February 9, 2006 * Conclusions: * NRC safety regulations are adequate to ensure package containment effectiveness over a wide range of transport conditions, including most credible accident conditions. * The radiological risks are well understood and are generally low, with the possible exception of risks from releases in extreme accidents involving long duration, fully engulfing fires.

24

Accident resistant transport container  

DOE Patents (OSTI)

The invention relates to a container for the safe air transport of plutonium having several intermediate wood layers and a load spreader intermediate an inner container and an outer shell for mitigation of shock during a hypothetical accident.

Andersen, John A. (Albuquerque, NM); Cole, James K. (Albuquerque, NM)

1980-01-01T23:59:59.000Z

25

Oil and Gas General Provisions (Montana)  

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

This chapter describes general provisions for the exploration and development of oil and gas resources in Montana. The chapter addresses royalty interests, regulations for the lease of local...

26

Fallen conductor accidents: The challenge to improve safety  

SciTech Connect

What is the worst nightmare of an electric utility manager or engineer Many respond that it is an electrocution resulting from a fallen conductor accident. Few subjects in the operation of an electric utility are more emotional and sobering than this. Traditionally, a utility could do little to prevent such accidents, but some answers from research are emerging, calling for a new look at this old problem.

Aucoin, B.M.; Russell, B.D.

1992-02-01T23:59:59.000Z

27

Study on drywell cooler applicability to severe accident management  

SciTech Connect

This paper concerns applicability of drywell cooler (DWC) heat removal under severe accident condition in BWR plants. Newly developed heat removal models based on DWC heat removal experiments were built into the MAAP3 code. And then, two types of Japanese BWR were selected to evaluate DWC heat removal performance under typical severe accident scenarios. According to the results of the evaluation, DWC delays or prevents containment failure or venting. (authors)

Nakagawa, Takahiro [Information and manufacturing systems division, Toshiba Plant Systems and Services Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan); Akinaga, Makoto [Power and Industrial Systems R and D Center, Toshiba Corporation, 4-1 Ukishima-cho, Kawasaki-ku, Kawasaki, 210-0862 (Japan); Hamazaki, Ryoichi [Isogo Nuclear Engineering Center, Toshiba Corporation, 8, Shinsugita-cho, Isogo-ku, Yokohama, 235-8523 (Japan); Matsuo, Toshihiro [Nuclear Power Engineering Department, Tokyo Electric Power Company, 1-3 Uchisaiwai-cho 1-chome, Chiyoda-ku, Tokyo 100-0011 (Japan); Hashimoto, Kouji [Nuclear Plant Engineering Department, HITACHI, Ltd., 1-1, Saiwai-cho, 3-chome, Hitachi-shi, Ibaraki-ken, 317-8511 (Japan)

2004-07-01T23:59:59.000Z

28

Microsoft Word - Unrelated Accident  

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

For Immediate Release For Immediate Release Truck Accident Did Not Involve WIPP Shipment CARLSBAD, N.M., October 1, 2009 - A Wednesday night truck accident north of Albuquerque on Highway 165 that involved an 18-wheeler is not related to Waste Isolation Pilot Plant (WIPP) transuranic waste shipments. Involved in the accident was a load of new, unused 55-gallon drums manufactured in Carlsbad that was en route to Richland, Washington. The Waste Isolation Pilot Plant is a U.S. Department of Energy facility designed to safely isolate defense-related transuranic waste from people and the environment. Waste temporarily stored at sites around the country is shipped to WIPP and permanently disposed in rooms mined out of an ancient salt formation 2,150 feet below the surface. WIPP, which began waste

29

Computerized Accident Incident Reporting System  

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

The Computerized Accident/Incident Reporting System is a database used to collect and analyze DOE and DOE contractor reports of injuries, illnesses, and other accidents that occur during DOE...

30

Energy Department Seeks Public Comment on Standby Support Provisions...  

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

Public Comment on Standby Support Provisions of Energy Policy Act of 2005 Energy Department Seeks Public Comment on Standby Support Provisions of Energy Policy Act of 2005 November...

31

Special Provisions Affecting Gas, Water, or Pipeline Companies...  

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

Agencies You are here Home Savings Special Provisions Affecting Gas, Water, or Pipeline Companies (South Carolina) Special Provisions Affecting Gas, Water, or Pipeline...

32

Alternative Fuels Data Center: Provision for Alternative Fuels Corridor  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Provision for Provision for Alternative Fuels Corridor Pilot Projects to someone by E-mail Share Alternative Fuels Data Center: Provision for Alternative Fuels Corridor Pilot Projects on Facebook Tweet about Alternative Fuels Data Center: Provision for Alternative Fuels Corridor Pilot Projects on Twitter Bookmark Alternative Fuels Data Center: Provision for Alternative Fuels Corridor Pilot Projects on Google Bookmark Alternative Fuels Data Center: Provision for Alternative Fuels Corridor Pilot Projects on Delicious Rank Alternative Fuels Data Center: Provision for Alternative Fuels Corridor Pilot Projects on Digg Find More places to share Alternative Fuels Data Center: Provision for Alternative Fuels Corridor Pilot Projects on AddThis.com... More in this section... Federal

33

Alternative Fuels Data Center: Provision for Establishment of Alternative  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Provision for Provision for Establishment of Alternative Fuel Incentives to someone by E-mail Share Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Incentives on Facebook Tweet about Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Incentives on Twitter Bookmark Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Incentives on Google Bookmark Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Incentives on Delicious Rank Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Incentives on Digg Find More places to share Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Incentives on AddThis.com... More in this section...

34

Order Module--DOE Order 225.1B, ACCIDENT INVESTIGATIONS | Department of  

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

Order 225.1B, ACCIDENT INVESTIGATIONS Order 225.1B, ACCIDENT INVESTIGATIONS Order Module--DOE Order 225.1B, ACCIDENT INVESTIGATIONS DOE O 225.1B prescribes organizational responsibilities, authorities, and requirements for conducting investigations of certain accidents occurring at DOE sites, facilities, areas, operations, and activities. The purpose of the accident investigation is to understand and identify the causes that contributed to the accident so those deficiencies can be addressed and corrected. This, in turn, is intended to prevent recurrence and promote improved environmental protection and safety and health of DOE employees, contractors, and the public. Moreover, accident investigations are used to promote the values and concepts of a learning organization. The department's integrated safety management (ISM) feedback and improvement

35

ADR Provisions in Federal Acquisition Regulation (FAR)  

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

ADR Provisions in Federal Acquisition Regulation (FAR) ADR Provisions in Federal Acquisition Regulation (FAR) d. Alternative means of dispute resolution. Notwithstanding any other provision of this chapter, a contractor and a contracting officer may use any alternative means of dispute resolution under subchapter IV of chapter 5 of title 5, or other mutually agreeable procedures, for resolving claims. In a case in which such alternative means of dispute resolution or other mutually agreeable procedures are used, the contractor shall certify that the claim is made in good faith, that the supporting data are accurate and complete to the best of his or her knowledge and belief, and that the amount requested accurately reflects the contract adjustment for which the contractor believes the Government is liable. All provisions of subchapter IV

36

Effect of helium injection on diffusion dominated air ingress accidents in pebble bed reactors  

E-Print Network (OSTI)

The primary objective of this thesis was to validate the sustained counter air diffusion (SCAD) method at preventing natural circulation onset in diffusion dominated air ingress accidents. The analysis presented in this ...

Yurko, Joseph Paul

2010-01-01T23:59:59.000Z

37

Barriers to Switching Accidents  

Science Conference Proceedings (OSTI)

The EPRI Switching Safety & Reliability Project Steering Committee sponsored development of a self-study based training program for personnel who perform switching. Some of the earlier EPRI Switching Safety & Reliability research projects that focused on the causes of switching errors, highlighted a need to reduce the 'complacency' that tends to develop as switching activities are performed over and over again and become 'routine.' Most switching accidents or incidents involve personnel who were trained ...

2005-12-22T23:59:59.000Z

38

Alternative Fuels Data Center: Provision for Establishment of Alternative  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Provision for Provision for Establishment of Alternative Fuel Vehicle (AFV) Acquisition Requirements to someone by E-mail Share Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Vehicle (AFV) Acquisition Requirements on Facebook Tweet about Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Vehicle (AFV) Acquisition Requirements on Twitter Bookmark Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Vehicle (AFV) Acquisition Requirements on Google Bookmark Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Vehicle (AFV) Acquisition Requirements on Delicious Rank Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Vehicle (AFV) Acquisition Requirements on Digg

39

Severe accident analysis using dynamic accident progression event trees.  

E-Print Network (OSTI)

??In present, the development and analysis of Accident Progression Event Trees (APETs) are performed in a manner that is computationally time consuming, difficult to reproduce (more)

Hakobyan, Aram P

2006-01-01T23:59:59.000Z

40

SRS - ARRA General Provisions and Related Documents  

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

American Recovery and Reinvestment Act (ARRA) American Recovery and Reinvestment Act (ARRA) General Provisions and Related Documents General Provisions/Terms and Conditions Documents Certifications Solicitation/Subcontract Documents Focused Observation Safety Checklists Construction Subcontract Documents/Forms General Provisions/Terms and Conditions Documents DOCUMENT NUMBER TITLE REVISION # or DATE SRNS-MS-2009-00069 Fixed Price Orders 5 SRNS-MS-2009-00072 Construction Subcontract Exhibit A 7 SRNS-MS-2009-00073 Time and Material / Labor Hour 5 SRNS-MS-2009-00074 Commercial Terms and Conditions for Dismantling, Demolition, or Removal of Improvements 5 SRNS-MS-2009-00075 Corporate Professional Services 6 SRNS-MS-2009-00076 Individual Consultants 5 SRNS-MS-2010-00085 Cost Reimbursement Orders with Educational Institutions 4

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


41

APS Guideline for Accident Investigations  

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

occurring in CATXSDs facilities at the APS. Definitions Accident: an unexpected event that produces personal injury, illness, or death; damage to or loss of property or...

42

T-541: Citrix Provisioning Services Unspecified Flaw Let's Remote Users  

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

41: Citrix Provisioning Services Unspecified Flaw Let's Remote 41: Citrix Provisioning Services Unspecified Flaw Let's Remote Users Execute Arbitrary Code T-541: Citrix Provisioning Services Unspecified Flaw Let's Remote Users Execute Arbitrary Code January 24, 2011 - 5:34pm Addthis PROBLEM: Citrix Provisioning Services Unspecified Flaw Let's Remote Users Execute Arbitrary Code PLATFORM: * Provisioning Services 5.1 * Provisioning Services 5.6 ABSTRACT: A vulnerability has been identified in Citrix Provisioning Services that could result in arbitrary code execution. This vulnerability can be triggered by an attacker sending a specially crafted packet to the Provisioning Services server. This vulnerability is present in all supported versions of Citrix Provisioning Services up to and including version 5.6. reference LINKS:

43

Alternative Fuels Data Center: Provision for Renewable Fuels Investment  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Provision for Provision for Renewable Fuels Investment to someone by E-mail Share Alternative Fuels Data Center: Provision for Renewable Fuels Investment on Facebook Tweet about Alternative Fuels Data Center: Provision for Renewable Fuels Investment on Twitter Bookmark Alternative Fuels Data Center: Provision for Renewable Fuels Investment on Google Bookmark Alternative Fuels Data Center: Provision for Renewable Fuels Investment on Delicious Rank Alternative Fuels Data Center: Provision for Renewable Fuels Investment on Digg Find More places to share Alternative Fuels Data Center: Provision for Renewable Fuels Investment on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type Provision for Renewable Fuels Investment To create jobs and improve the state's general infrastructure, the Florida

44

Stress in accident and post-accident management at Chernobyl ?  

E-Print Network (OSTI)

Abstract. The effects of the Chernobyl nuclear accident on the psychology of the affected population have been much discussed. The psychological dimension has been advanced as a factor explaining the emergence, from 1990 onwards, of a post-accident crisis in the main CIS countries affected. This article presents the conclusions of a series of European studies, which focused on the consequences of the Chernobyl accident. These studies show that the psychological and social effects associated with the post-accident situation arise from the interdependency of a number of complex factors exerting a deleterious effect on the population. We shall first attempt to characterise the stress phenomena observed among the population affected by the accident. Secondly, we will be presenting an analysis of the various factors that have contributed to the emerging psychological and social features of population reaction to the accident and in post-accident phases, while not neglecting the effects of the pre-accident situation on the target population. Thirdly, we shall devote some initial consideration to the conditions that might be conducive to better management of postaccident stress. In conclusion, we shall emphasise the need to restore confidence among the population generally. 1.

Gilles Heriard Dubreuil

1996-01-01T23:59:59.000Z

45

Flexible provisioning of web service workflows  

Science Conference Proceedings (OSTI)

Web services promise to revolutionize the way computational resources and business processes are offered and invoked in open, distributed systems, such as the Internet. These services are described using machine-readable metadata, which enables consumer ... Keywords: Web services, semantic Web services, service composition, service provisioning, service-oriented computing, workflows

Sebastian Stein; Terry R. Payne; Nicholas R. Jennings

2009-02-01T23:59:59.000Z

46

Strategic goods provision in Hezbollah's resistance  

E-Print Network (OSTI)

The provision of goods and services is thought to be a key way that groups are able to gain political power. However, current work has offered a highly fragmentary view of what specific gains can be made with what type of ...

Bartels, Elizabeth M. (Elizabeth Murphy)

2010-01-01T23:59:59.000Z

47

Accurate accident reconstruction in VANET  

Science Conference Proceedings (OSTI)

We propose a forensic VANET application to aid an accurate accident reconstruction. Our application provides a new source of objective real-time data impossible to collect using existing methods. By leveraging inter-vehicle communications, we compile ... Keywords: EDR, VANET, accident reconstruction, in-vehicle applications

Yuliya Kopylova; Csilla Farkas; Wenyuan Xu

2011-07-01T23:59:59.000Z

48

Nuclear Reactor Severe Accident Experiments  

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

Nuclear Reactor Severe Accident Experiments Nuclear Reactor Severe Accident Experiments Capabilities Engineering Experimentation Reactor Safety Testing and Analysis Overview Nuclear Reactor Severe Accident Experiments MAX NSTF SNAKE Aerosol Experiments System Components Laser Applications Robots Applications Other Facilities Other Capabilities Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Nuclear Reactor Severe Accident Experiments 1 2 3 4 5 6 7 We perform experiments simulating reactor core melt phenomena in which molten core debris ("corium") erodes the concrete floor of a containment building. This occurred during the Fukushima nuclear power plant accident though the extent of concrete damage is yet unknown. This video shows the top view of a churning molten pool of uranium oxide at 2000°C (3600°F) seen during an experiment at Argonne. Corium behaves much like lava.

49

Attachment F: Summary Checklist of Model AIP Provisions and Program  

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

F: Summary Checklist of Model AIP Provisions and Program F: Summary Checklist of Model AIP Provisions and Program Policies Attachment F: Summary Checklist of Model AIP Provisions and Program Policies Summary Checklist of Model AIP Provisions and Program Policies In response to concerns expressed by DOE and State AIP program representatives, the Office of Environmental Activities has developed a list of mandatory and non-mandatory model language provisions for new and renegotiated AIPs. The underlying concepts for the mandatory provisions are set forth in Attachment A. Other program policies are set forth in a question and answer format in Attachment B. The texts of the optional provisions and mandatory provisions that may be applicable are provided in Attachments C and D respectively. Suggested language related to emergency

50

Alternative Fuels Data Center: Provision for Establishment of Alternative  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Provision for Provision for Establishment of Alternative Fuel Use Mandate to someone by E-mail Share Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Use Mandate on Facebook Tweet about Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Use Mandate on Twitter Bookmark Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Use Mandate on Google Bookmark Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Use Mandate on Delicious Rank Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Use Mandate on Digg Find More places to share Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Use Mandate on AddThis.com...

51

Alternative Fuels Data Center: Provision for Establishment of Hydrogen  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Provision for Provision for Establishment of Hydrogen Program to someone by E-mail Share Alternative Fuels Data Center: Provision for Establishment of Hydrogen Program on Facebook Tweet about Alternative Fuels Data Center: Provision for Establishment of Hydrogen Program on Twitter Bookmark Alternative Fuels Data Center: Provision for Establishment of Hydrogen Program on Google Bookmark Alternative Fuels Data Center: Provision for Establishment of Hydrogen Program on Delicious Rank Alternative Fuels Data Center: Provision for Establishment of Hydrogen Program on Digg Find More places to share Alternative Fuels Data Center: Provision for Establishment of Hydrogen Program on AddThis.com... More in this section... Federal State Advanced Search All Laws & Incentives Sorted by Type

52

Alternative Fuels Data Center: Provision for Establishment of Alternative  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Provision for Provision for Establishment of Alternative Fuel Vehicle (AFV) Loan Program to someone by E-mail Share Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Vehicle (AFV) Loan Program on Facebook Tweet about Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Vehicle (AFV) Loan Program on Twitter Bookmark Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Vehicle (AFV) Loan Program on Google Bookmark Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Vehicle (AFV) Loan Program on Delicious Rank Alternative Fuels Data Center: Provision for Establishment of Alternative Fuel Vehicle (AFV) Loan Program on Digg Find More places to share Alternative Fuels Data Center: Provision

53

Alternative Fuels Data Center: Provision for Establishment of Clean Fuel  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Provision for Provision for Establishment of Clean Fuel Vehicle Insurance Incentives to someone by E-mail Share Alternative Fuels Data Center: Provision for Establishment of Clean Fuel Vehicle Insurance Incentives on Facebook Tweet about Alternative Fuels Data Center: Provision for Establishment of Clean Fuel Vehicle Insurance Incentives on Twitter Bookmark Alternative Fuels Data Center: Provision for Establishment of Clean Fuel Vehicle Insurance Incentives on Google Bookmark Alternative Fuels Data Center: Provision for Establishment of Clean Fuel Vehicle Insurance Incentives on Delicious Rank Alternative Fuels Data Center: Provision for Establishment of Clean Fuel Vehicle Insurance Incentives on Digg Find More places to share Alternative Fuels Data Center: Provision for Establishment of Clean Fuel Vehicle Insurance Incentives on

54

Alternative Fuels Data Center: Provision for Alternative Fuel Vehicle (AFV)  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Provision for Provision for Alternative Fuel Vehicle (AFV) Tax Reduction to someone by E-mail Share Alternative Fuels Data Center: Provision for Alternative Fuel Vehicle (AFV) Tax Reduction on Facebook Tweet about Alternative Fuels Data Center: Provision for Alternative Fuel Vehicle (AFV) Tax Reduction on Twitter Bookmark Alternative Fuels Data Center: Provision for Alternative Fuel Vehicle (AFV) Tax Reduction on Google Bookmark Alternative Fuels Data Center: Provision for Alternative Fuel Vehicle (AFV) Tax Reduction on Delicious Rank Alternative Fuels Data Center: Provision for Alternative Fuel Vehicle (AFV) Tax Reduction on Digg Find More places to share Alternative Fuels Data Center: Provision for Alternative Fuel Vehicle (AFV) Tax Reduction on AddThis.com... More in this section...

55

Sec. Herrington Leads Delegation in Response to Chernobyl Accident |  

National Nuclear Security Administration (NNSA)

Sec. Herrington Leads Delegation in Response to Chernobyl Accident | Sec. Herrington Leads Delegation in Response to Chernobyl Accident | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure Continuing Management Reform Countering Nuclear Terrorism About Us Our Programs Our History Who We Are Our Leadership Our Locations Budget Our Operations Media Room Congressional Testimony Fact Sheets Newsletters Press Releases Speeches Events Social Media Video Gallery Photo Gallery NNSA Archive Federal Employment Apply for Our Jobs Our Jobs Working at NNSA Blog Home > About Us > Our History > NNSA Timeline > Sec. Herrington Leads Delegation in Response to ... Sec. Herrington Leads Delegation in Response to Chernobyl Accident

56

Attachment C: Optional AIP Provisions | Department of Energy  

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

C: Optional AIP Provisions C: Optional AIP Provisions Attachment C: Optional AIP Provisions Optional AIP Provisions This attachment contains sample language for a number of optional provisions that sites may choose to include or not to include in their AIPs. Optional AIP provisions are not mandatory and the language presented is a sample which may be used as is, serve as a guideline for the creation of a modified provision to suit the site-specific needs of a particular AIP program, or not included in a new or renegotiated AIP. 1. Public Participation/Public Accountability in the DOE Planning Process "The DOE will make available to the public in a timely manner all environmental planning documents that require public comment. The DOE will promptly reply to, and confirm receipt of, requests for information

57

OSSA - An optimized approach to severe accident management: EPR application  

SciTech Connect

There is a recognized need to provide nuclear power plant technical staff with structured guidance for response to a potential severe accident condition involving core damage and potential release of fission products to the environment. Over the past ten years, many plants worldwide have implemented such guidance for their emergency technical support center teams either by following one of the generic approaches, or by developing fully independent approaches. There are many lessons to be learned from the experience of the past decade, in developing, implementing, and validating severe accident management guidance. Also, though numerous basic approaches exist which share common principles, there are differences in the methodology and application of the guidelines. AREVA/Framatome-ANP is developing an optimized approach to severe accident management guidance in a project called OSSA ('Operating Strategies for Severe Accidents'). There are still numerous operating power plants which have yet to implement severe accident management programs. For these, the option to use an updated approach which makes full use of lessons learned and experience, is seen as a major advantage. Very few of the current approaches covers all operating plant states, including shutdown states with the primary system closed and open. Although it is not necessary to develop an entirely new approach in order to add this capability, the opportunity has been taken to develop revised full scope guidance covering all plant states in addition to the fuel in the fuel building. The EPR includes at the design phase systems and measures to minimize the risk of severe accident and to mitigate such potential scenarios. This presents a difference in comparison with existing plant, for which severe accidents where not considered in the design. Thought developed for all type of plants, OSSA will also be applied on the EPR, with adaptations designed to take into account its favourable situation in that field. This revised approach will incorporate a number of new features which will simplify and streamline the guidance material while ensuring comprehensive guidance for response to any severe accident. Examples of such features include : - Identification of severe accident challenges based on plant specific studies. - Revision of the split of responsibilities between operations and technical support center staff. - Fixed setpoint entry conditions, ensuring that the transition from emergency procedures takes place at a consistent core/fuel condition (regardless of scenario), and which fixes the time window available to attempt ultimate preventive measures. - A safety function concept for monitoring plant conditions (in the control room). - An integrated graphic-based diagnostic tool including entry condition, challenge prioritization, and exit condition monitoring to be used by the technical support team. This paper describes the basic features of OSSA, and project status. (authors)

Sauvage, E. C.; Prior, R.; Coffey, K. [AREVA, FRAMATOME-ANP SAS, Paris, 92084 La Defense (France); Mazurkiewicz, S. M. [AREVA, FRAMATOME-ANP Inc, Lynchburg, VA 24506-0935 (United States)

2006-07-01T23:59:59.000Z

58

A CANDU Severe Accident Analysis  

Science Conference Proceedings (OSTI)

As interest in severe accident studies has increased in the last years, we have developed a set of simple models to analyze severe accidents for CANDU reactors that should be integrated in the EU codes. The CANDU600 reactor uses natural uranium fuel and heavy water (D2O) as both moderator and coolant, with the moderator and coolant in separate systems. We chose to analyze accident development for a LOCA with simultaneous loss of moderator cooling and the loss of emergency core cooling system (ECCS). This type of accident is likely to modify the reactor geometry and will lead to a severe accident development. When the coolant temperatures inside a pressure tube reaches 10000 deg C, a contact between pressure tube and calandria tube occurs and the residual heat is transferred to the moderator. Due to the lack of cooling, the moderator eventually begins to boil and is expelled, through the calandria vessel relief ducts, into the containment. Therefore the calandria tubes (fuel channels) will be uncovered, then will disintegrate and fall down to the calandria vessel bottom. After all the quantity of moderator is vaporized and expelled, the debris will heat up and eventually boil. The heat accumulated in the molten debris will be transferred through the calandria vessel wall to the shield tank water, which normally surrounds the calandria vessel. The phenomena described above are modelled, analyzed and compared with the existing data. The results are encouraging. (authors)

Negut, Gheorghe; Catana, Alexandru [Institute for Nuclear Research, 1, Compului Str., Mioveni, PO Box 78, 0300 Pitesti (Romania); Prisecaru, Ilie [University Politehnica Bucharest (Romania)

2006-07-01T23:59:59.000Z

59

T-730: Vulnerability in Citrix Provisioning Services could result in  

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

730: Vulnerability in Citrix Provisioning Services could result 730: Vulnerability in Citrix Provisioning Services could result in Arbitrary Code Execution T-730: Vulnerability in Citrix Provisioning Services could result in Arbitrary Code Execution September 29, 2011 - 8:30am Addthis PROBLEM: Vulnerability in Citrix Provisioning Services could result in Arbitrary Code Execution. PLATFORM: This vulnerability is present in all supported versions of Citrix Provisioning Services up to and including version 5.6 Service Pack 1. ABSTRACT: Citrix Provisioning Services is prone to a remote code-execution vulnerability. Successfully exploiting this issue will allow attackers to execute arbitrary code within the context of the application. reference LINKS: Citrix Document ID: CTX130846 Security Focus: Bugtraq ID 49803 IMPACT ASSESSMENT:

60

U-116: IBM Tivoli Provisioning Manager Express for Software Distribution  

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

6: IBM Tivoli Provisioning Manager Express for Software 6: IBM Tivoli Provisioning Manager Express for Software Distribution Multiple Vulnerabilities U-116: IBM Tivoli Provisioning Manager Express for Software Distribution Multiple Vulnerabilities March 5, 2012 - 7:00am Addthis PROBLEM: IBM Tivoli Provisioning Manager Express for Software Distribution Multiple Vulnerabilities PLATFORM: IBM Tivoli Provisioning Manager Express for Software Distribution 4.x ABSTRACT: Multiple vulnerabilities have been reported in IBM Tivoli Provisioning Manager Express for Software Distribution, which can be exploited by malicious people to conduct SQL injection attacks and compromise a user's system. reference LINKS: Secunia Advisory SA48216 CVE-2012-0198 CVE-2012-0199 IMPACT ASSESSMENT: High Discussion: Certain input passed via "Printer.getPrinterAgentKey" to the SoapServlet

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


61

Attachment D: Mandatory Provisions if Applicable | Department of Energy  

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

D: Mandatory Provisions if Applicable D: Mandatory Provisions if Applicable Attachment D: Mandatory Provisions if Applicable Mandatory Provisions if Applicable This attachment contains provisions that may be mandatory for an AIP if the State: (1) chooses to develop an emergency response program but does not want to use the suggested language in Attachment E; (2) receives DOE grant funding for both AIP and monitoring activities conducted under the Comprehensive Environmental Response, Compensation and Liability Act (CERCLA); and (3) if the parties anticipate that a state's sampling activities will generate hazardous waste mixed with radioactive materials. If emergency response activities will be included in a new or renegotiated AIP but the AIP does not incorporate the suggested model provisions related

62

Naval Spent Fuel Rail Shipment Accident Exercise Objectives ...  

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

Naval Spent Fuel Rail Shipment Accident Exercise Objectives Naval Spent Fuel Rail Shipment Accident Exercise Objectives Naval Spent Fuel Rail Shipment Accident Exercise Objectives...

63

Office of Inspector General report on inspection of selected issues regarding the Department of Energy accident investigation program  

Science Conference Proceedings (OSTI)

One method used by the Department of Energy (DOE) to promote worker safety is through the Department`s accident investigation program. The objectives of the program are, among other things, to enhance safety and health of employees, to prevent the recurrence of accidents, and to reduce accident fatality rates and promote a downward trend in the number and severity of accidents. The Assistant Secretary, Office of Environment, Safety and Health (EH), through the EH Office of the Deputy Assistant Secretary for Oversight, is responsible for implementation of the Department`s accident investigation program. As part of the inspection, the authors reviewed an April 1997 EH accident investigation report regarding an accident involving a Lockheed Martin Energy Systems (LMES) welder, who suffered fatal burns when his clothing caught fire while he was using a cutting torch at the Oak Ridge K-25 Site. They also reviewed reports of other accident investigations conducted by EH and DOE field organizations. Based on the review of these reports, the authors identified issues concerning the adequacy of the examination and reporting by accident investigation boards of specific management systems and organizations as a possible accident root cause. The inspection also identified issues concerning worker safety that they determined required immediate management attention, such as whether occurrences were being reported in the appropriate management systems and whether prompt consideration was being given to implementing revisions of national standards when the revisions increased worker safety.

NONE

1999-04-01T23:59:59.000Z

64

Summary of Major Energy Bill Provisions Affecting Federal Energy Managers  

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

of Major Energy Bill Provisions Affecting Federal Energy Managers of Major Energy Bill Provisions Affecting Federal Energy Managers Section Lead Agency Provisions 102. Energy management goals DOE * Annual energy reduction goal of 2% from FY 2006 - FY 2015 * Reporting baseline changed from 1985 to 2003 * In 180 days, DOE issues guidelines * Retention of energy and water savings by agencies * DOE reports annually on progress to the President and Congress

65

Summary of Major Energy Bill Provisions Affecting Federal Energy Managers  

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

of Major Energy Bill Provisions Affecting Federal Energy Managers of Major Energy Bill Provisions Affecting Federal Energy Managers Section Lead Agency Provisions 102. Energy management goals DOE * Annual energy reduction goal of 2% from FY 2006 - FY 2015 * Reporting baseline changed from 1985 to 2003 * In 180 days, DOE issues guidelines * Retention of energy and water savings by agencies * DOE reports annually on progress to the President and Congress

66

Pollution Prevention  

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

Pollution Prevention Pollution Prevention Pollution Prevention Promoting green purchasing, reuse and recycling, and the conservation of fuel, energy, and water. April 17, 2012 Pollution prevention and control at LANL Contact Environmental Communication & Public Involvement P.O. Box 1663 MS M996 Los Alamos, NM 87545 (505) 667-0216 Email Our goal is to reduce or eliminate waste whenever possible. Promoting pollution prevention to achieve sustainability Our commitment to environmental stewardship and sustainability helps us accomplish our work in a manner that is socially responsible, economically sound, and protective of the environment. The goal of the Laboratory's pollution prevention efforts is to reduce or eliminate waste whenever possible. However, when waste elimination is not

67

Intellectual Property Provisions (CSB-1003) Cooperative Agreement Research,  

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

Intellectual Property Provisions (CSB-1003) Cooperative Agreement Intellectual Property Provisions (CSB-1003) Cooperative Agreement Research, Development, or Demonstration Domestic Small Businesses Intellectual Property Provisions (CSB-1003) Cooperative Agreement Research, Development, or Demonstration Domestic Small Businesses 01. FAR 52.227-1 Authorization and Consent (JUL 1995)-Alternate I (APR 1984) 02. FAR 52.227-2 Notice and Assistance Regarding Patent and Copyright Infringement (AUG 1996) This clause is not applicable if the award is for less than $100,000, in aggregate. NOTE: In reading these provisions, any reference to "contractor" shall mean "recipient," and any reference to "contract" or "subcontract" shall mean "award" or "subaward." CSB-1003.PDF�

68

10 CFR 835 Subpart A - GEneral Provisions  

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

November 28, 2006 November 28, 2006 10 CFR 835 Subpart A - General Provisions § 835.1 Scope. (a) General. The rules in this part establish radiation protection standards, limits, and program requirements for protecting individuals from ionizing radiation resulting from the conduct of DOE activities. (b) Exclusion. Except as discussed in paragraph (c) of this section, the requirements in this part do not apply to: (1) Activities that are regulated through a license by the Nuclear Regulatory Commission or a State under an Agreement with the Nuclear Regulatory Commission, including activities certified by the Nuclear Regulatory Commission under section 1701 of the Atomic Energy Act; (2) Activities conducted under the authority of the Deputy Administrator for Naval Reactors,

69

Severe Accident Management Guidance Technical Basis Report  

Science Conference Proceedings (OSTI)

Guidance to aid operating crews in responding to a severe core damage accident was first developed as a response to the 1979 accident at Three Mile Island Unit 2. This guidance encompasses those actions that could be considered to arrest the progression of a core damage accident or to limit the extent of resulting releases of fission products. The original guidance was developed in a logical manner, starting with compiling the best information regarding severe-accident phenomena available at that ...

2012-10-31T23:59:59.000Z

70

Pollution Prevention  

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

Pollution Prevention Pollution Prevention Goal 5: Pollution Prevention LANL is dedicated to finding ways to reduce waste, prevent pollution, and recycle waste that cannot be reduced. Energy Conservation» Efficient Water Use & Management» High Performance Sustainable Buildings» Greening Transportation» Green Purchasing & Green Technology» Pollution Prevention» Science Serving Sustainability» ENVIRONMENTAL SUSTAINABILITY GOALS at LANL Technical Area 21: Water was sprayed during the demolition of 24 Cold War-era buildings at TA-21 to protect air quality. Recycling metal from the buildings at Technical Area 21 saved LANL from generating more than 3300 cubic yards of waste. Skilled excavator operator Gilbert Pacheco extracts an extra 16 tons of recyclable metal at Technical Area 21. Energy efficient LED lights were installed in the Occupational Medicine facility to lower costs and improve lighting conditions.

71

Evolvable neural networks ensembles for accidents diagnosis  

Science Conference Proceedings (OSTI)

Prediction and diagnosis of nuclear accidents is one of the most important tasks for nuclear safety. Since accurate diagnosis of nuclear accident is a very important issue for avoidance of disastrous outcomes, it is more desirable to make a decision ... Keywords: ensembles, neuroevolution, nuclear accidents

Hany Sallam; Carlo S. Regazzoni; Ihab Talkhan; Amir Atiya

2008-07-01T23:59:59.000Z

72

Why Mobile Wireless Carriers Share Networks and Services Provisioning  

Science Conference Proceedings (OSTI)

This paper provides a theory that empirically examines why mobile wireless carriers share the costs of building networks and provisioning wireless services. Of the cost drivers of network operators, the most influential on the industry's dynamics are ... Keywords: Active and Passive Infrastructure, Backhaul, Coverage, Network Sharing, Next-Generation Networks, Spectrum, Wireless Services Provisioning

Hemant K. Sabat

2010-07-01T23:59:59.000Z

73

Provisioning Virtual Resources Adaptively in Elastic Compute Cloud Platforms  

Science Conference Proceedings (OSTI)

Provisioning Virtual machines on demand is significant in elastic compute cloud for reliable service delivery. The importance and major difficulty lies in satisfying the conflicting objectives of satisfying contracted service level agreement while lowering ... Keywords: Dynamic Resource Provision, Multi-Tier Applications, Virtual Machines, Virtualized Cloud Platform

Fan Zhang; Junwei Cao; Hong Cai; Cheng Wu

2011-07-01T23:59:59.000Z

74

U-161: Citrix Provisioning Services Unspecified Flaw Lets Remote Users  

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

1: Citrix Provisioning Services Unspecified Flaw Lets Remote 1: Citrix Provisioning Services Unspecified Flaw Lets Remote Users Execute Arbitrary Code U-161: Citrix Provisioning Services Unspecified Flaw Lets Remote Users Execute Arbitrary Code May 3, 2012 - 7:00am Addthis PROBLEM: Citrix Provisioning Services Unspecified Flaw Lets Remote Users Execute Arbitrary Code PLATFORM: 6.1 and prior ABSTRACT: A vulnerability was reported in Citrix Provisioning Services. A remote user can execute arbitrary code on the target system. reference LINKS: SecurityTracker Alert ID: 1027004 Secunia Advisory SA48971 Citrix advisory IMPACT ASSESSMENT: Medium Discussion: A remote user can send a specially crafted packet to trigger an unspecified flaw and execute arbitrary code on the target system. The code will run with the privileges of the target service.

75

ACCIDENT ANALYSES & CONTROL OPTIONS IN SUPPORT OF THE SLUDGE WATER SYSTEM SAFETY ANALYSIS  

Science Conference Proceedings (OSTI)

This report documents the accident analyses and nuclear safety control options for use in Revision 7 of HNF-SD-WM-SAR-062, ''K Basins Safety Analysis Report'' and Revision 4 of HNF-SD-SNF-TSR-001, ''Technical Safety Requirements - 100 KE and 100 KW Fuel Storage Basins''. These documents will define the authorization basis for Sludge Water System (SWS) operations. This report follows the guidance of DOE-STD-3009-94, ''Preparation Guide for US. Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports'', for calculating onsite and offsite consequences. The accident analysis summary is shown in Table ES-1 below. While this document describes and discusses potential control options to either mitigate or prevent the accidents discussed herein, it should be made clear that the final control selection for any accident is determined and presented in HNF-SD-WM-SAR-062.

WILLIAMS, J.C.

2003-11-15T23:59:59.000Z

76

K Basins floor sludge retrieval system knockout pot basket fuel burn accident  

SciTech Connect

The K Basins Sludge Retrieval System Preliminary Hazard Analysis Report (HNF-2676) identified and categorized a series of potential accidents associated with K Basins Sludge Retrieval System design and operation. The fuel burn accident was of concern with respect to the potential release of contamination resulting from a runaway chemical reaction of the uranium fuel in a knockout pot basket suspended in the air. The unmitigated radiological dose to an offsite receptor from this fuel burn accident is calculated to be much less than the offsite risk evaluation guidelines for anticipated events. However, because of potential radiation exposure to the facility worker, this accident is precluded with a safety significant lifting device that will prevent the monorail hoist from lifting the knockout pot basket out of the K Basin water pool.

HUNT, J.W.

1998-11-11T23:59:59.000Z

77

Advance Network Reservation and Provisioning for Science  

Science Conference Proceedings (OSTI)

We are witnessing a new era that offers new opportunities to conduct scientific research with the help of recent advancements in computational and storage technologies. Computational intensive science spans multiple scientific domains, such as particle physics, climate modeling, and bio-informatics simulations. These large-scale applications necessitate collaborators to access very large data sets resulting from simulations performed in geographically distributed institutions. Furthermore, often scientific experimental facilities generate massive data sets that need to be transferred to validate the simulation data in remote collaborating sites. A major component needed to support these needs is the communication infrastructure which enables high performance visualization, large volume data analysis, and also provides access to computational resources. In order to provide high-speed on-demand data access between collaborating institutions, national governments support next generation research networks such as Internet 2 and ESnet (Energy Sciences Network). Delivering network-as-a-service that provides predictable performance, efficient resource utilization and better coordination between compute and storage resources is highly desirable. In this paper, we study network provisioning and advanced bandwidth reservation in ESnet for on-demand high performance data transfers. We present a novel approach for path finding in time-dependent transport networks with bandwidth guarantees. We plan to improve the current ESnet advance network reservation system, OSCARS [3], by presenting to the clients, the possible reservation options and alternatives for earliest completion time and shortest transfer duration. The Energy Sciences Network (ESnet) provides high bandwidth connections between research laboratories and academic institutions for data sharing and video/voice communication. The ESnet On-Demand Secure Circuits and Advance Reservation System (OSCARS) establishes guaranteed bandwidth of secure virtual circuits at a certain time, for a certain bandwidth and length of time. Though OSCARS operates within the ESnet, it also supplies end-to-end provisioning between multiple autonomous network domains. OSCARS gets reservation requests through a standard web service interface, and conducts a Quality-of-service (QoS) path for bandwidth guarantees. Multi-protocol Label Switching (MPLS) and the Resource Reservation Protocol (RSVP) enable to create a virtual circuit using Label Switched Paths (LSP's). It contains three main components: a reservation manager, a bandwidth scheduler, and a path setup subsystem. The bandwidth scheduler needs to have information about the current and future states of the network topology in order to accomplish end-to-end bandwidth guaranteed paths.

Balman, Mehmet; Chaniotakis, Evangelos; Shoshani, Arie; Sim, Alex

2009-07-10T23:59:59.000Z

78

Severe Accident Management Guidance Technical Basis Report: Volumes 1 and 2  

Science Conference Proceedings (OSTI)

Severe accident management guidance encompasses actions that would be taken to recover from a damaged core condition and to prevent or mitigate the release of fission products. This report provides the technical basis for developing such guidance by the nuclear steam supply system owners groups.

1993-04-01T23:59:59.000Z

79

Investigation of hydrogen stratification and its application for the assessment of containment failure modes for a BWR Mark III containment during core meltdown accidents  

DOE Green Energy (OSTI)

The BNL staff have performed an extensive assessment of potential failure modes for core meltdown accidents in a Boiling Water Reactor (BWR) with a Mark III containment. The particular Mark III containment under consideration did not initially include provision for any system to control H/sub 2/ burning, so that H/sub 2/ phenomena were found to be dominant contributors to containment failure. However, all Mark III containments will now have provisions for the control of H/sub 2/ burning, which will influence our current assessment of H/sub 2/ phenomena.

Jaung, R.; Pratt, W.T.

1985-01-01T23:59:59.000Z

80

Public Service Companies, General Provisions (Virginia) | Department of  

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

Service Companies, General Provisions (Virginia) Service Companies, General Provisions (Virginia) Public Service Companies, General Provisions (Virginia) < Back Eligibility Agricultural Commercial Construction Developer Fuel Distributor Industrial Installer/Contractor Investor-Owned Utility Local Government Municipal/Public Utility Rural Electric Cooperative State/Provincial Govt Systems Integrator Transportation Tribal Government Utility Savings Category Alternative Fuel Vehicles Hydrogen & Fuel Cells Buying & Making Electricity Water Home Weatherization Solar Wind Program Info State Virginia Program Type Safety and Operational Guidelines Siting and Permitting Provider Virginia State Corporation Commission Public Service Companies includes gas, pipeline, electric light, heat, power and water supply companies, sewer companies, telephone companies, and

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


81

Waters; General Provisions (North Dakota) | Department of Energy  

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

Waters; General Provisions (North Dakota) Waters; General Provisions (North Dakota) Waters; General Provisions (North Dakota) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Savings Category Water Buying & Making Electricity Program Info State North Dakota Program Type Siting and Permitting The waters of North Dakota are understood as belonging to the public and may be appropriated for beneficial uses. However, the right to use water in

82

Cold Vacuum Drying facility design basis accident analysis documentation  

SciTech Connect

This document provides the detailed accident analysis to support HNF-3553, Annex B, Spent Nuclear Fuel Project Final Safety Analysis Report (FSAR), ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the FSAR. The calculations in this document address the design basis accidents (DBAs) selected for analysis in HNF-3553, ''Spent Nuclear Fuel Project Final Safety Analysis Report'', Annex B, ''Cold Vacuum Drying Facility Final Safety Analysis Report.'' The objective is to determine the quantity of radioactive particulate available for release at any point during processing at the Cold Vacuum Drying Facility (CVDF) and to use that quantity to determine the amount of radioactive material released during the DBAs. The radioactive material released is used to determine dose consequences to receptors at four locations, and the dose consequences are compared with the appropriate evaluation guidelines and release limits to ascertain the need for preventive and mitigative controls.

CROWE, R.D.

2000-08-08T23:59:59.000Z

83

Improved Algorithm and Simulation of the Provision Refrigerating Unit  

Science Conference Proceedings (OSTI)

The dynamic model of reciprocating provision cooling plant is presented, and the algorithm of the model is amended, through the method of quoting an unknown variable, which is enthalpy of the refrigerant at the compressor outlet. Dynamic simulation of ...

HE Zhi-bin; ZHANG Jun-dong; SUN Yu-qing; ZENG Hong; GAN Hui-bing

2007-09-01T23:59:59.000Z

84

Oil and Gas Wells: Regulatory Provisions (Kansas) | Department of Energy  

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

Oil and Gas Wells: Regulatory Provisions (Kansas) Oil and Gas Wells: Regulatory Provisions (Kansas) Oil and Gas Wells: Regulatory Provisions (Kansas) < Back Eligibility Commercial Fuel Distributor Investor-Owned Utility Municipal/Public Utility Rural Electric Cooperative Utility Program Info State Kansas Program Type Environmental Regulations Provider Health and Environment It shall be unlawful for any person, firm or corporation having possession or control of any natural gas well, oil well or coalbed natural gas well, whether as a contractor, owner, lessee, agent or manager, to use or permit the use of gas by direct well pressure. Any person or persons, firm, company or corporation violating any of the provisions of this act shall be deemed guilty of a misdemeanor, and upon conviction shall be fined in any

85

Standard Intellectual Property (IP) Provisions for Financial Assistance  

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

Standard Intellectual Property (IP) Provisions for Financial Standard Intellectual Property (IP) Provisions for Financial Assistance Awards Standard Intellectual Property (IP) Provisions for Financial Assistance Awards Click on Set Number to Access Provisions: Type of Award Type of Project Special Data Statute e.g., EPACT) Type of Recipient Set Number (PDF) Cooperative Agreement Research, Development, or Demonstration (RD&D) No Domestic Small Business CSB-1003 Cooperative Agreement RD&D Yes Domestic Small Business CDSB-1003 Cooperative Agreement RD&D No Large Business, State or Local Government, and Foreign Entity CLB-1003 Cooperative Agreement RD&D Yes Large Business, State or Local Government, and Foreign Entity CDLB-1003 Grant RD&D No Domestic Small Business GSB-1003 Grant RD&D Yes Domestic Small Business GDSB-1003

86

Attachment A.1: Summary of Mandatory Language Provisions | Department of  

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

A.1: Summary of Mandatory Language Provisions A.1: Summary of Mandatory Language Provisions Attachment A.1: Summary of Mandatory Language Provisions SUMMARY OF MANDATORY LANGUAGE PROVISIONS 1. Regulatory and non-regulatory activities "The parties to this Agreement further understand that the oversight activities authorized by this Agreement are intended to supplement activities conducted under applicable environmental laws and regulations, but not to support specific State regulatory, permitting, and legally-required environmental oversight activities, such as issuance of regulatory permits, the review of DOE regulatory submissions when such review serves primarily as the basis for State action under regulatory programs, required regulatory inspections, required monitoring, issuance of regulatory notices of violation and other citations, nor to support the

87

Special Provisions Affecting Gas, Water, or Pipeline Companies (South Carolina)  

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

This legislation confers the rights and privileges of telegraph and telephone companies (S.C. Code 58-9) on pipeline and water companies, and contains several additional provisions pertaining to...

88

Elastic service availability: utility framework and optimal provisioning  

Science Conference Proceedings (OSTI)

Service availability is one of the most closely scrutinized metrics in offering network services. It is important to cost- effectively provision a managed and differentiated network with various service availability guarantees under a unified platform. ...

Dahai Xu; Ying Li; Mung Chiang; A. Calderbank

2008-08-01T23:59:59.000Z

89

Diversity, Social Goods Provision, and Performance in the Firm  

E-Print Network (OSTI)

The last decade has seen a growing interest among economists on the effect of diversity on the provision of social goods and the stock of social capital. Indeed, in the workplace, cooperation, trust, and other social goods ...

Ellison, Sara

2010-08-31T23:59:59.000Z

90

Bodman Statement On Senate Approval of ANWR Provisions | Department of  

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

Bodman Statement On Senate Approval of ANWR Provisions Bodman Statement On Senate Approval of ANWR Provisions Bodman Statement On Senate Approval of ANWR Provisions March 16, 2005 - 10:50am Addthis Washington, DC - Energy Secretary Samuel W. Bodman released the following statement today regarding Senate approval of ANWR provisions in the budget resolution: "The Senate's vote today to clear the way for environmentally responsible oil and gas exploration in a small portion of ANWR is a victory for American consumers, America's economy and America's energy security. "Alaska's frozen tundra has the potential to yield billions of barrels of domestically produced oil. Not only could these resources have a meaningful impact on our dependence on imported sources of oil; this means American jobs producing American oil for Americans.

91

Computerized Accident/Incident Reporting System  

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

Accident Recordkeeping and Reporting Accident Recordkeeping and Reporting Accident/Incident Recordkeeping and Reporting CAIRS logo Computerized Accident Incident Reporting System CAIRS Database The Computerized Accident/Incident Reporting System is a database used to collect and analyze DOE and DOE contractor reports of injuries, illnesses, and other accidents that occur during DOE operations. Injury and Illness Dashboard The Dashboard provides an alternate interface to CAIRS information. The initial release of the Dashboard allows analysis of composite DOE-wide information and summary information by Program Office, and site. Additional data feature are under development. CAIRS Registration Form CAIRS is a Government computer system and, as such, has security requirements that must be followed. Access to the

92

Executive Director for Operations FINAL RULE ON DECOMMISSIONING TRUST PROVISIONS  

E-Print Network (OSTI)

To request Commission approval to publish in the Federal Register a final rule on decommissioning trust provisions. BACKGROUND: The staff submitted Proposed Rule on Decommissioning Trust Provisions, (SECY-01-0049) to the Commission on March 23, 2001. The Commission issued a staff requirements memorandum (SRM) on April 20, 2001, approving publication of the proposed rule. The proposed rule was published in the Federal Register on May 30, 2001 (66 FR 29244). The staff issued

William D. Travers; Brian Richter Nrr/drip/rprp

2002-01-01T23:59:59.000Z

93

Accident investigation of the electrical shock incident at the PG and E PVUSA site Davis, California  

DOE Green Energy (OSTI)

This report summarizes the findings of the Accident Investigation Team (Team) assembled in response to a request from Pacific Gas and Electric Company (PG and E) to the US Department of Energy (DOE) to understand the events surrounding the electric shock of a worker at the PVUSA site in Davis, California and to provide recommendations to prevent such events from recurring. The report gives complete details on the sequence of events surrounding the accident and identifies 27 facts related to accident itself. Four technical deficiencies in the electrical systems which require further investigation were identified. The Team believes that the root cause of this accident was related to the absence of a proactive organizational entity responsible for overall health and safety on the site. Two contributing factors were identified. First, the prototype nature and associated operational difficulties of the electrical inverter resulted in large maintenance demands. Second, several of the injured employee`s co-workers noted that he occasionally failed to use appropriate personal protective equipment, but they never reported this practice to management. The direct cause of this accident was the failure of the injured employee to wear appropriate personal protective equipment (i.e., rubber gloves). Based on the review of the facts established in this investigation, five recommendations are presented to the funding agencies to reduce the possibility of future accidents at the PVUSA site.

Jacobson, L.; Moskowitz, P.D.; Garrett, J.O.; Tyler, R.

1992-02-01T23:59:59.000Z

94

Recommendations for Analyzing Accidents Under NEPA  

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

This DOE guidance clarifies and supplements "Recommendations for the Preparation of Environmental Assessments and Environmental Impact Statements." It focuses on principles of accident analyses under NEPA.

95

Accident Tolerant Fuels for Light Water Reactors  

Science Conference Proceedings (OSTI)

Presentation Title, Accident Tolerant Fuels for Light Water Reactors. Author(s), Steven J. Zinkle, Kurt A. Terrani, Lance L. Snead. On-Site Speaker (Planned)...

96

Systematics of Reconstructed Process Facility Criticality Accidents  

SciTech Connect

The systematics of the characteristics of twenty-one criticality accidents occurring in nuclear processing facilities of the Russian Federation, the United States, and the United Kingdom are examined. By systematics the authors mean the degree of consistency or agreement between the factual parameters reported for the accidents and the experimentally known conditions for criticality. The twenty-one reported process criticality accidents are not sufficiently well described to justify attempting detailed neutronic modeling. However, results of classic hand calculations confirm the credibility of the reported accident conditions.

Pruvost, N.L.; McLaughlin, T.P.; Monahan, S.P.

1999-09-19T23:59:59.000Z

97

ORISE: REAC/TS Radiation Accident Registries  

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

Accident Registries The Radiation Emergency Assistance CenterTraining Site (REACTS) at the Oak Ridge Institute for Science and Education (ORISE) maintains a number of radiation...

98

Accident Investigation Report Plutonium Contamination in the...  

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

Accident Investigation Report Plutonium Contamination in the Zero Power Physics Reactor Facility at the Idaho National Laboratory, November 8, 2011 January 2012 Disclaimer...

99

Markov Model of Severe Accident Progression and Management  

SciTech Connect

The earthquake and tsunami that hit the nuclear power plants at the Fukushima Daiichi site in March 2011 led to extensive fuel damage, including possible fuel melting, slumping, and relocation at the affected reactors. A so-called feed-and-bleed mode of reactor cooling was initially established to remove decay heat. The plan was to eventually switch over to a recirculation cooling system. Failure of feed and bleed was a possibility during the interim period. Furthermore, even if recirculation was established, there was a possibility of its subsequent failure. Decay heat has to be sufficiently removed to prevent further core degradation. To understand the possible evolution of the accident conditions and to have a tool for potential future hypothetical evaluations of accidents at other nuclear facilities, a Markov model of the state of the reactors was constructed in the immediate aftermath of the accident and was executed under different assumptions of potential future challenges. This work was performed at the request of the U.S. Department of Energy to explore 'what-if' scenarios in the immediate aftermath of the accident. The work began in mid-March and continued until mid-May 2011. The analysis had the following goals: (1) To provide an overall framework for describing possible future states of the damaged reactors; (2) To permit an impact analysis of 'what-if' scenarios that could lead to more severe outcomes; (3) To determine approximate probabilities of alternative end-states under various assumptions about failure and repair times of cooling systems; (4) To infer the reliability requirements of closed loop cooling systems needed to achieve stable core end-states and (5) To establish the importance for the results of the various cooling system and physical phenomenological parameters via sensitivity calculations.

Bari, R.A.; Cheng, L.; Cuadra,A.; Ginsberg,T.; Lehner,J.; Martinez-Guridi,G.; Mubayi,V.; Pratt,W.T.; Yue, M.

2012-06-25T23:59:59.000Z

100

A review of monitoring, sampling and analysis of reactor coolant, reactor containment atmosphere and airborne reactor effluents in post accident concentrations  

Science Conference Proceedings (OSTI)

A post-implementation review has been made in NRC Region I of the post-accident sampling systems (PASS), the gaseous effluent monitors, and the provisions for sampling effluent particulates and radioiodines which were required by the NRC subsequent to the TMI-2 accident (NUREG-0737). Prefabricated PASS systems were predominant. Problems included insufficient purge times, inadequate separation of dissolved gases, excessive dilution and the accuracy of analytical techniques in the presence of interferences. Microprocessor-controlled high-range gas monitors with integral provisions for sampling particulates and radioiodines in high concentrations were widely used. Calibration information was generally insufficient for the unambiguous conversion of monitor readings to release rates for a varying postaccident mixture of radiogases. The referenced sampling guidance (ANSI-N 13.1-1969) was inappropriate for the long sampling lines customarily used. Generic research is needed to establish the behavior of particulates and radioiodines in these lines.

Hull, A.P.; White, J.R.; Knox, W.H.

1986-01-01T23:59:59.000Z

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


101

Hydrogen-control systems for severe LWR accident conditions - a state-of-technology report  

Science Conference Proceedings (OSTI)

This report reviews the current state of technology regarding hydrogen safety issues in light water reactor plants. Topics considered in this report relate to control systems and include combustion prevention, controlled combustion, minimization of combustion effects, combination of control concepts, and post-accident disposal. A companion report addresses hydrogen generation, distribution, and combustion. The objectives of the study were to identify the key safety issues related to hydrogen produced under severe accident conditions, to describe the state of technology for each issue, and to point out ongoing programs aimed at resolving the open issues.

Hilliard, R.K.; Postma, A.K.; Jeppson, D.W.

1983-03-01T23:59:59.000Z

102

The Hartford Life and Accident Insurance  

E-Print Network (OSTI)

The Hartford Life and Accident Insurance Company Group Numbers Basic Group Term Life AD&D-677984 Life and Accident Insurance Company. (Referred to as The Hartford or Hartford.) General information industry. Europ Assist has been helping customers in times of crisis for more than 46 years. They have

103

Does Daylight Savings Time Affect Traffic Accidents?  

E-Print Network (OSTI)

This paper studies the effect of changes in accident pattern due to Daylight Savings Time (DST). The extension of the DST in 2007 provides a natural experiment to determine whether the number of traffic accidents is affected by shifts in hours of daylight using the year as control group. Using data on traffic accidents in Texas based on crash reports provided by the Texas Transportation Institute, and a difference in differences technique, this study creates a regression model to determine how significant this factor is in affecting traffic accident patterns as observed in the data. Results show that DST has no statistically significant effect on traffic accidents of all categories including (but not limited to) highway, non-highway, and accidents, accidents with injuries and no injuries, and accidents by drivers of all age-groups. This implies that the federal governments policy of DST (and its extension) has no costs incurred by a rise in motor vehicle crashes when it gets dark early.

Deen, Sophia 1988-

2012-05-01T23:59:59.000Z

104

Accident states simulation: process fluids release  

Science Conference Proceedings (OSTI)

Seveso II Directive imposes for high hazardous plants quantitative risk evaluation of the major accident. In a general context the risk is defined as product between frequency and consequences of accident state. There are five steps in quantitative risk ... Keywords: hazard, hydrogen sulphide, mathematical model, release, risk, safety system, simulation

Cornelia Croitoru; Mihai Anghel; Floarea Pop; Ioan Stefanescu; Gheorghe Titescu; Mihai Patrascu; Ervin Watzlawek; Dorin Cheresdi

2008-08-01T23:59:59.000Z

105

RADIOACTIVE WASTE MANAGEMENT IN THE CHERNOBYL EXCLUSION ZONE - 25 YEARS SINCE THE CHERNOBYL NUCLEAR POWER PLANT ACCIDENT  

Science Conference Proceedings (OSTI)

Radioactive waste management is an important component of the Chernobyl Nuclear Power Plant accident mitigation and remediation activities of the so-called Chernobyl Exclusion Zone. This article describes the localization and characteristics of the radioactive waste present in the Chernobyl Exclusion Zone and summarizes the pathways and strategy for handling the radioactive waste related problems in Ukraine and the Chernobyl Exclusion Zone, and in particular, the pathways and strategies stipulated by the National Radioactive Waste Management Program. The brief overview of the radioactive waste issues in the ChEZ presented in this article demonstrates that management of radioactive waste resulting from a beyond-designbasis accident at a nuclear power plant becomes the most challenging and the costliest effort during the mitigation and remediation activities. The costs of these activities are so high that the provision of radioactive waste final disposal facilities compliant with existing radiation safety requirements becomes an intolerable burden for the current generation of a single country, Ukraine. The nuclear accident at the Fukushima-1 NPP strongly indicates that accidents at nuclear sites may occur in any, even in a most technologically advanced country, and the Chernobyl experience shows that the scope of the radioactive waste management activities associated with the mitigation of such accidents may exceed the capabilities of a single country. Development of a special international program for broad international cooperation in accident related radioactive waste management activities is required to handle these issues. It would also be reasonable to consider establishment of a dedicated international fund for mitigation of accidents at nuclear sites, specifically, for handling radioactive waste problems in the ChEZ. The experience of handling Chernobyl radioactive waste management issues, including large volumes of radioactive soils and complex structures of fuel containing materials can be fairly useful for the entire world's nuclear community and can help make nuclear energy safer.

Farfan, E.; Jannik, T.

2011-10-01T23:59:59.000Z

106

Commercial SNF Accident Release Fractions  

Science Conference Proceedings (OSTI)

The purpose of this analysis is to specify and document the total and respirable fractions for radioactive materials that could be potentially released from an accident at the repository involving commercial spent nuclear fuel (SNF) in a dry environment. The total and respirable release fractions are used to support the preclosure licensing basis for the repository. The total release fraction is defined as the fraction of total commercial SNF assembly inventory, typically expressed as an activity inventory (e.g., curies), of a given radionuclide that is released to the environment from a waste form. Radionuclides are released from the inside of breached fuel rods (or pins) and from the detachment of radioactive material (crud) from the outside surfaces of fuel rods and other components of fuel assemblies. The total release fraction accounts for several mechanisms that tend to retain, retard, or diminish the amount of radionuclides that are available for transport to dose receptors or otherwise can be shown to reduce exposure of receptors to radiological releases. The total release fraction includes a fraction of airborne material that is respirable and could result in inhalation doses; this subset of the total release fraction is referred to as the respirable release fraction. Accidents may involve waste forms characterized as: (1) bare unconfined intact fuel assemblies, (2) confined intact fuel assemblies, or (3) canistered failed commercial SNF. Confined intact commercial SNF assemblies at the repository are contained in shipping casks, canisters, or waste packages. Four categories of failed commercial SNF are identified: (1) mechanically and cladding-penetration damaged commercial SNF, (2) consolidated/reconstituted assemblies, (3) fuel rods, pieces, and debris, and (4) nonfuel components. It is assumed that failed commercial SNF is placed into waste packages with a mesh screen at each end (CRWMS M&O 1999). In contrast to bare unconfined fuel assemblies, the container that confines the fuel assemblies could provide an additional barrier for diminishing the total release fraction should the fuel rod cladding breach during an accident. This analysis, however, does not take credit for the additional barrier and establishes only the total release fractions for bare unconfined intact commercial SNF assemblies, which may be conservatively applied to confined intact commercial I SNF assemblies.

J. Schulz

2004-11-05T23:59:59.000Z

107

The Fukushima Daiichi Accident Study Information Portal  

SciTech Connect

This paper presents a description of The Fukushima Daiichi Accident Study Information Portal. The Information Portal was created by the Idaho National Laboratory as part of joint NRC and DOE project to assess the severe accident modeling capability of the MELCOR analysis code. The Fukushima Daiichi Accident Study Information Portal was created to collect, store, retrieve and validate information and data for use in reconstructing the Fukushima Daiichi accident. In addition to supporting the MELCOR simulations, the Portal will be the main DOE repository for all data, studies and reports related to the accident at the Fukushima Daiichi nuclear power station. The data is stored in a secured (password protected and encrypted) repository that is searchable and accessible to researchers at diverse locations.

Shawn St. Germain; Curtis Smith; David Schwieder; Cherie Phelan

2012-11-01T23:59:59.000Z

108

Web Based Course: SAF-230DE, Accident Investigation Overview...  

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

Web Based Course: SAF-230DE, Accident Investigation Overview Promotional Video Web Based Course: SAF-230DE, Accident Investigation Overview Promotional Video September 20, 2013 -...

109

ORISE: The Medical Basis for Radiation-Accident Preparedness...  

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

The Medical Basis for Radiation-Accident Preparedness: Medical Management Proceedings of the Fifth International REACTS Symposium on the Medical Basis for Radiation-Accident...

110

Audit of the Department of Energy's Transportation Accident Resistant...  

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

Transportation Accident Resistant Container Program, IG-0380 Audit of the Department of Energy's Transportation Accident Resistant Container Program, IG-0380 Audit of the...

111

Microsoft Word - Intellectual Property Provisions _NRD-1003_.doc  

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

Intellectual Property Provisions (NRD-1003) Intellectual Property Provisions (NRD-1003) Nonresearch and Development Nonprofit organizations are subject to the intellectual property requirements at 10 CFR 600.136(a), (c) and (d). For all other organizations, the following intellectual property provisions shall apply: (a) Recipients may copyright any work that is subject to copyright and was developed, or for which ownership was purchased, under an award. DOE reserves a royalty- free, nonexclusive and irrevocable right to reproduce, publish or otherwise use the work for Federal purposes and to authorize others to do so. (b) The DOE has the right to: (1) obtain, reproduce, publish or otherwise use the data first produced under an award; and (2) authorize others to receive, reproduce,

112

Energy Department Seeks Public Comment on Standby Support Provisions of  

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

Seeks Public Comment on Standby Support Seeks Public Comment on Standby Support Provisions of Energy Policy Act of 2005 Energy Department Seeks Public Comment on Standby Support Provisions of Energy Policy Act of 2005 November 17, 2005 - 2:49pm Addthis Workshop is first step to develop regulation for risk insurance for nuclear plants WASHINGTON, DC -- The U.S. Department of Energy (DOE) announced today that a workshop to receive public comments on the "standby support" provisions of the Energy Policy Act of 2005 has been scheduled for December 15, 2005. The workshop is the first step in developing a regulation for risk insurance for nuclear power plants and will be held from 8:30 a.m. - 12:00 p.m. and from 1:00 p.m. - 5:00 p.m. at the Marriott Residence Inn in Bethesda, Maryland. Standby support, or, "risk insurance," for new nuclear power plants is a

113

Dynamic Deferral of Workload for Capacity Provisioning in Data Centers  

E-Print Network (OSTI)

Recent increase in energy prices has led researchers to find better ways for capacity provisioning in data centers to reduce energy wastage due to the variation in workload. This paper explores the opportunity for cost saving and proposes a novel approach for capacity provisioning under bounded latency requirements for the workload. We investigate how many servers to be kept active and how much workload to be delayed for energy saving while meeting every deadline. We present an offline LP formulation for capacity provisioning by dynamic deferral and give two online algorithms to determine the capacity of the data center and the assignment of workload to servers dynamically. We prove the feasibility of the online algorithms and show that their worst case performance are bounded by a constant factor with respect to the offline formulation. We validate our algorithms on synthetic workload generated from two real HTTP traces and show that they actually perform much better in practice than the worst case, resultin...

Adnan, Muhammad Abdullah; Sugihara, Ryo; Gupta, Rajesh

2011-01-01T23:59:59.000Z

114

Pollution Prevention Awards  

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

Pollution Prevention Awards Pollution Prevention Awards Pollution Prevention awards are presented each year for minimized waste, conserved resources, and other sustainable...

115

Exploring Power-Efficient Provisioning for Online Virtual Network Requests  

Science Conference Proceedings (OSTI)

In the paradigm of cloud computing, multiple users can share the cloud infrastructure resources. The application or service requests from a user can be abstracted as a virtual network (VN) request and submitted to the cloud-based data centers. How to ... Keywords: power efficien, provisioning, virtual network request, embedding, datacenters

Gang Sun, Hongfang Yu, Vishal Anand, Dan Liao, Lemin Li

2012-10-01T23:59:59.000Z

116

Power provisioning for a warehouse-sized computer  

Science Conference Proceedings (OSTI)

Large-scale Internet services require a computing infrastructure that can beappropriately described as a warehouse-sized computing system. The cost ofbuilding datacenter facilities capable of delivering a given power capacity tosuch a computer can rival ... Keywords: energy efficiency, power modeling, power provisioning

Xiaobo Fan; Wolf-Dietrich Weber; Luiz Andre Barroso

2007-06-01T23:59:59.000Z

117

Prosumerization of Mobile Service Provision: A Conceptual Approach  

Science Conference Proceedings (OSTI)

Prosumerization is the enabling of users to act as producers. Prosumerization of content for the mobile internet, in which users are consumers and producers of content, is a recent trend. However, user-generated mobile services are the next big step ... Keywords: Mass Customization, Mobile Services, Prosumer, Service Provision, User-Centricity

Dirk Werth; Andreas Emrich; Alexandra Chapko

2011-10-01T23:59:59.000Z

118

Renewable energy provisioning for ICT services in a future internet  

Science Conference Proceedings (OSTI)

As one of the first worldwide initiatives provisioning ICT (Information and Communication Technologies) services entirely based on renewable energy such as solar, wind and hydroelectricity across Canada and around the world, the GreenStar Network (GSN) ... Keywords: Mantychore FP7, future internet, green ICT, green star network

Kim Khoa Nguyen; Mohamed Cheriet; Mathieu Lemay; Bill St. Arnaud; Victor Reijs; Andrew Mackarel; Pau Minoves; Alin Pastrama; Ward Van Heddeghem

2011-01-01T23:59:59.000Z

119

Analyses of Selected Provisions of Proposed Energy Legislation: 2003  

Reports and Publications (EIA)

This study responds to a July 31, 2003 request from Senator Byron L. Dorgan. The study is based primarily on analyses EIA has previously done for studies requested by Congress. It includes analysis of the Renewable Portfolio Standard, Renewable Fuels Standard, production in the Alaskan National Wildlife Refuge, the construction of an Alaskan Natural Gas pipeline, and various tax provisions.

Paul Holtberg

2003-09-01T23:59:59.000Z

120

Towards cost-effective storage provisioning for DBMSs  

Science Conference Proceedings (OSTI)

Data center operators face a bewildering set of choices when considering how to provision resources on machines with complex I/O subsystems. Modern I/O subsystems often have a rich mix of fast, high performing, but expensive SSDs sitting alongside with ...

Ning Zhang; Junichi Tatemura; Jignesh M. Patel; Hakan Hacigm?

2011-12-01T23:59:59.000Z

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


121

EPACT2005: Status of Provisions (Update) (released in AEO2007)  

Reports and Publications (EIA)

EPACT2005 was signed into law by President Bush on August 8, 2005, and became Public Law 109-058. A number of provisions from EPACT2005 were included in the AEO2006 projections. Many others were not considered in AEO2006particularly, those that require funding appropriations or further specification by Federal agencies or Congress before implementation.

Information Center

2007-02-22T23:59:59.000Z

122

Decontamination Dressdown at a Transportation Accident Involving  

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

Decontamination Dressdown at a Transportation Accident Involving Decontamination Dressdown at a Transportation Accident Involving Radioactive Material Decontamination Dressdown at a Transportation Accident Involving Radioactive Material The purpose of this User's Guide is to provide instructors with an overview of the key points covered in the video. The Student Handout portion of this Guide is designed to assist the instructor in reviewing those points with students. The Student Handout should be distributed to students after the video is shown and the instructor should use the Guide to facilitate a discussion on how the decontamination dressdown process is implemented. During this discussion, the instructor can present various scenarios, each of which would discuss decontamination at the accident scene. The purpose of this discussion would be to cover how responders

123

A systems approach to food accident analysis  

E-Print Network (OSTI)

Food borne illnesses lead to 3000 deaths per year in the United States. Some industries, such as aviation, have made great strides increasing safety through careful accident analysis leading to changes in industry practices. ...

Helferich, John D

2011-01-01T23:59:59.000Z

124

Chernobyl accident: A comprehensive risk assessment  

SciTech Connect

The authors, all of whom are Ukrainian and Russian scientists involved with Chernobyl nuclear power plant since the April 1986 accident, present a comprehensive review of the accident. In addition, they present a risk assessment of the remains of the destroyed reactor and its surrounding shelter, Chernobyl radioactive waste storage and disposal sites, and environmental contamination in the region. The authors explore such questions as the risks posed by a collapse of the shelter, radionuclide migration from storage and disposal facilities in the exclusion zone, and transfer from soil to vegetation and its potential regional impact. The answers to these questions provide a scientific basis for the development of countermeasures against the Chernobyl accident in particular and the mitigation of environmental radioactive contamination in general. They also provide an important basis for understanding the human health and ecological risks posed by the accident.

Vargo, G.J.; Poyarkov, V.; Baryakhtar, V.; Kukhar, V.; Los, I.

1999-11-01T23:59:59.000Z

125

A SUMMARY OF INDUSTRIAL ACCIDENTS IN USAEC FACILITIES  

SciTech Connect

The summary includes descriptions of serious accidents for l959 and 1960, AEC industrial injury frequency rates, criticality accidents, radiation exposures, accidents involving radioactive materials in AEC activities during 1959 and 1960, and accidents involving fatalities in AEC activities during l959 and 1960. (B.O.G.)

1961-12-01T23:59:59.000Z

126

Three Mile Island accident and post-accident recovery: what did we learn  

SciTech Connect

A description of the accident at Three Mile Island-2 reactor is presented. Activities related to the cleanup and decontamination of the reactor are described.

Collins, E.D.

1982-01-01T23:59:59.000Z

127

Low level waste shipment accident lessons learned  

SciTech Connect

On October 1, 1994 a shipment of low-level waste from the Fernald Environmental Management Project, Fernald, Ohio, was involved in an accident near Rolla, Missouri. The accident did not result in the release of any radioactive material. The accident did generate important lessons learned primarily in the areas of driver and emergency response communications. The shipment was comprised of an International Standards Organization (ISO) container on a standard flatbed trailer. The accident caused the low-level waste package to separate from the trailer and come to rest on its top in the median. The impact of the container with the pavement and median inflicted relatively minor damage to the container. The damage was not substantial enough to cause failure of container integrity. The success of the package is attributable to the container design and the packaging procedures used at the Fernald Environmental Management Project for low-level waste shipments. Although the container survived the initial wreck, is was nearly breached when the first responders attempted to open the ISO container. Even though the container was clearly marked and the shipment documentation was technically correct, this information did not identify that the ISO container was the primary containment for the waste. The lessons learned from this accident have DOE complex wide applicability. This paper is intended to describe the accident, subsequent emergency response operations, and the lessons learned from this incident.

Rast, D.M.; Rowe, J.G.; Reichel, C.W.

1995-02-01T23:59:59.000Z

128

Alternative Fuels Data Center: Provision for Plug-In Electric Vehicle (PEV)  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Provision for Plug-In Provision for Plug-In Electric Vehicle (PEV) Charging Incentives to someone by E-mail Share Alternative Fuels Data Center: Provision for Plug-In Electric Vehicle (PEV) Charging Incentives on Facebook Tweet about Alternative Fuels Data Center: Provision for Plug-In Electric Vehicle (PEV) Charging Incentives on Twitter Bookmark Alternative Fuels Data Center: Provision for Plug-In Electric Vehicle (PEV) Charging Incentives on Google Bookmark Alternative Fuels Data Center: Provision for Plug-In Electric Vehicle (PEV) Charging Incentives on Delicious Rank Alternative Fuels Data Center: Provision for Plug-In Electric Vehicle (PEV) Charging Incentives on Digg Find More places to share Alternative Fuels Data Center: Provision for Plug-In Electric Vehicle (PEV) Charging Incentives on AddThis.com...

129

Efficient network QoS provisioning based on per node traffic shaping  

Science Conference Proceedings (OSTI)

Keywords: ATM, QoS provisioning, end-to-end delay guarantees, real-time traffic, scheduling, traffic shaping

Leonidas Georgiadis; Roch Gurin; Vinod Peris; Kumar N. Sivarajan

1996-08-01T23:59:59.000Z

130

Instrument Performance Under Severe Accident Conditions: Ways to Acquire Information From Instrumentation Affected by an Accident  

Science Conference Proceedings (OSTI)

Under accident conditions, information is needed for diagnosing plant status and confirming plant responses to mitigative actions. This makes it important to understand how instruments behave in severe accident environments and to find ways to obtain information from the instruments under conditions that can be more severe than their design bases.

1993-12-01T23:59:59.000Z

131

Comonotonic approximations for a generalized provisioning problem with application to optimal portfolio selection  

Science Conference Proceedings (OSTI)

In this paper we discuss multiperiod portfolio selection problems related to a specific provisioning problem. Our results are an extension of Dhaene et al. (2005) [14], where optimal constant mix investment strategies are obtained in a provisioning and ... Keywords: Comonotonicity, Constant mix strategies, Portfolio selection, Provisioning

Koen Van Weert; Jan Dhaene; Marc Goovaerts

2011-03-01T23:59:59.000Z

132

Chemical accident databases: what they tell us and how they can be improved to establish national safety goals  

E-Print Network (OSTI)

The objectives of this research are to examine and critique eight chemical accident databases, document any trends in accident occurrences, develop a strategy for improving current databases, and to establish national safety goals on the basis of those improvements. This synopsis found that it is impossible to draw any conclusions about the state of chemical safety, past or present, based on the information in the various databases. The databases are deficient in many ways. First, they have been developed using inconsistent and faulty data-collecting methods, and the terms used to describe accidents are often ambiguous. Secondly, the ever-changing reporting requirements prevent comparisons to be made from year to year, making trends impossible to identify. Lastly, the databases provide little to no information about the specifics of accidents, and many accidents are incorrectly lumped under the heading of chemical accidents. All these factors compromise the overall quality of the data. Thus, it is very difficult, if not impossible, to make definitive conclusions. In addition, it is impossible to determine the effectiveness of governmental regulations or industry standards and practices, when there is no reliable data available for comparison. Finally, this study makes recommendations for database improvement by addressing each of the deficiencies, developing a structure for a new database, and establishing a foundation for the development of national safety goals.

McCray, Eboni Trevette

2000-01-01T23:59:59.000Z

133

SAF-230DE - Web Based Course: Accident Investigation Overview | Department  

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

SAF-230DE - Web Based Course: Accident Investigation Overview SAF-230DE - Web Based Course: Accident Investigation Overview SAF-230DE - Web Based Course: Accident Investigation Overview September 18, 2013 - 10:52am Addthis SAF-230DE - Web Based Course: Accident Investigation Overview The Office of Health Safety and Security (HSS) National Training Center (NTC) in collaboration with the HSS Accident Investigation Program (HS-24) has developed and released a course that provides an overview of the fundamentals of accident investigation. This course is intended to meet the every five year refresher training requirement for DOE Federal Accident Investigators under DOE Order 225.1B "Accident Investigations", and serves as an orientation to other DOE Federal Accident Investigation Board Members who need a basic knowledge of

134

EMERGENCY RESPONSE TO A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

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

Emer Emer Emer Emer Emer Emergency Response to a T gency Response to a T gency Response to a T gency Response to a T gency Response to a Transportation ransportation ransportation ransportation ransportation Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material Accident Involving Radioactive Material DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond the scope of this video and requires either additional

135

Severe accident testing of a personnel airlock  

Science Conference Proceedings (OSTI)

Sandia National Laboratories (Sandia) is investigating the leakage potential of mechanical penetrations as part of a research program on containment integrity under severe accident loads for the US Nuclear Regulatory Commission (NRC). Barnes et al. (1984) and Shackelford et al. (1985) identified leakage from personnel airlocks as an important failure mode of containments subject to severe accident loads. However, these studies were based on relatively simple analysis methods. The complex structural interaction between the door, gasket, and bulkhead in personnel airlocks makes analytical evaluation of leakage difficult. In order to provide data to validate methods for evaluating the leakage potential, a full-size personnel airlock was subject to simulated severe accident loads consisting of pressure and temperature up to 300 psig and 800/degree/F. The test was conducted at Chicago Bridge and Iron under contract to Sandia. Julien and Peters (1989) provide a detailed report on the test program. 6 refs., 5 figs.

Clauss, D.B.; Parks, M.B.; Julien, J.T.; Peters, S.W.

1989-01-01T23:59:59.000Z

136

Assessment of CRBR core disruptive accident energetics  

Science Conference Proceedings (OSTI)

The results of an independent assessment of core disruptive accident energetics for the Clinch River Breeder Reactor are presented in this document. This assessment was performed for the Nuclear Regulatory Commission under the direction of the CRBR Program Office within the Office of Nuclear Reactor Regulation. It considered in detail the accident behavior for three accident initiators that are representative of three different classes of events; unprotected loss of flow, unprotected reactivity insertion, and protected loss of heat sink. The primary system's energetics accommodation capability was realistically, yet conservatively, determined in terms of core events. This accommodation capability was found to be equivalent to an isentropic work potential for expansion to one atmosphere of 2550 MJ or a ramp rate of about 200 $/s applied to a classical two-phase disassembly.

Theofanous, T.G.; Bell, C.R.

1984-03-01T23:59:59.000Z

137

A Review of Criticality Accidents 2000 Revision  

SciTech Connect

Criticality accidents and the characteristics of prompt power excursions are discussed. Sixty accidental power excursions are reviewed. Sufficient detail is provided to enable the reader to understand the physical situation, the chemistry and material flow, and when available the administrative setting leading up to the time of the accident. Information on the power history, energy release, consequences, and causes are also included when available. For those accidents that occurred in process plants, two new sections have been included in this revision. The first is an analysis and summary of the physical and neutronic features of the chain reacting systems. The second is a compilation of observations and lessons learned. Excursions associated with large power reactors are not included in this report.

Thomas P. McLaughlin; Shean P. Monahan; Norman L. Pruvost; Vladimir V. Frolov; Boris G. Ryazanov; Victor I. Sviridov

2000-05-01T23:59:59.000Z

138

Accident progression event tree analysis for postulated severe accidents at N Reactor  

SciTech Connect

A Level II/III probabilistic risk assessment (PRA) has been performed for N Reactor, a Department of Energy (DOE) production reactor located on the Hanford reservation in Washington. The accident progression analysis documented in this report determines how core damage accidents identified in the Level I PRA progress from fuel damage to confinement response and potential releases the environment. The objectives of the study are to generate accident progression data for the Level II/III PRA source term model and to identify changes that could improve plant response under accident conditions. The scope of the analysis is comprehensive, excluding only sabotage and operator errors of commission. State-of-the-art methodology is employed based largely on the methods developed by Sandia for the US Nuclear Regulatory Commission in support of the NUREG-1150 study. The accident progression model allows complex interactions and dependencies between systems to be explicitly considered. Latin Hypecube sampling was used to assess the phenomenological and systemic uncertainties associated with the primary and confinement system responses to the core damage accident. The results of the analysis show that the N Reactor confinement concept provides significant radiological protection for most of the accident progression pathways studied.

Wyss, G.D.; Camp, A.L.; Miller, L.A.; Dingman, S.E.; Kunsman, D.M. (Sandia National Labs., Albuquerque, NM (USA)); Medford, G.T. (Science Applications International Corp., Albuquerque, NM (USA))

1990-06-01T23:59:59.000Z

139

LESSONS LEARNED FROM A RECENT LASER ACCIDENT  

SciTech Connect

A graduate student received a laser eye injury from a femtosecond Ti:sapphire laser beam while adjusting a polarizing beam splitter optic. The direct causes for the accident included failure to follow safe alignment practices and failure to wear the required laser eyewear protection. Underlying root causes included inadequate on-the-job training and supervision, inadequate adherence to requirements, and inadequate appreciation for dimly visible beams outside the range of 400-700nm. This paper describes how the accident occurred, discusses causes and lessons learned, and describes corrective actions being taken.

Woods, Michael; /SLAC

2011-01-26T23:59:59.000Z

140

Accident Investigation of the Fall Injury at the Savannah River...  

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

U.S. Department of Energy Office of Environmental Management Accident Investigation Report Fall Injury Accident at the Savannah River Site on July 1, 2011 August 8, 2011 Disclaimer...

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


141

Uncertainty Assessments in Severe Nuclear Accident Scenarios  

Science Conference Proceedings (OSTI)

Managing uncertainties in industrial systems is a daily challenge to ensure improved design, robust operation, accountable performance and responsive risk control. This paper aims to illustrate the different depth analyses that the uncertainty software ... Keywords: Monte Carlo simulation, nuclear power plant, sensitivity analysis, severe accident, uncertainty

Bertrand Iooss; Fabrice Gaudier; Michel Marques; Bertrand Spindler; Bruno Tourniaire

2009-09-01T23:59:59.000Z

142

Blasting practices and explosives accidents in Utah coal mines  

SciTech Connect

Practices in use in Utah are commended and accidents incident to blasting are reviewed with suggestions as to future avoidance.

Parker, D.J.

1935-01-01T23:59:59.000Z

143

Accident Investigation and Materials Failure Analysis at the ...  

Science Conference Proceedings (OSTI)

Both are independent federal agencies charged with investigating transportation accidents in all modes, including aviation, railroad, highway, marine, pipeline,...

144

DOE O 225.1B, Accident Investigations  

Directives, Delegations, and Requirements

This Order prescribes organizational responsibilities, authorities, and requirements for conducting investigations of certain accidents occurring at DOE sites, ...

2011-03-04T23:59:59.000Z

145

Accident Response Group | National Nuclear Security Administration  

National Nuclear Security Administration (NNSA)

Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy Emergency Response Recapitalizing Our Infrastructure...

146

Radionuclide monitoring in Northern Ireland of the Chernobyl nuclear reactor accident  

E-Print Network (OSTI)

Northern Ireland received higher radiation doses due to the radionuclide contamination from the Chernobyl nuclear reactor accident than did the south of England. Levels of radioactive iodine (1311) and caesium (137Cs) in cows ' milk in Northern Ireland increased to 166 and 120 Bq/l respectively in May 1986, but had decreased by factors of one million, and of twenty-five, respectively, by 1 September 1986. The resultant radiation doses represent less than one per cent of those received by a Northern Ireland individual over a period of 40 years from natural background radiation sources. The added risk to any individual from the Chernobyl accident will therefore be very small and may best bejudged in the context of the enormously greater risk of death due to potentially preventable diseases, such as smoking-related lung cancer, and coronary heart disease.

B J Gilmore; K Cranley

1987-01-01T23:59:59.000Z

147

ANSI/ANS-8.23-1997: nuclear criticality accident emergency planning and response.  

SciTech Connect

American National Standard ANSUANS-8.23 was developed to expand upon the basic emergency response guidance given in American National Standard, 'Administrative Practices for Nuclear Criticality Safety' ANSI/ANS-8.19-1996 (Ref. 1). This standard provides guidance for minimizing risks to personnel during emergency response to a nuclear criticality accident outside reactors. This standard is intended to apply to those facilities for which a criticality accident alarm system, as specified in American National Standard, 'Criticality Accident Alarm System', ANSI/ANS-8.3-1997 (Ref. 2) is in use. The Working Group was established in 1990, with Norman L. Pruvost as chairman. The Working Group had up to twenty-three members representing a broad range of the nuclear industry, and has included members from Canada, Japan and the United Kingdom. The initial edition of ANSI/ANS-8.23 was approved by the American National Standards Institute on December 30, 1997. It provides guidance for the following topics: (1) Management and technical staff responsibilities; (2) Evaluation of a potential criticality accident; (3) Emergency plan provisions; (4) Evacuation; (5) Re-entry, rescue and stabilization; and (6) Classroom training, exercises and evacuation drills. This guidance is not for generic emergency planning issues, but is specific to nuclear criticality accidents. For example, it assumes that an Emergency Plan is already established at facilities that implement the standard. During the development of the initial edition of ANSI/ANS-8.23, each Working Group member evaluated potential use of the standard at a facility with which the member was familiar. This revealed areas where a facility could have difficulty complying with the standard. These reviews helped identify and eliminate many potential problems and ambiguities with the guidance. The Working Group has received very limited feedback from the user community since the first edition of the standard was published. Suggestions for improvements to increase the usefulness of this standard are being solicited. The Working Group currently has ten members and is drafting a revision of ANSI/ANS-8.23. The focus of this effort is to include additional technical guidance on the following topics: (1) Recommendations for radiation monitoring instruments that may be used during an emergency response to a criticality accident; (2) Recommended resources for a criticality safety specialist during an emergency response to a criticality accident; (3) An example showing how to construct an emergency exercise for a fissile material processing facility. This includes: (a) Estimating the fission source term based on a credible accident scenario; (b) Estimating doses to nearby personnel; (c) Estimating doses to rescuers; (d) A discussion of evacuation and rescue considerations; (e) A review of dosimetry and medical response issues; and (f) Recommendations for the conduct of drills and exercises. This additional guidance will be contained in appendices to the revised standard. In addition, the revised standard will include a reference to an extensive bibliography of resources for emergency planning. The first revision of ANSI/ANS-8.23 should be provided to ANS-8 for ballot by the fall of 2004.

Baker, J. S. (James S.)

2004-01-01T23:59:59.000Z

148

Towards Cost-Effective Storage Provisioning for DBMSs  

E-Print Network (OSTI)

Data center operators face a bewildering set of choices when considering how to provision resources on machines with complex I/O subsystems. Modern I/O subsystems often have a rich mix of fast, high performing, but expensive SSDs sitting alongside with cheaper but relatively slower (for random accesses) traditional hard disk drives. The data center operators need to determine how to provision the I/O resources for specific workloads so as to abide by existing Service Level Agreements (SLAs), while minimizing the total operating cost (TOC) of running the workload, where the TOC includes the amortized hardware costs and the run time energy costs. The focus of this paper is on introducing this new problem of TOC-based storage allocation, cast in a framework that is compatible with traditional DBMS query optimization and query processing architecture. We also present a heuristic-based solution to this problem, called DOT. We have implemented DOT in PostgreSQL, and experiments using TPC-H and TPC-C demonstrate sig...

Zhang, Ning; Patel, Jignesh M; Hac?gm?, Hakan

2012-01-01T23:59:59.000Z

149

REAC/TS Radiation Accident Registry: An Overview  

Science Conference Proceedings (OSTI)

Over the past four years, REAC/TS has presented a number of case reports from its Radiation Accident Registry. Victims of radiological or nuclear incidents must meet certain dose criteria for an incident to be categorized as an accident and be included in the registry. Although the greatest numbers of accidents in the United States that have been entered into the registry involve radiation devices, the greater percentage of serious accidents have involved sealed sources of one kind or another. But if one looks at the kinds of accident scenarios that have resulted in extreme consequence, i.e., death, the greater share of deaths has occurred in medical settings.

Doran M. Christensen, DO, REAC /TS Associate Director and Staff Physician Becky Murdock, REAC/TS Registry and Health Physics Technician

2012-12-12T23:59:59.000Z

150

Trends status: Post-accident fission product chemistry  

DOE Green Energy (OSTI)

It is important to understand and model the chemical and physical behavior of vapor iodine species in containment environments for the following reasons: This behavior can contribute significantly to severe accident source terms; the development of accident mitigation or management strategies (e.g., an effective filter system); for long-term clean-up and recovery following an accident; regulatory requirements (e.g., spray or pool additives); and design basis accidents (i.e., steam generator tube rupture). This document discusses the Oak Ridge National Laboratory ''Post-Accident'' Chemistry Program.

Kress, T.S.; Beahm, E.C.; Shockley, W.C.; Weber, C.F.

1988-01-01T23:59:59.000Z

151

Environment/Health/Safety (EHS): Monthly Accident Statistics  

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

Monthly Accident Statistics Monthly Accident Statistics Latest Accident Statistics Accident Statistics (through December 2013) Archived Accident Statistics 2013 Through November Through October Through September Through August Through July Through June Through May Through April Through March Through February Through January 2012 Through December Through November Through October Through September Through August Through July Through June Through May Through February Through January 2011 Through December Through November Through October Through September Through August Through July Through June Through May Through April Through March Through February Through January 2010 Through December Through November Through October Through September Through August Through July Through June Through May Through April Through March Through February

152

Bike-Sharing:History, Impacts, Models of Provision, and Future | Open  

Open Energy Info (EERE)

Bike-Sharing:History, Impacts, Models of Provision, and Future Bike-Sharing:History, Impacts, Models of Provision, and Future Jump to: navigation, search Tool Summary Name: Bike-Sharing:History, Impacts, Models of Provision, and Future Agency/Company /Organization: MetroBike Focus Area: Non-Motorized Transport, Transportation Topics: Potentials & Scenarios Resource Type: Publications User Interface: Website Website: www.metrobike.net/index.php?s=file_download&id=26 Cost: Free Bike-Sharing:History, Impacts, Models of Provision, and Future Screenshot References: Bike-Sharing:History, Impacts, Models of Provision, and Future[1] This paper discusses the history of bike-sharing from the early 1st generation program to present day 3rd generation programs. Included are a detailed examination of models of provision, with benefits and detriments

153

Accident, Maryland: Energy Resources | Open Energy Information  

Open Energy Info (EERE)

Accident, Maryland: Energy Resources Accident, Maryland: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 39.628696°, -79.319759° Loading map... {"minzoom":false,"mappingservice":"googlemaps3","type":"ROADMAP","zoom":14,"types":["ROADMAP","SATELLITE","HYBRID","TERRAIN"],"geoservice":"google","maxzoom":false,"width":"600px","height":"350px","centre":false,"title":"","label":"","icon":"","visitedicon":"","lines":[],"polygons":[],"circles":[],"rectangles":[],"copycoords":false,"static":false,"wmsoverlay":"","layers":[],"controls":["pan","zoom","type","scale","streetview"],"zoomstyle":"DEFAULT","typestyle":"DEFAULT","autoinfowindows":false,"kml":[],"gkml":[],"fusiontables":[],"resizable":false,"tilt":0,"kmlrezoom":false,"poi":true,"imageoverlays":[],"markercluster":false,"searchmarkers":"","locations":[{"text":"","title":"","link":null,"lat":39.628696,"lon":-79.319759,"alt":0,"address":"","icon":"","group":"","inlineLabel":"","visitedicon":""}]}

154

Less than severe worst case accidents  

Science Conference Proceedings (OSTI)

Many systems can provide tremendous benefit if operating correctly, produce only an inconvenience if they fail to operate, but have extreme consequences if they are only partially disabled such that they operate erratically or prematurely. In order to assure safety, systems are often tested against the most severe environments and accidents that are considered possible to ensure either safe operation or safe failure. However, it is often the less severe environments which result in the ``worst case accident`` since these are the conditions in which part of the system may be exposed or rendered unpredictable prior to total system failure. Some examples of less severe mechanical, thermal, and electrical environments which may actually be worst case are described as cautions for others in industries with high consequence operations or products.

Sanders, G.A.

1996-08-01T23:59:59.000Z

155

Characterization of a nuclear accident dosimeter  

E-Print Network (OSTI)

The 23rd nuclear accident dosimetry intercomparison was held during the week of June 12-16, 1995 at Los Alamos National Laboratory. This report presents the results of this event, referred to as NAD 23, as related to the performance of Sandia National Laboratories' (SNL) personal nuclear accident dosimeter (PNAD). Two separate critical assemblies, SHEBA and Godiva, were used to generate seven separate neutron spectra for use in dose comparisons. SNL's PNAD measured absorbed doses that were within +16 to +26 percent of the reference doses. In addition, a preliminary investigation was undertaken to determine the feasibility of using the data obtained from an irradiated PNAD to correct for body orientation. This portion of the experiment was performed with a TRIGA reactor at the Nuclear Science Center at Texas A&M University.

Burrows, Ronald Allen

1995-01-01T23:59:59.000Z

156

Characterization of a nuclear accident dosimeter  

Science Conference Proceedings (OSTI)

The 23rd nuclear accident dosimetry intercomparison was held during the week of June 12--16, 1995 at Los Alamos National Laboratory. This report presents the results of this event, referred to as NAD 23, as related to the performance of Sandia National Laboratories (SNL) personal nuclear accident dosimeter (PNAD). Two separate critical assemblies, SHEBA and Godiva, were used to generate seven separate neutron spectra for use in dose comparisons. SNL`s PNAD measured absorbed doses that were within +16 to +26% of the reference doses. In addition, a preliminary investigation was undertaken to determine the feasibility of using the data obtained from an irradiated PNAD to correct for body orientation. This portion of the experiment was performed with a TRIGA reactor at the Nuclear Science Center at Texas A and M University.

Burrows, R.A.

1995-12-01T23:59:59.000Z

157

US Department of Energy Chernobyl accident bibliography  

SciTech Connect

This bibliography has been prepared by Pacific Northwest Laboratory (PNL) for the US Department of Energy (DOE) Office of Health and Environmental Research to provide bibliographic information in a usable format for research studies relating to the Chernobyl nuclear accident that occurred in the Ukrainian Republic, USSR in 1986. This report is a product of the Chernobyl Database Management project. The purpose of this project is to produce and maintain an information system that is the official United States repository for information related to the accident. Two related products prepared for this project are the Chernobyl Bibliographic Search System (ChernoLit{trademark}) and the Chernobyl Radiological Measurements Information System (ChernoDat). This report supersedes the original release of Chernobyl Bibliography (Carr and Mahaffey, 1989). The original report included about 2200 references. Over 4500 references and an index of authors and editors are included in this report.

Kennedy, R.A.; Mahaffey, J.A.; Carr, F. Jr.

1992-04-01T23:59:59.000Z

158

Just Provisions: Food, Identity, and Contested Space in Urban America, 1800-1875  

E-Print Network (OSTI)

sugar, molasses, and wheat flour amid other provisions. "white sugar, molasses, and wheat flour; for his efforts, heflour, she followed, should be avoided because the wheat had

Branch, Michelle

2012-01-01T23:59:59.000Z

159

Impact of Renewable Fuels Standard/MTBE Provisions of S. 517 Requested by Sens. Daschle & Murkowski  

Reports and Publications (EIA)

Additional analysis of the impact of the Renewable Fuels Standard (RFS) and methyl tertiary butyl ether (MTBE) ban provisions of S. 517.

Information Center

2002-04-01T23:59:59.000Z

160

Impact of Renewable Fuels Standard/MTBE Provisions of S.1766  

U.S. Energy Information Administration (EIA)

SR/OIAF/2002-06 Release date: March 2002 This report analyzes the Renewable Fuels Standard (RFS)/methyl tertiary butyl ether (MTBE) provisions of S. 1766.

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


161

Fukushima Daiichi Accident -- Technical Causal Factor Analysis  

Science Conference Proceedings (OSTI)

On March 11, 2011, the Fukushima Daiichi nuclear power plant experienced a seismic event and subsequent tsunami. The accident and the ensuing mitigation and recovery activities occurred over several days, involved a number of incidents, and might provide several opportunities for lessons learned. The objective of this report is to determine the fundamental causative factors for the loss of critical systems at the Fukushima Daiichi reactors that resulted in core damage and subsequent radioactive release. ...

2012-03-27T23:59:59.000Z

162

European Pressurized water Reactor (EPR) SAR ATWS Accident Analyses by using 3D Code Internal Coupling Method  

SciTech Connect

Anticipated Transients Without Scram (ATWS) accident analyses make part of the Safety Analysis Report of the European Pressurized water Reactor (EPR), covering Risk Reduction Category A (Core Melt Prevention) events. This paper deals with three of the most penalizing RRC-A sequences of ATWS caused by mechanical blockage of the control/shutdown rods, regarding their consequences on the Reactor Coolant System (RCS) and core integrity. A new 3D code internal coupling calculation method has been introduced. (authors)

Gagner, Renata; Lafitte, Helene; Dormeau, Pascal [Framatome ANP, Tour Areva - 1, place de la Coupole - 92084 Paris La Defense (France); Stoudt, Roger H. [Framatome ANP, Lynchburg - 3315 Old Forest Road, Lynchburg, VA 24501 (United States)

2004-07-01T23:59:59.000Z

163

CEQ Regulations for Implementing the Procedural Provisions of NEPA  

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

Executive Office of the President Executive Office of the President REGULATIONS For Implementing The Procedural Provisions Of The NATIONAL ENVIRONMENTAL POLICY ACT Reprint 40 CFR Parts 1500-1508 (2005) This page is blank (inside front cover) TABLE OF CONTENTS PART 1500-PURPOSE, POLICY AND MANDATE Sec. 1500.1 Purpose. 1500.2 Policy. 1500.3 Mandate. 1500.4 Reducing paperwork. 1500.5 Reducing delay. 1500.6 Agency authority. PART 1501-NEPA AND AGENCY PLANNING Sec. 1501.1 Purpose. 1501.2 Apply NEPA early in the process. 1501.3 When to prepare an environmental assessment. 1501.4 Whether to prepare an environmental impact statement. 1501.5 Lead agencies. 1501.6 Cooperating agencies. 1501.7 Scoping. 1501.8 Time limits. PART 1502-ENVIRONMENTAL IMPACT STATEMENT Sec. 1502.1 Purpose. 1502.2 Implementation. 1502.3 Statutory requirements for statements.

164

Executive Director for Operations PROPOSED RULE ON DECOMMISSIONING TRUST PROVISIONS  

E-Print Network (OSTI)

To request Commission approval to publish a proposed rule in the Federal Register on decommissioning trust agreement requirements. BACKGROUND: The staff presented a rulemaking plan (SECY-00-0002) to the Commission on December 30, 1999. The plan discussed two actions relating to amending nuclear power reactor decommissioning trust provisions i.e., to amend 10 CFR 50.75 and revise Regulatory Guide 1.159. Subsequently, in a February 9, 2000, staff requirements memorandum (SRM) to the Executive Director for Operations (Attachment 1), the Commission authorized the staff to proceed with the rulemaking plan. Further, the Commission instructed the staff that any specific trust fund terms and conditions necessary to protect the funds fully should be set out in the rule itself, not in the regulatory guide. Sample language for trust agreements consistent with the terms and conditions within the rule may be provided within the associated regulatory guide. The attached Federal Register notice (FRN) responds to the SRM. DISCUSSION: Contact:

William D. Travers; Brian Richter

2001-01-01T23:59:59.000Z

165

Statistical profiling-based techniques for effective power provisioning in data centers  

Science Conference Proceedings (OSTI)

Current capacity planning practices based on heavy over-provisioning of power infrastructure hurt (i) the operational costs of data centers as well as (ii) the computational work they can support. We explore a combination of statistical multiplexing ... Keywords: data center, power provisioning, power supply hierarchy, prediction, profiling

Sriram Govindan; Jeonghwan Choi; Bhuvan Urgaonkar; Anand Sivasubramaniam; Andrea Baldini

2009-04-01T23:59:59.000Z

166

Enabling the simulation of service-oriented computing and provisioning policies for autonomic utility grids  

Science Conference Proceedings (OSTI)

There are key challenges in utility computing environments such as the provisioning, orchestration and allocation of resources to services. In these environments, providers need to decide how resources are allocated to service applications according ... Keywords: grid computing, resource provisioning, simulation framework, utility computing

Marcos Dias de Assuno; Werner Streitberger; Torsten Eymann; Rajkumar Buyya

2007-08-01T23:59:59.000Z

167

Zircaloy-oxidation and hydrogen-generation rates in degraded-core accident situations  

DOE Green Energy (OSTI)

Oxidation of Zircaloy cladding is the primary source of hydrogen generated during a degraded-core accident. In this paper, reported Zircaloy oxidation rates, either measured at 1500 to 1850/sup 0/C or extrapolated from the low-temperature data obtained at <1500/sup 0/C, are critically reviewed with respect to their applicability to a degraded-core accident situation in which the high-temperature fuel cladding is likely to be exposed to and oxidized in mixtures of hydrogen and depleted steam, rather than in an unlimited flux of pure steam. New results of Zircaloy oxidation measurements in various mixtures of hydrogen and steam are reported for >1500/sup 0/C. The results show significantly smaller oxidation and, hence, hydrogen-generation rates in the mixture, compared with those obtained in pure steam. It is also shown that a significant fraction of hydrogen, generated as a result of Zircaloy oxidation, is dissolved in the cladding material itself, which prevents that portion of hydrogen from reaching the containment building space. Implications of these findings are discussed in relation to a more realistic method of quantifying the hydrogen source term for a degraded-core accident analysis.

Chung, H.M.; Thomas, G.R.

1983-02-01T23:59:59.000Z

168

Depressurization as an accident management strategy to minimize the consequences of direct containment heating  

Science Conference Proceedings (OSTI)

Probabilistic Risk Assessments (PRAs) have identified severe accidents for nuclear power plants that have the potential to cause failure of the containment through direct containment heating (DCH). Prevention of DCH or mitigation of its effects may be possible using accident management strategies that intentionally depressurize the reactor coolant system (RCS). The effectiveness of intentional depressurization during a station blackout TMLB' sequence was evaluated considering the phenomenological behavior, hardware performance, and operational performance. Phenomenological behavior was calculated using the SCDAP/RELAP5 severe accident analysis code. Two strategies to mitigate DCH by depressurization of the RCS were considered. One strategy, called early depressurization, assumed that the reactor head vent and pressurizer power-operated relief valves (PORVs) were latched open at steam generator dryout. The second strategy, called late depression, assumed that the head vent and PORVs were latched open at a core exit temperature of {approximately}922 K (1200{degree}F). Depressurization of the RCS to a low value that may mitigate DCH was predicted prior to reactor pressure vessel breach for both early and late depressurization. The strategy of late depressurization is preferred over early depressurization because there are greater opportunities to recover plant functions prior to core damage and because failure uncertainties are lessened. 22 refs., 38 figs., 6 tabs.

Hanson, D.J.; Golden, D.W.; Chambers, R.; Miller, J.D.; Hallbert, B.P.; Dobbe, C.A. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1990-10-01T23:59:59.000Z

169

TMI-2 accident: core heat-up analysis  

SciTech Connect

This report summarizes NSAC study of reactor core thermal conditions during the accident at Three Mile Island, Unit 2. The study focuses primarily on the time period from core uncovery (approximately 113 minutes after turbine trip) through the initiation of sustained high pressure injection (after 202 minutes). The transient analysis is based upon established sequences of events; plant data; post-accident measurements; interpretation or indirect use of instrument responses to accident conditions.

Ardron, K.H.; Cain, D.G.

1981-01-01T23:59:59.000Z

170

Preliminary dose assessment of the Chernobyl accident  

Science Conference Proceedings (OSTI)

From the major accident at Unit 4 of the Chernobyl nuclear power station, a plume of airborne radioactive fission products was initially carried northwesterly toward Poland, thence toward Scandinavia and into Central Europe. Reports of the levels of radioactivity in a variety of media and of external radiation levels were collected in the Department of Energy's Emergency Operations Center and compiled into a data bank. Portions of these and other data which were obtained directly from published and official reports were utilized to make a preliminary assessment of the extent and magnitude of the external dose to individuals downwind from Chernobyl. Radioactive /sup 131/I was the predominant fission product. The time of arrival of the plume and the maximum concentrations of /sup 131/I in air, vegetation and milk and the maximum reported depositions and external radiation levels have been tabulated country by country. A large amount of the total activity in the release was apparently carried to a significant elevation. The data suggest that in areas where rainfall occurred, deposition levels were from ten to one-hundred times those observed in nearby ''dry'' locations. Sufficient spectral data were obtained to establish average release fractions and to establish a reference spectra of the other nuclides in the release. Preliminary calculations indicated that the collective dose equivalent to the population in Scandinavia and Central Europe during the first year after the Chernobyl accident would be about 8 x 10/sup 6/ person-rem. From the Soviet report, it appears that a first year population dose of about 2 x 10/sup 7/ person-rem (2 x 10/sup 5/ Sv) will be received by the population who were downwind of Chernobyl within the U.S.S.R. during the accident and its subsequent releases over the following week. 32 refs., 14 figs., 20 tabs.

Hull, A.P.

1987-01-01T23:59:59.000Z

171

Median Light Rail Crossing: Accident Causation And Countermeasures  

E-Print Network (OSTI)

Integration of Light Rail Transit Into City Streets. TCRPInfluencing Safety at Highway-Rail Grade Crossings. InK. , W. Hucke and W. Berg. Rail Highway Crossing Accident

Coifman, Benjamin; Bertini, Robert L.

1997-01-01T23:59:59.000Z

172

Next-generation nuclear fuel withstands high-temperature accident...  

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

(more than 200 degrees Celsius greater than postulated accident conditions) most fission products remained inside the fuel particles, which each boast their own primary...

173

HEALTH EFFECTS OF THE NUCLEAR ACCIDENT AT THREE MILE ISLAND  

E-Print Network (OSTI)

In) Symposium on Nuclear Reactor Safety: Perspective. Ahealth effects of the nuclear reactor accident at Three Mile50-mile radius of the nuclear reactor site, approximately

Fabrikant, J.I.

2010-01-01T23:59:59.000Z

174

Analysis of Severe Accident Management Strategy for a BWR-4 Nuclear Power Plant  

SciTech Connect

The Chinshan nuclear power plant (NPP) is a Mark-I boiling water reactor (BWR) NPP located in northern Taiwan. The Chinshan NPP severe accident management guidelines (SAMGs) were developed based on the BWR Owners Group Emergency Procedure Guidelines/Severe Accident Guidelines and were developed at the end of 2003. The MAAP4 code has been used as a tool to validate the SAMG strategies. The development process and characteristics of the Chinshan SAMGs are described. The T{sub 5}U{sub t}X{sub C} sequence, the highest core damage frequency in the probabilistic risk assessment insight of the Chinshan NPP, is cited as a reference case for SAMG validation. Not all safety injection systems are operated in the T{sub 5}U{sub t}X{sub C} sequence. The severe accident progression is simulated, and the entry condition of the SAMGs is described. Then, the T{sub 5}U{sub t}X{sub C} sequence is simulated with reactor pressure vessel (RPV) depressurization. Mitigation actions based on the Chinshan NPP SAMGs are then applied to demonstrate the effectiveness of the SAMGs. Sensitivity studies on RPV depressurization with the reactor water level and minimum RPV injection flow rate are also investigated in this study. Based on MAAP4 calculation and the default values of the parameters calculating the severe accident phenomena, the result shows that RPV depressurization before the reactor water level reaches one-fourth of the core water level can prevent the core from damage in the T{sub 5}U{sub t}X{sub C} sequence. The flow rate of two control rod drive pumps is enough to maintain the reactor water level above the top of active fuel and cool down the core in the T{sub 5}U{sub t}X{sub C} sequence without operator action.

Wang, T.-C.; Wang, S.-J.; Teng, J.-T

2005-12-15T23:59:59.000Z

175

Preventive Action Number:  

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

8 Preventive Action Report Planning Worksheet 11_0414 1 of 3 8 Preventive Action Report Planning Worksheet 11_0414 1 of 3 EOTA - Business Form Document Title: Preventive Action Report Planning Worksheet Document Number: F-018 Rev 11_0414 Document Owner: Elizabeth Sousa Backup Owner: Melissa Otero Approver(s): Melissa Otero Parent Document: P-008, Corrective/Preventive Action Notify of Changes: EOTA Employees Referenced Document(s): N/A F-018 Preventive Action Report Planning Worksheet 11_0414 2 of 3 Revision History: Rev. Description of Change 08_0613 Initial Release 09_0924 Worksheet modified to reflect External Audit recommendation for identification of "Cause for Potential Nonconformance". Minor editing changes. 11_0414 Added Preventive Action Number block to match Q-Pulse

176

Preliminary analysis of loss-of-coolant accident in Fukushima nuclear accident  

Science Conference Proceedings (OSTI)

Loss-of-Coolant Accident (LOCA) in Boiling Water Reactor (BWR) especially on Fukushima Nuclear Accident will be discussed in this paper. The Tohoku earthquake triggered the shutdown of nuclear power reactors at Fukushima Nuclear Power station. Though shutdown process has been completely performed, cooling process, at much smaller level than in normal operation, is needed to remove decay heat from the reactor core until the reactor reach cold-shutdown condition. If LOCA happen at this condition, it will cause the increase of reactor fuel and other core temperatures and can lead to reactor core meltdown and exposure of radioactive material to the environment such as in the Fukushima Dai Ichi nuclear accident case. In this study numerical simulation has been performed to calculate pressure composition, water level and temperature distribution on reactor during this accident. There are two coolant regulating system that operational on reactor unit 1 at this accident, Isolation Condensers (IC) system and Safety Relief Valves (SRV) system. Average mass flow of steam to the IC system in this event is 10 kg/s and could keep reactor core from uncovered about 3,2 hours and fully uncovered in 4,7 hours later. There are two coolant regulating system at operational on reactor unit 2, Reactor Core Isolation Condenser (RCIC) System and Safety Relief Valves (SRV). Average mass flow of coolant that correspond this event is 20 kg/s and could keep reactor core from uncovered about 73 hours and fully uncovered in 75 hours later. There are three coolant regulating system at operational on reactor unit 3, Reactor Core Isolation Condenser (RCIC) system, High Pressure Coolant Injection (HPCI) system and Safety Relief Valves (SRV). Average mass flow of water that correspond this event is 15 kg/s and could keep reactor core from uncovered about 37 hours and fully uncovered in 40 hours later.

Su'ud, Zaki; Anshari, Rio [Nuclear and Biophysics Research Group, Dept. of Physics, Bandung Institute of Technology, Jl.Ganesha 10, Bandung, 40132 (Indonesia)

2012-06-06T23:59:59.000Z

177

Resource provisioning of Web applications in heterogeneous clouds  

E-Print Network (OSTI)

Cloud computing platforms provide very little guarantees regarding the performance of seemingly identical virtual machine instances. Such instances have been shown to exhibit significantly different performance from each other. This heterogeneity creates two challenges when hosting multi-tier Web applications in the Cloud. First, different machine instances have different processing capacity so balancing equal amounts of load to different instances leads to poor performance. Second, when an application must be reprovisioned, depending on the performance characteristics of the new machine instance it may be more beneficial to add the instance to one tier or another. This paper shows how we can efficiently benchmark the individual performance profile of each individual virtual machine instance when we obtain it from the Cloud. These performance profiles allow us to balance the request load more efficiently than standard load balancers, leading to better performance at lower costs. The performance profiles also allow us to predict the performance that the overall application would have if the new machine instance would be added to any of the application tiers, and therefore to decide how to make best use of newly acquired machine instances. We demonstrate the effectiveness of our techniques by provisioning the TPC-W e-commerce benchmark in the Amazon EC2 platform. 1

Jiang Dejun; Chi-hung Chi

2011-01-01T23:59:59.000Z

178

The OSHA and EPA programs on preventing chemical accidents and potential applications in the photovoltaic industry  

DOE Green Energy (OSTI)

OSHA issued in 1992, the Process Safety Management (PSM) of Highly Hazardous Substances. This rule requires owners/operators of facilities that handle hazardous chemicals in quantities greater than the listed thresholds to establish all the elements of a PSM. EPA has issued in June 1996, the rules for a Risk Management Program which also refers to specific substances and threshold quantities. These rules are applicable to all the facilities that use or store any of 139 regulated substances at quantities ranging from 100 lb to 10,000 lb. The RMP rule covers off-site hazards, while the OSHA Process Safety Management (PSM) rule covers worker safety issues within the plant boundary. Some of the listed substances may be found in photovoltaic manufacturing facilities. This brief report presents the basic elements of these two rules and discusses their potential applicability in the photovoltaic industry.

Fthenakis, V.M.

1996-08-01T23:59:59.000Z

179

DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL  

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

Video User' s Guide Video User' s Guide DECONTAMINATION DRESSDOWN AT A TRANSPORTATION ACCIDENT INVOLVING RADIOACTIVE MATERIAL DISCLAIMER Viewing this video and completing the enclosed printed study material do not by themselves provide sufficient skills to safely engage in or perform duties related to emergency response to a transportation accident involving radioactive material. Meeting that goal is beyond

180

Variable selection and ranking for analyzing automobile traffic accident data  

Science Conference Proceedings (OSTI)

Variable ranking and feature selection are important concepts in data mining and machine learning. This paper introduces a new variable ranking technique named Sum Max Gain Ratio (SMGR). The new technique is evaluated within the domain of traffic accident ... Keywords: decision tree, traffic accident data, variable and feature selection, variable ranking

Huanjing Wang; Allen Parrish; Randy K. Smith; Susan Vrbsky

2005-03-01T23:59:59.000Z

Note: This page contains sample records for the topic "accident prevention provisions" from the National Library of EnergyBeta (NLEBeta).
While these samples are representative of the content of NLEBeta,
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181

Evaluation of Accident Frequencies at the Canister Storage Bldg (CSB)  

DOE Green Energy (OSTI)

By using simple frequency calculations and fault tree logic, an evaluation of the design basis accident frequencies at the Canister Storage Building has been performed. The following are the design basis accidents: Mechanical damage of MCO; Gaseous release from the MCO; MCO internal hydrogen deflagration; MCO external hydrogen deflagration; Thermal runaway reactions inside the MCO; and Violation of design temperature criteria.

POWERS, T.B.

2000-03-20T23:59:59.000Z

182

Canister Storage Building (CSB) Design Basis Accident Analysis Documentation  

Science Conference Proceedings (OSTI)

This document provided the detailed accident analysis to support HNF-3553, Spent Nuclear Fuel Project Final Safety Analysis Report, Annex A, ''Canister Storage Building Final Safety Analysis Report''. All assumptions, parameters, and models used to provide the analysis of the design basis accidents are documented to support the conclusions in the Canister Storage Building Final Safety Analysis Report.

CROWE, R.D.; PIEPHO, M.G.

2000-03-23T23:59:59.000Z

183

Assessment of Existing Plant Instrumentation for Severe Accident Management  

Science Conference Proceedings (OSTI)

During an accident, information would be needed for diagnosing a plant's status and confirming its response to mitigative actions. It is important to determine the information necessary for severe accident management and to ensure that this information could be derived from plant instrumentation.

1993-12-01T23:59:59.000Z

184

Web Based Course: SAF-230DE, Accident Investigation Overview Promotional Video  

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

This course that provides an overview of the fundamentals of accident investigation. The course is intended to meet the every five year refresher training requirement for DOE Federal Accident Investigators under DOE O 225.1B, Accident Investigations.

185

Corrective and Preventive Action  

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

8 Corrective/Preventive Action Process 11_0414 Page 1 of 8 8 Corrective/Preventive Action Process 11_0414 Page 1 of 8 EOTA - Business Process Document Title: Corrective/Preventive Action Process Document Number: P-008 Rev 11_0414 Document Owner: Elizabeth Sousa Backup Owner: Melissa Otero Approver(s): Melissa Otero Parent Document: Q-001, Quality Manual Notify of Changes: EOTA Employees Referenced Document(s): P-004 Business System Management Review, F-017 Corrective Action Report Planning Worksheet or F-018 Preventive Action Report Planning Worksheet P-008 Corrective/Preventive Action Process 11_0414 Page 2 of 8 Revision History: Rev. Description of Change A Initial Release 08_0310 Implemented Multiple reviewer of "Root Cause" into process. 08_0313 Changed verbiage in Process, Responsibility and Definitions for clarification. Assigned new Backup Document Owner.

186

Naval Spent Fuel Rail Shipment Accident Exercise Objectives  

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

NAVAL SPENT FUEL RAIL SHIPMENT NAVAL SPENT FUEL RAIL SHIPMENT ACCIDENT EXERCISE OBJECTIVES * Familiarize stakeholders with the Naval spent fuel ACCIDENT EXERCISE OBJECTIVES Familiarize stakeholders with the Naval spent fuel shipping container characteristics and shipping practices * Gain understanding of how the NNPP escorts who accompany the spent fuel shipments will interact with civilian emergency services representatives g y p * Allow civilian emergency services agencies the opportunity to evaluate their response to a pp y p simulated accident * Gain understanding of how the communications links that would be activated in an accident involving a Naval spent fuel shipment would work 1 NTSF May 11 ACCIDENT EXERCISE TYPICAL TIMELINE * Conceptual/Organizational Meeting - April 6 E R T i d it t t d TYPICAL TIMELINE

187

Status of shipping provisions for large lithium batteries  

DOE Green Energy (OSTI)

In 1990, the Electric and Hybrid Propulsion Division of the US Department of Energy (DOE) established its ad hoc Advanced Battery Readiness Working Group to identify regulatory barriers to the commercialization of advanced electric vehicle (EV) battery technologies and to facilitate the removal of these barriers. As one of three sub-working groups, the Shipping Sub-working Group (SSWG) was formed to address regulatory issues associated with the domestic and international transport of new battery technologies under development for EV and hybrid electric vehicle (HEV) applications. The SSWG is currently working with DOT on a proposal, which is intended for submission and consideration at the July 1998 meeting of the UN Sub-Committee of Experts. It is their intent to secure full support for the revised proposal from both the German and French delegations prior to its submission. It is critical to obtain UN Sub-Committee approval in July 1998, so that the DOT proposal can be considered and approved by the UN Committee of Experts at their meeting in December 1998. The UN Committee of Experts meets only on even numbered years, so failure to secure their approval in December 1998 will cause a two-year delay in implementing international regulations for large EV and HEV lithium-ion and lithium-polymer batteries. Details of the DOT proposal are provided in this paper, including provisions that would relax the lithium and lithium-alloy mass restrictions in a general way, thereby providing a measure of relief for small cells and batteries.

Henriksen, G.L.

1998-01-01T23:59:59.000Z

188

MELCOR accident analysis for ARIES-ACT  

Science Conference Proceedings (OSTI)

We model a loss of flow accident (LOFA) in the ARIES-ACT1 tokamak design. ARIES-ACT1 features an advanced SiC blanket with LiPb as coolant and breeder, a helium cooled steel structural ring and tungsten divertors, a thin-walled, helium cooled vacuum vessel, and a room temperature water-cooled shield outside the vacuum vessel. The water heat transfer system is designed to remove heat by natural circulation during a LOFA. The MELCOR model uses time-dependent decay heats for each component determined by 1-D modeling. The MELCOR model shows that, despite periodic boiling of the water coolant, that structures are kept adequately cool by the passive safety system.

Paul W. Humrickhouse; Brad J. Merrill

2012-08-01T23:59:59.000Z

189

Angular dependence of a simple accident dosimeter  

SciTech Connect

A simple dosimeter made of a sulfur tablet, bare and cadmium covered indium foils and a cadmium covered copper foil has been modeled using MCNP5. Studies of the model without phantom or other confounding factors have shown that the cross sections and fluence-to-dose factors generated by the Monte Carlo method agree with those generated by analytic expressions for the high energy component. The threshold cross sections for the detectors on a phantom were calculated. The resulting doses assigned agree well with exposures made to three critical assemblies. In this study the angular dependence on a phantom is studied and compared with measurements taken on the GODIVA reactor. The dosimeter positions on the phantom are facing the source, on the back and the side. In previous papers the modeling of a simple dosimeter made of a sulfur tablet, bare and cadmium covered indium foils and a cadmium covered copper foil has been modeled using MCNP5. The conclusion made was that most of the neutron dose from criticality assemblies results from the high energy neutron fluences determined by the sulfur and indium detectors. The results using doses measured from the GODIVA, SHEBA, and bare and lead shielded SILENE reactors confirmed this. The angular dependence of an accident dosemeter is of interest in evaluating the exposure of personnel. To investigate this effect accident dosemeters were placed on a phantom and exposed to the GODIVA reactor at phantom orientations of 0{sup o}, 45{sup o}, 90{sup o}, 135{sup o}, and 180{sup o} to the assembly center line.

Devine, R. T. (Robert T.); Romero, L. L. (Leonard L.); Olsher, R. H. (Richard H.)

2004-01-01T23:59:59.000Z

190

Calculation notes in support of TWRS FSAR spray leak accident analysis  

SciTech Connect

This document contains the detailed calculations that support the spray leak accident analysis in the Tank Waste Remediation System (TWRS) Final Safety Analysis Report (FSAR). The consequence analyses in this document form the basis for the selection of controls to mitigate or prevent spray leaks throughout TWRS. Pressurized spray leaks can occur due to a breach in containment barriers along transfer routes, during waste transfers. Spray leaks are of particular safety concern because, depending on leak dimensions, and waste pressure, they can be relatively efficient generators of dispersible sized aerosols that can transport downwind to onsite and offsite receptors. Waste is transferred between storage tanks and between processing facilities and storage tanks in TWRS through a system of buried transfer lines. Pumps for transferring waste and jumpers and valves for rerouting waste are located inside below grade pits and structures that are normally covered. Pressurized spray leaks can emanate to the atmosphere due to breaches in waste transfer associated equipment inside these structures should the structures be uncovered at the time of the leak. Pressurized spray leaks can develop through holes or cracks in transfer piping, valve bodies or pump casings caused by such mechanisms as corrosion, erosion, thermal stress, or water hammer. Leaks through degraded valve packing, jumper gaskets, or pump seals can also result in pressurized spray releases. Mechanisms that can degrade seals, packing and gaskets include aging, radiation hardening, thermal stress, etc. An1782other common cause for spray leaks inside transfer enclosures are misaligned jumpers caused by human error. A spray leak inside a DST valve pit during a transfer of aging waste was selected as the bounding, representative accident for detailed analysis. Sections 2 through 5 below develop this representative accident using the DOE- STD-3009 format. Sections 2 describes the unmitigated and mitigated accident scenarios evaluated to determine the need for safety class SSCs or TSR controls. Section 3 develops the source terms associated with the unmitigated and mitigated accident scenarios. Section 4 estimates the radiological and toxicological consequences for the unmitigated and mitigated scenarios. Section 5 compares the radiological and toxicological consequences against the TWRS evaluation guidelines. Section 6 extrapolates from the representative accident case to other represented spray leak sites to assess the conservatism in using the representative case to define controls for other postulated spray leak sites throughout TWRS. Section 7 discusses the sensitivities of the consequence analyses to the key parameters and assumptions used in the analyses. Conclusions are drawn in Section 8. The analyses herein pertain to spray leaks initiated due to internal mechanisms (e.g., corrosion, erosion, thermal stress, etc). External initiators of spray leaks (e.g., excavation accidents), and natural phenomena initiators (e.g., seismic events) are to be covered in separate accident analyses.

Hall, B.W.

1996-09-25T23:59:59.000Z

191

Estate-level facility provision and management in market-rate and resettlement coexisting housing compounds  

E-Print Network (OSTI)

Market-rate and resettlement coexisting housing compound (MRCHC) is a special model of mixed-income neighborhood merging with the dilapidated housing renewal in the major cities of China. The provision and management of ...

Bai, Jie, M.C.P. Massachusetts Institute of Technology

2008-01-01T23:59:59.000Z

192

SLA-based resource provisioning for heterogeneous workloads in a virtualized cloud datacenter  

Science Conference Proceedings (OSTI)

Efficient provisioning of resources is a challenging problem in cloud computing environments due to its dynamic nature and the need for supporting heterogeneous applications with different performance requirements. Currently, cloud datacenter providers ...

Saurabh Kumar Garg; Srinivasa K. Gopalaiyengar; Rajkumar Buyya

2011-10-01T23:59:59.000Z

193

Volunteering for market-based environmental regulation : the substitution provision of the SO? emissions trading program  

E-Print Network (OSTI)

In this paper we explore the practical and welfare implications of a system of voluntary compliance within a market-based environmental regulation. The Substitution Provision of the SO2 emissions trading program allows the ...

Montero, Juan Pablo

194

Summary Impacts of Modeled Provisions of the 2003 Conference Energy Bill  

Reports and Publications (EIA)

This service report was undertaken at the February 2, 2004, request of Senator John Sununu to perform an assessment of the Conference Energy Bill of 2003. This report summarizes the CEB provisions that can be analyzed using the National Energy Modeling System (NEMS) and have the potential to affect energy consumption, supply, and prices. The impacts are estimated by comparing the projections with the CEB provisions to the AEO2004 Reference Case.

Andy Kydes

2004-02-01T23:59:59.000Z

195

Prevention & Treatment  

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

Prevention and Treatment Prevention and Treatment These steps may help prevent the spread of respiratory illnesses such as the flu: Stay Healthy Vaccination Antivirals Stay Informed Stay Healthy Cover your nose and mouth with a tissue when you cough or sneeze-throw the tissue away immediately after you use it. Wash your hands often with soap and water, especially after you cough or sneeze. If you are not near water, use an alcohol-based (60-95%) hand cleaner. Avoid close contact with people who are sick. When you are sick, keep your distance from others to protect them from getting sick too. If you get the flu, stay home from work, school, and social gatherings. This will help prevent others from catching your illness. Try not to touch your eyes, nose, or mouth. Germs often spread this way.

196

Spider Web Preventing  

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

Spider Web Preventing Name: William and Martha Location: NA Country: NA Date: NA Question: Hello. I found your site through the AskJeeves search engine doing a search for...

197

Investigation of Strategies for Mitigating Radiological Releases in Severe Accidents  

Science Conference Proceedings (OSTI)

The Fukushima Dai-ichi accident highlights the need to reduce the magnitude of radioactive fission product releases from BWR Mark I and II containments following beyond-design-basis events. There is no evidence that this accident has a long-term effect on public health and safety; however, the Fukushima Dai-ichi accident did result in widespread contamination of surrounding areas, both on-site and off-site. This report assesses various strategies that can be used to maintain BWR Mark I and II ...

2012-09-24T23:59:59.000Z

198

Severe accident sequences analyzed for a two-loop PWR  

Science Conference Proceedings (OSTI)

Different severe accident sequences have been analyzed for a two-loop Westinghouse pressurized water reactor (PWR) using the MELCOR code, version 1.8.4. The purpose of this study was to calculate source terms and the timing of events for severe accident sequences at this type of PWR to be used in the HAS-CAL code .The results calculated by MELCOR have been compared to results from the individual plant examination (IPE) of the Kewaunee nuclear power plant, also a two-loop Westinghouse PWR. The results of the Kewaunee IPE were obtained with the severe accident code MAAP.

Carbajo, J.J. [Oak Ridge National Lab., TN (United States)

1997-12-01T23:59:59.000Z

199

Progress in Addressing DNFSB Recommendation 2002-1 Issues: Improving Accident Analysis Software Applications  

Science Conference Proceedings (OSTI)

Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1 (''Quality Assurance for Safety-Related Software'') identified a number of quality assurance issues on the use of software in Department of Energy (DOE) facilities for analyzing hazards, and designing and operating controls to prevent or mitigate potential accidents. Over the last year, DOE has begun several processes and programs as part of the Implementation Plan commitments, and in particular, has made significant progress in addressing several sets of issues particularly important in the application of software for performing hazard and accident analysis. The work discussed here demonstrates that through these actions, Software Quality Assurance (SQA) guidance and software tools are available that can be used to improve resulting safety analysis. Specifically, five of the primary actions corresponding to the commitments made in the Implementation Plan to Recommendation 2002-1 are identified and discussed in this paper. Included are the web-based DOE SQA Knowledge Portal and the Central Registry, guidance and gap analysis reports, electronic bulletin board and discussion forum, and a DOE safety software guide. These SQA products can benefit DOE safety contractors in the development of hazard and accident analysis by precluding inappropriate software applications and utilizing best practices when incorporating software results to safety basis documentation. The improvement actions discussed here mark a beginning to establishing stronger, standard-compliant programs, practices, and processes in SQA among safety software users, managers, and reviewers throughout the DOE Complex. Additional effort is needed, however, particularly in: (1) processes to add new software applications to the DOE Safety Software Toolbox; (2) improving the effectiveness of software issue communication; and (3) promoting a safety software quality assurance culture.

VINCENT, ANDREW

2005-04-25T23:59:59.000Z

200

Environment/Health/Safety/Security (EHSS): Report an Accident...  

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

Report an Accident or Incident car and foot The law and DOE require prompt notification of all work-related EHS incidentsaccidents. Report all such events immediately to your...

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


201

Emergency Response to a Transportation Accident Involving Radioactive  

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

Response to a Transportation Accident Involving Response to a Transportation Accident Involving Radioactive Material Emergency Response to a Transportation Accident Involving Radioactive Material The purpose of this User's Guide is to provide instructors with an overview of the key points covered in the video. The Student Handout portion of this Guide is designed to assist the instructor in reviewing those points with students. The Student Handout should be distributed to students after the video is shown and the instructor should use the Guide to facilitate a discussion on each response disciplines' activities or duties at the scene. During this discussion, the instructor can present response scenarios, each of which would have a different discipline arriving first at the accident scene. The purpose of this discussion

202

Accidents, engineering and history at NASA: 1967-2003  

E-Print Network (OSTI)

The manned spaceflight program of the National Aeronautics and Space Administration (NASA) has suffered three fatal accidents: one in the Apollo program and two in the Space Transportation System (the Shuttle). These were ...

Brown, Alexander F. G. (Alexander Frederic Garder), 1970-

2009-01-01T23:59:59.000Z

203

FAQ 30-Have there been accidents involving uranium hexafluoride...  

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

UF6 was released, which reacted with steam from the process and created HF and uranyl fluoride. This accident resulted in two deaths from HF inhalation and three individuals...

204

HEALTH EFFECTS OF THE NUCLEAR ACCIDENT AT THREE MILE ISLAND  

E-Print Network (OSTI)

within 50 miles of the nuclear power plant was estimated tothe radiation from the nuclear power plant accident. From anand the Peach Bottom nuclear power plants, like the general

Fabrikant, J.I.

2010-01-01T23:59:59.000Z

205

Advanced Steels for Accident Tolerant Fuel Cladding in Commercial ...  

Science Conference Proceedings (OSTI)

... (depending on the LWR system and accident scenario) while maintaining or ... Analysis of the Fragmentation of AlON and Three MgAl2O4 Spinels under...

206

Structural evaluation of electrosleeved tubes under severe accident transients.  

Science Conference Proceedings (OSTI)

A flow stress model was developed for predicting failure of Electrosleeved PWR steam generator tubing under severe accident transients. The Electrosleeve, which is nanocrystalline pure nickel, loses its strength at temperatures greater than 400 C during severe accidents because of grain growth. A grain growth model and the Hall-Petch relationship were used to calculate the loss of flow stress as a function of time and temperature during the accident. Available tensile test data as well as high temperature failure tests on notched Electrosleeved tube specimens were used to derive the basic parameters of the failure model. The model was used to predict the failure temperatures of Electrosleeved tubes with axial cracks in the parent tube during postulated severe accident transients.

Majumdar, S.

1999-11-12T23:59:59.000Z

207

Geometry features measurement of traffic accident for reconstruction based on close-range photogrammetry  

Science Conference Proceedings (OSTI)

This paper studies the feasibility of investigating a traffic accident and offering initial data for traffic accident reconstruction (TAR) using a photogrammetric technique. Compared with the conventional roller tape applied by the traffic police of ... Keywords: Accident reconstruction, Close-range photogrammetry, Direct linear transformation, Traffic accident scene, Vehicle deformation

Xinguang Du; Xianlong Jin; Xiaoyun Zhang; Jie Shen; Xinyi Hou

2009-07-01T23:59:59.000Z

208

Evaluation of Accident Frequencies at the Canister Storage Bldg (CSB)  

DOE Green Energy (OSTI)

By using the fault tree logic, an evaluation of the design basis accident frequencies at the Canister Storage Building has been performed. The evaluation demonstrates that due to low frequency of occurrences, the following design basis accidents are considered not credible (annual frequency of less than 10{sup -6}): Rearrangement of multidster overpack (MCO) internals; Gaseous release from the MCO; MCO internal hydrogen explosion; MCO external hydrogen explosion; Thermal runaway reactions inside the MCO; and Violation of design temperature criteria.

LIU, Y.J.

1999-09-02T23:59:59.000Z

209

Review of cladding-coolant interactions during LWR accident transients  

Science Conference Proceedings (OSTI)

Some of the coolant-cladding interactions that can take place during the design basis loss-of-coolant accident and the Three Mile Island loss-of-coolant accident are analyzed. The physical manifestations of the interactions are quite similar, but the time sequences involved can cause very different end results. These results are described and a listing is given of the main research programs that are involved in coolant-cladding interaction research.

Hobson, D.O.

1980-01-01T23:59:59.000Z

210

Trees as Filters of Radioactive Fallout from the Chernobyl Accident  

E-Print Network (OSTI)

This paper is a copy of an unpublished study of the filtering effect of red maple trees (acer rubrum) on fission product fallout near Binghamton, NY, USA following the 1986 Chernobyl accident. The conclusions of this work may offer some insight into what is happening in the forests exposed to fallout from the Fukushima Daiichi Nuclear Plant accident. This posting is in memory of Noel K. Yeh.

Brownridge, James D

2011-01-01T23:59:59.000Z

211

Modular Accident Analysis Program (MAAP5) Applications Assessment  

Science Conference Proceedings (OSTI)

The Modular Accident Analysis Program (MAAP) is widely used throughout North America, Europe, and the Far East to analyze plant responses over a broad spectrum of potential accident conditions. The use of MAAP continues to increase because its representation of integral plant response and short run times make this program ideal for supporting engineering evaluations. With greater use, however, the level of detail to be represented within the reactor core, reactor coolant system (RCS), and containment has...

2005-12-08T23:59:59.000Z

212

Evaluation of accident frequencies at the canister storage building  

DOE Green Energy (OSTI)

By using the fault tree logic, an evaluation of the design basis accident frequencies at the Canister Storage Building has been performed. The evaluation demonstrates that due to low frequency of occurrences, the following design basis accidents are considered not credible (annual frequency of less than 10{sup -6}): Rearrangement of multi-canister overpack (MCO) internals; Gaseous release from the MCO; MCO internal hydrogen explosion; MCO external hydrogen explosion; Thermal runaway reactions inside the MCO; and Violation of design temperature criteria.

LIU, Y.J.

1999-05-13T23:59:59.000Z

213

Industry approach to seismic severe accident policy implementation  

Science Conference Proceedings (OSTI)

The Nuclear Regulatory Commission (NRC) issued a severe reactor accident policy for existing plants on August 8, 1985 which describes the formal basis by which the NRC intends to resolve issues related to potential severe reactor accidents. Examination of plant-specific vulnerabilities due to seismic and other externally initiated events was considered on a later schedule and is addressed in Supplement 4 of the NRC Generic Letter No. 88-20 and a NRC guidance document, NUREG-1407, issued in June 1991. This report was prepared to provide a coherent and effective approach for seismic severe accident review which meets the intent of Generic Letter No. 88-20, Supplement 4. The recommendations in this report provide guidance on plant review types and review implementations which is consistent with the limited-scope'' intent of systematic evaluations as described in the NRC's Severe Accident Policy Statement. In addition, to assist in implementing cost-effective modifications that reduce vulnerabilities, this report also presents specific guidelines for identification and treatment of vulnerabilities that may be used as a basis for defining closure of earthquake-related severe-accident issues. This report provides procedural instructions and guidance to support resolution of earthquake-related severe accident issues. More detailed background and technical justifications for the methods are documented elsewhere, and are referenced throughout this report as appropriate.

Reed, J.W. (Benjamin (Jack R.) and Associates, Inc., Mountain View, CA (United States)); O'Hara, T.F.; Jacobson, J.P. (Yankee Atomic Electric Co., Bolton, MA (United States)); Sewell, R.T.; Cornell, C.A. (Risk Engineering, Inc., Golden, CO (United States)); Buttemer, D.R. (Pickard, Lowe and Garrick, Inc., Encinitas, CA (United States)); Schmidt, W.R.; Freed, D.A. (MPR Associates, Inc., Washington, D

1991-11-01T23:59:59.000Z

214

Severe accidents in spent fuel pools in support of generic safety, Issue 82  

SciTech Connect

This investigation provides an assessment of the likelihood and consequences of a severe accident in a spent fuel storage pool - the complete draining of the pool. Potential mechanisms and conditions for failure of the spent fuel, and the subsequent release of the fission products, are identified. Two older PWR and BWR spent fuel storage pool designs are considered based on a preliminary screening study which tried to identify vulnerabilities. Internal and external events and accidents are assessed. Conditions which could lead to failure of the spent fuel Zircaloy cladding as a result of cladding rupture or as a result of a self-sustaining oxidation reaction are presented. Propagation of a cladding fire to older stored fuel assemblies is evaluated. Spent fuel pool fission product inventory is estimated and the releases and consequences for the various cladding scenarios are provided. Possible preventive or mitigative measures are qualitatively evaluated. The uncertainties in the risk estimate are large, and areas where additional evaluations are needed to reduce uncertainty are identified.

Sailor, V.L.; Perkins, K.R.; Weeks, J.R.; Connell, H.R.

1987-07-01T23:59:59.000Z

215

R and D Activities Supporting Severe Accident Management in CAREM-25  

Science Conference Proceedings (OSTI)

As part of the advanced design CAREM-25 Severe Accident Management Investigation Project (SAMIP), In-Vessel Retention (IVR) strategy analyses are carried on. One of the most promising initiatives in this area, is the development of an in-vessel metallic core catcher (IVCC) to arrest reactor vessel meltdown sequences during a severe accident, therefore preventing the reactor lower head to fail due to corium interactions. The concept working principle consists in the mixing of the catcher metallic material (so-called sacrificial material) with the corium relocating fragments in the reactor lower head after the initiation of relocation process. The catcher will limit the catcher-corium mixture temperature by boiling the sacrificial material. For this purpose, a low-boiling point material is chosen. A methodology consisting in thermo-hydraulic and FEA (Finite Elements Analysis) calculations was applied to evaluate the reactor vessel temperature profile in several scenarios. The calculational input was based, mainly, on data from CAREM-25 Preliminary Safety Analysis Report (PSAR). Sensitivity studies were performed to investigate the uncertainties in key parameters for these analyses. Calculation results indicate that less margin existed for vessel failure mechanisms when crust is not considered in the analyses. In addition, calculations suggest that additional evaluations are needed to reduce uncertainties in models for predicting corium catcher interaction. (author)

Pomier Baez, Lazaro E. [Instituto CEDIAC, Facultad de Ingenieria, Universidad Nacional de Cuyo, Parque Gral. San Martin, Mendoza 5500 (Argentina)

2002-07-01T23:59:59.000Z

216

Pollution Prevention and NEPA  

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

Council on Environmental Quality AGENCY: Council on Environmental Quality, Executive Office of the President ACTION: Information only--Memorandum to Heads of Federal Departments and Agencies Regarding Pollution Prevention and the National Environmental Policy Act SUMMARY: This memorandum provides guidance to the federal agencies on incorporating pollution prevention principles, techniques, and mechanisms into their planning and decisionmaking processes and evaluating and reporting those efforts in documents prepared pursuant to the National Environmental Policy Act. FOR FURTHER INFORMATION CONTACT: Lucinda Low Swartz, Deputy General Counsel, Council on Environmental Quality, 722 Jackson Place, N.W., Washington, D.C. 20503. Telephone: 202/395-5754.

217

Significant factors in rail freight accidents: A statistical analysis of predictive and severity indices in the FRA accident/incident data base  

Science Conference Proceedings (OSTI)

The Federal Railroad Association maintains a file of carrier-reported accidents and incidents that meet threshold criteria for damage cost and/or casualties. Using a five year period from this data base, an investigation was conducted into the relationship between quantifiable risk factors and accident frequency and severity. Specific objectives were to identify key variables in accidents, formulate a model to predict future accidents, and assess the relative importance of these variables from the perspective of routing and shipping decision making. The temporal factors YEAR and MONTH were found to be significant predictors of risk; accident severity was greatest for accidents caused by track and roadbed defects. Train speed was an indicator of accident severity; track class and training tonnage were inversely proportional to accident severity. Investigation of the data base is continuing, with a final report expected by late summer. 15 refs., 1 fig., 10 tabs.

Lee, Tze-San; Saricks, C.L.

1991-01-01T23:59:59.000Z

218

Preventing Electrical Shock  

E-Print Network (OSTI)

Most electrocution deaths on farms involve moving tall equipment that comes in contact with power lines. Other causes are damaged electrical systems in buildings and misuse of extension cords. This publication lists specific safety precautions you can take to prevent electrocution and handle emergencies should they occur.

Smith, David

2004-09-16T23:59:59.000Z

219

Policy Flash 2013-28 Implementation of Indian Energy Preference Provision  

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

8 Implementation of Indian Energy Preference 8 Implementation of Indian Energy Preference Provision in EP Act 2005 and Acquisition Letter 2013-02 Policy Flash 2013-28 Implementation of Indian Energy Preference Provision in EP Act 2005 and Acquisition Letter 2013-02 Attached is Policy Flash 2013-28 Implementation of Indian Energy Preference Provision in EP Act 2005 and Acquisition Letter 2013-02 Questions concerning this policy flash should be directed to Jason Taylor of the Contract and Financial Assistance Policy Division, Office of Policy, Office of Acquisition and Project Management at (202) 287-1945 or at jason.taylor@hq.doe.gov. Policy Flash for Indian Energy Preference (2).pdf AL 02 01 13 (2).pdf Attch_Secretarial Decision Memo_ Indian Energy Preference.pdf Attch_Secretarial Policy Memo.pdf More Documents & Publications

220

Energy Independence and Security Act of 2007: Summary of Provisions (released in AEO2008)  

Reports and Publications (EIA)

The Energy Independence and Security Act of 2007 was signed into law on December 19, 2007, and became Public Law 110-140 [8]. Provisions in EISA2007 that require funding appropriations to be implemented, whose impact is highly uncertain, or that require further specification by Federal agencies or Congress are not included in AEO2008. For example, EIA does not try to anticipate policy responses to the many studies required by EISA2007, nor to predict the impact of research and development (R&D) funding authorizations included in the bill. Moreover, AEO2008 does not include any provision that addresses a level of detail beyond that modeled in NEMS, which was used to develop the AEO2008 projections. AEO2008 addresses only those provisions in EISA2007 that establish specific tax credits, incentives, or standards, including the following:

Information Center

2008-06-26T23:59:59.000Z

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


221

SILENE Benchmark Critical Experiments for Criticality Accident Alarm Systems  

SciTech Connect

In October 2010 a series of benchmark experiments was conducted at the Commissariat a Energie Atomique et aux Energies Alternatives (CEA) Valduc SILENE [1] facility. These experiments were a joint effort between the US Department of Energy (DOE) and the French CEA. The purpose of these experiments was to create three benchmarks for the verification and validation of radiation transport codes and evaluated nuclear data used in the analysis of criticality accident alarm systems (CAASs). This presentation will discuss the geometric configuration of these experiments and the quantities that were measured and will present some preliminary comparisons between the measured data and calculations. This series consisted of three single-pulsed experiments with the SILENE reactor. During the first experiment the reactor was bare (unshielded), but during the second and third experiments it was shielded by lead and polyethylene, respectively. During each experiment several neutron activation foils and thermoluminescent dosimeters (TLDs) were placed around the reactor, and some of these detectors were themselves shielded from the reactor by high-density magnetite and barite concrete, standard concrete, and/or BoroBond. All the concrete was provided by CEA Saclay, and the BoroBond was provided by Y-12 National Security Complex. Figure 1 is a picture of the SILENE reactor cell configured for pulse 1. Also included in these experiments were measurements of the neutron and photon spectra with two BICRON BC-501A liquid scintillators. These two detectors were provided and operated by CEA Valduc. They were set up just outside the SILENE reactor cell with additional lead shielding to prevent the detectors from being saturated. The final detectors involved in the experiments were two different types of CAAS detectors. The Babcock International Group provided three CIDAS CAAS detectors, which measured photon dose and dose rate with a Geiger-Mueller tube. CIDAS detectors are currently in use at Y-12 in the newly constructed Highly Enriched Uranium Materials Facility. The second CAAS detector used a {sup 6}LiF TLD to absorb neutrons and a silicon detector to count the charge particles released by these absorption events. Lawrence Livermore National Laboratory provided four of these detectors, which had formerly been used at the Rocky Flats facility in the United States.

Miller, Thomas Martin [ORNL; Reynolds, Kevin H. [Y-12 National Security Complex

2011-01-01T23:59:59.000Z

222

PNNL Results from 2010 CALIBAN Criticality Accident Dosimeter Intercomparison Exercise  

SciTech Connect

This document reports the results of the Hanford personnel nuclear accident dosimeter (PNAD) and fixed nuclear accident dosimeter (FNAD) during a criticality accident dosimeter intercomparison exercise at the CEA Valduc Center on September 20-23, 2010. Pacific Northwest National Laboratory (PNNL) participated in a criticality accident dosimeter intercomparison exercise at the Commissariat a Energie Atomique (CEA) Valduc Center near Dijon, France on September 20-23, 2010. The intercomparison exercise was funded by the U.S. Department of Energy, Nuclear Criticality Safety Program, with Lawrence Livermore National Laboratory as the lead Laboratory. PNNL was one of six invited DOE Laboratory participants. The other participating Laboratories were: Lawrence Livermore National Laboratory (LLNL), Los Alamos National Laboratory (LANL), Savannah River Site (SRS), the Y-12 National Security Complex at Oak Ridge, and Sandia National Laboratory (SNL). The goals of PNNL's participation in the intercomparison exercise were to test and validate the procedures and algorithm currently used for the Hanford personnel nuclear accident dosimeters (PNADs) on the metallic reactor, CALIBAN, to test exposures to PNADs from the side and from behind a phantom, and to test PNADs that were taken from a historical batch of Hanford PNADs that had varying degrees of degradation of the bare indium foil. Similar testing of the PNADs was done on the Valduc SILENE test reactor in 2009 (Hill and Conrady, 2010). The CALIBAN results are reported here.

Hill, Robin L.; Conrady, Matthew M.

2011-10-28T23:59:59.000Z

223

Dog Bite Prevention  

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

Bite Prevention Bite Prevention Did you know that ...  4.7 million people in this country are bitten by dogs every year  children are by far the most common victims  800,000 Americans receive medical attention for dog bites each year  children are far more likely to be severely injured; approximately 400,000 receive medical attention every year  most dog bites affecting young children occur during everyday activities and while interacting with familiar dogs  senior citizens are the second most common dog bite victims There are a number of things that you can do to avoid dog bites, ranging from properly training and socializing your pet to educating your children on how, or if, they should approach a dog. Information is one of the best cures for this public health crisis.

224

Prevention and Control Strategies  

Science Conference Proceedings (OSTI)

Table 7   Prevention of corrosion in industrial facilities...? X ? X X Tanks, batteries ? X X ? X X External pipelines ? X X ? ? ? Internal pipelines ? ? ? ? ? ? Gas ? X ? X X ? Oil ? ? ? X X X Storage tanks X X X X X X Cooling systems (cooling towers, heat exchangers) X ? X ? X X...

225

Decommissioning And Its Financing In Belgium: Better To Prevent Than To Cure  

E-Print Network (OSTI)

Since 1985 the Belgian legislature has taken measures to guarantee the financing of the ultimate life period of nuclear facilities. An agreement was concluded with the utilities for the settlement of financial provisions for the later decommissioning of all commercial nuclear power plants. In 1991, the preventive measures were extended to all other nuclear facilities in the country, including healing actions for those plants having a lack of financial provisions to carry out the later decommissioning programs, as well as plants for which the operator or owner has failed to satisfy his legal obligation to decommission the plant. In 1997, the legislature extended the precautionary measures to financing for the remediation of all sites within the country containing radioactive substances liable to present risks for the public health or for the environment. The implementation and control of the measures taken since 1991 have been entrusted by laws to ONDRAF/NIRAS. 1.0 THE EVOLUTION...

Marnix Braeckeveldt Roger; Roger Verbeke; Manfred Schrauben; Ingrid Verstraeten

2000-01-01T23:59:59.000Z

226

Impact of seismic code provisions in the central U.S.: a performance evaluation of a reinforced concrete building  

E-Print Network (OSTI)

The close proximity to the New Madrid Seismic Zone and the significant population and infrastructure presents a potentially substantial risk for central U.S. cities such as Memphis, Tennessee. However, seismic provisions in currently adopted Memphis building codes for non-essential structures have a lower seismic design intensity level than the 2003 International Building Code (IBC) with broader acceptance nationally. As such, it is important to evaluate structures designed with these local seismic provisions to determine whether they will perform adequately during two different design-level earthquakes in this region. A four-story reinforced concrete (RC) moment frame with wide-module pan joists was designed according to current building codes relevant to the central U.S.: the 2003 IBC, the City of Memphis and Shelby County locally amended version of the 2003 IBC, and the 1999 Standard Building Code (SBC). Special moment frames (SMFs) were required for the IBC and SBC designs, but lower design forces in the amended IBC case study permitted an intermediate moment frame (IMF). However, the margin by which a SMF was required was very small for the SBC design. For slightly different conditions IMFs could be used. Nonlinear push-over and dynamic analyses using synthetic ground motions developed for Memphis for 2% and 10% probabilities of exceedance in 50 years were conducted for each of the three designs. The FEMA 356 recommended Basic Safety Objective (BSO) is to dually achieve Life Safety (LS) for the 10% in 50 years earthquake and Collapse Prevention (CP) for the 2% in 50 years earthquake. For the member-level evaluation, the SMF designs met the LS performance objective, but none of the designs met the CP performance objective or the BSO. However, the margin by which the SMF buildings exceeded CP performance was relatively small compared to that of the IMF building. Fragility curves were also developed to provide an estimate of the probability of exceeding various performance levels and quantitative performance limits. These relationships further emphasize the benefits of using an SMF as required by the IBC and, in this case, the SBC.

Kueht, Erin

2007-08-01T23:59:59.000Z

227

An application of probabilistic safety assessment methods to model aircraft systems and accidents  

DOE Green Energy (OSTI)

A case study modeling the thrust reverser system (TRS) in the context of the fatal accident of a Boeing 767 is presented to illustrate the application of Probabilistic Safety Assessment methods. A simplified risk model consisting of an event tree with supporting fault trees was developed to represent the progression of the accident, taking into account the interaction between the TRS and the operating crew during the accident, and the findings of the accident investigation. A feasible sequence of events leading to the fatal accident was identified. Several insights about the TRS and the accident were obtained by applying PSA methods. Changes proposed for the TRS also are discussed.

Martinez-Guridi, G.; Hall, R.E.; Fullwood, R.R.

1998-08-01T23:59:59.000Z

228

Accident Investigation at the Idaho National Laboratory Engineering  

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

Accident Investigation at the Idaho National Laboratory Engineering Accident Investigation at the Idaho National Laboratory Engineering Demonstration Facility, February 2013 Accident Investigation at the Idaho National Laboratory Engineering Demonstration Facility, February 2013 On Monday, February 12, 2013, a principal investigator at the Idaho National Laboratory (INL) Engineering Demonstration Facility (IEDF) was testing the system configuration of experimental process involving liquid sodium carbonate. An unanticipated event occurred that resulted in the ejection of the 900° C liquid sodium carbonate from the system. The ejected liquid came into contact with the principal investigator and caused multiple second and third degree burn injuries to approximately 10 percent of his body. The Office of Health, Safety and Security (HSS) Site Lead for

229

Simple and Effective Dynamic Provisioning for Power-Proportional Data Centers  

E-Print Network (OSTI)

Energy consumption represents a significant cost in data center operation. A large fraction of the energy, however, is used to power idle servers when the workload is low. Dynamic provisioning techniques aim at saving this portion of the energy, by turning off unnecessary servers. In this paper, we explore how much performance gain can knowing future workload information brings to dynamic provisioning. In particular, we study the dynamic provisioning problem under the cost model that a running server consumes a fixed amount energy per unit time, and develop online solutions with and without future workload information available. We first reveal an elegant structure of the off-line dynamic provisioning problem, which allows us to characterize and achieve the optimal solution in a {}"divide-and-conquer" manner. We then exploit this insight to design three online algorithms with competitive ratios $2-\\alpha$, $(e-\\alpha)/(e-1)\\approx1.58-\\alpha/(e-1)$ and $e/(e-1+\\alpha)$, respectively, where $0\\leq\\alpha\\leq1$ ...

Lu, Tan

2011-01-01T23:59:59.000Z

230

A survey of trust and reputation systems for online service provision  

Science Conference Proceedings (OSTI)

Trust and reputation systems represent a significant trend in decision support for Internet mediated service provision. The basic idea is to let parties rate each other, for example after the completion of a transaction, and use the aggregated ratings ... Keywords: Collaboration, Decision, E-commerce, Reputation, Security, Transitivity, Trust

Audun Jsang; Roslan Ismail; Colin Boyd

2007-03-01T23:59:59.000Z

231

Agent-Based Support for Context-Aware Provisioning of IMS-Enabled Ubiquitous Services  

Science Conference Proceedings (OSTI)

Multimedia applications executed on mobile devices allow users to be present and communicate with other users, anywhere and anytime, through wide area cellular networks, wireless local area networks (WLAN), or fixed networks. In order to enable ubiquitous ... Keywords: IMS-enabled services, context-aware service provisioning, multi-agent system, session mobility

Ana Petric; Krunoslav Trzec; Kresimir Jurasovic; Vedran Podobnik; Gordan Jezic; Mario Kusek; Igor Ljubi

2009-11-01T23:59:59.000Z

232

UC COMPENSATION FOR INJURY 1a. GENERAL PROVISION OF MEDICAL TREATMENT OR REIMBURSEMENT OF MEDICAL COST  

E-Print Network (OSTI)

UC COMPENSATION FOR INJURY GUIDELINES 1a. GENERAL PROVISION OF MEDICAL TREATMENT OR REIMBURSEMENT OF MEDICAL COST The University of California will provide to any injured subject any and all medical or illness is a consequence of a medical research procedure which is designed to benefit the subject directly

El Zarki, Magda

233

Analysis of QoS Provisioning in Cognitive Radio Networks: A Case Study  

Science Conference Proceedings (OSTI)

Dynamic Spectrum Access (DSA) is a promising solution to the problem of spectrum inefficiency. Based on Cognitive Radio (CR) technology, DSA allows a CR device to opportunistically access unused or less crowded spectrum while ensuring protection for ... Keywords: Cognitive radio, Dynamic spectrum access, QoS provisioning, Spectrum sensing

Ashwini Kumar; Jianfeng Wang; Kiran Challapali; Kang G. Shin

2011-03-01T23:59:59.000Z

234

Cloud Resource Provisioning to Extend the Capacity of Local Resources in the Presence of Failures  

E-Print Network (OSTI)

infrastructures through web services. In this platform, the complexity of man- aging an IT infrastructure cost-aware and failure-aware provisioning poli- cies that can be utilized by an organization is completely hidden from its users. One particular type of Cloud service, known as Infrastructure- as

Buyya, Rajkumar

235

Performance analysis of allocation policies for interGrid resource provisioning  

Science Conference Proceedings (OSTI)

Several Grids have been established and used for varying science applications during the last years. Most of these Grids, however, work in isolation and with different utilisation levels. Previous work has introduced an architecture and a mechanism to ... Keywords: Grid computing, InterGrid resource allocation, Resource provisioning

Marcos Dias de Assuno; Rajkumar Buyya

2009-01-01T23:59:59.000Z

236

Dynamic provisioning in next-generation data centers with on-site power production  

Science Conference Proceedings (OSTI)

The critical need for clean and economical sources of energy is transforming data centers that are primarily energy consumers to also energy producers. We focus on minimizing the operating costs of next-generation data centers that can jointly optimize ... Keywords: data centers, dynamic provisioning, on-site power production, online algorithm

Jinlong Tu, Lian Lu, Minghua Chen, Ramesh K. Sitaraman

2013-01-01T23:59:59.000Z

237

Enterprise Storage Provisioning with Flash Drives In the past, enterprise storage systems were configured  

E-Print Network (OSTI)

only SCSI devices in all key as- pects: price, performance and energy consumption. As we relax new concern is the energy consumed by a stor- age system, driven in part by the trend toward "green.3, we look forward to see how these trends change as flash decreases in price. 6.1 Example: Provisioning

Bachmat, Eitan

238

PROPHET: Goal-Oriented Provisioning for Highly Tunable Multicore Processors in Cloud Computing  

E-Print Network (OSTI)

Hyuk Woo Hsien-Hsin S. Lee School of Electrical and Computer Engineering Georgia Institute PROPHET, a goal-oriented provisioning infrastructure based on execution history profile gathered from of energy, power, and performance when running parallel workloads poses a new challenge to both large

Lee, Hsien-Hsin "Sean"

239

Energy Improvement and Extension Act of 2008: Summary of Provisions (released in AEO2009)  

Reports and Publications (EIA)

The Emergency Economic Stabilization Act of 2008 (Public Law 110-343), which was signed into law on October 3, 2008, incorporates EIEA2008 in Division B. Provisions in EIEA2008 that require funding appropriations to be implemented, whose impact is highly uncertain or that require further specification by Federal agencies or Congress, are not included in AEO2009.

Information Center

2009-03-31T23:59:59.000Z

240

American Recovery and Reinvestment Act of 2009: Summary of Provisions (released in AEO2010)  

Reports and Publications (EIA)

ARRA, signed into law in mid-February 2009, provides significant new Federal funding, loan guarantees, and tax credits to stimulate investments in energy efficiency and renewable energy. The provisions of ARRA were incorporated initially as part of a revision to the AEO2009 Reference case that was released in April 2009, and they also are included in AEO2010.

Information Center

2010-05-11T23:59:59.000Z

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


241

Towards Standardized and Automated Fault Management and Service Provisioning for NGNs  

Science Conference Proceedings (OSTI)

The IP Multimedia Subsystem (IMS), already widely recognized as a fundamental core component of Next Generation Networks (NGNs), enables proliferation of a huge variety of value added services. Simultaneous to the emergence of triple play services there ... Keywords: IP Multimedia Subsystem, New Generation Operations Systems and Software, Service Oriented Architectures, Service assurance, Service fulfillment, Service provisioning

Niklas Blum; Piotr Jacak; Florian Schreiner; Dragos Vingarzan; Peter Weik

2008-03-01T23:59:59.000Z

242

Online job provisioning for large scale science experiments over an optical grid infrastructure  

Science Conference Proceedings (OSTI)

Many emerging science experiments require that the massive data generated by big instruments be accessible and analyzed by a large number of geographically dispersed users. Such large scale science experiments are enabled by an Optical Grid infrastructure ... Keywords: WDM network, grid, job provisioning, large scale science experiment, resource co-scheduling

Xiang Yu; Chunming Qiao; Dantong Yu

2009-04-01T23:59:59.000Z

243

Resource provisioning with budget constraints for adaptive applications in cloud environments  

Science Conference Proceedings (OSTI)

Utility computing was a vision stated more than 40 years ago. It refers to the idea that computing resources and services can be delivered, utilized, and paid for as utilities such as water or electricity. The recent emergence of cloud computing ... Keywords: adaptive applications, cloud computing, resource provisioning

Qian Zhu; Gagan Agrawal

2010-06-01T23:59:59.000Z

244

An Analysis of Provisioning and Allocation Policies for Infrastructure-as-a-Service Clouds  

Science Conference Proceedings (OSTI)

Today, many commercial and private cloud computing providers offer resources for leasing under the infrastructure as a service (IaaS) paradigm. Although an abundance of mechanisms already facilitate the lease and use of single infrastructure resources, ... Keywords: Scheduling, Cloud computing, provisioning policies, allocation policies, empirical performance analysis

David Villegas; Athanasios Antoniou; Seyed Masoud Sadjadi; Alexandru Iosup

2012-05-01T23:59:59.000Z

245

A general scalable and accurate decentralized level monitoring method for large-scale dynamic service provision in hybrid clouds  

Science Conference Proceedings (OSTI)

Hybrid cloud computing combines private clouds with geographically-distributed resources from public clouds, desktop grids or in-house gateways to provide the most flexibility of each kind of cloud platforms. Service provisioning for wide-area applications ... Keywords: Application health monitoring, Decentralized algorithm, Decentralized matrix factorization, Hierarchical decomposition, K-means clustering, Service provision

Yongquan Fu; Yijie Wang; Ernst Biersack

2013-07-01T23:59:59.000Z

246

Comparison of fusedose and MACCS2 accident dose codes  

Science Conference Proceedings (OSTI)

The purpose of this paper is to present and document the differences discovered when comparing the two accident dose codes FUSEDOSE and MACCS2. Each code`s methodology is first discussed. With this background, the important comparison parameters are discussed and the resulting differences are presented. It is not the purpose of this paper to draw conclusions as to which code is more reliable but, it is hoped that the data presented will help in deciding upon further actions to be taken, if at all, to improve accident dose calculations. 7 refs., 1 fig., 1 tab.

Sevigny, L.M. [Univ. of California, Berkeley, CA (United States)

1996-12-31T23:59:59.000Z

247

Initiatives for proliferation prevention  

SciTech Connect

Preventing the proliferation of weapons of mass destruction is a central part of US national security policy. A principal instrument of the Department of Energy`s (DOE`s) program for securing weapons of mass destruction technology and expertise and removing incentives for scientists, engineers and technicians in the newly independent states (NIS) of the former Soviet Union to go to rogue countries or assist terrorist groups is the Initiatives for Proliferation Prevention (IPP). IPP was initiated pursuant to the 1994 Foreign Operations Appropriations Act. IPP is a nonproliferation program with a commercialization strategy. IPP seeks to enhance US national security and to achieve nonproliferation objectives by engaging scientists, engineers and technicians from former NIS weapons institutes; redirecting their activities in cooperatively-developed, commercially viable non-weapons related projects. These projects lead to commercial and economic benefits for both the NIS and the US IPP projects are funded in Russian, Ukraine, Kazakhstan and Belarus. This booklet offers an overview of the IPP program as well as a sampling of some of the projects which are currently underway.

1997-04-01T23:59:59.000Z

248

Three dimensional effects in analysis of PWR steam line break accident  

E-Print Network (OSTI)

A steam line break accident is one of the possible severe abnormal transients in a pressurized water reactor. It is required to present an analysis of a steam line break accident in the Final Safety Analysis Report (FSAR) ...

Tsai, Chon-Kwo

249

Report on the Scope of the Accident Investigation of the Tristan...  

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

Report on the Scope of the Accident Investigation of the Tristan Fire at the DOE Brookhaven National Laboratory, IG-0386 Report on the Scope of the Accident Investigation of the...

250

Substantiation of Thermodynamic Criteria of Explosion Safety in Process of Severe Accidents in Pressure Vessel Reactors  

E-Print Network (OSTI)

The paper represents original development of thermodynamic criteria of occurrence conditions of steam-gas explosions in the process of severe accidents. The received results can be used for modelling of processes of severe accidents in pressure vessel reactors.

Skalozubov, V I; Jarovoj, S S; Kochnyeva, V Yu

2012-01-01T23:59:59.000Z

251

Substantiation of Thermodynamic Criteria of Explosion Safety in Process of Severe Accidents in Pressure Vessel Reactors  

E-Print Network (OSTI)

The paper represents original development of thermodynamic criteria of occurrence conditions of steam-gas explosions in the process of severe accidents. The received results can be used for modelling of processes of severe accidents in pressure vessel reactors.

V. I. Skalozubov; V. N. Vashchenko; S. S. Jarovoj; V. Yu. Kochnyeva

2012-03-27T23:59:59.000Z

252

Combining neural methods and knowledge-based methods in accident management  

Science Conference Proceedings (OSTI)

Accident management became a popular research issue in the early 1990s. Computerized decision support was studied from many points of view. Early fault detection and information visualization are important key issues in accident management also today. ...

Miki Sirola, Jaakko Talonen

2012-01-01T23:59:59.000Z

253

Normal accidents: Data quality problems in ERP-enabled manufacturing  

Science Conference Proceedings (OSTI)

The efficient operation of Enterprise Resource Planning (ERP) systems largely depends on data quality. ERP can improve data quality and information sharing within an organization. It can also pose challenges to data quality. While it is well known that ... Keywords: Data quality, ERP, complexity, enterprise resource planning, normal accident, tight coupling

Lan Cao, Hongwei Zhu

2013-05-01T23:59:59.000Z

254

Hanford Waste Tank Bump Accident and Consequence Analysis  

Science Conference Proceedings (OSTI)

This report provides a new evaluation of the Hanford tank bump accident analysis and consequences for incorporation into the Authorization Basis. The analysis scope is for the safe storage of waste in its current configuration in single-shell and double-shell tanks.

BRATZEL, D.R.

2000-06-20T23:59:59.000Z

255

Criticality accident alarm system at the Fernald Environmental Management Project  

SciTech Connect

The purpose of this paper is to give a description of the Criticality Accident Alarm System (CAAS) presently installed at the Fernald Environmental Management Project (FEMP) for monitoring areas requiring criticality controls, and some of the concerns associated with the operation of this system. The system at the FEMP is known as the Radiation Detection Alarm (RDA) System.

Marble, R.C.; Brown, T.D.; Wooldridge, J.C.

1994-06-01T23:59:59.000Z

256

THE ANALYSIS OF FATAL ACCIDENTS IN INDIAN D. Sengupta1  

E-Print Network (OSTI)

THE ANALYSIS OF FATAL ACCIDENTS IN INDIAN COAL MINES A. Mandal D. Sengupta1 Indian Statistical of Indian coal mines from April 1989 to March 1998. It is found that Indian mines have considerably higher over 600,000 miners and other workers. Safety in the Indian coal mines is therefore a very important

Mandal, Abhyuday

257

A SUMMARY OF INDUSTRIAL ACCIDENTS IN USAEC FACILITIES  

SciTech Connect

The accident experience of the AEC contractor operation for 1959 and 1960 is reported. Incidents involving radio active materials are described. A table of inadvertent criticality was included to supplement other tables. A tabulation of exposure records at values from 0 to 15 r is given. (M.C.G.)

1962-10-31T23:59:59.000Z

258

Test Data for USEPR Severe Accident Code Validation  

SciTech Connect

This document identifies data that can be used for assessing various models embodied in severe accident analysis codes. Phenomena considered in this document, which were limited to those anticipated to be of interest in assessing severe accidents in the USEPR developed by AREVA, include: Fuel Heatup and Melt Progression Reactor Coolant System (RCS) Thermal Hydraulics In-Vessel Molten Pool Formation and Heat Transfer Fuel/Coolant Interactions during Relocation Debris Heat Loads to the Vessel Vessel Failure Molten Core Concrete Interaction (MCCI) and Reactor Cavity Plug Failure Melt Spreading and Coolability Hydrogen Control Each section of this report discusses one phenomenon of interest to the USEPR. Within each section, an effort is made to describe the phenomenon and identify what data are available modeling it. As noted in this document, models in US accident analysis codes (MAAP, MELCOR, and SCDAP/RELAP5) differ. Where possible, this report identifies previous assessments that illustrate the impact of modeling differences on predicting various phenomena. Finally, recommendations regarding the status of data available for modeling USEPR severe accident phenomena are summarized.

J. L. Rempe

2007-05-01T23:59:59.000Z

259

Getting to necessary and sufficient-developing accident scenarios for risk assessment  

Science Conference Proceedings (OSTI)

This paper presents a simple, systematic approach for developing accident scenarios using generic accident types. Result is a necessary and sufficient set of accident scenarios that can be used to establish the safety envelope for a facility or operation. Us of this approach along with the methodology of SAND95-0320 will yield more consistent accident analyses between facilities and provide a sound basis for allocating limited risk reduction resources.

Mahn, J.A.

1996-05-01T23:59:59.000Z

260

K West Basin Integrated Water Treatment System (IWTS) E-F Annular Filter Vessel Accident Calculations  

DOE Green Energy (OSTI)

Three bounding accidents postdated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing, and a hydrogen explosion. Event trees and accident probabilities are estimated. In all cases, the unmitigated dose consequences are below the risk evaluation guidelines.

RITTMANN, P.D.

1999-10-07T23:59:59.000Z

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


261

K West Basin Integrated Water Treatment System (IWTS) E-F Annular Filter Vessel Accident Calculations  

DOE Green Energy (OSTI)

Four bounding accidents postulated for the K West Basin integrated water treatment system are evaluated against applicable risk evaluation guidelines. The accidents are a spray leak during fuel retrieval, spray leak during backflushing a hydrogen explosion, and a fire breaching filter vessel and enclosure. Event trees and accident probabilities are estimated. In all cases, the unmitigated dose consequences are below the risk evaluation guidelines.

PIEPHO, M.G.

2000-01-10T23:59:59.000Z

262

A SUMMARY OF INDUSTRIAL ACCIDENTS IN USAEC FACILITIES, 1961-1962  

SciTech Connect

Information is presented on accidents andd incidents occurring during 1961 and 1962 in plants owned and operated by the AEC. Revised reporting requirements established by the AEC in April 1962 are outlined. Data are summarized on radiation exposure of AEC contractor personnel, accidents involving radioactive materials, andd accidents involving fatalities. (C.H.)

1964-10-31T23:59:59.000Z

263

Radionuclide release calculations for selected severe accident scenarios  

Science Conference Proceedings (OSTI)

This report provides the results of source term calculations that were performed in support of the NUREG-1150 study. Severe Accident Risks: An Assessment for Five US Nuclear Power Plants.'' This is the sixth volume of a series of reports. It supplements results presented in the earlier volumes. Analyses were performed for three of the NUREG-1150 plants: Peach Bottom, a Mark I, boiling water reactor; Surry, a subatmospheric containment, pressurized water reactor; and Sequoyah, an ice condenser containment, pressurized water reactor. Complete source term results are presented for the following sequences: short term station blackout with failure of the ADS system in the Peach Bottom plant; station blackout with a pump seal LOCA for the Surry plant; station blackout with a pump seal LOCA in the Sequoyah plant; and a very small break with loss of ECC and spray recirculation in the Sequoyah plant. In addition, some partial analyses were performed which did not require running all of the modules of the Source Term Code Package. A series of MARCH3 analyses were performed for the Surry and Sequoyah plants to evaluate the effects of alternative emergency operating procedures involving primary and secondary depressurization on the progress of the accident. Only thermal-hydraulic results are provided for these analyses. In addition, three accident sequences were analyzed for the Surry plant for accident-induced failure of steam generator tubes. In these analyses, only the transport of radionuclides within the primary system and failed steam generator were examined. The release of radionuclides to the environment is presented for the phase of the accident preceding vessel meltthrough. 17 refs., 176 figs., 113 tabs.

Denning, R.S.; Leonard, M.T.; Cybulskis, P.; Lee, K.W.; Kelly, R.F.; Jordan, H.; Schumacher, P.M.; Curtis, L.A. (Battelle Columbus Div., OH (USA))

1990-08-01T23:59:59.000Z

264

Accident management for indian pressurized heavy water reactors  

Science Conference Proceedings (OSTI)

Indian nuclear power program as of now is mainly based on Pressurized Heavy Water Reactors (PHWRs). Operating Procedures for normal power operation and Emergency Operating Procedures for operational transients and accidents within design basis exist for all Indian PHWRs. In addition, on-site and off-site emergency response procedures are also available for these NPPs. The guidelines needed for severe accidents mitigation are now formally being documented for Indian PHWRs. Also, in line with International trend of having symptom based emergency handling, the work is in advanced stage for preparation of symptom-based emergency operating procedures. Following a plant upset condition; a number of alarms distributed in different information systems appear in the control room to aid operator to identify the nature of the event. After identifying the event, appropriate intervention in the form of event based emergency operating procedure is put into use by the operating staff. However, if the initiating event cannot be unambiguously identified or after the initial event some other failures take place, then the selected event based emergency operating procedure will not be optimal. In such a case, reactor safety is ensured by monitoring safety functions (depicted by selected plant parameters grouped together) throughout the event handling so that the barriers to radioactivity release namely, fuel and fuel cladding, primary heat transport system integrity and containment remain intact. Simultaneous monitoring of all these safety functions is proposed through status trees and this concept will be implemented through a computer-based system. For beyond design basis accidents, event sequences are identified which may lead to severe core damage. As part of this project, severe accident mitigation guidelines are being finalized for the selected event sequences. The paper brings out the details of work being carried out for Indian PHWRs for symptom based event handling and severe accident management. (authors)

Hajela, S.; Grover, R.; Ghadge, S.G.; Bajaj, S.S. [Directorate of Safety, Nuclear Power Corporation of India Limited Nabhikiya Urja Bhawan, Anushakti Nagar, Mumbai-400 094 (India)

2006-07-01T23:59:59.000Z

265

Preventive Action Number:  

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

7 Corrective Action Report Planning Worksheet 11_0414 1 of 3 7 Corrective Action Report Planning Worksheet 11_0414 1 of 3 EOTA - Business Form Document Title: Corrective Action Report Planning Worksheet Document Number: F-017 Rev 11_0414 Document Owner: Elizabeth Sousa Backup Owner: Melissa Otero Approver(s): Melissa Otero Parent Document: P-008, Corrective/Preventive Action Notify of Changes: EOTA Employees Referenced Document(s): N/A F-017 Corrective Action Report Planning Worksheet 11_0414 2 of 3 Revision History: Rev. Description of Change 08_0613 Initial Release 11_0414 Added problem statement to first block. F-017 Corrective Action Report Planning Worksheet 11_0414 3 of 3 Corrective Action Report Planning Worksheet Corrective Action Number: Source: Details/Problem Statement: Raised By: Raised Date: Target Date:

266

Pocket Guide: Preventing Switching Errors  

Science Conference Proceedings (OSTI)

There are many conditions that are frequently identified as factors contributing to, if not directly causing, accidents and other unwanted events. These have come to be called "error-likely conditions." In 2010, the Electric Power Research Institute (EPRI) published report 1020018, Error-Likely Situations in Power Switching. That report was the first large-scale effort to fill the knowledge gap in the area of error-likely situations in power switching, and it identified over 100 potentially error-likely ...

2011-12-12T23:59:59.000Z

267

Cost-Effectiveness Analysis of the 2009 and 2012 IECC Residential Provisions -- Technical Support Document  

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

2068 2068 Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 Cost-Effectiveness Analysis of the 2009 and 2012 IECC Residential Provisions - Technical Support Document V Mendon R Lucas S Goel April 2013 PNNL-22068 Cost-Effectiveness Analysis of the 2009 and 2012 IECC Residential Provisions - Technical Support Document V Mendon R Lucas S Goel April 2013 Prepared for the U.S. Department of Energy under Contract DE-AC05-76RL01830 Pacific Northwest National Laboratory Richland, Washington 99352 iii Executive Summary This analysis was conducted by Pacific Northwest National Laboratory (PNNL) in support of the U.S. Department of Energy's (DOE) Building Energy Codes Program (BECP). DOE supports the

268

Preventive Maintenance | Department of Energy  

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

Preventive Maintenance Preventive Maintenance Preventive Maintenance October 7, 2013 - 9:44am Addthis Preventive maintenance aims to sustain or extend system lifespan through a set of actions that detect, preclude, or mitigate system degradation. These actions are based on either calendar time or machine run time. Advantages Federal agencies can greatly extend equipment reliability and lifespan by expending the necessary resources for regular maintenance. In most cases, the system designer or manufacturer outlines regular maintenance under a preventive strategy. In addition to increased reliability and lifespan, budget is saved over the life of the system. Preventive maintenance programs can save as much as 12% to 18% in equipment repair and replacement. Other advantages of preventitive maintenance are:

269

Mitigation of Severe Accident Consequences Using Inherent Safety Principles  

Science Conference Proceedings (OSTI)

Sodium-cooled fast reactors are designed to have a high level of safety. Events of high probability of occurrence are typically handled without consequence through reliable engineering systems and good design practices. For accidents of lower probability, the initiating events are characterized by larger and more numerous challenges to the reactor system, such as failure of one or more major engineered systems and can also include a failure to scram the reactor in response. As the initiating conditions become more severe, they have the potential for creating serious consequences of potential safety significance, including fuel melting, fuel pin disruption and recriticality. If the progression of such accidents is not mitigated by design features of the reactor, energetic events and dispersal of radioactive materials may result. For severe accidents, there are several approaches that can be used to mitigate the consequences of such severe accident initiators, which typically include fuel pin failures and core disruption. One approach is to increase the reliability of the reactor protection system so that the probability of an ATWS event is reduced to less than 1 x 10-6 per reactor year, where larger accident consequences are allowed, meeting the U.S. NRC goal of relegating such accident consequences as core disruption to these extremely low probabilities. The main difficulty with this approach is to convincingly test and guarantee such increased reliability. Another approach is to increase the redundancy of the reactor scram system, which can also reduce the probability of an ATWS event to a frequency of less than 1 x 10-6 per reactor year or lower. The issues with this approach are more related to reactor core design, with the need for a greater number of control rod positions in the reactor core and the associated increase in complexity of the reactor protection system. A third approach is to use the inherent reactivity feedback that occurs in a fast reactor to automatically respond to the change in reactor conditions and to result in a benign response to these events. This approach has the advantage of being relatively simple to implement, and does not face the issue of reliability since only fundamental physical phenomena are used in a passive manner, not active engineered systems. However, the challenge is to present a convincing case that such passive means can be implemented and used. The purpose of this paper is to describe this third approach in detail, the technical basis and experimental validation for the approach, and the resulting reactor performance that can be achieved for ATWS events.

R. A. Wigeland; J. E. Cahalan

2009-12-01T23:59:59.000Z

270

Portsmouth Site Plant Surpasses Five Years Without Lost-Time Accident |  

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

Plant Surpasses Five Years Without Lost-Time Plant Surpasses Five Years Without Lost-Time Accident Portsmouth Site Plant Surpasses Five Years Without Lost-Time Accident November 26, 2013 - 12:00pm Addthis BWCS employees from all departments of the DUF6 project at the Portsmouth site come together to mark five years without a lost-time accident. BWCS employees from all departments of the DUF6 project at the Portsmouth site come together to mark five years without a lost-time accident. Russ Hall, environment, safety and health supervisor, changes the DUF6 project sign to mark five years without a lost-time accident. Russ Hall, environment, safety and health supervisor, changes the DUF6 project sign to mark five years without a lost-time accident. BWCS employees from all departments of the DUF6 project at the Portsmouth site come together to mark five years without a lost-time accident.

271

Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident  

Alternative Fuels and Advanced Vehicles Data Center (EERE)

Natural Gas Safety Natural Gas Safety after a Traffic Accident to someone by E-mail Share Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Facebook Tweet about Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Twitter Bookmark Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Google Bookmark Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Delicious Rank Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on Digg Find More places to share Alternative Fuels Data Center: Natural Gas Safety after a Traffic Accident on AddThis.com... More in this section... Natural Gas Basics Benefits & Considerations Stations Vehicles Availability Conversions Emissions

272

Grandfathering provisions  

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

National Renewable Fuel Standard National Renewable Fuel Standard Program - 2010 and Beyond 2010 Energy Conference April 6 & 7, 2010 Paul Argyropoulos Office of Transportation and Air Quality US Environmental Protection Agency 2 Overview  National Renewable Fuel Standards as Required by EISA  Key Highlights of the RFS2 Rule  The 2010 Standards  Example RFS2 2022 Projections  EISA Waiver Authorities  Conclusions / Questions 3 Key Changes Required by EISA  Energy Independence and Security Act (December 2007) required changes to the RFS program  Significantly increased volumes of renewable fuel - to 36 billion gallons  Expanded from on road gasoline to on and off-road gasoline and diesel  Separation of the volume requirements into four separate categories of renewable

273

Oil and Natural Gas Market Supply and Renewable Portfolio Standard Impacts of Selected Provisions of H.R. 3221  

Gasoline and Diesel Fuel Update (EIA)

Oil and Natural Gas Market Supply and Renewable Portfolio Standard Impacts of Selected Provisions of Oil and Natural Gas Market Supply and Renewable Portfolio Standard Impacts of Selected Provisions of H.R. 3221 1 Oil and Natural Gas Market Supply and Renewable Portfolio Standard Impacts of Selected Provisions of H.R. 3221 November 2007 This paper responds to an October 31, 2007, request from Representatives Barton, McCrery, and Young. Their letter, a copy of which is provided as Appendix A, asks the Energy Information Administration (EIA) to assess selected provisions of H.R. 3221, the energy bill adopted by the House of Representatives in early August 2007. EIA was asked to focus on Title VII, dealing with energy on Federal lands; Section 9611, which would establish a Federal renewable portfolio standard (RPS) for certain electricity sellers; and Section 13001, which would eliminate the

274

Volume II - Accident and Operational Safety Analysis Handbook  

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

208-2012 208-2012 July 2012 DOE HANDBOOK Accident and Operational Safety Analysis Volume II: Operational Safety Analysis Techniques U.S. Department of Energy Washington, D.C. 20585 NOT MEASUREMENT SENSITIVE DOE-HDBK-1208-2012 i ACKNOWLEDGEMENTS This Department of Energy (DOE) Accident and Operational Safety Analysis Handbook was prepared under the sponsorship of the DOE Office of Health Safety and Security (HSS), Office of Corporate Safety Programs, and the Energy Facility Contractors Operating Group (EFCOG), Industrial Hygiene and Safety Sub-group of the Environmental Health and Safety Working Group. The preparers would like to gratefully acknowledge the authors whose works are referenced in this document, and the individuals who provided valuable technical insights and/or specific

275

The Nevada railroad system: Physical, operational, and accident characteristics  

Science Conference Proceedings (OSTI)

This report provides a description of the operational and physical characteristics of the Nevada railroad system. To understand the dynamics of the rail system, one must consider the system`s physical characteristics, routing, uses, interactions with other systems, and unique operational characteristics, if any. This report is presented in two parts. The first part is a narrative description of all mainlines and major branchlines of the Nevada railroad system. Each Nevada rail route is described, including the route`s physical characteristics, traffic type and volume, track conditions, and history. The second part of this study provides a more detailed analysis of Nevada railroad accident characteristics than was presented in the Preliminary Nevada Transportation Accident Characterization Study (DOE, 1990).

NONE

1991-09-01T23:59:59.000Z

276

Review of ARAC's involvement in the Titan II missile accident  

SciTech Connect

The Atmospheric Release Advisory Capability (ARAC) response to the Titan II accident near Damascus, Arkansas on 19 September 1980 entailed 12 personnel for periods ranging from 2 to 12 hours. The first call was a NEST Standby alert at 0415L (PCT), followed by a request for dispersal calculations at 0615L, personnel callout at 0630L, crude estimates of plausible source term scenarios at 0845-0900L, first model calculations at 1130L and final model calculations at 1500L. While several new firsts were recorded for ARAC, demonstrating expanded capabilities for NEST-type responses, time lines were very long, essential information was very scant to non-existent, and useful communication of final calculations to the accident site impossible. A detailed chronology is found in Appendix A and a list of acronyms and abbreviations is contained in Appendix B.

Sullivan, T.J.

1980-10-01T23:59:59.000Z

277

Enhanced Accident Tolerant LWR Fuels National Metrics Workshop Report  

SciTech Connect

The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), in collaboration with the nuclear industry, has been conducting research and development (R&D) activities on advanced Light Water Reactor (LWR) fuels for the last few years. The emphasis for these activities was on improving the fuel performance in terms of increased burnup for waste minimization and increased power density for power upgrades, as well as collaborating with industry on fuel reliability. After the events at the Fukushima Nuclear Power Plant in Japan in March 2011, enhancing the accident tolerance of LWRs became a topic of serious discussion. In the Consolidated Appropriations Act, 2012, Conference Report 112-75, the U.S. Congress directed DOE-NE to: Give priority to developing enhanced fuels and cladding for light water reactors to improve safety in the event of accidents in the reactor or spent fuel pools. Give special technical emphasis and funding priorityto activities aimed at the development and near-term qualification of meltdown-resistant, accident-tolerant nuclear fuels that would enhance the safety of present and future generations of light water reactors. Report to the Committee, within 90 days of enactment of this act, on its plan for development of meltdown-resistant fuels leading to reactor testing and utilization by 2020. Fuels with enhanced accident tolerance are those that, in comparison with the standard UO2-zirconium alloy system currently used by the nuclear industry, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, and operational transients, as well as design-basis and beyond design-basis events. The overall draft strategy for development and demonstration is comprised of three phases: Feasibility Assessment and Down-selection; Development and Qualification; and Commercialization. The activities performed during the feasibility assessment phase include laboratory scale experiments; fuel performance code updates; and analytical assessment of economic, operational, safety, fuel cycle, and environmental impacts of the new concepts. The development and qualification stage will consist of fuel fabrication and large scale irradiation and safety basis testing, leading to qualification and ultimate NRC licensing of the new fuel. The commercialization phase initiates technology transfer to industry for implementation. Attributes for fuels with enhanced accident tolerance include improved reaction kinetics with steam and slower hydrogen generation rate, while maintaining acceptable cladding thermo-mechanical properties; fuel thermo-mechanical properties; fuel-clad interactions; and fission-product behavior. These attributes provide a qualitative guidance for parameters that must be considered in the development of fuels and cladding with enhanced accident tolerance. However, quantitative metrics must be developed for these attributes. To initiate the quantitative metrics development, a Light Water Reactor Enhanced Accident Tolerant Fuels Metrics Development Workshop was held October 10-11, 2012, in Germantown, Maryland. This document summarizes the structure and outcome of the two-day workshop. Questions regarding the content can be directed to Lori Braase, 208-526-7763, lori.braase@inl.gov.

Lori Braase

2013-01-01T23:59:59.000Z

278

Evironmental health policy in ukraine after the Chernobyl accident  

SciTech Connect

The 1986 accident at the Chernobyl nuclear power plant in Ukraine produced severe environmental health problems. This paper reports on the environmental health conditions in Ukraine after the accident and the health policy approaches employed to respond to the environmental conditions and health problems. Crisis conditions and a period of rapid change in Ukraine contributed to the difficulties of developing and implementing policy to address serious environmental health problems. Despite these difficulties, Ukraine is taking effective action. The paper describes the primary environmental health problem areas and the efforts taken to solve them. The effect of intense public fear of radiation on policymaking is described. The paper discusses the ability of public fear to distort health policy towards certain problems, leaving problems of greater importance with fewer resources. 35 refs., 1 fig.

Page, G.W.; Bobyleva, O.A.; Naboka, M.V. [and others

1995-09-01T23:59:59.000Z

279

December 2005 PREVENTING AND HANDLING  

E-Print Network (OSTI)

, and remote access servers. NIST SP 800-61, Computer Security Incident Handling Guide, describes the fourDecember 2005 PREVENTING AND HANDLING MALWARE INCIDENTS: HOW TO PROTECT INFORMATION TECHNOLOGY SYSTEMS FROM MALICIOUS CODE AND SOFTWARE PREVENTING AND HANDLING MALWARE INCIDENTS: HOW TO PROTECT

280

AQUATIC ASSESSMENT OF THE CHERNOBYL NUCLEAR ACCIDENT AND ITS REMEDIATION  

Science Conference Proceedings (OSTI)

This modeling study evaluated aquatic environment affected by the Chernobyl nuclear accident and the effectiveness of remediation efforts. Study results indicate that radionuclide concentrations in the Pripyat and Dnieper rivers were well above the drinking water limits immediately after the Chernobyl accident, but have decreased significantly in subsequent years due to flashing, burying, and decay. Because high concentrations of 90Sr and 137Cs, the major radionuclides affecting human health through aquatic pathways, are associated with flooding, an earthen dike was constructed along the Pripyat River in its most contaminated floodplain. The dike was successful in reducing the 90Sr influx to the river by half. A 100-m-high movable dome called the New Safe Confinement is planned to cover the Chernobyl Shelter (formally called the sarcophagus) that was erected shortly after the accident. The NSC will reduce radionuclide contamination further in these rivers and nearby groundwater; however, even if the Chernobyl Shelter collapses before the NSC is built, the resulting peak concentrations of 90Sr and 137Cs in the Dnieper River would still be below the drinking water limits.

Onishi, Yasuo; Kivva, Sergey L.; Zheleznyak, Mark J.; Voitsekhovitch, Oleg V.

2007-11-01T23:59:59.000Z

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


281

Internally deposited fallout from the Chernobyl reactor accident  

SciTech Connect

Measurements of fallout radioactivity were made in the thyroid region, abdomen, whole body, or urine of 96 persons who were in eastern Europe at the time of the Chernobyl reactor accident or who went there shortly afterward. The most frequently encountered radionuclides were /sup 131/I, /sup 134,137/Cs, and /sup 103/Ru//sup 103/Rh. The median /sup 131/I activity in the thyroids of 42 subjects in whom radioiodine was detected and who were in Europe when the accident began was projected as 42 nCi the day the accident began. The median total body activity of /sup 134/Cs in 40 subjects in which it was detected was 1.7 nCi upon arrival in the US. For 51 subjects with detectable /sup 137/Cs burdens, the total body activity was 4.6 nCi. The risk of fatal thyroid cancer is less than 3 x 10/sup -6/ for nearly all subjects in this series. The risk of fatal cancer from /sup 134,137/Cs for subjects with cesium exposures similar to the ones observed by us, but who remained in Europe, is estimated as 1.4 x 10/sup -6/ to 4.2 x 10/sup -5/ with 95% of the risk attributable to /sup 137/Cs. 5 refs., 4 tabs.

Schlenker, R.A.; Oltman, B.G.; Lucas, H.F.

1987-01-01T23:59:59.000Z

282

ANS-8. 23: Criticality accident emergency planning and response  

SciTech Connect

A study group has been formed under the auspices of ANS-8 to examine the need for a standard on nuclear criticality accident emergency planning and response. This standard would be ANS-8.23. ANSI/ANS-8.19-1984, Administrative Practices for Nuclear Criticality Safety, provides some guidance on the subject in Section 10 titled -- Planned Response to Nuclear Criticality Accidents. However, the study group has formed a consensus that Section 10 is inadequate in that technical guidance in addition to administrative guidance is needed. The group believes that a new standard which specifically addresses emergency planning and response to a perceived criticality accident is needed. Plans for underway to request the study group be designated a writing group to create a draft of such a new standard. The proposed standard will divide responsibility between management and technical staff. Generally, management will be charged with providing the necessary elements of emergency planning such as a criticality detection and alarm system, training, safe evacuation routes and assembly areas, a system for timely accountability of personnel, and an effective emergency response organization. The technical staff, on the other hand, will be made responsible for establishing specific items such as safe and clearly posted evacuation evacuation routes and dose criteria for personnel assembly areas. The key to the question of responsibilities is that management must provide the resources for the technical staff to establish the elements of an emergency response effort.

Pruvost, N.L.

1991-06-24T23:59:59.000Z

283

Enhanced Accident Tolerant Fuels for LWRS - A Preliminary Systems Analysis  

Science Conference Proceedings (OSTI)

The severe accident at Fukushima Daiichi nuclear plants illustrates the need for continuous improvements through developing and implementing technologies that contribute to safe, reliable and cost-effective operation of the nuclear fleet. Development of enhanced accident tolerant fuel contributes to this effort. These fuels, in comparison with the standard zircaloy UO2 system currently used by the LWR industry, should be designed such that they tolerate loss of active cooling in the core for a longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, operational transients, and design-basis events. This report presents a preliminary systems analysis related to most of these concepts. The potential impacts of these innovative LWR fuels on the front-end of the fuel cycle, on the reactor operation and on the back-end of the fuel cycle are succinctly described without having the pretension of being exhaustive. Since the design of these various concepts is still a work in progress, this analysis can only be preliminary and could be updated as the designs converge on their respective final version.

Gilles Youinou; R. Sonat Sen

2013-09-01T23:59:59.000Z

284

Health effects of the nuclear accident at Three Mile Island  

SciTech Connect

Between March 28 and April 15, 1979 the collective dose resulting from the radioactivity released to the population living within a 50-mile radius of the Three Mile Island nuclear plant was about 2000 person-rems, less than 1% of the annual natural background level. The average dose to a person living within 5 miles of the nuclear plant was less than 10% of annual background radiation. The maximum estimated radiation dose received by any one individual in the general population (excluding the nuclear plant workers) during the accident was 70 mrem. The doses received by the general population as a result of the accident were so small that there will be no detectable additional cases of cancer, developmental abnormalities, or genetic ill-health. Three Three Mile Island nuclear workers received radiation doses of about 3 to 4 rem, exceeding maximum permissible quarterly dose of 3 rem. The major health effect of the accident at Three Mile Island was that of a pronounced demoralizing effect on the general population in the Three Mile Island area, including teenagers and mothers of preschool children and the nuclear plant workers. However, this effect proved transient in all groups studied except the nuclear workers.

Fabrikant, J.I.

1980-05-01T23:59:59.000Z

285

Analysis of PWR RCS Injection Strategy During Severe Accident  

Science Conference Proceedings (OSTI)

Reactor coolant system (RCS) injection is an important strategy for severe accident management of a pressurized water reactor (PWR) system. Maanshan is a typical Westinghouse PWR nuclear power plant (NPP) with large, dry containment. The severe accident management guideline (SAMG) of Maanshan NPP is developed based on the Westinghouse Owners Group (WOG) SAMG.The purpose of this work is to analyze the RCS injection strategy of PWR system in an overheated core condition. Power is assumed recovered as the vessel water level drops to the bottom of active fuel. The Modular Accident Analysis Program version 4.0.4 (MAAP4) code is chosen as a tool for analysis. A postulated station blackout sequence for Maanshan NPP is cited as a reference case for this analysis. The hot leg creep rupture occurs during the mitigation action with immediate injection after power recovery according to WOG SAMG, which is not desired. This phenomenon is not considered while developing the WOG SAMG. Two other RCS injection methods are analyzed by using MAAP4. The RCS injection strategy is modified in the Maanshan SAMG. These results can be applied for typical PWR NPPs.

Wang, S.-J. [Institute of Nuclear Energy Research, Taiwan (China); Chiang, K.-S. [Institute of Nuclear Energy Research, Taiwan (China); Chiang, S.-C. [Taiwan Power Company, Taiwan (China)

2004-05-15T23:59:59.000Z

286

Rail transportation risk and accident severity: A statistical analysis of variables in FRA's accident/incident data base  

Science Conference Proceedings (OSTI)

The Federal Railroad Administration (US DOT) maintains a file of carrier-reported railroad accidents and incidents that meet stipulated threshold criteria for damage cost and/or casualties. A thoroughly-cleaned five-year time series of this data base was subjected to unbiased statistical procedures to discover (a) important causative variables in severe (high damage cost) accidents and (b) other key relationships between objective accident conditions and frequencies. Just under 6000 records, each representing a single event involving rail freight shipments moving on mainline track, were subjected to statistical frequency analysis, then included in the construction of classification and regression trees as described by Breimann et al. (1984). Variables related to damage cost defined the initial splits,'' or branchings of the tree. An interesting implication of the results of this analysis with respect to transportation of hazardous wastes by rail is that movements should be avoided when ambient temperatures are extreme (significantly 80{degrees}F), but that there should be no a priori bias against shipping wastes in longer train consists. 2 refs., 2 figs., 12 tabs.

Saricks, C.L. (Argonne National Lab., IL (USA). Energy Systems Div.); Janssen, I. (Argonne National Lab., IL (USA). Biological and Medical Research Div.)

1991-01-01T23:59:59.000Z

287

Summary Impacts of Modeled Provisions of the 2003 Conference Energy Bill  

Gasoline and Diesel Fuel Update (EIA)

2 2 Summary Impacts of Modeled Provisions of the 2003 Conference Energy Bill February 2004 Energy Information Administration Office of Integrated Analysis and Forecasting U.S. Department of Energy Washington, DC 20585 This Service Report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should be attributed to the Energy Information Administration and should not be construed as advocating or reflecting any policy position of the Department of Energy or of any other organization. Service Reports are prepared by the Energy Information Administration upon special request and are based on assumptions specified by the requestor.

288

Analysis of Five Selected Tax Provisions of the Conference Energy Bill of 2003  

Gasoline and Diesel Fuel Update (EIA)

1 1 Analysis of Five Selected Tax Provisions of the Conference Energy Bill of 2003 February 2004 Energy Information Administration Office of Integrated Analysis and Forecasting U.S. Department of Energy Washington, DC 20585 This Service Report was prepared by the Energy Information Administration, the independent statistical and analytical agency within the Department of Energy. The information contained herein should be attributed to the Energy Information Administration and should not be construed as advocating or reflecting any policy position of the Department of Energy or of any other organization. Service Reports are prepared by the Energy Information Administration upon special request and are based on assumptions specified by the requestor.

289

Federal Energy Management Program: Preventive Maintenance  

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

Preventive Preventive Maintenance to someone by E-mail Share Federal Energy Management Program: Preventive Maintenance on Facebook Tweet about Federal Energy Management Program: Preventive Maintenance on Twitter Bookmark Federal Energy Management Program: Preventive Maintenance on Google Bookmark Federal Energy Management Program: Preventive Maintenance on Delicious Rank Federal Energy Management Program: Preventive Maintenance on Digg Find More places to share Federal Energy Management Program: Preventive Maintenance on AddThis.com... Sustainable Buildings & Campuses Operations & Maintenance Federal Requirements Program Management Commissioning Metering Computerized Maintenance Management Systems Maintenance Types Reactive Preventive Predictive Reliability-Centered Major Equipment Types

290

DOE Order Self Study Modules - DOE O 225.1B, Accident Investigation  

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

225.1B 225.1B ACCIDENT INVESTIGATIONS DOE O 225.1B Accident Investigations Familiar Level June 2011 1 June 2011 DOE ORDER O 225.1B ACCIDENT INVESTIGATIONS FAMILIAR LEVEL OBJECTIVES Given the familiar level of this module and the resources listed below, you will be able to: 1. State the purpose of implementing U.S. Department of Energy (DOE) O 225.1B. 2. Discuss the responsibilities of the heads of field elements for accident investigations. 3. Discuss the responsibilities of the appointing official in an accident investigation. 4. Discuss the responsibilities of the Accident Investigation Board Chairperson. 5. Discuss the criteria identified in appendix A of DOE O 225.1B. Note: If you think that you can complete the practice at the end of this level without

291

Sandia National Laboratories: Pollution Prevention  

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

Pollution Prevention Pollution Prevention Environmental Management System Pollution Prevention Sustainable Acquisition Electronics Stewardship Recycling Reuse Outreach Awards News About Pollution Prevention 13,051 lbs of Carpet Sent for Reuse Forklift carrying carpet on pallet Sandia Awarded for Electronics Stewardship Electronics Stewardship Award Zero Waste Lunch Goes Beyond Recycling Zero Waste Station No More Green Waste in the Landfill Dup truck dumping green waste Recycling Lead Acid Batteries Responsibly Lead Acid Batteries 39,000 Pounds of Ceiling Tiles Recycled Ceiling tile shipment for recycling Sustainable Acquisition Icon Sustainable Acquisition Greening the supply chain Electronics Stewardship Icon Electronics Stewardship Managing the full life-cycle Outreach Icon Outreach Teaming with our community Recycling Icon

292

Toxic Pollution Prevention Act (Illinois)  

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

It is the purpose of this Act to reduce the disposal and release of toxic substances which may have adverse and serious health and environmental effects, to promote toxic pollution prevention as...

293

Tanker safety and pollution prevention  

SciTech Connect

The U.S. Coast Guard announces a delay in issuing final regulations for segregated ballast tanks, dedicated clean ballast tanks, crude oil washing systems, inert gas and deck foam systems, and improved steering gear standards on tank vessels. These regulations are expected to be published as final regulations no later than 10/1/79. Although the final regulations will be published and become effective in the fall of 1979, under the provisions of the Port and Tanker Safety Act, those regulations will provide that a tank vessel that is contracted for after 6/1/79, but before issuance of the final regulations must be in compliance with the applicable requirements of the Act and the final regulations in order to be issued a certificate of inspection or a certificate of compliance.

1979-06-07T23:59:59.000Z

294

Descriptions of selected accidents that have occurred at nuclear reactor facilities  

SciTech Connect

This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established.

Bertini, H.W.

1980-04-01T23:59:59.000Z

295

Descriptions of selected accidents that have occurred at nuclear reactor facilities  

SciTech Connect

This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief description of 44 accidents which have occurred throughout the world and which meet at least one of the severity criteria that were established.

Bertini, H.W.

1980-04-01T23:59:59.000Z

296

MACCS usage at Rocky Flats Plant for consequence analysis of postulated accidents  

Science Conference Proceedings (OSTI)

The MELCOR Accident Consequence Code System (MACCS) has been applied to the radiological consequence assessment of potential accidents from a non-reactor nuclear facility. MACCS has been used in a variety of applications to evaluate radiological dose and health effects to the public from postulated plutonium releases and from postulated criticalities. These applications were conducted to support deterministic and probabilistic accident analyses for safety analyses for safety analysis reports, radiological sabotage studies, and other regulatory requests.

Foppe, T.L.; Peterson, V.L.

1993-10-01T23:59:59.000Z

297

MAAP5 Simulation of Accidents at Fukushima Dai-ichi Units 1, 2, and 3  

Science Conference Proceedings (OSTI)

The original MAAP4 code functional design specification (circa 1989) was defined to address the full extent of degraded core accidents with the potential for reflooding of a badly damaged core. It was intended to support probabilistic risk assessment (PRA) and severe accident management guideline (SAMG) applications that previously were limited by the relatively rudimentary design for MAAP3.0B, the predecessor code.The accidents at Fukushima Dai-ichi Units 1, 2, and 3 prompted a ...

2013-02-23T23:59:59.000Z

298

Safety evaluation of MHTGR licensing basis accident scenarios  

SciTech Connect

The safety potential of the Modular High-Temperature Gas Reactor (MHTGR) was evaluated, based on the Preliminary Safety Information Document (PSID), as submitted by the US Department of Energy to the US Nuclear Regulatory Commission. The relevant reactor safety codes were extended for this purpose and applied to this new reactor concept, searching primarily for potential accident scenarios that might lead to fuel failures due to excessive core temperatures and/or to vessel damage, due to excessive vessel temperatures. The design basis accident scenario leading to the highest vessel temperatures is the depressurized core heatup scenario without any forced cooling and with decay heat rejection to the passive Reactor Cavity Cooling System (RCCS). This scenario was evaluated, including numerous parametric variations of input parameters, like material properties and decay heat. It was found that significant safety margins exist, but that high confidence levels in the core effective thermal conductivity, the reactor vessel and RCCS thermal emissivities and the decay heat function are required to maintain this safety margin. Severe accident extensions of this depressurized core heatup scenario included the cases of complete RCCS failure, cases of massive air ingress, core heatup without scram and cases of degraded RCCS performance due to absorbing gases in the reactor cavity. Except for no-scram scenarios extending beyond 100 hr, the fuel never reached the limiting temperature of 1600/degree/C, below which measurable fuel failures are not expected. In some of the scenarios, excessive vessel and concrete temperatures could lead to investment losses but are not expected to lead to any source term beyond that from the circulating inventory. 19 refs., 56 figs., 11 tabs.

Kroeger, P.G.

1989-04-01T23:59:59.000Z

299

Markov Model of Accident Progression at Fukushima Daiichi  

DOE Green Energy (OSTI)

On March 11, 2011, a magnitude 9.0 earthquake followed by a tsunami caused loss of offsite power and disabled the emergency diesel generators, leading to a prolonged station blackout at the Fukushima Daiichi site. After successful reactor trip for all operating reactors, the inability to remove decay heat over an extended period led to boil-off of the water inventory and fuel uncovery in Units 1-3. A significant amount of metal-water reaction occurred, as evidenced by the quantities of hydrogen generated that led to hydrogen explosions in the auxiliary buildings of the Units 1 & 3, and in the de-fuelled Unit 4. Although it was assumed that extensive fuel damage, including fuel melting, slumping, and relocation was likely to have occurred in the core of the affected reactors, the status of the fuel, vessel, and drywell was uncertain. To understand the possible evolution of the accident conditions at Fukushima Daiichi, a Markov model of the likely state of one of the reactors was constructed and executed under different assumptions regarding system performance and reliability. The Markov approach was selected for several reasons: It is a probabilistic model that provides flexibility in scenario construction and incorporates time dependence of different model states. It also readily allows for sensitivity and uncertainty analyses of different failure and repair rates of cooling systems. While the analysis was motivated by a need to gain insight on the course of events for the damaged units at Fukushima Daiichi, the work reported here provides a more general analytical basis for studying and evaluating severe accident evolution over extended periods of time. This work was performed at the request of the U.S. Department of Energy to explore 'what-if' scenarios in the immediate aftermath of the accidents.

Cuadra A.; Bari R.; Cheng, L-Y; Ginsberg, T.; Lehner, J.; Martinez-Guridi, G.; Mubayi, V.; Pratt, T.; Yue, M.

2012-11-11T23:59:59.000Z

300

Assessment of ICARE/CATHARE V1 Severe Accident Code  

SciTech Connect

The ICARE/CATHARE code system has been developed by the French 'Institut de Radioprotection et de Surete Nucleaire' (IRSN) in the last decade for the detailed evaluation of Severe Accident (SA) consequences in a primary system. It is composed of the coupling of the core degradation IRSN code ICARE2 and of the thermal-hydraulics French code CATHARE2. It has been extensively used to support the level 2 Probabilistic Safety Assessment (PSA-2) of the 900 MWe PWR. This paper presents the synthesis of the ICARE/CATHARE V1 assessment which was conducted in the frame of the 'International ICARE/CATHARE Users' Club', under the management of IRSN. The ICARE/CATHARE V1 validation matrix is composed of more than 60 experiments, distributed in few thermal-hydraulics non-regression tests (to handle the front end phase of a severe accident), numerous Separate-Effect Tests, about 30 Integral Tests covering both the early and the late degradation phases, as well as a 'circuit' experiment including hydraulics loops. Finally, the simulation of the TMI-2 accident was also added to assess the code against real conditions. This validation task was aimed at assessing the ICARE/CATHARE V1 capabilities (including the stand-alone ICARE2 V3mod1 version) and also at proposing recommendations for an optimal use of this version ('Users' Guidelines'). Thus, with a correct account for the recommended guidelines, it appeared that the last ICARE/CATHARE V1 version could be reasonably used to perform best-estimate reactor studies up to a large corium slumping into the lower head. (authors)

Chatelard, Patrick; Fleurot, Joelle; Marchand, Olivier; Drai, Patrick [IRSN, 31, avenue de la Division Leclerc, BP 17 - 92262 Fontenay-aux-Roses Cedex (France)

2006-07-01T23:59:59.000Z

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


301

Accident analysis and safety review of DOE Category B reactors  

SciTech Connect

DOE is employing the principle of comparability with the NRC requirements to guide its safety program. Since the safety record of research reactors licensed by the NRC has been established and accepted, the comparison of DOE Orders applicable to DOE research reactors with the NRC regulations applicable to research reactors would identify strengths and weaknesses of the DOE Orders. The comparison was made in 14 general topics of safety which are labeled Areas of Safety Concerns. This paper focuses on the Area of accident analysis and safety review and presents recommendations in these areas. 12 refs.

Kimura, C.Y.

1990-08-07T23:59:59.000Z

302

Advance plant severe accident/thermal hydraulic issues for ACRS  

DOE Green Energy (OSTI)

The ACRS has been reviewing various advance plant designs for certification. The most active reviews have been for the ABWR, AP600, and System 80+. We have completed the reviews for ABWR and System 80+ and are presently concentrating on AP600. The ACRS gave essentially unqualified certification approval for the two completed reviews, yet,,during the process of review a number of issues arose and the plant designs changed somewhat to accommodate some of the ACRS concerns. In this talk, I will describe some of the severe accident and thermal hydraulic related issues we discussed in our reviews.

Kress, T.S.

1994-09-01T23:59:59.000Z

303

Compendium of information on hydrogen behavior during LWR accidents  

DOE Green Energy (OSTI)

A manual has been written which attempts to present, in a simple and understandable way, information concerning the generation, transport, detection and combustion of hydrogen which might occur during serious accidents in light water reactors. More than a thousand documents were surveyed over a three month period. Of these, several hundred documents were extensively reviewed. The manual summarizes the results of this review. The manual is divided into four major sections covering hydrogen generation, detection, combustion, and existing schemes for mitigating the effects of combustion.

Berman, M.

1980-01-01T23:59:59.000Z

304

Determination of influence factors and accident rates for the Armored Tractor/Safe Secure Trailer  

Science Conference Proceedings (OSTI)

Operating environments, such as road type, road location, and time of day, play an important role in the observed accident rates of heavy trucks used in general commerce. These same factors influence the accident rate of the Armored Tractor/Safe Secure Trailer (AT/SST) used by the Department of Energy to transport hazardous cargos within the continental United States. This report discusses the development of accident rate influence factors. These factors, based on heavy trucks used in general commerce, are used to modify the observed overall AT/SST accident rate to account for the different operating environments.

Phillips, J.S.; Clauss, D.B. [Sandia National Labs., Albuquerque, NM (United States); Blower, D.F. [Univ. of Michigan Transportation Research Institute, Ann Arbor, MI (United States). Center for National Truck Statistics

1994-04-01T23:59:59.000Z

305

Summary of the SRS Severe Accident Analysis Program, 1987--1992  

SciTech Connect

The Severe Accident Analysis Program (SAAP) is a program of experimental and analytical studies aimed at characterizing severe accidents that might occur in the Savannah River Site Production Reactors. The goals of the Severe Accident Analysis Program are: To develop an understanding of severe accidents in SRS reactors that is adequate to support safety documentation for these reactors, including the Safety Analysis Report (SAR), the Probabilistic Risk Assessment (PRA), and other studies evaluating the safety of reactor operation; To provide tools and bases for the evaluation of existing or proposed safety related equipment in the SRS reactors; To provide bases for the development of accident management procedures for the SRS reactors; To develop and maintain on the site a sufficient body of knowledge, including documents, computer codes, and cognizant engineers and scientists, that can be used to authoritatively resolve questions or issues related to reactor accidents. The Severe Accident Analysis Program was instituted in 1987 and has already produced a substantial amount of information, and specialized calculational tools. Products of the Severe Accident Analysis Program (listed in Section 9 of this report) have been used in the development of the Safety Analysis Report (SAR) and the Probabilistic Risk Assessment (PRA), and in the development of technical specifications for the SRS reactors. A staff of about seven people is currently involved directly in the program and in providing input on severe accidents to other SRS activities.

Long, T.A.; Hyder, M.L.; Britt, T.E.; Allison, D.K.; Chow, S.; Graves, R.D.; DeWald, A.B. Jr.; Monson, P.R. Jr.; Wooten, L.A.

1992-11-01T23:59:59.000Z

306

Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement  

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

Facts and Lessons of the Fukushima Nuclear Accident and Safety Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints September 19, 2012 Presenter: Akira Kawano, General Manager, Nuclear International Relations and Strategy Group, Nuclear Power and Plant Siting Administrative Department, Tokyo Electric Power Company Topics Covered: How Tsunami Struck Fukushima Sites Tsunami Height Estimation How we responded in the Recovery Process Safety Improvement and Further Enhancement of Nuclear Safety Facts and Lessons of the Fukushima Nuclear Accident and Safety Improvement - The Operator Viewpoints More Documents & Publications January2005 NNSANews Meeting Materials: June 15, 2011

307

Order Module--DOE Order 225.1B, ACCIDENT INVESTIGATIONS  

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

DOE O 225.1B prescribes organizational responsibilities, authorities, and requirements for conducting investigations of certain accidents occurring at DOE sites, facilities, areas, operations, and...

308

A comparative analysis of accident risks in fossil, hydro, and nuclear energy chains  

Science Conference Proceedings (OSTI)

This study presents a comparative assessment of severe accident risks in the energy sector, based on the historical experience of fossil (coal, oil, natural gas, and LPG (Liquefied Petroleum Gas)) and hydro chains contained in the comprehensive Energy-related Severe Accident Database (ENSAD), as well as Probabilistic Safety Assessment (PSA) for the nuclear chain. Full energy chains were considered because accidents can take place at every stage of the chain. Comparative analyses for the years 1969-2000 included a total of 1870 severe ({>=} 5 fatalities) accidents, amounting to 81,258 fatalities. Although 79.1% of all accidents and 88.9% of associated fatalities occurred in less developed, non-OECD countries, industrialized OECD countries dominated insured losses (78.0%), reflecting their substantially higher insurance density and stricter safety regulations. Aggregated indicators and frequency-consequence (F-N) curves showed that energy-related accident risks in non-OECD countries are distinctly higher than in OECD countries. Hydropower in non-OECD countries and upstream stages within fossil energy chains are most accident-prone. Expected fatality rates are lowest for Western hydropower and nuclear power plants; however, the maximum credible consequences can be very large. Total economic damages due to severe accidents are substantial, but small when compared with natural disasters. Similarly, external costs associated with severe accidents are generally much smaller than monetized damages caused by air pollution.

Burgherr, P.; Hirschberg, S. [Paul Scherrer Institute, Villigen (Switzerland)

2008-07-01T23:59:59.000Z

309

Severe Accident Phenomenology Analyses and Fission Gas Release in Advanced Nuclear Reactors.  

E-Print Network (OSTI)

??The aim of this work is to contribute to qualify a model in order to simulate the progression of a severe accident (SA), evaluating the (more)

MAZZINI, GUIDO

2012-01-01T23:59:59.000Z

310

Guidance on Incorporating EPA's Pollution Prevention Strategy...  

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

Review Process The guidance discusses the Environmental Protection Agency's definition of pollution prevention; how to incorporate pollution prevention into the EPA...

311

Accident Fault Trees for Defense Waste Processing Facility  

Science Conference Proceedings (OSTI)

The purpose of this report is to document fault tree analyses which have been completed for the Defense Waste Processing Facility (DWPF) safety analysis. Logic models for equipment failures and human error combinations that could lead to flammable gas explosions in various process tanks, or failure of critical support systems were developed for internal initiating events and for earthquakes. These fault trees provide frequency estimates for support systems failures and accidents that could lead to radioactive and hazardous chemical releases both on-site and off-site. Top event frequency results from these fault trees will be used in further APET analyses to calculate accident risk associated with DWPF facility operations. This report lists and explains important underlying assumptions, provides references for failure data sources, and briefly describes the fault tree method used. Specific commitments from DWPF to provide new procedural/administrative controls or system design changes are listed in the ''Facility Commitments'' section. The purpose of the ''Assumptions'' section is to clarify the basis for fault tree modeling, and is not necessarily a list of items required to be protected by Technical Safety Requirements (TSRs).

Sarrack, A.G.

1999-06-22T23:59:59.000Z

312

Accident sequence precursor events with age-related contributors  

SciTech Connect

The Accident Sequence Precursor (ASP) Program at ORNL analyzed about 14.000 Licensee Event Reports (LERs) filed by US nuclear power plants 1987--1993. There were 193 events identified as precursors to potential severe core accident sequences. These are reported in G/CR-4674. Volumes 7 through 20. Under the NRC Nuclear Plant Aging Research program, the authors evaluated these events to determine the extent to which component aging played a role. Events were selected that involved age-related equipment degradation that initiated an event or contributed to an event sequence. For the 7-year period, ORNL identified 36 events that involved aging degradation as a contributor to an ASP event. Except for 1992, the percentage of age-related events within the total number of ASP events over the 7-year period ({approximately}19%) appears fairly consistent up to 1991. No correlation between plant ape and number of precursor events was found. A summary list of the age-related events is presented in the report.

Murphy, G.A.; Kohn, W.E.

1995-12-31T23:59:59.000Z

313

An analysis of evacuation options for nuclear accidents  

Science Conference Proceedings (OSTI)

In this report we consider the threat posed by the accidental release of radionuclides from a nuclear power plant. The objective is to establish relationships between radiation dose and the cost of evacuation under a wide variety of conditions. The dose can almost always be reduced by evacuating the population from a larger area. However, extending the evacuation zone outward will cause evacuation costs to increase. The purpose of this analysis was to provide the Environmental Protection Agency (EPA) a data base for evaluating whether implementation costs and risks averted could be used to justify evacuation at lower doses. The procedures used and results of these analyses are being made available as background information for use by others. We develop cost/dose relationships for 54 scenarios that are based upon the severity of the reactor accident, meteorological conditions during the release of radionuclides into the environment, and the angular width of the evacuation zone. The 54 scenarios are derived from combinations of three accident severity levels, six meteorological conditions and evacuation zone widths of 70{degree}, 90{degree}, and 180{degree}.

Tawil, J.J.; Strenge, D.L.; Schultz, R.W. [Battelle Memorial Inst., Richland, WA (United States)

1987-11-01T23:59:59.000Z

314

PERSPECTIVES ON A DOE CONSEQUENCE INPUTS FOR ACCIDENT ANALYSIS APPLICATIONS  

Science Conference Proceedings (OSTI)

Department of Energy (DOE) accident analysis for establishing the required control sets for nuclear facility safety applies a series of simplifying, reasonably conservative assumptions regarding inputs and methodologies for quantifying dose consequences. Most of the analytical practices are conservative, have a technical basis, and are based on regulatory precedent. However, others are judgmental and based on older understanding of phenomenology. The latter type of practices can be found in modeling hypothetical releases into the atmosphere and the subsequent exposure. Often the judgments applied are not based on current technical understanding but on work that has been superseded. The objective of this paper is to review the technical basis for the major inputs and assumptions in the quantification of consequence estimates supporting DOE accident analysis, and to identify those that could be reassessed in light of current understanding of atmospheric dispersion and radiological exposure. Inputs and assumptions of interest include: Meteorological data basis; Breathing rate; and Inhalation dose conversion factor. A simple dose calculation is provided to show the relative difference achieved by improving the technical bases.

(NOEMAIL), K; Jonathan Lowrie, J; David Thoman (NOEMAIL), D; Austin Keller (NOEMAIL), A

2008-07-30T23:59:59.000Z

315

Advanced sodium fast reactor accident source terms : research needs.  

Science Conference Proceedings (OSTI)

An expert opinion elicitation has been used to evaluate phenomena that could affect releases of radionuclides during accidents at sodium-cooled fast reactors. The intent was to identify research needed to develop a mechanistic model of radionuclide release for licensing and risk assessment purposes. Experts from the USA, France, the European Union, and Japan identified phenomena that could affect the release of radionuclides under hypothesized accident conditions. They qualitatively evaluated the importance of these phenomena and the need for additional experimental research. The experts identified seven phenomena that are of high importance and have a high need for additional experimental research: High temperature release of radionuclides from fuel during an energetic eventEnergetic interactions between molten reactor fuel and sodium coolant and associated transfer of radionuclides from the fuel to the coolantEntrainment of fuel and sodium bond material during the depressurization of a fuel rod with breached claddingRates of radionuclide leaching from fuel by liquid sodiumSurface enrichment of sodium pools by dissolved and suspended radionuclidesThermal decomposition of sodium iodide in the containment atmosphereReactions of iodine species in the containment to form volatile organic iodides. Other issues of high importance were identified that might merit further research as development of the mechanistic model of radionuclide release progressed.

Powers, Dana Auburn; Clement, Bernard [IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France] IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France; Denning, Richard [Ohio State University, Columbus, OH] Ohio State University, Columbus, OH; Ohno, Shuji [Japan Atomic Energy Agency, Ibaraki, Japan] Japan Atomic Energy Agency, Ibaraki, Japan; Zeyen, Roland [Institute for Energy Petten, Saint-Paul-lez-Durance, France] Institute for Energy Petten, Saint-Paul-lez-Durance, France

2010-09-01T23:59:59.000Z

316

Advanced sodium fast reactor accident source terms : research needs.  

SciTech Connect

An expert opinion elicitation has been used to evaluate phenomena that could affect releases of radionuclides during accidents at sodium-cooled fast reactors. The intent was to identify research needed to develop a mechanistic model of radionuclide release for licensing and risk assessment purposes. Experts from the USA, France, the European Union, and Japan identified phenomena that could affect the release of radionuclides under hypothesized accident conditions. They qualitatively evaluated the importance of these phenomena and the need for additional experimental research. The experts identified seven phenomena that are of high importance and have a high need for additional experimental research: High temperature release of radionuclides from fuel during an energetic eventEnergetic interactions between molten reactor fuel and sodium coolant and associated transfer of radionuclides from the fuel to the coolantEntrainment of fuel and sodium bond material during the depressurization of a fuel rod with breached claddingRates of radionuclide leaching from fuel by liquid sodiumSurface enrichment of sodium pools by dissolved and suspended radionuclidesThermal decomposition of sodium iodide in the containment atmosphereReactions of iodine species in the containment to form volatile organic iodides. Other issues of high importance were identified that might merit further research as development of the mechanistic model of radionuclide release progressed.

Powers, Dana Auburn; Clement, Bernard [IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France] IRSN/DPAM.SEMIC Bt 702, Saint-Paul-lez-Durance, France; Denning, Richard [Ohio State University, Columbus, OH] Ohio State University, Columbus, OH; Ohno, Shuji [Japan Atomic Energy Agency, Ibaraki, Japan] Japan Atomic Energy Agency, Ibaraki, Japan; Zeyen, Roland [Institute for Energy Petten, Saint-Paul-lez-Durance, France] Institute for Energy Petten, Saint-Paul-lez-Durance, France

2010-09-01T23:59:59.000Z

317

Worldwide health effects of the Fukushima Daiichi nuclear accident  

E-Print Network (OSTI)

This study quantifies worldwide health effects of the Fukushima Daiichi nuclear accident on 11 March 2011. Effects are quantified with a 3-D global atmospheric model driven by emission estimates and evaluated against daily worldwide Comprehensive Nuclear-Test-Ban Treaty Organization (CTBTO) measurements and observed deposition rates. Inhalation exposure, ground-level external exposure, and atmospheric external exposure pathways of radioactive iodine-131, cesium-137, and cesium-134 released from Fukushima are accounted for using a linear no-threshold (LNT) model of human exposure. Exposure due to ingestion of contaminated food and water is estimated by extrapolation. We estimate an additional 130 (151100) cancer-related mortalities and 180 (241800) cancer-related morbidities incorporating uncertainties associated with the exposuredose and doseresponse models used in the study. We also discuss the LNT models uncertainty at low doses. Sensitivities to emission rates, gas to particulate I-131 partitioning, and the mandatory evacuation radius around the plant are also explored, and may increase upper bound mortalities and morbidities in the ranges above to 1300 and 2500, respectively. Radiation exposure to workers at the plant is projected to result in 2 to 12 morbidities. An additional 600 mortalities have been reported due to non-radiological causes such as mandatory evacuations. Lastly, a hypothetical accident at the Diablo Canyon Power Plant in

John E. Ten Hoeve A; Mark Z. Jacobson B

2012-01-01T23:59:59.000Z

318

Policy Flash 2013-28 Implementation of Indian Energy Preference Provision in EP Act 2005 and Acquisition Letter 2013-02  

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

Attached is Policy Flash 2013-28 Implementation of Indian Energy Preference Provision in EP Act 2005 and Acquisition Letter 2013-02

319

Analysis of traffic accident severity using Decision Rules via Decision Trees  

Science Conference Proceedings (OSTI)

A Decision Tree (DT) is a potential method for studying traffic accident severity. One of its main advantages is that Decision Rules (DRs) can be extracted from its structure. And these DRs can be used to identify safety problems and establish certain ... Keywords: Decision Rules, Decision Trees, Road safety, Severity, Traffic accident

JoaquN AbellN, Griselda LPez, Juan De OA

2013-11-01T23:59:59.000Z

320

Recommendations for Analyzing Accidents under the National Environmental Policy Act (July 2002)  

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

National National Environmental Policy Act RECOMMENDATIONS for ANALYZING ACCIDENTS under the NATIONAL ENVIRONMENTAL POLICY ACT N E P A July 2002 U.S. Department of Energy Environment, Safety and Health Office of NEPA Policy and Compliance Recommendations for Analyzing Accidents under NEPA Contents 1.0 Introduction ............................................................................................................................... 1 1.1 Definition............................................................................................................................ 1 1.2 Purpose.............................................................................................................................. 1 1.3 Sliding Scale ......................................................................................................................

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


321

SD-GIS-based temporal-spatial simulation of water quality in sudden water pollution accidents  

Science Conference Proceedings (OSTI)

System dynamics (SD) is well suited for studying dynamic nonlinear complex systems. In this paper, SD is applied to a rapid-onset water pollution accident using a 1-D water quality model and a conceptual GIS-SD framework is constructed to simulate the ... Keywords: System dynamics, Temporal-spatial simulation, Water pollution accidents

Bo Zhang; Yu Qin; Mingxiang Huang; Qiang Sun; Shun Li; Liqiang Wang; Chaohui Yu

2011-07-01T23:59:59.000Z

322

A novel approach for traffic accidents sanitary resource allocation based on multi-objective genetic algorithms  

Science Conference Proceedings (OSTI)

The development of communication technologies integrated in vehicles allows creating new protocols and applications to improve assistance in traffic accidents. Combining this technology with intelligent systems will permit to automate most of the decisions ... Keywords: Multi-objective genetic algorithms, Resource allocation, Traffic accidents assistance

Manuel Fogue; Piedad Garrido; Francisco J. Martinez; Juan-Carlos Cano; Carlos T. Calafate; Pietro Manzoni

2013-01-01T23:59:59.000Z

323

Fast Transient And Spatially Non-Homogenous Accident Analysis Of Two-Dimensional Cylindrical Nuclear Reactor  

Science Conference Proceedings (OSTI)

The research about fast transient and spatially non-homogenous nuclear reactor accident analysis of two-dimensional nuclear reactor has been done. This research is about prediction of reactor behavior is during accident. In the present study, space-time diffusion equation is solved by using direct methods which consider spatial factor in detail during nuclear reactor accident simulation. Set of equations that obtained from full implicit finite-difference discretization method is solved by using iterative methods ADI (Alternating Direct Implicit). The indication of accident is decreasing macroscopic absorption cross-section that results large external reactivity. The power reactor has a peak value before reactor has new balance condition. Changing of temperature reactor produce a negative Doppler feedback reactivity. The reactivity will reduce excess positive reactivity. Temperature reactor during accident is still in below fuel melting point which is in secure condition.

Yulianti, Yanti [Dept. of Physics, Universitas Lampung (UNILA), Jl. Sumantri Brojonegor No.1 Bandar Lampung (Indonesia); Dept. of Physics, Institut Teknologi Bandung (ITB), Jl. Ganesha 10 Bandung (Indonesia); Su'ud, Zaki; Waris, Abdul; Khotimah, S. N. [Dept. of Physics, Institut Teknologi Bandung (ITB), Jl. Ganesha 10 Bandung (Indonesia); Shafii, M. Ali [Dept. of Physics, Institut Teknologi Bandung (ITB), Jl. Ganesha 10 Bandung (Indonesia); Dept. of Physics, Universitas Andalas (UNAND), Kampus Limau Manis, Padang, Sumatera Barat (Indonesia)

2010-12-23T23:59:59.000Z

324

Application of accident progression event tree technology to the Savannah River Site Defense Waste Processing Facility SAR analysis  

SciTech Connect

The Accident Analysis in the Safety Analysis Report (SAR) for the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) has recently undergone an upgrade. Non-reactor SARs at SRS (and other Department of Energy (DOE) sites) use probabilistic techniques to assess the frequency of accidents at their facilities. This paper describes the application of an extension of the Accident Progression Event Tree (APET) approach to accidents at the SRS DWPF. The APET technique allows an integrated model of the facility risk to be developed, where previous probabilistic accident analyses have been limited to the quantification of the frequency and consequences of individual accident scenarios treated independently. Use of an APET allows a more structured approach, incorporating both the treatment of initiators that are common to more than one accident, and of accident progression at the facility.

Brandyberry, M.D.; Baker, W.H.; Wittman, R.S. [Westinghouse Savannah River Co., Aiken, SC (United States); Amos, C.N. [Science Applications International Corp., Albuquerque, NM (United States)

1993-12-31T23:59:59.000Z

325

Pollution Prevention at Brookhaven - Environmental Protection Division  

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

Pollution Prevention Pollution Prevention at Brookhaven National Laboratory BNL Pollution Prevention Program Description Pollution Prevention Regulations and Policies Cost Savings from Pollution Prevention & Recycling Initiatives Recycling Program Information BNL Recycles by the TON...recycling statistics BNL Energy Challenge Executive Order 13514 and Site Sustainability Plans Federal Leadership in Environmental, Energy, and Economic Performance Pollution Prevention Funding Opportunities P2 Proposal Form Pollution Prevention Awards Program DOE, BNL, and external Buying "Green" Products Information on Environmentally Preferable Purchasing Other P2 Resources/Databases Other P2 websites of interest How Do I Manage This Waste Stream? How-to advice on long list of common wastes

326

POLLUTION PREVENTION AND MANAGEMENT STRATEGIES  

E-Print Network (OSTI)

by intentional addition of silica and lime. Fluxes such as calcium fluoride may be added to make the slag more Systems ..................................4-9 4.7.5 Off-site Recycle by Reuse as a Construction Material separate from those of pollution prevention assessment.) Reclamation - Denotes internal reuse of materials

Shor, Leslie McCabe

327

The Accident Sequence Precursor program: Methods improvements and current results  

Science Conference Proceedings (OSTI)

Changes in the US NRC Accident Sequence Precursor program methods since the initial program evaluations of 1969-81 operational events are described, along with insights from the review of 1984-85 events. For 1984-85, the number of significant precursors was consistent with the number observed in 1980-81, dominant sequences associated with significant events were reasonably consistent with PRA estimates for BWRs, but lacked the contribution due to small-break LOCAs previously observed and predicted in PWRs, and the frequency of initiating events and non-recoverable system failures exhibited some reduction compared to 1980-81. Operational events which provide information concerning additional PRA modeling needs are also described.

Minarick, J.W.; Manning, F.M.; Harris, J.D.

1987-01-01T23:59:59.000Z

328

Down syndrome clusters in Germany after the Chernobyl accident  

Science Conference Proceedings (OSTI)

In two independent studies using different approaches and covering West Berlin and Bavaria, respectively, highly significant temporal clusters of Down syndrome were found. Both sharp increases occurred in areas receiving relatively low Chernobyl fallout and concomitant radiation exposures. Only for the Berlin cluster was fallout present at the time of the affected meiosis, whereas the Nuremberg cluster preceded the radioactive contamination by 1 month. Hypotheses on possible causal relationships are compared. Radiation from the Chernobyl accident is an unlikely factor, because the associated cumulative dose was so low in comparison with natural background. Microdosimetric considerations would indicate that fewer than 1 in 200 oocyte nuclei would have experienced an ionizing event from Chernobyl radioactivity. Given the lack of understanding of what causes Down syndrome, other than factors associated with increased maternal age, additional research into environmental and infectious risk factors is warranted. 23 refs., 4 figs., 2 tabs.

Burkart, W.; Grosche, B.; Schoetzau, A. [Institute for Radiation Hygiene, Oberschleissheim (Germany)

1997-03-01T23:59:59.000Z

329

The role of chemical reactions in the Chernobyl accident  

SciTech Connect

It is shown that chemical reactions played an essential role in the Chernobyl accident at all of its stages. It is important that the reactor before the explosion was at maximal xenon poisoning, and its reactivity, apparently, was not destroyed by the explosion. The reactivity release due to decay of Xe-235 on the second day after the explosion led to a reactor power of 80-110 MW. Owing to this power, the chemical reactions of reduction of uranium, plutonium, and other metals at a temperature of about 2000 Degree-Sign C occurred in the core. The yield of fission products thus sharply increased. Uranium and other metals flew down in the bottom water communications and rooms. After reduction of the uranium and its separation from the graphite, the chain reaction stopped, the temperature of the core decreased, and the activity yield stopped.

Grishanin, E. I., E-mail: egrishanin@orexovo.net [Russian Research Center Kurchatov Institute (Russian Federation)

2010-12-15T23:59:59.000Z

330

Hypothetical accident conditions thermal analysis of the 5320 package  

Science Conference Proceedings (OSTI)

An axisymmetric model of the 5320 package was created to perform hypothetical accident conditions (HAC) thermal calculations. The analyses assume the 5320 package contains 359 grams of plutonium-238 (203 Watts) in the form of an oxide powder at a minimum density of 2.4 g/cc or at a maximum density of 11.2 g/cc. The solution from a non-solar 100 F ambient steady-state analysis was used as the initial conditions for the fire transient. A 30 minute 1,475 F fire transient followed by cooling via natural convection and thermal radiation to a 100 F non-solar environment was analyzed to determine peak component temperatures and vessel pressures. The 5320 package was considered to be horizontally suspended within the fire during the entire transient.

Hensel, S.J.; Gromada, R.J.

1995-12-31T23:59:59.000Z

331

Probabilistic Accident Consequence Uncertainty - A Joint CEC/USNRC Study  

Science Conference Proceedings (OSTI)

The joint USNRC/CEC consequence uncertainty study was chartered after the development of two new probabilistic accident consequence codes, MACCS in the U.S. and COSYMA in Europe. Both the USNRC and CEC had a vested interest in expanding the knowledge base of the uncertainty associated with consequence modeling, and teamed up to co-sponsor a consequence uncertainty study. The information acquired from the study was expected to provide understanding of the strengths and weaknesses of current models as well as a basis for direction of future research. This paper looks at the elicitation process implemented in the joint study and discusses some of the uncertainty distributions provided by eight panels of experts from the U.S. and Europe that were convened to provide responses to the elicitation. The phenomenological areas addressed by the expert panels include atmospheric dispersion and deposition, deposited material and external doses, food chain, early health effects, late health effects and internal dosimetry.

Gregory, Julie J.; Harper, Frederick T.

1999-07-28T23:59:59.000Z

332

MACCS2: An improved code for assessing nuclear accident consequences  

Science Conference Proceedings (OSTI)

The MACCS computer code was developed to predict probabilistic assessments of the consequences from severe accidents at nuclear power plants.For DOE applications and sensitivity studies of emergency response actions at nuclear power plants, MACCS2 represents a significant improvement in modeling flexibility over MACCS 1.5. This increased flexibility is obtained with an approximate doubling of the code`s run time and memory requirements. The software can be adapted to most computers. An executable is included in the code package for 386/486 IBM-compatible personal computers with 8 megabytes of random access memory (RAM). MACCS2 is being benchmarked against the RSAC-5 code developed by INEL. A new set of code documentation is being prepared that describes the use of the code, the models implemented, and the code benchmarking. Current plans are to have the code package (including source code) available to the public at the end of fiscal year 1994.

Chanin, D.I.; Banjac, V.; Miller, L.A. [Sandia National Lab., Albuquerque, NM (United States)

1994-12-31T23:59:59.000Z

333

Corium Physical Properties for Severe Accident R and D  

SciTech Connect

Corium is a mixture formed - in the hypothetical case of a severe accident - of molten core and products from the decomposition of the internal structures, the vessel and the concrete. Before any calculation, any modelling, any experimental interpretation can be made, it is necessary to estimate the corium physical properties. Corium being a multicomponent mixture, special attention has been given at CEA to the mixing laws for multi-phase, multi-constituent mixtures. Compared to the previous database, considerable progress in characterizing of corium constituents physical properties has been achieved. The thermo-physical data of corium constituents for pure components and mixtures and the different physical laws that are recommended by experts are now implemented in the CORPRO (Corium Properties) database. (authors)

Journeau, C.; Piluso, P.; Frolov, K.N. [CEA Cadarache, Severe Accident Mastering Laboratory (DEN/DTN/STRI/LMA), 13108 St Paul lez Durance (France)

2004-07-01T23:59:59.000Z

334

The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA)  

E-Print Network (OSTI)

of Materials Properties for Light Water Reactor Accident Analysis", NUREG/CR-6150, INEL-96.0422, chapter 4

Motta, Arthur T.

335

Technical evaluation: 300 Area steam line valve accident  

SciTech Connect

On June 7, 1993, a journeyman power operator (JPO) was severely burned and later died as a result of the failure of a 6-in. valve that occurred when he attempted to open main steam supply (MSS) valve MSS-25 in the U-3 valve pit. The pit is located northwest of Building 331 in the 300 Area of the Hanford Site. Figure 1-1 shows a layout of the 300 Area steam piping system including the U-3 steam valve pit. Figure 1-2 shows a cutaway view of the approximately 10- by 13- by 16-ft-high valve pit with its various steam valves and connecting piping. Valve MSS-25, an 8-in. valve, is located at the bottom of the pit. The failed 6-in. valve was located at the top of the pit where it branched from the upper portion of the 8-in. line at the 8- by 8- by 6-in. tee and was then ``blanked off`` with a blind flange. The purpose of this technical evaluation was to determine the cause of the accident that led to the failure of the 6-in. valve. The probable cause for the 6-in. valve failure was determined by visual, nondestructive, and destructive examination of the failed valve and by metallurgical analysis of the fractured region of the valve. The cause of the accident was ultimately identified by correlating the observed failure mode to the most probable physical phenomenon. Thermal-hydraulic analyses, component stress analyses, and tests were performed to verify that the probable physical phenomenon could be reasonably expected to produce the failure in the valve that was observed.

Not Available

1993-08-01T23:59:59.000Z

336

WHEN MODEL MEETS REALITY A REVIEW OF SPAR LEVEL 2 MODEL AGAINST FUKUSHIMA ACCIDENT  

SciTech Connect

The Standardized Plant Analysis Risk (SPAR) models are a set of probabilistic risk assessment (PRA) models used by the Nuclear Regulatory Commission (NRC) to evaluate the risk of operations at U.S. nuclear power plants and provide inputs to risk informed regulatory process. A small number of SPAR Level 2 models have been developed mostly for feasibility study purpose. They extend the Level 1 models to include containment systems, group plant damage states, and model containment phenomenology and accident progression in containment event trees. A severe earthquake and tsunami hit the eastern coast of Japan in March 2011 and caused significant damages on the reactors in Fukushima Daiichi site. Station blackout (SBO), core damage, containment damage, hydrogen explosion, and intensive radioactivity release, which have been previous analyzed and assumed as postulated accident progression in PRA models, now occurred with various degrees in the multi-units Fukushima Daiichi site. This paper reviews and compares a typical BWR SPAR Level 2 model with the real accident progressions and sequences occurred in Fukushima Daiichi Units 1, 2, and 3. It shows that the SPAR Level 2 model is a robust PRA model that could very reasonably describe the accident progression for a real and complicated nuclear accident in the world. On the other hand, the comparison shows that the SPAR model could be enhanced by incorporating some accident characteristics for better representation of severe accident progression.

Zhegang Ma

2013-09-01T23:59:59.000Z

337

Analysis of Kuosheng Station Blackout Accident Using MELCOR 1.8.4  

Science Conference Proceedings (OSTI)

The MELCOR code, developed by Sandia National Laboratories, is a fully integrated, relatively fast-running code that models the progression of severe accidents in commercial light water nuclear power plants (NPPs).A specific station blackout (SBO) accident for Kuosheng (BWR-6) NPP is simulated using the MELCOR 1.8.4 code. The MELCOR input deck for Kuosheng NPP is established based on Kuosheng NPP design data and the MELCOR users' guides. The initial steady-state conditions are generated with a developed self-initialization algorithm. The main severe accident phenomena and the fission product release fractions associated with the SBO accident were simulated. The predicted results are plausible and as expected in light of current understanding of severe accident phenomena. The uncertainty of this analysis is briefly discussed. The important features of the MELCOR 1.8.4 are described. The estimated results provide useful information for the probabilistic risk assessment (PRA) of Kuosheng NPP. This tool will be applied to the PRA, the severe accident analysis, and the severe accident management study of Kuosheng NPP in the near future.

Wang, S.-J.; Chien, C.-S.; Wang, T.-C.; Chiang, K.-S

2000-11-15T23:59:59.000Z

338

Hazards and accident analyses, an integrated approach, for the Plutonium Facility at Los Alamos National Laboratory  

Science Conference Proceedings (OSTI)

This paper describes an integrated approach to perform hazards and accident analyses for the Plutonium Facility at Los Alamos National Laboratory. A comprehensive hazards analysis methodology was developed that extends the scope of the preliminary/process hazard analysis methods described in the AIChE Guidelines for Hazard Evaluations. Results fro the semi-quantitative approach constitute a full spectrum of hazards. For each accident scenario identified, there is a binning assigned for the event likelihood and consequence severity. In addition, each accident scenario is analyzed for four possible sectors (workers, on-site personnel, public, and environment). A screening process was developed to link the hazard analysis to the accident analysis. Specifically the 840 accident scenarios were screened down to about 15 accident scenarios for a more through deterministic analysis to define the operational safety envelope. The mechanics of the screening process in the selection of final scenarios for each representative accident category, i.e., fire, explosion, criticality, and spill, is described.

Pan, P.Y.; Goen, L.K.; Letellier, B.C.; Sasser, M.K.

1995-07-01T23:59:59.000Z

339

Community emergency response to nuclear power plant accidents: A selected and partially annotated bibliography  

SciTech Connect

The role of responding to emergencies at nuclear power plants is often considered the responsibility of the personnel onsite. This is true for most, if not all, of the incidents that may happen during the course of the plant`s operating lifetime. There is however, the possibility of a major accident occurring at anytime. Major nuclear accidents at Chernobyl and Three Mile Island have taught their respective countries and communities a significant lesson in local emergency preparedness and response. Through these accidents, the rest of the world can also learn a great deal about planning, preparing and responding to the emergencies unique to nuclear power. This bibliography contains books, journal articles, conference papers and government reports on emergency response to nuclear power plant accidents. It does not contain citations for ``onsite`` response or planning, nor does it cover the areas of radiation releases from transportation accidents. The compiler has attempted to bring together a sampling of the world`s collective written experience on dealing with nuclear reactor accidents on the sate, local and community levels. Since the accidents at Three Mile Island and Chernobyl, that written experience has grown enormously.

Youngen, G.

1988-10-01T23:59:59.000Z

340

NEWTON: Preventing Tire Dry Rot  

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

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

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


341

Pollution prevention program plan 1996  

SciTech Connect

This plan serves as the principal crosscutting guidance to Department of Energy (DOE) Headquarters, Operations Office, laboratory, and contractor management to fully implement pollution prevention programs within the DOE complex between now and 2000. To firmly demonstrate DOE`s commitment to pollution prevention, the Secretary of Energy has established goals, to be achieved by December 31, 1999, that will aggressively reduce DOE`s routine generation of radioactive, mixed, and hazardous wastes, and total releases and offsite transfers of toxic chemicals. The Secretary also has established sanitary waste reduction, recycling, and affirmative procurement goals. Site progress in meeting these goals will be reported annually to the Secretary in the Annual Report on Waste Generation and Waste Minimization Progress, using 1993 as the baseline year. Implementation of this plan will represent a major step toward reducing the environmental risks and costs associated with DOE operations.

NONE

1996-06-01T23:59:59.000Z

342

Pollution Prevention - Environmental Impact Reduction Checklists for  

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

Pollution Prevention - Environmental Impact Reduction Checklists Pollution Prevention - Environmental Impact Reduction Checklists for NEPA/309 Reviewers Pollution Prevention - Environmental Impact Reduction Checklists for NEPA/309 Reviewers The environmental review process under the National Environmental Policy Act (NEPA) provides a valuable opportunity for Federal agency NEPA/309 reviewers to incorporate pollution prevention and environmental impact reduction into actions (or projects). This Environmental Protection Agency guidance was prepared to assist NEPA/309 reviewers in incorporating pollution prevention into each step of the environmental review process, including scoping, mitigation, monitoring, and enforcement. POLLUTION PREVENTION - ENVIRONMENTAL IMPACT REDUCTION CHECKLISTS FOR NEPA/309 REVIEWERS JANUARY 1995

343

Pollution Prevention - Environmental Impact Reduction Checklists for  

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

Pollution Prevention - Environmental Impact Reduction Checklists Pollution Prevention - Environmental Impact Reduction Checklists for NEPA/309 Reviewers Pollution Prevention - Environmental Impact Reduction Checklists for NEPA/309 Reviewers The environmental review process under the National Environmental Policy Act (NEPA) provides a valuable opportunity for Federal agency NEPA/309 reviewers to incorporate pollution prevention and environmental impact reduction into actions (or projects). This Environmental Protection Agency guidance was prepared to assist NEPA/309 reviewers in incorporating pollution prevention into each step of the environmental review process, including scoping, mitigation, monitoring, and enforcement. POLLUTION PREVENTION - ENVIRONMENTAL IMPACT REDUCTION CHECKLISTS FOR NEPA/309 REVIEWERS JANUARY 1995

344

August 2003, Columbia Accident Investigation Report Volume I. Chapter 5-8  

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

9 7 9 7 R e p o r t V o l u m e I A u g u s t 2 0 0 3 Part Two Why The Accident Occurred Many accident investigations do not go far enough. They identify the technical cause of the accident, and then connect it to a variant of "operator error" - the line worker who forgot to insert the bolt, the engineer who miscalculated the stress, or the manager who made the wrong decision. But this is sel-

345

Audit of the Department of Energy's Transportation Accident Resistant Container Program, IG-0380  

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

1, 1995 1, 1995 IG-1 INFORMATION: Report on "Audit of the Department of Energy's Transportation Accident Resistant Container Program" The Secretary BACKGROUND: The U.S. Department of Energy (Department) has ultimate responsibility for the safety of all nuclear explosives and weapons operations conducted by the Department and its contractors. The Department also has joint responsibility for the safety of nuclear weapons in the custody of the Armed Services. Since the 1970s, the Department has designed, developed, and produced accident resistant containers to promote safety when transporting certain types of nuclear weapons by air. DISCUSSION: After successfully developing and modifying accident resistant containers for

346

Study on the Accidental Rupture of Hot Leg or Surge Line in SBO Accident  

Science Conference Proceedings (OSTI)

The postulated total station blackout accident (SBO) of PWR NPP with 600 MWe in China is analyzed as the base case using SCDAP/RELAP5 code. Then the hot leg or surge line are assumed to rupture before the lower head of Reactor Pressure Vessel (RPV) ruptures, and the progressions are analyzed in detail comparing with the base case. The results show that the accidental rupture of hot leg or surge line will greatly influence the progression of accident. The probability of hot leg or surge line rupture in intentional depressurization is also studied in this paper, which provides a suggestion to the development of Severe Accident Management Guidelines (SAMG). (authors)

Kun Zhang; Xuewu Cao [Shanghai Jiaotong University, Shanghai (China)

2006-07-01T23:59:59.000Z

347

Statistical description of heavy truck accidents on representative segments of interstate highway  

SciTech Connect

Any quantitative analysis of the risk of transportation accidents requires the use of many different statistical distributions. Included among these are the types of accidents which occur and the severity of these when they do occur. Several previous studies have derived this type of information for truck traffic over U. S. highways in general; these data are not necessarily applicable for the anticipated LMFBR spent fuel cask routes. This report presents data for highway segments representative of the specific LMFBR cask routes which are anticipated. These data are based upon a detailed record-by-record review of filed reports for accidents which occurred along the specified route segments.

Hartman, W.F.; Davidson, C.A.; Foley, J.T.

1977-01-01T23:59:59.000Z

348

Air toxics provisions of the Clean Air Act: Potential impacts on energy  

SciTech Connect

This report provides an overview of the provisions of the Clean Air Act and its Amendments of 1990 that identify hazardous air pollutant (HAP) emissions and addresses their regulation by the US Environmental Protection Agency (EPA). It defines the major energy sector sources of these HAPs that would be affected by the regulations. Attention is focused on regulations that would cover coke oven emissions; chromium emission from industrial cooling towers and the electroplating process; HAP emissions from tank vessels, asbestos-related activities, organic solvent use, and ethylene oxide sterilization; and emissions of air toxics from municipal waste combustors. The possible implications of Title III regulations for the coal, natural gas, petroleum, uranium, and electric utility industries are examined. The report discusses five major databases of HAP emissions: (1) TRI (EPA`s Toxic Release Inventory); (2) PISCES (Power Plant Integrated Systems: Chemical Emissions Studies developed by the Electric Power Research Institute); (3) 1985 Emissions Inventory on volatile organic compounds (used for the National Acid Precipitation Assessment Program); (4) Particulate Matter Species Manual (EPA); and (5) Toxics Emission Inventory (National Aeronautics and Space Administration). It also offers information on emission control technologies for municipal waste combustors.

Hootman, H.A.; Vernet, J.E.

1991-11-01T23:59:59.000Z

349

Air toxics provisions of the Clean Air Act: Potential impacts on energy  

SciTech Connect

This report provides an overview of the provisions of the Clean Air Act and its Amendments of 1990 that identify hazardous air pollutant (HAP) emissions and addresses their regulation by the US Environmental Protection Agency (EPA). It defines the major energy sector sources of these HAPs that would be affected by the regulations. Attention is focused on regulations that would cover coke oven emissions; chromium emission from industrial cooling towers and the electroplating process; HAP emissions from tank vessels, asbestos-related activities, organic solvent use, and ethylene oxide sterilization; and emissions of air toxics from municipal waste combustors. The possible implications of Title III regulations for the coal, natural gas, petroleum, uranium, and electric utility industries are examined. The report discusses five major databases of HAP emissions: (1) TRI (EPA's Toxic Release Inventory); (2) PISCES (Power Plant Integrated Systems: Chemical Emissions Studies developed by the Electric Power Research Institute); (3) 1985 Emissions Inventory on volatile organic compounds (used for the National Acid Precipitation Assessment Program); (4) Particulate Matter Species Manual (EPA); and (5) Toxics Emission Inventory (National Aeronautics and Space Administration). It also offers information on emission control technologies for municipal waste combustors.

Hootman, H.A.; Vernet, J.E.

1991-11-01T23:59:59.000Z

350

Bandwidth provisioning in infrastructure-based wireless networks employing directional antennas  

Science Conference Proceedings (OSTI)

Motivated by the widespread proliferation of wireless networks employing directional antennas, we study the problem of provisioning bandwidth in such networks. Given a set of subscribers and one or more access points possessing directional antennas, we formalize the problem of orienting these antennas in two fundamental settings: (1) subscriber-centric, where the objective is to fairly allocate bandwidth among the subscribers and (2) provider-centric, where the objective is to maximize the revenue generated by satisfying the bandwidth requirements of subscribers. For both the problems, we first design algorithms for a network with only one access point working under the assumption that the number of antennas does not exceed the number of noninterfering channels. Using the well-regarded lexicographic max-min fair allocation as the objective for a subscriber-centric network, we present an optimum dynamic programming algorithm. For a provider-centric network, the allocation problem turns out to be NP-hard. We present a greedy heuristic based algorithm that guarantees almost half of the optimum revenue. We later enhance both these algorithms to operate in more general networks with multiple access points and no restrictions on the relative numbers of antennas and channels. A simulation-based evaluation using OPNET demonstrates the efficacy of our approaches and provides us further in insights into these problems.

Hasiviswanthan, Shiva [Los Alamos National Laboratory; Zhao, Bo [PENN STATE UNIV.; Vasudevan, Sudarshan [UNIV OF MASS AMHERST; Yrgaonkar, Bhuvan [PENN STATE UNIV.

2009-01-01T23:59:59.000Z

351

Sandia National Laboratories: Pollution Prevention: Reuse  

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

Contribution Programs Volunteer Programs Education Programs Environmental Responsibility Environmental Management System Pollution Prevention History Diversity Locations Missions...

352

Sandia National Laboratories: Pollution Prevention: Outreach  

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

Contribution Programs Volunteer Programs Education Programs Environmental Responsibility Environmental Management System Pollution Prevention History Diversity Locations Missions...

353

Sandia National Laboratories: Pollution Prevention: Goals  

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

Contribution Programs Volunteer Programs Education Programs Environmental Responsibility Environmental Management System Pollution Prevention History Diversity Locations Missions...

354

Dendrite Growth Prevention Technology for Lithium Metal ...  

Search PNNL. PNNL Home; About; Research; Publications; Jobs; News; Contacts; Dendrite Growth Prevention Technology for Lithium Metal Batteries. ...

355

Accident Performance of Light Water Reactor Cladding Materials  

DOE Green Energy (OSTI)

During a loss of coolant accident as experienced at Fukushima, inadequate cooling of the reactor core forces component temperatures ever higher where they must withstand aggressive chemical environments. Conventional zirconium cladding alloys will readily oxidize in the presence of water vapor at elevated temperatures, rapidly degrading and likely failing. A cladding breach removes the critical barrier between actinides and fission products and the coolant, greatly increasing the probability of the release of radioactivity in the event of a containment failure. These factors have driven renewed international interest in both study and improvement of the materials used in commercial light water reactors. Characterization of a candidate cladding alloy or oxidation mitigation technique requires understanding of both the oxidation kinetics and hydrogen production as a function of temperature and atmosphere conditions. Researchers in the MST division supported by the DOE-NE Fuel Cycle Research and Development program are working to evaluate and quantify these parameters across a wide range of proposed cladding materials. The primary instrument employed is a simultaneous thermal analyzer (STA) equipped with a specialized water vapor furnace capable of maintaining temperatures above 1200 C in a range of atmospheres and water vapor contents. The STA utilizes thermogravimetric analysis and a coupled mass spectrometer to measure in situ oxidation and hydrogen production of candidate materials. This capability is unprecedented in study of materials under consideration for reactor cladding use, and is currently being expanded to investigate proposed coating techniques as well as the effect of coating defects on corrosion resistance.

Nelson, Andrew T. [Los Alamos National Laboratory

2012-07-24T23:59:59.000Z

356

Source terms for analysis of accidents at a high level waste repository  

SciTech Connect

This paper describes an approach to identifying source terms from possible accidents during the preclosure phase of a high-level nuclear waste repository. A review of the literature on repository safety analyses indicated that source term estimation is in a preliminary stage, largely based on judgement-based scoping analyses. The approach developed here was to partition the accident space into domains defined by certain threshold values of temperature and impact energy density which may arise in potential accidents and specify release fractions of various radionuclides, present in the waste form, in each domain. Along with a more quantitative understanding of accident phenomenology, this approach should help in achieving a clearer perspective on scenarios important to preclosure safety assessments of geologic repositories. 18 refs., 3 tabs.

Mubayi, V.; Davis, R.E.; Youngblood, R.

1989-01-01T23:59:59.000Z

357

Human error and general aviation accidents: A comprehensive, fine-grained analysis using HFACS  

E-Print Network (OSTI)

The Human Factors Analysis and Classification System (HFACS) is a theoretically based tool for investigating and analyzing human error associated with accidents and incidents. Previous research performed at both at the University of Illinois and the Civil Aerospace Medical Institute (CAMI) have been highly successful and have shown that HFACS can be reliably used to analyze the underlying human causes of both commercial and general aviation (GA) accidents. these analyses have helped identify general trends in the types of human factors issues and aircrew errors that have contributed to civil aviation accidents. The next step is to identify the exact nature of the human errors identified. The purpose of this research effort, therefore, was to address these questions by performing a fine-grained HFACS analysis of the individual human causal factors associated with GA accidents and to assist in the generation of intervention programs. This report details those findings and offers an approach for developing interventions to address them.

Douglas A. Wiegmann; Albert Boquet; Cristy Detwiler; Kali Holcomb; Troy Faaborg; Douglas A. Wiegmann, Ph.D., Ph.D.; Albert Boquet, Ph.D.; Cristy Detwiler; Kali Holcomb; Troy Faaborg

2005-01-01T23:59:59.000Z

358

A methodology for analyzing precursors to earthquake-initiated and fire-initiated accident sequences  

SciTech Connect

This report covers work to develop a methodology for analyzing precursors to both earthquake-initiated and fire-initiated accidents at commercial nuclear power plants. Currently, the U.S. Nuclear Regulatory Commission sponsors a large ongoing project, the Accident Sequence Precursor project, to analyze the safety significance of other types of accident precursors, such as those arising from internally-initiated transients and pipe breaks, but earthquakes and fires are not within the current scope. The results of this project are that: (1) an overall step-by-step methodology has been developed for precursors to both fire-initiated and seismic-initiated potential accidents; (2) some stylized case-study examples are provided to demonstrate how the fully-developed methodology works in practice, and (3) a generic seismic-fragility date base for equipment is provided for use in seismic-precursors analyses. 44 refs., 23 figs., 16 tabs.

Budnitz, R.J.; Lambert, H.E.; Apostolakis, G. [and others] and others

1998-04-01T23:59:59.000Z

359

Meteorological Factors Influencing the Radioactive Deposition in Finland after the Chernobyl Accident  

Science Conference Proceedings (OSTI)

After the accident at the Chernobyl nuclear plant on 26 April 1986, much of Europe was affected by radioactive pollution. The first releases were transported toward Scandinavia, where most of the fallout was attributable to wet deposition. This ...

Timo Puhakka; Kirsti Jylh; Pirkko Saarikivi; Jarmo Koistinen; Janne Koivukoski

1990-09-01T23:59:59.000Z

360

Mining complex power networks for blackout prevention  

Science Conference Proceedings (OSTI)

Following the recent devastating blackouts in North America, UK and Italy, blackout prevention has attracted significant attention, though it is known as a notoriously difficult task. To prevent the blackout, it is essential to accurately predict the ... Keywords: blackout prevention, graph mining, power networks

Jun Hua Zhao; Zhao Yang Dong; Pei Zhang

2007-08-01T23:59:59.000Z

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361

Accident Analysis for the NIST Research Reactor Before and After Fuel Conversion  

SciTech Connect

Postulated accidents have been analyzed for the 20 MW D2O-moderated research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The analysis has been carried out for the present core, which contains high enriched uranium (HEU) fuel and for a proposed equilibrium core with low enriched uranium (LEU) fuel. The analyses employ state-of-the-art calculational methods. Three-dimensional Monte Carlo neutron transport calculations were performed with the MCNPX code to determine homogenized fuel compositions in the lower and upper halves of each fuel element and to determine the resulting neutronic properties of the core. The accident analysis employed a model of the primary loop with the RELAP5 code. The model includes the primary pumps, shutdown pumps outlet valves, heat exchanger, fuel elements, and flow channels for both the six inner and twenty-four outer fuel elements. Evaluations were performed for the following accidents: (1) control rod withdrawal startup accident, (2) maximum reactivity insertion accident, (3) loss-of-flow accident resulting from loss of electrical power with an assumption of failure of shutdown cooling pumps, (4) loss-of-flow accident resulting from a primary pump seizure, and (5) loss-of-flow accident resulting from inadvertent throttling of a flow control valve. In addition, natural circulation cooling at low power operation was analyzed. The analysis shows that the conversion will not lead to significant changes in the safety analysis and the calculated minimum critical heat flux ratio and maximum clad temperature assure that there is adequate margin to fuel failure.

Baek J.; Diamond D.; Cuadra, A.; Hanson, A.L.; Cheng, L-Y.; Brown, N.R.

2012-09-30T23:59:59.000Z

362

Site restoration: Estimation of attributable costs from plutonium-dispersal accidents  

SciTech Connect

A nuclear weapons accident is an extremely unlikely event due to the extensive care taken in operations. However, under some hypothetical accident conditions, plutonium might be dispersed to the environment. This would result in costs being incurred by the government to remediate the site and compensate for losses. This study is a multi-disciplinary evaluation of the potential scope of the post-accident response that includes technical factors, current and proposed legal requirements and constraints, as well as social/political factors that could influence decision making. The study provides parameters that can be used to assess economic costs for accidents postulated to occur in urban areas, Midwest farmland, Western rangeland, and forest. Per-area remediation costs have been estimated, using industry-standard methods, for both expedited and extended remediation. Expedited remediation costs have been evaluated for highways, airports, and urban areas. Extended remediation costs have been evaluated for all land uses except highways and airports. The inclusion of cost estimates in risk assessments, together with the conventional estimation of doses and health effects, allows a fuller understanding of the post-accident environment. The insights obtained can be used to minimize economic risks by evaluation of operational and design alternatives, and through development of improved capabilities for accident response.

Chanin, D.I.; Murfin, W.B. [Technadyne Engineering Consultants, Inc., Albuquerque, NM (United States)

1996-05-01T23:59:59.000Z

363

Bibliography for nuclear criticality accident experience, alarm systems, and emergency management  

SciTech Connect

The characteristics, detection, and emergency management of nuclear criticality accidents outside reactors has been an important component of criticality safety for as long as the need for this specialized safety discipline has been recognized. The general interest and importance of such topics receives special emphasis because of the potentially lethal, albeit highly localized, effects of criticality accidents and because of heightened public and regulatory concerns for any undesirable event in nuclear and radiological fields. This bibliography lists references which are potentially applicable to or interesting for criticality alarm, detection, and warning systems; criticality accident emergency management; and their associated programs. The lists are annotated to assist bibliography users in identifying applicable: industry and regulatory guidance and requirements, with historical development information and comments; criticality accident characteristics, consequences, experiences, and responses; hazard-, risk-, or safety-analysis criteria; CAS design and qualification criteria; CAS calibration, maintenance, repair, and testing criteria; experiences of CAS designers and maintainers; criticality accident emergency management (planning, preparedness, response, and recovery) requirements and guidance; criticality accident emergency management experience, plans, and techniques; methods and tools for analysis; and additional bibliographies.

Putman, V.L.

1995-09-01T23:59:59.000Z

364

Application of RELAP/SCDAPSIM and COCOSYS Codes for Severe Accident Analysis in RBMK-1500 Reactor  

Science Conference Proceedings (OSTI)

Regardless low probability of occurrence the severe accident phenomena are investigated for all types of nuclear reactors in the world because the consequences of such accident could be catastrophic. Most of research is performed for the prevailing vessel-type light water reactors like PWRs and BWRs. Less research is performed for the channel-type reactors like CANDUs and RBMKs as they are operated just in a few countries. Up to now the phenomena that could occur in case of a severe accident in RBMK reactors were not analysed in detail and little literature is available on this topic. The paper presents one of the first integrated analyses of severe accident in RBMK-1500 reactor. RELAP/SCDAPSIM code is used to simulate the phenomena in the reactor core and reactor cooling system and COCOSYS code is used to simulate the confinement phenomena during the same accident scenario. The performed analysis provided information regarding code acceptability for the severe accident analysis in RBMK reactor and assessment of the timing of the key events, i.e. core uncover, fuel cladding rupture, etc, and provided assessment regarding hydrogen distribution in confinement. (authors)

Urbonavicius, E.; Uspuras, E.; Rimkevicius, S.; Kaliatka, A. [Lithuanian Energy Institute, Breslaujos g. 3, LT-44403 Kaunas (Lithuania)

2006-07-01T23:59:59.000Z

365

Pollution prevention cost savings potential  

SciTech Connect

The waste generated by DOE facilities is a serious problem that significantly impacts current operations, increases future waste management costs, and creates future environmental liabilities. Pollution Prevention (P2) emphasizes source reduction through improved manufacturing and process control technologies. This concept must be incorporated into DOE`s overall operating philosophy and should be an integral part of Total Quality Management (TQM) program. P2 reduces the amount of waste generated, the cost of environmental compliance and future liabilities, waste treatment, and transportation and disposal costs. To be effective, P2 must contribute to the bottom fine in reducing the cost of work performed. P2 activities at LLNL include: researching and developing innovative manufacturing; evaluating new technologies, products, and chemistries; using alternative cleaning and sensor technologies; performing Pollution Prevention Opportunity Assessments (PPOAs); and developing outreach programs with small business. Examples of industrial outreach are: innovative electroplating operations, printed circuit board manufacturing, and painting operations. LLNL can provide the infrastructure and technical expertise to address a wide variety of industrial concerns.

Celeste, J.

1994-12-01T23:59:59.000Z

366

Thermoplastic film prevents proppant flowback  

Science Conference Proceedings (OSTI)

Thermoplastic film added to proppants is effective and economical for preventing proppant flowback after an hydraulic fracturing treatment. Most other methods, such as resin-coated proppant and fiber, for controlling proppant flowback have drawbacks that added to treatment costs by requiring long downtime, costly additives, or frequent equipment replacement. Thermoplastic film does not react chemically with fracturing fluids. After the proppant is placed in the fracture, the film strips intertwine with the proppant grains or at higher temperatures, the strips become adhesive and shrink forming consolidated clusters that hold open the newly created fractures and prevent proppant from flowing back. The low cost of the film means that the strips can be used throughout the fracturing job or in selected stages. The strips are compatible with fracturing fluid chemistry, including breakers and crosslinkers, and can be used in wells with a wide range of bottom hole temperatures. The end result is a well that can be brought back on-line in a short time with little proppant flowback. This paper reviews the cost benefits and performance of these proppants.

Nguyen, P.D.; Weaver, J.D.; Parker, M.A.; King, D.G. [Halliburton Energy Services, Duncan, OK (United States)

1996-02-05T23:59:59.000Z

367

Orientation to pollution prevention for facility design  

Science Conference Proceedings (OSTI)

This material was developed to assist engineers in incorporating pollution prevention into the design of new or modified facilities within the U.S. Department of Energy (DOE). The material demonstrates how the design of a facility can affect the generation of waste throughout a facility`s entire life and it offers guidance on how to prevent the generation of waste during design. Contents include: Orientation to pollution prevention for facility design training course booklet; Pollution prevention design guideline; Orientation to pollution prevention for facility design lesson plan; Training participant survey and pretest; and Training facilitator`s guide and schedule.

Raney, E.A.; Whitehead, J.K.; Encke, D.B. [Westinghouse Hanford Co., Richland, WA (United States); Dorsey, J.A. [Kaiser Engineers Hanford Co., Richland, WA (United States)

1994-01-01T23:59:59.000Z

368

Environmental evaluation of municipal waste prevention  

Science Conference Proceedings (OSTI)

Highlights: > Influence of prevention on waste management systems, excluding avoided production, is relatively minor. > Influence of prevention on overall supply chain, including avoided production is very significant. > Higher relative benefits of prevention are observed in waste management systems relying mainly on landfills. - Abstract: Waste prevention has been addressed in the literature in terms of the social and behavioural aspects, but very little quantitative assessment exists of the environmental benefits. Our study evaluates the environmental consequences of waste prevention on waste management systems and on the wider society, using life-cycle thinking. The partial prevention of unsolicited mail, beverage packaging and food waste is tested for a 'High-tech' waste management system relying on high energy and material recovery and for a 'Low-tech' waste management system with less recycling and relying on landfilling. Prevention of 13% of the waste mass entering the waste management system generates a reduction of loads and savings in the waste management system for the different impacts categories; 45% net reduction for nutrient enrichment and 12% reduction for global warming potential. When expanding our system and including avoided production incurred by the prevention measures, large savings are observed (15-fold improvement for nutrient enrichment and 2-fold for global warming potential). Prevention of food waste has the highest environmental impact saving. Prevention generates relatively higher overall relative benefit for 'Low-tech' systems depending on landfilling. The paper provides clear evidence of the environmental benefits of waste prevention and has specific relevance in climate change mitigation.

Gentil, Emmanuel C.; Gallo, Daniele [Department of Environmental Engineering, Building 115, Technical University of Denmark, DK-2800 Kongens Lyngby (Denmark); Christensen, Thomas H., E-mail: thho@env.dtu.dk [Department of Environmental Engineering, Building 115, Technical University of Denmark, DK-2800 Kongens Lyngby (Denmark)

2011-12-15T23:59:59.000Z

369

Pollution Prevention Checklists for NEPA/309 Reviewers  

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

Pollution Prevention Checklists for NEPA/309 Reviewers Pollution Prevention Checklists for NEPA/309 Reviewers US Environmental Protection Agency Office of Federal Activities POLLUTION PREVENTION - ENVIRONMENTAL IMPACT REDUCTION CHECKLISTS FOR NEPA/309 REVIEWERS JANUARY 1995 Prepared by SCIENCE APPLICATIONS INTERNATIONAL CORPORATION 7600-A LEESBURG PIKE FALLS CHURCH, VA 22043 EPA CONTRACT NO. 68-W2-0026 EPA WORK ASSIGNMENT NO. 33-II SAIC PROJECT NO. 01-1030-07-1605-000 Table of Contents 1.0 INTRODUCTION 1.1 What Is Pollution Prevention? 1.2 Why Practice Pollution Prevention? 2.0 INCORPORATING POLLUTION PREVENTION INTO NEPA 3.0 POLLUTION PREVENTION/ENVIRONMENTAL IMPACT REDUCTION CHECKLISTS FOR NEPA REVIEWERS q Checklist for Energy Management file:///D|/40369.010_EPA%20NEPA%20CD/Old/HTML/Pollprev.htm (1 of 10) [9/11/2002 2:19:58 PM]

370

A New Approach in Advance Network Reservation and Provisioning for High-Performance Scientific Data Transfers  

Science Conference Proceedings (OSTI)

Scientific applications already generate many terabytes and even petabytes of data from supercomputer runs and large-scale experiments. The need for transferring data chunks of ever-increasing sizes through the network shows no sign of abating. Hence, we need high-bandwidth high speed networks such as ESnet (Energy Sciences Network). Network reservation systems, i.e. ESnet's OSCARS (On-demand Secure Circuits and Advance Reservation System) establish guaranteed bandwidth of secure virtual circuits at a certain time, for a certain bandwidth and length of time. OSCARS checks network availability and capacity for the specified period of time, and allocates requested bandwidth for that user if it is available. If the requested reservation cannot be granted, no further suggestion is returned back to the user. Further, there is no possibility from the users view-point to make an optimal choice. We report a new algorithm, where the user specifies the total volume that needs to be transferred, a maximum bandwidth that he/she can use, and a desired time period within which the transfer should be done. The algorithm can find alternate allocation possibilities, including earliest time for completion, or shortest transfer duration - leaving the choice to the user. We present a novel approach for path finding in time-dependent networks, and a new polynomial algorithm to find possible reservation options according to given constraints. We have implemented our algorithm for testing and incorporation into a future version of ESnet?s OSCARS. Our approach provides a basis for provisioning end-to-end high performance data transfers over storage and network resources.

Balman, Mehmet; Chaniotakis, Evangelos; Shoshani, Arie; Sim, Alex

2010-01-28T23:59:59.000Z

371

Evaluating Alternative "Countermeasures" Against Food Contamination Resulting From Nuclear Accidents  

E-Print Network (OSTI)

Nuclear accidents such as Chernobyl have far reaching impacts on ecological systems. Likewise they have major implications for agricultural systems, since crops and livestock can become contaminated and rendered unfit for human consumption. A range of `countermeasures' exists however, which can mitigate these impacts and allow food products to be saved. The CESER project has been concerned with the development of a system to assess the environmental side-effects of such countermeasures. Estimates of the economic costs of these environmental side-effects have been made for a number of case study sites in the UK, using environmental models and an original contingent valuation study. Estimates of farm level (private) costs are also included. 1. Professor, Department of Economics, University of Glasgow, Glasgow G12 8RT 2. Senior Lecturer, Department of Environmental Science, University of Stirling, Stirling FK9 4LA 3. former Research Associate, Department of Environmental Science, University of Stirling 4. former Research Associate, Department. of Environmental Science, University of Stirling. Manuscript date: 4/10/2000. Acknowledgements An earlier version of this paper was presented to the Agricultural Economics Society conference, Belfast, March 1999. The CESER project was funded by the European Union's Fourth Framework, Nuclear Fission Safety Programme (DGXII). Several academic institutions from across Europe participated in this project, including the University of Stirling, University of Bremen, Finnish Environment Institute, North-Trondelag College (Norway) and University of Salzburg. David Aitchison and Bill Jamieson of the cartography unit in the Department of Environmental Science, University of Stirling created the images used in the contingent valuation su...

Nick Hanley; Carol A. Salt; Mike Wilson; Meara Culligan-Dunsmore

2000-01-01T23:59:59.000Z

372

Cladding embrittlement during postulated loss-of-coolant accidents.  

DOE Green Energy (OSTI)

The effect of fuel burnup on the embrittlement of various cladding alloys was examined with laboratory tests conducted under conditions relevant to loss-of-coolant accidents (LOCAs). The cladding materials tested were Zircaloy-4, Zircaloy-2, ZIRLO, M5, and E110. Tests were performed with specimens sectioned from as-fabricated cladding, from prehydrided (surrogate for high-burnup) cladding, and from high-burnup fuel rods which had been irradiated in commercial reactors. The tests were designed to determine for each cladding material the ductile-to-brittle transition as a function of steam oxidation temperature, weight gain due to oxidation, hydrogen content, pre-transient cladding thickness, and pre-transient corrosion-layer thickness. For short, defueled cladding specimens oxidized at 1000-1200 C, ring compression tests were performed to determine post-quench ductility at {le} 135 C. The effect of breakaway oxidation on embrittlement was also examined for short specimens oxidized at 800-1000 C. Among other findings, embrittlement was found to be sensitive to fabrication processes--especially surface finish--but insensitive to alloy constituents for these dilute zirconium alloys used as cladding materials. It was also demonstrated that burnup effects on embrittlement are largely due to hydrogen that is absorbed in the cladding during normal operation. Some tests were also performed with longer, fueled-and-pressurized cladding segments subjected to LOCA-relevant heating and cooling rates. Recommendations are given for types of tests that would identify LOCA conditions under which embrittlement would occur.

Billone, M.; Yan, Y.; Burtseva, T.; Daum, R.; Nuclear Engineering Division

2008-07-31T23:59:59.000Z

373

Applications of human factors engineering to LNG release prevention and control  

SciTech Connect

The results of an investigation of human factors engineering and human reliability applications to LNG release prevention and control are reported. The report includes a discussion of possible human error contributions to previous LNG accidents and incidents, and a discussion of generic HF considerations for peakshaving plants. More specific recommendations for improving HF practices at peakshaving plants are offered based on visits to six facilities. The HF aspects of the recently promulgated DOT regulations are reviewed, and recommendations are made concerning how these regulations can be implemented utilizing standard HF practices. Finally, the integration of HF considerations into overall system safety is illustrated by a presentation of human error probabilities applicable to LNG operations and by an expanded fault tree analysis which explicitly recognizes man-machine interfaces.

Shikiar, R.; Rankin, W.L.; Rideout, T.B.

1982-06-01T23:59:59.000Z

374

Retrospection of Chernobyl nuclear accident for decision analysis concerning remedial actions in Ukraine  

SciTech Connect

It is considered the efficacy of decisions concerning remedial actions when of-site radiological monitoring in the early and (or) in the intermediate phases was absent or was not informative. There are examples of such situations in the former Soviet Union where many people have been exposed: releases of radioactive materials from 'Krasnoyarsk-26' into Enisey River, releases of radioactive materials from 'Chelabinsk-65' (the Kishtim accident), nuclear tests at the Semipalatinsk Test Site, the Chernobyl nuclear accident etc. If monitoring in the early and (or) in the intermediate phases is absent the decisions concerning remedial actions are usually developed on the base of permanent monitoring. However decisions of this kind may be essentially erroneous. For these cases it is proposed to make retrospection of radiological data of the early and intermediate phases of nuclear accident and to project decisions concerning remedial actions on the base of both retrospective data and permanent monitoring data. In this Report the indicated problem is considered by the example of the Chernobyl accident for Ukraine. Their of-site radiological monitoring in the early and intermediate phases was unsatisfactory. In particular, the pasture-cow-milk monitoring had not been made. All official decisions concerning dose estimations had been made on the base of measurements of {sup 137}Cs in body (40 measurements in 135 days and 55 measurements in 229 days after the Chernobyl accident). For the retrospection of radiological data of the Chernobyl accident dynamic model has been developed. This model has structure similar to the structure of Pathway model and Farmland model. Parameters of the developed model have been identified for agricultural conditions of Russia and Ukraine. By means of this model dynamics of 20 radionuclides in pathways and dynamics of doses have been estimated for the early, intermediate and late phases of the Chernobyl accident. The main results are following: - During the first year after the Chernobyl accident 75-93% of Commitment Effective Dose had been formed; - During the first year after the Chernobyl accident 85-90% of damage from radiation exposure had been formed. During the next 50 years (the late phase of accident) only 10-15% of damage from radiation exposure will have been formed; - Remedial actions (agricultural remedial actions as most effective) in Ukraine are intended for reduction of the damage from consumption of production which is contaminated in the late phase of accident. I.e. agricultural remedial actions have been intended for minimization only 10 % of the total damage from radiation exposure; - Medical countermeasures can minimize radiation exposure damage by an order of magnitude greater than agricultural countermeasures. - Thus, retrospection of nuclear accident has essentially changed type of remedial actions and has given a chance to increase effectiveness of spending by an order of magnitude. This example illustrates that in order to optimize remedial actions it is required to use data of retrospection of nuclear accidents in all cases when monitoring in the early and (or) intermediate phases is unsatisfactory. (author)

Georgievskiy, Vladimir [Russian Research Center 'Kurchatov Insitute', Kurchatov Sq., 1, 123182 Moscow (Russian Federation)

2007-07-01T23:59:59.000Z

375

Evaluation of LLNL's Nuclear Accident Dosimeters at the CALIBAN Reactor September 2010  

Science Conference Proceedings (OSTI)

The Lawrence Livermore National Laboratory uses neutron activation elements in a Panasonic TLD holder as a personnel nuclear accident dosimeter (PNAD). The LLNL PNAD has periodically been tested using a Cf-252 neutron source, however until 2009, it was more than 25 years since the PNAD has been tested against a source of neutrons that arise from a reactor generated neutron spectrum that simulates a criticality. In October 2009, LLNL participated in an intercomparison of nuclear accident dosimeters at the CEA Valduc Silene reactor (Hickman, et.al. 2010). In September 2010, LLNL participated in a second intercomparison of nuclear accident dosimeters at CEA Valduc. The reactor generated neutron irradiations for the 2010 exercise were performed at the Caliban reactor. The Caliban results are described in this report. The procedure for measuring the nuclear accident dosimeters in the event of an accident has a solid foundation based on many experimental results and comparisons. The entire process, from receiving the activated NADs to collecting and storing them after counting was executed successfully in a field based operation. Under normal conditions at LLNL, detectors are ready and available 24/7 to perform the necessary measurement of nuclear accident components. Likewise LLNL maintains processing laboratories that are separated from the areas where measurements occur, but contained within the same facility for easy movement from processing area to measurement area. In the event of a loss of LLNL permanent facilities, the Caliban and previous Silene exercises have demonstrated that LLNL can establish field operations that will very good nuclear accident dosimetry results. There are still several aspects of LLNL's nuclear accident dosimetry program that have not been tested or confirmed. For instance, LLNL's method for using of biological samples (blood and hair) has not been verified since the method was first developed in the 1980's. Because LLNL and the other DOE participants were limited in what they were allowed to do at the Caliban and Silene exercises and testing of various elements of the nuclear accident dosimetry programs cannot always be performed as guests at other sites, it has become evident that DOE needs its own capability to test nuclear accident dosimeters. Angular dependence determination and correction factors for NADs desperately need testing as well as more evaluation regarding the correct determination of gamma doses. It will be critical to properly design any testing facility so that the necessary experiments can be performed by DOE laboratories as well as guest laboratories. Alternate methods of dose assessment such as using various metals commonly found in pockets and clothing have yet to be evaluated. The DOE is planning to utilize the Godiva or Flattop reactor for testing nuclear accident dosimeters. LLNL has been assigned the primary operational authority for such testing. Proper testing of nuclear accident dosimeters will require highly specific characterization of the pulse fields. Just as important as the characterization of the pulsed fields will be the design of facilities used to process the NADs. Appropriate facilities will be needed to allow for early access to dosimeters to test and develop quick sorting techniques. These facilities will need appropriate laboratory preparation space and an area for measurements. Finally, such a facility will allow greater numbers of LLNL and DOE laboratory personnel to train on the processing and interpretation of nuclear accident dosimeters and results. Until this facility is fully operational for test purposes, DOE laboratories may need to continue periodic testing as guests of other reactor facilities such as Silene and Caliban.

Hickman, D P; Wysong, A R; Heinrichs, D P; Wong, C T; Merritt, M J; Topper, J D; Gressmann, F A; Madden, D J

2011-06-21T23:59:59.000Z

376

The lived experience of post-traumatic stress disorder as described by motor vehicle accident victims in Jordan.  

E-Print Network (OSTI)

??Aim: To explore the lived experience of post-traumatic stress disorder (PTSD) as described by individuals who have been involved in a motor vehicle accident (MVA) (more)

Al-Kofahy, Lilibeth

2011-01-01T23:59:59.000Z

377

Thermo-fluid-dynamics analysis of the unit 3 Fukushima Daiichi Accident with the RELAP5\\SCDAP code.  

E-Print Network (OSTI)

??The aim of this thesis is the analysis of the physical phenomena involved in the nuclear accident at Fukushima NPP. This study has been articulated (more)

VENTURI, FRANCESCO LINO

2012-01-01T23:59:59.000Z

378

Experimental and Analytical Simulation of MFCI (Molten Fuel Coolant Interaction) during CDA (Core Disruptive Accident) in Sodium Cooled Fast Reactor.  

E-Print Network (OSTI)

??With increasing demand for understanding Severe Accident Scenario in Sodium Cooled Fast Reactors, there is an urgent need of enhancing numerical and experimental simulation techniques. (more)

Natarajan, Venkataraman

2011-01-01T23:59:59.000Z

379

Risk-averse periodic preventive maintenance optimization.  

E-Print Network (OSTI)

??We consider a class of periodic preventive maintenance (PM) optimization problems, for a single piece of equipment that deteriorates with time or use, and can (more)

Singh, Inderjeet,1978-

2011-01-01T23:59:59.000Z

380

Pollution Prevention Tracking and Reporting System  

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

Welcome to the Department of Energy's Pollution Prevention Tracking and Reporting System (PPTRS). DOE uses this system to collect information about, and assess the performance of, the Department's...

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


381

Pollutant Discharge Prevention and Control Act (Florida)  

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

The Department of Environmental Protection is responsible for enacting regulations to prevent and mitigate the release of pollutants into the land and waters of the state. This legislation...

382

Sandia National Laboratories: Pollution Prevention: Regulatory...  

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

diverting a minimum of 50% of non-hazardous solid waste, and construction and demolition waste. Pollution Prevention Act Department of Energy Strategic Sustainability Performance...

383

Ultraviolet Germicidal Irradiation for Preventing Infectious...  

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

Ultraviolet Germicidal Irradiation for Preventing Infectious Disease Transmission Speaker(s): Peng Xu Date: February 19, 2002 - 12:00pm Location: Bldg. 90 The transmission of...

384

Pollution Prevention Act (Delaware) | Department of Energy  

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

Pollution Prevention Act (Delaware) Pollution Prevention Act (Delaware) Pollution Prevention Act (Delaware) < Back Eligibility Utility Fed. Government Commercial Agricultural Investor-Owned Utility State/Provincial Govt Industrial Construction Municipal/Public Utility Local Government Residential Installer/Contractor Rural Electric Cooperative Tribal Government Low-Income Residential Schools Retail Supplier Institutional Multi-Family Residential Systems Integrator Fuel Distributor Nonprofit General Public/Consumer Transportation Program Info State Delaware Program Type Environmental Regulations This act lays out objectives for pollution prevention, education and outreach. The Department shall create a multimedia waste reduction assistance program to provide technical assistance to targeted industries, focusing on small

385

Insights into the behavior of nuclear power plant containments during severe accidents  

SciTech Connect

The containment building surrounding a nuclear reactor offers the last barrier to the release of radioactive materials from a severe accident into the environment. The loading environment of the containment under severe accident conditions may include much greater than design pressures and temperatures. Investigations into the performance of containments subject to ultimate or failure pressure and temperature conditions have been performed over the last several years through a program administered by the Nuclear Regulatory Commission (NRC). These NRC sponsored investigations are subsequently discussed. Reviewed are the results of large scale experiments on reinforced concrete, prestressed concrete, and steel containment models pressurized to failure. In conjunction with these major tests, the results of separate effect testing on many of the critical containment components; that is, aged and unaged seals, a personnel air lock and electrical penetration assemblies subjected to elevated temperature and pressure have been performed. An objective of the NRC program is to gain an understanding of the behavior of typical existing and planned containment designs subject to postulated severe accident conditions. This understanding has led to the development of experimentally verified analytical tools that can be applied to accurately predict their ultimate capacities useful in developing severe accident mitigation schemes. Finally, speculation on the response of containments subjected to severe accident conditions is presented.

Horschel, D.S.; Ludwigsen, J.S.; Parks, M.B.; Lambert, L.D. [Sandia National Labs., Albuquerque, NM (United States); Dameron, R.A.; Rashid, Y.R. [ANATECH Research Corp., San Diego, CA (United States)

1993-06-01T23:59:59.000Z

386

A POTENTIAL APPLICATION OF UNCERTAINTY ANALYSIS TO DOE-STD-3009-94 ACCIDENT ANALYSIS  

Science Conference Proceedings (OSTI)

The objective of this paper is to assess proposed transuranic waste accident analysis guidance and recent software improvements in a Windows-OS version of MACCS2 that allows the inputting of parameter uncertainty. With this guidance and code capability, there is the potential to perform a quantitative uncertainty assessment of unmitigated accident releases with respect to the 25 rem Evaluation Guideline (EG) of DOE-STD-3009-94 CN3 (STD-3009). Historically, the classification of safety systems in a U.S. Department of Energy (DOE) nuclear facility's safety basis has involved how subject matter experts qualitatively view uncertainty in the STD-3009 Appendix A accident analysis methodology. Specifically, whether consequence uncertainty could be larger than previously evaluated so the site-specific accident consequences may challenge the EG. This paper assesses whether a potential uncertainty capability for MACCS2 could provide a stronger technical basis as to when the consequences from a design basis accident (DBA) truly challenges the 25 rem EG.

Palmrose, D E; Yang, J M

2007-05-10T23:59:59.000Z

387

Documentation for RISKIN: A risk integration code for MACCS (MELCOR Accident Consequence Code System) output  

Science Conference Proceedings (OSTI)

This document has been prepared as a user's guide for the computer program RISKIN developed at Sandia National Laboratories. The RISKIN code generates integrated risk tables and the weighted mean risk associated with a user-selected set of consequences from up to five output files generated by the MELCOR Accident Consequence Code System (MACCS). Each MACCS output file can summarize the health and economic consequences resulting from up to 60 distinct severe accident source terms. Since the accident frequency associated with these source terms is not included as a MACCS input parameter a postprocessor is required to derived results that must incorporate accident frequency. The RISKIN code is such a postprocessor. RISKIN will search the MACCS output files for the mean and peak consequence values and the complementary cumulative distributive function (CCDF) tables for each requested consequence. Once obtained, RISKIN combines this data with accident frequency data to produce frequency weighted results. A postprocessor provides RISKIN an interface to the proprietary DISSPLA plot package. The RISKIN code has been written using ANSI Standard FORTRAN 77 to maximize its portability.

Rollstin, J.A. (GRAM, Inc., Albuquerque, NM (USA)); Hong, Kou-John (Argonne National Lab., IL (USA))

1990-11-01T23:59:59.000Z

388

Testing and analysis of structural integrity of electrosleeved tubes under severe accident transients  

Science Conference Proceedings (OSTI)

The structural integrity of flawed steam generator tubing with Electrosleeves{trademark} under simulated severe accident transients was analyzed by analytical models that used available material properties data and results from high-temperature tests conducted on Electrosleeved tubes. The Electrosleeve material is almost pure Ni and derives its strength and other useful properties from its nanocrystalline microstructure, which is stable at reactor operating temperatures. However, it undergoes rapid grain growth, at the high temperatures expected during severe accidents, resulting in a loss of strength and a corresponding decrease in flow stress. The magnitude of this decrease depends on the time-temperature history during the accident. Failure tests were conducted at ANL and FTI on internally pressurized Electrosleeved tubes with 80% and 100% throughwall machined axial notches in tie parent tubes that were subjected to simulated severe accident temperature transients. The test results, together with the analytical model, were used to estimate the unaged flow stress curve of the Electrosleeved material at high temperatures. Failure temperatures for Electrosleeved tubes with throughwall and part-throughwall axial cracks of various lengths in the parent tubes were calculated for a postulated severe accident transient.

Majumdar, S.

1999-12-10T23:59:59.000Z

389

Small Business Pollution Prevention Assistance Account Loan Program...  

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

Small Business Pollution Prevention Assistance Account Loan Program Small Business Pollution Prevention Assistance Account Loan Program Eligibility Commercial Industrial Savings...

390

Waste Minimization and Pollution Prevention | Department of Energy  

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

Waste Minimization and Pollution Prevention Waste Minimization and Pollution Prevention Calibration Facilities Ecosystem Management Team Environmental Justice Environmental...

391

NNSA, Philippine Nuclear Research Institute to Prevent Radiological...  

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

Philippine Nuclear Research Institute to Prevent Radiological Terrorism | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation...

392

U.S. Department of Energy Accident Resistant SiC Clad Nuclear Fuel  

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

U.S. Department of Energy Accident Resistant SiC Clad Nuclear Fuel U.S. Department of Energy Accident Resistant SiC Clad Nuclear Fuel Development U.S. Department of Energy Accident Resistant SiC Clad Nuclear Fuel Development A significant effort is being placed on silicon carbide ceramic matrix composite (SiC CMC) nuclear fuel cladding by Light Water Reactor Sustainability (LWRS) Advanced Light Water Reactor Nuclear Fuels Pathway. The intent of this work is to invest in a high-risk, high-reward technology that can be introduced in a relatively short time. The LWRS goal is to demonstrate successful advanced fuels technology that suitable for commercial development to support nuclear relicensing. Ceramic matrix composites are an established non-nuclear technology that utilizes ceramic fibers embedded in a ceramic matrix. A thin interfacial layer between the

393

WIPP Workers Reach Two Million Man-Hours Without a Lost-Time Accident  

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

Workers Reach Two Million Man-Hours Workers Reach Two Million Man-Hours Without a Lost-Time Accident CARLSBAD, N.M., February 22, 2001 - Workers at the U.S. Department of Energy's (DOE) Waste Isolation Pilot Plant (WIPP) reached a safety milestone Feb. 19 by working two million man-hours without a lost-time accident. According to the National Safety Council, facilities with the same industry code as WIPP lose an average of 20.6 workdays (or 164.8 man-hours) a year to accidents. "Safety is at the core of all WIPP operations," said Dr. Inés Triay, Manager of DOE's Carlsbad Field Office. "We are particularly pleased that WIPP workers reached the two million mark during the time in which they mined a new panel and increased shift work." "To make safety a number one priority means more than creating a safe

394

Natural Circulation Level Optimization and the Effect during ULOF Accident in the SPINNOR Reactors  

Science Conference Proceedings (OSTI)

Natural circulation level optimization and the effect during loss of flow accident in the 250 MWt MOX fuelled small Pb-Bi Cooled non-refueling nuclear reactors (SPINNOR) have been performed. The simulation was performed using FI-ITB safety code which has been developed in ITB. The simulation begins with steady state calculation of neutron flux, power distribution and temperature distribution across the core, hot pool and cool pool, and also steam generator. When the accident is started due to the loss of pumping power the power distribution and the temperature distribution of core, hot pool and cool pool, and steam generator change. Then the feedback reactivity calculation is conducted, followed by kinetic calculation. The process is repeated until the optimum power distribution is achieved. The results show that the SPINNOR reactor has inherent safety capability against this accident.

Abdullah, Ade Gafar [Physics Dept. Institut Teknologi Bandung (ITB), Jl. Ganesha 10 Bandung (Indonesia); Electrical Engineering Dept. Universitas Pendidikan Indonesia (UPI), Jl. Dr. Setiabudhi 229 Bandung (Indonesia); Su'ud, Zaki; Kurniadi, Rizal; Kurniasih, Neny [Physics Dept. Institut Teknologi Bandung (ITB), Jl. Ganesha 10 Bandung (Indonesia); Yulianti, Yanti [Physics Dept. Institut Teknologi Bandung (ITB), Jl. Ganesha 10 Bandung (Indonesia); Physics Dept. Universitas Lampung (UNILA), Jl. Sumantri Brojonegoro 1 Bandar Lampung (Indonesia)

2010-12-23T23:59:59.000Z

395

Slide Rule for Rapid Response Estimation of Radiological Dose from Criticality Accidents  

SciTech Connect

This paper describes a functional slide rule that provides a readily usable ?in-hand? method for estimating nuclear criticality accident information from sliding graphs, thereby permitting (1) the rapid estimation of pertinent criticality accident information without laborious or sophisticated calculations in a nuclear criticality emergency situation, (2) the appraisal of potential fission yields and external personnel radiation exposures for facility safety analyses, and (3) a technical basis for emergency preparedness and training programs at nonreactor nuclear facilities. The slide rule permits the estimation of neutron and gamma dose rates and integrated doses based upon estimated fission yields, distance from the fission source, and time-after criticality accidents for five different critical systems. Another sliding graph permits the estimation of critical solution fission yields based upon fissile material concentration, critical vessel geometry, and solution addition rate. Another graph provides neutron and gamma dose-reduction factors for water, steel, and concrete shields.

Broadhead, B.L.; Childs, R.L.; Hopper, C.M.; Parks, C.V.

1999-09-20T23:59:59.000Z

396

Final safety analysis report for the Galileo Mission: Volume 2, Book 2: Accident model document: Appendices  

Science Conference Proceedings (OSTI)

This section of the Accident Model Document (AMD) presents the appendices which describe the various analyses that have been conducted for use in the Galileo Final Safety Analysis Report II, Volume II. Included in these appendices are the approaches, techniques, conditions and assumptions used in the development of the analytical models plus the detailed results of the analyses. Also included in these appendices are summaries of the accidents and their associated probabilities and environment models taken from the Shuttle Data Book (NSTS-08116), plus summaries of the several segments of the recent GPHS safety test program. The information presented in these appendices is used in Section 3.0 of the AMD to develop the Failure/Abort Sequence Trees (FASTs) and to determine the fuel releases (source terms) resulting from the potential Space Shuttle/IUS accidents throughout the missions.

Not Available

1988-12-15T23:59:59.000Z

397

RELAP5 Application to Accident Analysis of the NIST Research Reactor  

Science Conference Proceedings (OSTI)

Detailed safety analyses have been performed for the 20 MW D{sub 2}O moderated research reactor (NBSR) at the National Institute of Standards and Technology (NIST). The time-dependent analysis of the primary system is determined with a RELAP5 transient analysis model that includes the reactor vessel, the pump, heat exchanger, fuel element geometry, and flow channels for both the six inner and twenty-four outer fuel elements. A post-processing of the simulation results has been conducted to evaluate minimum critical heat flux ratio (CHFR) using the Sudo-Kaminaga correlation. Evaluations are performed for the following accidents: (1) the control rod withdrawal startup accident and (2) the maximum reactivity insertion accident. In both cases the RELAP5 results indicate that there is adequate margin to CHF and no damage to the fuel will occur because of sufficient coolant flow through the fuel channels and the negative scram reactivity insertion.

Baek, J.; Cuadra Gascon, A.; Cheng, L.Y.; Diamond, D.

2012-03-18T23:59:59.000Z

398

Analysis of Reactivity Induced Accident for Control Rods Ejection with Loss of Cooling  

E-Print Network (OSTI)

Understanding of the time-dependent behavior of the neutron population in nuclear reactor in response to either a planned or unplanned change in the reactor conditions, is a great importance to the safe and reliable operation of the reactor. In the present work, the point kinetics equations are solved numerically using stiffness confinement method (SCM). The solution is applied to the kinetics equations in the presence of different types of reactivities and is compared with different analytical solutions. This method is also used to analyze reactivity induced accidents in two reactors. The first reactor is fueled by uranium and the second is fueled by plutonium. This analysis presents the effect of negative temperature feedback with the addition positive reactivity of control rods to overcome the occurrence of control rod ejection accident and damaging of the reactor. Both power and temperature pulse following the reactivity- initiated accidents are calculated. The results are compared with previous works and...

Saad, Hend Mohammed El Sayed; Wahab, Moustafa Aziz Abd El

2013-01-01T23:59:59.000Z

399

Estimates of the financial consequences of nuclear-power-reactor accidents  

SciTech Connect

This report develops preliminary techniques for estimating the financial consequences of potential nuclear power reactor accidents. Offsite cost estimates are based on CRAC2 calculations. Costs are assigned to health effects as well as property damage. Onsite costs are estimated for worker health effects, replacement power, and cleanup costs. Several classes of costs are not included, such as indirect costs, socio-economic costs, and health care costs. Present value discounting is explained and then used to calculate the life cycle cost of the risks of potential reactor accidents. Results of the financial consequence estimates for 156 reactor-site combinations are summarized, and detailed estimates are provided in an appendix. The results indicate that, in general, onsite costs dominate the consequences of potential accidents.

Strip, D.R.

1982-09-01T23:59:59.000Z

400

Evaluation of severe accident risks, Peach Bottom, Unit 2: Main report  

Science Conference Proceedings (OSTI)

In support of the Nuclear Regulatory Commission's (NRC's) assessment of the risk from severe accidents at commercial nuclear power plants in the US reported NUREG-1150, the Severe Accident Risk Reduction Program (SARRP) has completed a revised calculation of the risk to the general public from severe accidents at the Peach Bottom Atomic Power Station, Unit 2. This power plant, located in southeastern Pennsylvania, is operated by the Philadelphia Electric Company. The emphasis in this risk analysis was not on determining a so-called'' point estimate of risk. Rather, it was to determine the distribution of risk, and to discover the uncertainties that account for the breadth of this distribution. Off-site risk initiated by events both internal and external to the power station were assessed. 39 refs., 174 figs., 133 tabs.

Payne, A.C.; Breeding, R.J.; Jow, H.N.; Shiver, A.W. (Sandia National Labs., Albuquerque, NM (USA)); Helton, J.C. (Arizona State Univ., Tempe, AZ (USA)); Smith, L.N. (Science Applications International Corp., Albuquerque, NM (USA))

1990-12-01T23:59:59.000Z

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


401

Analysis of Reactivity Induced Accident for Control Rods Ejection with Loss of Cooling  

E-Print Network (OSTI)

Understanding of the time-dependent behavior of the neutron population in nuclear reactor in response to either a planned or unplanned change in the reactor conditions, is a great importance to the safe and reliable operation of the reactor. In the present work, the point kinetics equations are solved numerically using stiffness confinement method (SCM). The solution is applied to the kinetics equations in the presence of different types of reactivities and is compared with different analytical solutions. This method is also used to analyze reactivity induced accidents in two reactors. The first reactor is fueled by uranium and the second is fueled by plutonium. This analysis presents the effect of negative temperature feedback with the addition positive reactivity of control rods to overcome the occurrence of control rod ejection accident and damaging of the reactor. Both power and temperature pulse following the reactivity- initiated accidents are calculated. The results are compared with previous works and satisfactory agreement is found.

Hend Mohammed El Sayed Saad; Hesham Mohammed Mohammed Mansour; Moustafa Aziz Abd El Wahab

2013-06-05T23:59:59.000Z

402

Management of Ultimate Risk of Nuclear Power Plants by Source Terms - Lessons Learned from the Chernobyl Accident  

Science Conference Proceedings (OSTI)

The term 'ultimate risk' is used here to describe the probabilities and radiological consequences that should be incorporated in siting, containment design and accident management of nuclear power plants for hypothetical accidents. It is closely related with the source terms specified in siting criteria which assures an adequate separation of radioactive inventories of the plants from the public, in the event of a hypothetical and severe accident situation. The author would like to point out that current source terms which are based on the information from the Windscale accident (1957) through TID-14844 are very outdated and do not incorporate lessons learned from either the Three Miles Island (TMI, 1979) nor Chernobyl accident (1986), two of the most severe accidents ever experienced. As a result of the observations of benign radionuclides released at TMI, the technical community in the US felt that a more realistic evaluation of severe reactor accident source terms was necessary. In this background, the 'source term research project' was organized in 1984 to respond to these challenges. Unfortunately, soon after the time of the final report from this project was released, the Chernobyl accident occurred. Due to the enormous consequences induced by then accident, the one time optimistic perspectives in establishing a more realistic source term were completely shattered. The Chernobyl accident, with its human death toll and dispersion of a large part of the fission fragments inventories into the environment, created a significant degradation in the public's acceptance of nuclear energy throughout the world. In spite of this, nuclear communities have been prudent in responding to the public's anxiety towards the ultimate safety of nuclear plants, since there still remained many unknown points revolving around the mechanism of the Chernobyl accident. In order to resolve some of these mysteries, the author has performed a scoping study of the dispersion and deposition mechanisms of fuel particles and fission fragments during the initial phase of the Chernobyl accident. Through this study, it is now possible to generally reconstruct the radiological consequences by using a dispersion calculation technique, combined with the meteorological data at the time of the accident and land contamination densities of {sup 137}Cs measured and reported around the Chernobyl area. Although it is challenging to incorporate lessons learned from the Chernobyl accident into the source term issues, the author has already developed an example of safety goals by incorporating the radiological consequences of the accident. The example provides safety goals by specifying source term releases in a graded approach in combination with probabilities, i.e. risks. The author believes that the future source term specification should be directly linked with safety goals. (author)

Genn Saji [Ex-Secretariate of Nuclear Safety Commission of Japan (Japan)

2006-07-01T23:59:59.000Z

403

Sodium fast reactor gaps analysis of computer codes and models for accident analysis and reactor safety.  

SciTech Connect

This report summarizes the results of an expert-opinion elicitation activity designed to qualitatively assess the status and capabilities of currently available computer codes and models for accident analysis and reactor safety calculations of advanced sodium fast reactors, and identify important gaps. The twelve-member panel consisted of representatives from five U.S. National Laboratories (SNL, ANL, INL, ORNL, and BNL), the University of Wisconsin, the KAERI, the JAEA, and the CEA. The major portion of this elicitation activity occurred during a two-day meeting held on Aug. 10-11, 2010 at Argonne National Laboratory. There were two primary objectives of this work: (1) Identify computer codes currently available for SFR accident analysis and reactor safety calculations; and (2) Assess the status and capability of current US computer codes to adequately model the required accident scenarios and associated phenomena, and identify important gaps. During the review, panel members identified over 60 computer codes that are currently available in the international community to perform different aspects of SFR safety analysis for various event scenarios and accident categories. A brief description of each of these codes together with references (when available) is provided. An adaptation of the Predictive Capability Maturity Model (PCMM) for computational modeling and simulation is described for use in this work. The panel's assessment of the available US codes is presented in the form of nine tables, organized into groups of three for each of three risk categories considered: anticipated operational occurrences (AOOs), design basis accidents (DBA), and beyond design basis accidents (BDBA). A set of summary conclusions are drawn from the results obtained. At the highest level, the panel judged that current US code capabilities are adequate for licensing given reasonable margins, but expressed concern that US code development activities had stagnated and that the experienced user-base and the experimental validation base was decaying away quickly.

Carbajo, Juan (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin, Madison, WI); Schmidt, Rodney Cannon; Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Ludewig, Hans (Brookhaven National Laboratory, Upton, NY); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Serre, Frederic (Centre d'%C3%94etudes nucl%C3%94eaires de Cadarache %3CU%2B2013%3E CEA, France)

2011-06-01T23:59:59.000Z

404

TMI-2 - A Case Study for PWR Instrumentation Performance during a Severe Accident  

SciTech Connect

The accident at the Three Mile Island Unit 2 (TMI-2) reactor provided a unique opportunity to evaluate sensors exposed to severe accident conditions. Conditions associated with the release of coolant and the hydrogen burn that occurred during this accident exposed instrumentation to harsh conditions, including direct radiation, radioactive contamination, and high humidity with elevated temperatures and pressures. As part of a program initiated in 2012 by the Department of Energy Office of Nuclear Energy (DOE-NE), a review was completed to gain insights from prior TMI-2 sensor survivability and data qualification efforts. This new effort focussed upon a set of sensors that provided critical data to TMI-2 operators for assessing the condition of the plant and the effects of mitigating actions taken by these operators. In addition, the effort considered sensors providing data required for subsequent accident simulations. Over 100 references related to instrumentation performance and post-accident evaluations of TMI-2 sensors and measurements were reviewed. Insights gained from this review are summarized within this report. For each sensor, a description is provided with the measured data and conclusions related to the sensors survivability, and the basis for conclusions about its survivability. As noted within this document, several techniques were invoked in the TMI-2 post-accident evaluation program to assess sensor status, including comparisons with data from other sensors, analytical calculations, laboratory testing, and comparisons with sensors subjected to similar conditions in large-scale integral tests and with sensors that were similar in design but more easily removed from the TMI-2 plant for evaluations. Conclusions from this review provide important insights related to sensor survivability and enhancement options for improving sensor performance. In addition, this document provides recommendations related to the sensor survivability and data evaluation process that could be implemented in upcoming Fukushima Daiichi recovery efforts.

Joy L. Rempe; Darrell L. Knudson

2013-03-01T23:59:59.000Z

405

Integrating Pollution Prevention with NEPA Planning Activities  

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

DATE: REPLY TO ATTN OF: SUBJECT: TO: October 15, 1992 EH-25 Integrating Pollution Prevention with NEPA Planning Activities NEPA Compliance Officers The purpose of this memorandum is to advise you of the direction that the Environmental Protection Agency (EPA) and Council on Environmental Quality (CEQ) appear to be taking regarding pollution prevention and NEPA, and to encourage you to use the NEPA process to incorporate pollution prevention principles into the DOE planning and decisionmaking process. The Pollution Prevention Act of 1990 affirms Congressional commitment to a new approach in improving environmental quality. The Act establishes as national policy the following hierarchy of actions for environmental protection: 1. prevent or reduce pollution at the source wherever

406

Importance of emergency response actions to reactor accidents within a probabilistic consequence assessment model  

Science Conference Proceedings (OSTI)

An uncertainty and sensitivity analysis of early health consequences of severe accidents at nuclear power plants as a function of the emergency response parameters has been performed using a probabilistic consequence assessment code. The importance of various emergency response parameters in predicting the consequences for a range of accident source terms was determined through training a neural network algorithm which relates the sensitivity of the output to various choices of the input. Extensions of this approach should be helpful to planners in prioritizing the emergency responses at nuclear power plants.

Mubayi, V.; Neymotin, L.

1997-03-01T23:59:59.000Z

407

Technical Advisory Team (TAT) report on the rocket sled test accident of October 9, 2008.  

DOE Green Energy (OSTI)

This report summarizes probable causes and contributing factors that led to a rocket motor initiating prematurely while employees were preparing instrumentation for an AIII rocket sled test at SNL/NM, resulting in a Type-B Accident. Originally prepared by the Technical Advisory Team that provided technical assistance to the NNSA's Accident Investigation Board, the report includes analyses of several proposed causes and concludes that the most probable source of power for premature initiation of the rocket motor was the independent battery contained in the HiCap recorder package. The report includes data, evidence, and proposed scenarios to substantiate the analyses.

Stofleth, Jerome H.; Dinallo, Michael Anthony; Medina, Anthony J.

2009-01-01T23:59:59.000Z

408

Thermal-Hydraulic Modeling of the Primary Coolant System of Light Water Reactors During Severely Degraded Core Accidents  

Science Conference Proceedings (OSTI)

The transport of fission-product vapors and aerosols that would be released from an LWR primary system in postulated severe accidents depends on the prevalent thermal-hydraulic conditions. The analytic models developed in this study are incorporated in the PSAAC modular computer program, which can help predict more realistic estimates of accident consequences.

1984-07-01T23:59:59.000Z

409

Simulation of an ammonia plant accident using rigorous heterogeneous models: Effect of shift converters disturbances on the methanator  

Science Conference Proceedings (OSTI)

Disturbance introduced into the shift converters section of the ammonia production line may lead to problems in the ammonia production line which manifest themselves in other units of the production line. A real accident that took place in an ammonia ... Keywords: Accident, Ammonia, Catalytic reactors, Heterogeneous models, Modelling, Simulation

F. M. Alhabdan; S. S. E. H. Elnashaie

1995-02-01T23:59:59.000Z

410

Ballast Accidents Analysis and Evaluation of Urban Rail Transit Based on Method of Causality Analysis and Faulty Tree Analysis  

Science Conference Proceedings (OSTI)

Ballast casualty often incurs severe sequence once takes place, such as abnormal operation,, personnel injury or even death accident , especially for lines below grade. Causality Analysis and Fault Tree analysis method is applied to research of personnel ... Keywords: ballast accident, causality analysis, faulty tree analysis, urban rail transit

Jing He; Zhi-gang Liu

2009-04-01T23:59:59.000Z

411

The U.S. Department of Energy`s (DOE) response to requests for exemption from provisions of Title 10 code of Federal Regulations Part 835  

SciTech Connect

Following the issuance of Title 10 Code of Federal Regulations Part 835 (10 CFR 835), {open_quotes}Occupational Radiation Protection,{close_quotes} in the Federal Register on 14 December 1993, all DOE facilities subject to the rule provisions were required to submit a radiation protection program that Sets forth the plans, schedules, and other measures for achieving compliance with the rule by 1 January 1996. Numerous DOE facilities identified areas of the rule where their facility needed either (1) a clarification of the intent and expectation of a provisions or (2) an exemption from the provisions. In response, the DOE Office of Worker Protection Programs and Hazards Management (EH-52) prepared and disseminated eight Radiological Control Technical Positions (RCTPs). These RCTPs provided clarifications of DOE`s intent and expectations for compliance with specific provisions of the rule. EH-52 also processed requests for exemptions from provisions of 10 CFR 835 received from twelve different DOE facilities. The DOE issued 21 separate responses to these facilities, each one addressing the specific exepemtion request. Each response contained (1) an Exemption Decision and (2) a Technical Position discussing the basis for either denying or granting with conditions, as applicable, the exemption request.

Rabovsky, J.L.; Zobel, S.G.; O`Connell, P.V. [Dept. of Energy, Germantown, MD (United States)

1996-06-01T23:59:59.000Z

412

Co-relation of Variables Involved in the Occurrence of Crane Accidents in U.S. through Logit Modeling.  

E-Print Network (OSTI)

One of the primary reasons of the escalating rates of injuries and fatalities in the construction industry is the ever so complex, dynamic and continually changing nature of construction work. Use of cranes has become imperative to overcome technical challenges, which has lead to escalation of danger on a construction site. Data from OSHA show that crane accidents have increased rapidly from 2000 to 2004. By analyzing the characteristics of all the crane accident inspections, we can better understand the significance of the many variables involved in a crane accident. For this research, data were collected from the U.S. Department of Labor website via the OSHA database. The data encompass crane accident inspections for all the states. The data were divided into categories with respect to accident types, construction operations, degree of accident, fault, contributing factors, crane types, victims occupation, organs affected and load. Descriptive analysis was performed to compliment the previous studies, the only difference being that both fatal and non-fatal accidents have been considered. Multinomial regression has been applied to derive probability models and correlation between different accident types and the factors involved for each crane accident type. A log likelihood test as well as chi-square test was performed to validate the models. The results show that electrocution, crane tip over and crushed during assembly/disassembly have more probability of occurrence than other accident types. Load is not a significant factor for the crane accidents, and manual fault is more probable a cause for crane accident than is technical fault. Construction operations identified in the research were found to be significant for all the crane accident types. Mobile crawler crane, mobile truck crane and tower crane were found to be more susceptible. These probability models are limited as far as the inculcation of unforeseen variables in construction accidents are concerned. In fact, these models utilize the past to portray the future, and therefore significant change in the variables involved is required to be added to attain correct and expedient results.

Bains, Amrit Anoop Singh

2010-08-01T23:59:59.000Z

413

Potential health risks from postulated accidents involving the Pu-238 RTG (radioisotope thermoelectric generator) on the Ulysses solar exploration mission  

DOE Green Energy (OSTI)

Potential radiation impacts from launch of the Ulysses solar exploration experiment were evaluated using eight postulated accident scenarios. Lifetime individual dose estimates rarely exceeded 1 mrem. Most of the potential health effects would come from inhalation exposures immediately after an accident, rather than from ingestion of contaminated food or water, or from inhalation of resuspended plutonium from contaminated ground. For local Florida accidents (that is, during the first minute after launch), an average source term accident was estimated to cause a total added cancer risk of up to 0.2 deaths. For accidents at later times after launch, a worldwide cancer risk of up to three cases was calculated (with a four in a million probability). Upper bound estimates were calculated to be about 10 times higher. 83 refs.

Goldman, M. (California Univ., Davis, CA (USA)); Nelson, R.C. (EG and G Idaho, Inc., Idaho Falls, ID (USA)); Bollinger, L. (Air Force Inspection and Safety Center, Kirtland AFB, NM (USA)); Hoover, M.D. (Lovelace Biomedical and Environmental Research Inst., Albuquerque, NM (USA). Inhalation Toxicology Research Inst.); Templeton, W. (Pacific Northwest Lab., Richland, WA (USA)); Anspaugh, L. (Lawren

1990-11-02T23:59:59.000Z

414

EH&S Standards Set for LBNL Rev 7/16/2009 Page 1 of 9  

E-Print Network (OSTI)

(2000) ANSI Z49.1, Safety In Welding, Cutting, and Allied Processes, Sections 4.3 and E4.3 (1999) NFPA 70, National Electrical Code (2005) NFPA 70E, Standard for Electrical Safety in the Workplace (2004. 68 - Chemical Accident Prevention Provisions g. 82 - Protection of Stratospheric Ozone 41. 40 CFR 110

415

An Analysis on the Characteristics of Boiling Liquid Expanding Vapor Explosion Accidents in Marine Transportation  

Science Conference Proceedings (OSTI)

BLEVE is a kind of disaster that may cause serious consequences in the process of maritime transportation of liquefied petroleum gas, liquefied natural gas. To analyze the accident characteristics of both the external environment and the internal causes ... Keywords: BLEVE, boiler, characteristics analysis, liquefied gas storage tank

Sining Chen; Yinquan Duo; Lijun Wei

2010-01-01T23:59:59.000Z

416

Topical Report on Reactivity Initiated Accident: Bases for RIA Fuel and Core Coolability Criteria  

Science Conference Proceedings (OSTI)

Revised acceptance criteria have been developed for the response of light water reactor (LWR) fuel under reactivity initiated accidents (RIA). Development of these revisions is part of an industry effort to extend burnup levels beyond currently licensed limits. The revised criteria are proposed for use in licensing burnup extensions or new fuel designs.

2002-05-22T23:59:59.000Z

417

A review of the technical issues of air ingression during severe reactor accidents  

Science Conference Proceedings (OSTI)

Severe reactor accident scenarios involving air ingression into the reactor coolant system are described. Evidence from modem reactor accident analyses and from the accident at Three Mile Island show residual fuel will be present in the core region when air ingression is possible. This residual fuel can interact with the air. Exploratory calculations with the MELCOR code of station blackout accidents during shutdown conditions and during operations are used to examine clad oxidation by air and ruthenium release from fuel in air. Extensive ruthenium release is predicted when air ingression rates exceed about 10 moles/s. Past studies of air interactions with irradiated reactor fuel are reviewed. Effects air ingression may have on fission product release, transport, deposition and revaporization are discussed. Perhaps the most important effects of air ingression are expected to be enhanced release of ruthenium from the fuel and the formation of copious amounts of aerosol from uranium oxide vapors. Revaporization of iodine and tellurium retained in the reactor coolant system might be expected.

Powers, D.A.; Kmetyk, L.N.; Schmidt, R.C.

1994-09-01T23:59:59.000Z

418

Computer simulation of femur fractures in the case of car accidents  

Science Conference Proceedings (OSTI)

According to a study carried out by one of the authors at the County Clinical Emergency Hospital in Arad, over 40% of the accidents resulting in femur fracture take place on roads and highways. This work briefly presents these results, and on the basis ... Keywords: biomechanics, femur, fractures, model, simulation

Cris Precup; Antoanela Naaji; Csongor Toth; Arpad Toth

2008-06-01T23:59:59.000Z

419

A data assimilation methodology for the plume phase of a nuclear accident  

Science Conference Proceedings (OSTI)

In the aftermath of the Chernobyl nuclear accident and following more than ten years of research and development, the Real time On-line DecisiOn Support system (RODOS) offers a wide range of alternatives to dealing in an effective and efficient fashion ...

R. O. Puch; P. Astrup; J. Q. Smith; H. P. Wynn; C. Turcanu; C. Rojas-Palma

2002-01-01T23:59:59.000Z

420

Incorporation of phenomenological uncertainties in probabilistic safety analysis - application to LMFBR core disruptive accident energetics  

SciTech Connect

This report describes a method for quantifying frequency and consequence uncertainty distribution associated with core disruptive accidents (CDAs). The method was developed to estimate the frequency and magnitude of energy impacting the reactor vessel head of the Clinch River Breeder Plant (CRBRP) given the occurrence of hypothetical CDAs. The methodology is illustrated using the CRBR example.

Najafi, B.; Theofanous, T.G.; Rumble, E.T.; Atefi, B.

1984-08-01T23:59:59.000Z

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


421

An expert system for strategic control of accidents and insurers' risks in building construction projects  

Science Conference Proceedings (OSTI)

Building construction projects appear to have higher accident rates. Contractors procure workers' compensation insurance (WCI) to transfer these risks to insurance companies. The commitment of insurers under WCI is extremely broad; there are no exclusions ... Keywords: Buildings, Expert system, Fuzzy logic, Occupational health and safety, Singapore, Workers' compensation insurance

Kamardeen Imriyas

2009-03-01T23:59:59.000Z

422

Potential for containment leak paths through electrical penetration assemblies under severe accident conditions. [PWR; BWR  

Science Conference Proceedings (OSTI)

The leakage behavior of containments beyond design conditions and knowledge of failure modes is required for evaluation of mitigation strategies for severe accidents, risk studies, emergency preparedness planning, and siting. These studies are directed towards assessing the risk and consequences of severe accidents. An accident sequence analysis conducted on a Boiling Water Reactor (BWR), Mark I (MK I), indicated very high temperatures in the dry-well region, which is the location of the majority of electrical penetration assemblies. Because of the high temperatures, it was postulated in the ORNL study that the sealants would fail and all the electrical penetration assemblies would leak before structural failure would occur. Since other containments had similar electrical penetration assemblies, it was concluded that all containments would experience the same type of failure. The results of this study, however, show that this conclusion does not hold for PWRs because in the worst accident sequence, the long time containment gases stabilize to 350/sup 0/F. BWRs, on the other hand, do experience high dry-well temperatures and have a higher potential for leakage.

Sebrell, W.

1983-07-01T23:59:59.000Z

423

VEACON: A Vehicular Accident Ontology designed to improve safety on the roads  

Science Conference Proceedings (OSTI)

Vehicles are nowadays provided with a variety of new sensors capable of gathering information about themselves and from their surroundings. In a near future, these vehicles will also be capable of sharing all the harvested information, with the surrounding ... Keywords: Intelligent Transportation Systems (ITS), Ontologies, VANETs, Vehicular Networks, Vehicular accidents

Javier Barrachina; Piedad Garrido; Manuel Fogue; Francisco J. Martinez; Juan-Carlos Cano; Carlos T. Calafate; Pietro Manzoni

2012-11-01T23:59:59.000Z

424

Los Alamos wins 2008 Pollution Prevention awards  

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

2008 Pollution Prevention awards 2008 Pollution Prevention awards Los Alamos wins 2008 Pollution Prevention awards Winner of two Best-in-Class Pollution Prevention awards and six Environmental Stewardship awards from the National Nuclear Security Administration. February 7, 2008 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials. Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials.

425

Pollution Prevention Applications for Solvent Use  

Science Conference Proceedings (OSTI)

Utilities are working to eliminate or minimize the production of waste in power plant and auxiliary operations. This report presents a six-step process for pollution prevention and case studies with five utilities demonstrating successful applications for solvent uses.

1995-05-09T23:59:59.000Z

426

Optimization Online - Optimizing Preventive Maintenance Models  

E-Print Network (OSTI)

Jun 29, 2004 ... Optimizing Preventive Maintenance Models ... It is assumed that there is a known model which predicts the frequency of system failure as a function of ... Category 2: Applications -- OR and Management Sciences (Scheduling ).

427

Managing preventative maintenance activities at Intel Corporation  

E-Print Network (OSTI)

The work for this thesis was completed at Intel Corporation in Colorado Springs, Colorado at Fab 23, a semiconductor fabrication facility making flash memory. The project focused on evaluating and managing preventative ...

Fearing, Rebecca Cassler

2006-01-01T23:59:59.000Z

428

The relationship between truck accidents and geometric design of road sections: Poisson versus negative binomial regressions  

SciTech Connect

This paper evaluates the performance of Poisson and negative binomial (NB) regression models in establishing the relationship between truck accidents and geometric design of road sections. Three types of models are considered. Poisson regression, zero-inflated Poisson (ZIP) regression, and NB regression. Maximum likelihood (ML) method is used to estimate the unknown parameters of these models. Two other feasible estimators for estimating the dispersion parameter in the NB regression model are also examined: a moment estimator and a regression-based estimator. These models and estimators are evaluated based on their (1) estimated regression parameters, (2) overall goodness-of-fit, (3) estimated relative frequency of truck accident involvements across road sections, (4) sensitivity to the inclusion of short mad sections, and (5) estimated total number of truck accident involvements. Data from the highway Safety Information System (HSIS) are employed to examine the performance of these models in developing such relationships. The evaluation results suggest that the NB regression model estimated using the moment and regression-based methods should be used with caution. Also, under the ML method, the estimated regression parameters from all three models are quite consistent and no particular model outperforms the other two models in terms of the estimated relative frequencies of truck accident involvements across road sections. It is recommended that the Poisson regression model be used as an initial model for developing the relationship. If the overdispersion of accident data is found to be moderate or high, both the NB and ZIP regression model could be explored. Overall, the ZIP regression model appears to be a serious candidate model when data exhibit excess zeros due, e.g., to underreporting.

Miaou, Shaw-Pin

1993-07-01T23:59:59.000Z

429

Evaluation of the 17 June 1997 Criticality Accident at Arzamas-16  

Science Conference Proceedings (OSTI)

On June 17, 1997, a critically accident occurred at Arzamas-16, which resulted in the death (within three days) of A. N. Zakharov, a Russian scientist with 20 years' experience conducting multiassembly experiments. In this case, the multiplying assembly was a fast metal system consisting of a {sup 235}U (90% enriched) core and a copper reflector. According to the Russian press, ''Zakharov misjudged the degree of criticality of the breeding system and committed several gross violations of regulations.'' As we see it, there were three major causes of this accident. First, the experiment was flawed by Zakharov's misreading of the appropriate size of the assembly, which he took from a notebook that described the old experiment he was attempting to repeat. Second, he disregarded the appropriate procedures and safety regulations. Third, these two mistakes were compounded by an improperly set audible alarm system and Zakharov's unsafe use of the table. We also discuss our reconstruction of the accident based on information given by the Russians to US scientists and information culled from Russian newspaper and magazine articles. We also describe our thoughts on the behavior of the assembly following the accident and the radiation dose level Zakharov may have received. These levels match values we have lately obtained from translations of Russian news articles. This accident clearly points out the penalty for weak administrative control of work with multiplying systems. Criticality experimentation requires formality of operation. The experimenter, his peers, and a trained safety person need to document that they understand the experiment and how it will be conducted. Knowing that the experiment was successfully run several decades ago does not justify bypassing a safety evaluation.

Morris Klein

1999-04-01T23:59:59.000Z

430

Uncertainty and sensitivity analysis of food pathway results with the MACCS Reactor Accident Consequence Model  

Science Conference Proceedings (OSTI)

Uncertainty and sensitivity analysis techniques based on Latin hypercube sampling, partial correlation analysis and stepwise regression analysis are used in an investigation with the MACCS model of the food pathways associated with a severe accident at a nuclear power station. The primary purpose of this study is to provide guidance on the variables to be considered in future review work to reduce the uncertainty in the important variables used in the calculation of reactor accident consequences. The effects of 87 imprecisely-known input variables on the following reactor accident consequences are studied: crop growing season dose, crop long-term dose, milk growing season dose, total food pathways dose, total ingestion pathways dose, total long-term pathways dose, area dependent cost, crop disposal cost, milk disposal cost, condemnation area, crop disposal area and milk disposal area. When the predicted variables are considered collectively, the following input variables were found to be the dominant contributors to uncertainty: fraction of cesium deposition on grain fields that is retained on plant surfaces and transferred directly to grain, maximum allowable ground concentrations of Cs-137 and Sr-90 for production of crops, ground concentrations of Cs-134, Cs-137 and I-131 at which the disposal of milk will be initiated due to accidents that occur during the growing season, ground concentrations of Cs-134, I-131 and Sr-90 at which the disposal of crops will be initiated due to accidents that occur during the growing season, rate of depletion of Cs-137 and Sr-90 from the root zone, transfer of Sr-90 from soil to legumes, transfer of Cs-137 from soil to pasture, transfer of cesium from animal feed to meat, and the transfer of cesium, iodine and strontium from animal feed to milk.

Helton, J.C. [Arizona State Univ., Tempe, AZ (United States); Johnson, J.D.; Rollstin, J.A. [GRAM, Inc., Albuquerque, NM (United States); Shiver, A.W.; Sprung, J.L. [Sandia National Labs., Albuquerque, NM (United States)

1995-01-01T23:59:59.000Z

431

Definition and Means of Maintaining the Criticality Prevention Design Features Portion of the PFP Safety Envelope  

SciTech Connect

The purpose of this document is to record the technical evaluation of the Operational Safety Requirements described in the Plutonium Finishing Plant Final (PFP) Operational Safety Requirements, WHC-SD-CP-OSR-010. Rev. 0-N , Section 3.1.1, ''Criticality Prevention System.'' This document, with its appendices, provides the following: (1) The results of a review of Criticality Safety Analysis Reports (CSAR), later called Criticality Safety Evaluation Reports (CSER), and Criticality Prevention Specifications (CPS) to determine which equipment or components analyzed in the CSER or CPS are considered as one of the two unlikely, independent, and concurrent changes before a criticality accident is possible. (2) Evaluations of equipment or components to determine the safety boundary for the system (Section 4). (3) A list of essential drawings that show the safety system or component (Appendix A). (4) A list of the safety envelope (SE) equipment (Appendix B). (5) Functional requirements for the individual safety envelope equipment (Sections 3 and 4). (6) A list of the operational and surveillance procedures necessary to maintain the system equipment within the safety envelope (Section 5).

RAMBLE, A.L.

2000-07-28T23:59:59.000Z

432

Model development for household waste prevention behaviour  

Science Conference Proceedings (OSTI)

Highlights: Black-Right-Pointing-Pointer We model waste prevention behaviour using structure equation modelling. Black-Right-Pointing-Pointer We merge attitude-behaviour theories with wider models from environmental psychology. Black-Right-Pointing-Pointer Personal norms and perceived behaviour control are the main behaviour predictors. Black-Right-Pointing-Pointer Environmental concern, moral obligation and inconvenience are the main influence on the behaviour. Black-Right-Pointing-Pointer Waste prevention and recycling are different dimensions of waste management behaviour. - Abstract: Understanding waste prevention behaviour (WPB) could enable local governments and decision makers to design more-effective policies for reducing the amount of waste that is generated. By merging well-known attitude-behaviour theories with elements from wider models from environmental psychology, an extensive cognitive framework that provides new and valuable insights is developed for understanding the involvement of individuals in waste prevention. The results confirm the usefulness of the theory of planned behaviour and of Schwartz's altruistic behaviour model as bases for modelling participation in waste prevention. A more elaborate integrated model of prevention was shown to be necessary for the complete analysis of attitudinal aspects associated with waste prevention. A postal survey of 158 respondents provided empirical support for eight of 12 hypotheses. The proposed structural equation indicates that personal norms and perceived behaviour control are the main predictors and that, unlike the case of recycling, subjective norms have a weak influence on WPB. It also suggests that, since social norms have not presented a direct influence, WPB is likely to be influenced by a concern for the environment and the community as well by perceptions of moral obligation and inconvenience. Results also proved that recycling and waste prevention represent different dimensions of waste management behaviour requiring particular approaches to increase individuals' engagement in future policies.

Bortoleto, Ana Paula, E-mail: a.bortoleto@sheffield.ac.uk [Department of Urban Engineering, University of Tokyo, 7-3-1, Hongo, Bunkyo-ku, Tokyo 113-8656 (Japan); Kurisu, Kiyo H.; Hanaki, Keisuke [Department of Urban Engineering, University of Tokyo, 7-3-1, Hongo, Bunkyo-ku, Tokyo 113-8656 (Japan)

2012-12-15T23:59:59.000Z

433

Pollution prevention opportunity assessment for organization 1700.  

Science Conference Proceedings (OSTI)

This Pollution Prevention Opportunity Assessment (PPOA) was conducted for Sandia National Laboratories/New Mexico Organization 1700 in June, 2006. The primary purpose of this PPOA is to provide recommendations to assist Organization 1700 in reducing the generation of waste and improving the efficiency of their processes and procedures. This report contains a summary of the information collected, analyses performed and recommended options for implementation. The Sandia National Laboratories Pollution Prevention staff will continue to work with Organization 1700 to implement the recommendations.

Gerard, Morgan Evan

2007-06-01T23:59:59.000Z

434

Microsoft Word - ProvisionsFundsColvilleConfederatedTribesPurchaseLoupLoupCreekAeneasCreekProperties_CX.doc  

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

7, 2011 7, 2011 REPLY TO ATTN OF: KEC-4 SUBJECT: Environmental Clearance Memorandum Dave Roberts Project Manager - KEWU-4 Proposed Action: Provisions of funds to the Colville Confederated Tribes for purchase of the Loup Loup Creek and Aeneas Creek properties. Fish and Wildlife Project No.: 2008-104-00 Categorical Exclusion Applied (from Subpart D, 10 C.F.R. Part 1021): B1.25 Transfer, lease, disposition or acquisition of interests in uncontaminated land for habitat preservation or wildlife management, and only associated buildings that support these purposes. Uncontaminated means that there would be no potential for release of substances at a level, or in a form, that would pose a threat to public health or the environment.

435

www.elsevier.com/locate/csi A SOAP-based system for the provision of e-services  

E-Print Network (OSTI)

This paper describes an open-architecture system for the provision of e-services to home residents, consisting of healthcare, safety and security services. The proposed system exploits the open Internet standards and is based on the hub-and-spoke connection model between home users and service providers, through an intermediate entity called service aggregator. Health status of each residential user, together with safety and security parameters are monitored and stored locally in each users home system. Periodically, the measured values are transmitted and stored at the corresponding service providers databases. Furthermore, each measured value is checked for the detection of alarms, which initiates notification transmissions to specific users and/or service providers. The access rights to monitor/control the home system(s), retrieve historical data and configure operation parameters are granted to several types of users based on their authorization level.

Vassilis Kapsalis; Konstantinos Charatsis; Manos Georgoudakis; Efstratios Nikoloutsos; George Papadopoulos

2004-01-01T23:59:59.000Z

436

Training Quality and Earnings: The Effects of Competition on the Provision of Public-Sponsored Training Programs, Mimeo  

E-Print Network (OSTI)

This paper evaluates the effectiveness of market-based approaches in the provision of publicsponsored training programs. In particular, we study the link between training quality and labor earnings using a Peruvian program that targets disadvantaged youths. Multiple proxies for training quality are identified from bidding processes in which public and private training institutions that operate for profit compete for limited public funding. Using difference-indifferences kernel matching and standard regression-based approaches, we find that beneficiaries attending high-quality training courses have higher average and marginal treatment impacts. These earnings differentials are larger for females rather than males, and are larger in the medium term rather than in the short run. External validity was assessed by using five different cohorts of individuals over an eight-year period.

Alberto Chong; Jose Galdo

2006-01-01T23:59:59.000Z

437

Accident source terms for light-water nuclear power plants using high-burnup or MOX fuel.  

Science Conference Proceedings (OSTI)

Representative accident source terms patterned after the NUREG-1465 Source Term have been developed for high burnup fuel in BWRs and PWRs and for MOX fuel in a PWR with an ice-condenser containment. These source terms have been derived using nonparametric order statistics to develop distributions for the timing of radionuclide release during four accident phases and for release fractions of nine chemical classes of radionuclides as calculated with the MELCOR 1.8.5 accident analysis computer code. The accident phases are those defined in the NUREG-1465 Source Term - gap release, in-vessel release, ex-vessel release, and late in-vessel release. Important differences among the accident source terms derived here and the NUREG-1465 Source Term are not attributable to either fuel burnup or use of MOX fuel. Rather, differences among the source terms are due predominantly to improved understanding of the physics of core meltdown accidents. Heat losses from the degrading reactor core prolong the process of in-vessel release of radionuclides. Improved understanding of the chemistries of tellurium and cesium under reactor accidents changes the predicted behavior characteristics of these radioactive elements relative to what was assumed in the derivation of the NUREG-1465 Source Term. An additional radionuclide chemical class has been defined to account for release of cesium as cesium molybdate which enhances molybdenum release relative to other metallic fission products.

Salay, Michael (U.S. Nuclear Regulatory Commission, Washington, D.C.); Gauntt, Randall O.; Lee, Richard Y. (U.S. Nuclear Regulatory Commission, Washington, D.C.); Powers, Dana Auburn; Leonard, Mark Thomas

2011-01-01T23:59:59.000Z

438

Metal-fueled HWR (heavy water reactors) severe accident issues: Differences and similarities to commercial LWRs (light water reactors)  

DOE Green Energy (OSTI)

Differences and similarities in severe accident progression and phenomena between commercial Light Water Reactors (LWR) and metal-fueled isotopic production Heavy Water Reactors (HWR) are described. It is very important to distinguish between accident progression in the two systems because each reactor type behaves in a unique manner to a fuel melting accident. Some of the lessons learned as a result of the extensive commercial severe accident research are not applicable to metal-fueled heavy water reactors. A direct application of severe accident phenomena developed from oxide-fueled LWRs to metal-fueled HWRs may lead to large errors or substantial uncertainties. In general, the application of severe accident LWR concepts to HWRs should be done with the intent to define the relevant issues, define differences, and determine areas of overlap. This paper describes the relevant differences between LWR and metal-fueled HWR severe accident phenomena. Also included in the paper is a description of the phenomena that govern the source term in HWRs, the areas where research is needed to resolve major uncertainties, and areas in which LWR technology can be directly applied with few modifications.

Ellison, P.G.; Hyder, M.L.; Monson, P.R. (Westinghouse Savannah River Co., Aiken, SC (USA)); Coryell, E.W. (EG and G Idaho, Inc., Idaho Falls, ID (USA))

1990-01-01T23:59:59.000Z

439

PREVENTIVE CONSERVATION: A CONCEPT SUITED TO THE CONSERVATION OF EARTHEN  

E-Print Network (OSTI)

PREVENTIVE CONSERVATION: A CONCEPT SUITED TO THE CONSERVATION OF EARTHEN ARCHITECTURAL HERITAGE and Construction Key words: Preventive conservation, traditional conservation practices, risk reduction, heritage management Abstract The concept of "preventive conservation" is relatively old as it has already been

Recanati, Catherine

440

Light-Weight Radioisotope Heater Unit final safety analysis report (LWRHU-FSAR): Volume 2: Accident Model Document (AMD)  

Science Conference Proceedings (OSTI)

The purpose of this volume of the LWRHU SAR, the Accident Model Document (AMD), are to: Identify all malfunctions, both singular and multiple, which can occur during the complete mission profile that could lead to release outside the clad of the radioisotopic material contained therein; Provide estimates of occurrence probabilities associated with these various accidents; Evaluate the response of the LWRHU (or its components) to the resultant accident environments; and Associate the potential event history with test data or analysis to determine the potential interaction of the released radionuclides with the biosphere.

Johnson, E.W.

1988-10-01T23:59:59.000Z

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


441

SARNET: Integrating Severe Accident Research in Europe - Safety Issues in the Source Term Area  

SciTech Connect

SARNET (Severe Accident Research Network) is a Network of Excellence of the EU 6. Framework Programme that integrates in a sustainable manner the research capabilities of about fifty European organisations to resolve important remaining uncertainties and safety issues concerning existing and future nuclear plant, especially water-cooled reactors, under hypothetical severe accident conditions. It emphasises integrating activities, spreading of excellence (including knowledge transfer) and jointly-executed research. This paper summarises the main results obtained at the middle of the current 4-year term, highlighting those concerning radioactive release to the environment. Integration is pursued through different methods: the ASTEC integral computer code for severe accident modelling, development of PSA level 2 methods, a means for definition, updating and resolution of safety issues, and development of a web database for storing experimental results. These activities are helped by an evolving Advanced Communication Tool, easing communication amongst partners. Concerning spreading of excellence, educational courses covering severe accident analysis methodology and level 2 PSA have been organised for early 2006. A text book on Severe Accident Phenomenology is being written. A mobility programme for students and young researchers has started. Results are disseminated mainly through open conference proceedings, with journal publications planned. The 1. European Review Meeting on Severe Accidents in November 2005 covered SARNET activities during its first 18 months. Jointly executed research activities concern key issues grouped in the Corium, Containment and Source Term areas. In Source Term, behaviour of the highly radio-toxic ruthenium under oxidising conditions, including air ingress, is investigated. Models are proposed for fuel and ruthenium oxidation. Experiments on transport of oxide ruthenium species are performed. Reactor scenario studies assist in defining conditions for new experiments. Regarding predictability of iodine species exiting the Reactor Coolant System (RCS), which affects the amount entering the containment, iodine behaviour in the circuit and silver-indium-cadmium (SIC) release have been reviewed. New experiments are being discussed and performed, and SIC degradation and release models are being improved. For the radioactive aerosol source term, work is conducted in the risk-relevant areas of steam generator (SG) tube rupture, transport through cracks in containment walls and revaporization from previous deposits in the RCS that could lead to a delayed source term. Models for aerosol retention in containment cracks and interpretation of data on retention in the SG secondary side are proposed. For radioactive iodine release to the environment, many physical and chemical processes affect the iodine concentration in the containment atmosphere; of these effects, mass transfer phenomena and radiolytic oxidation are being investigated first. (authors)

Haste, T. [Paul Scherrer Institute, 5232 Villigen PSI (Switzerland); Giordano, P.; Micaelli, J.-C. [Institut de Radioprotection et de S et Nucl ire, IRSN, BP 3 13115 St Paul lez Durance Cedex (France); Herranz, L. [Centro de Investigaciones Energeticas Medio Ambientales y Tecnologica, CIEMAT, Avda. Complutense 22, 28040 Madrid (Spain)

2006-07-01T23:59:59.000Z

442

NNSA, Peru Sign Agreement to Prevent Nuclear Smuggling | National...  

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

Agreement to Prevent Nuclear Smuggling Press Release NNSA, Peru Sign Agreement to Prevent Nuclear Smuggling Aug 13, 2013 Secretary of Energy Ernest Moniz and Peru's Minister of...

443

Prevention and Treatment of Fouled Medical Device Surfaces  

ORNL 2011-G00256/jcn UT-B ID 200902324 09.2011 Prevention and Treatment of Fouled Medical Device Surfaces Technology Summary To prevent infection due ...

444

Massachusetts Oil and Hazardous Material Release Prevention and...  

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

Oil and Hazardous Material Release Prevention and Response Act, State Superfund Law (Massachusetts) Massachusetts Oil and Hazardous Material Release Prevention and Response Act,...

445

Los Alamos National Laboratory employees receive Pollution Prevention...  

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

Employees receive Pollution Prevention awards Los Alamos National Laboratory employees receive Pollution Prevention awards Nearly 400 employees on 47 teams received Pollution...

446

Los Alamos National Laboratory employees receive Pollution Prevention...  

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

Employees Receive Pollution Prevention Awards Los Alamos National Laboratory employees receive Pollution Prevention Awards Nearly 400 employees on 47 teams received Pollution...

447

NNSA, China Sign Agreement to Prevent Nuclear Smuggling | National...  

National Nuclear Security Administration (NNSA)

China Sign Agreement to Prevent Nuclear Smuggling | National Nuclear Security Administration Our Mission Managing the Stockpile Preventing Proliferation Powering the Nuclear Navy...

448

Methods for Detector Placement and Analysis of Criticality Accident Alarm Systems  

Science Conference Proceedings (OSTI)

Determining the optimum placement to minimize the number of detectors for a criticality accident alarm system (CAAS) in a large manufacturing facility is a complex problem. There is typically a target for the number of detectors that can be used over a given zone of the facility. A study to optimize detector placement typically begins with some initial guess at the placement of the detectors and is followed by either predictive calculations of accidents at specific locations or adjoint calculations based on preferred detector locations. Within an area of a facility, there may be a large number of potential criticality accident sites. For any given placement of the detectors, the list of accident sites can be reduced to a smaller number of locations at which accidents may be difficult for detectors to detect. Developing the initial detector placement and determining the list of difficult accident locations are both based on the practitioner's experience. Simulations following fission particles released from an accident location are called 'forward calculations.' These calculations can be used to answer the question 'where would an alarm be triggered?' by an accident at a specified location. Conversely, 'adjoint calculations' start at a detector site using the detector response function as a source and essentially run in reverse. These calculations can be used to answer the question 'where would an accident be detected?' by a specified detector location. If the number of accidents, P, is much less than the number of detectors, Q, then forward simulations may be more convenient and less time-consuming. If Q is large or the detectors are not placed yet, then a mesh tally of dose observed by a detector at any location must be computed over the entire zone. If Q is much less than P, then adjoint calculations may be more efficient. Adjoint calculations employing a mesh tally can be even more advantageous because they do not rely on a list of specific difficult-to-detect accident sites, which may not have included every possible accident location. Analog calculations (no biasing) simply follow particles naturally. For sparse buildings and line-of-sight calculations, analog Monte Carlo (MC) may be adequate. For buildings with internal walls or large amounts of heavy equipment (dense geometry), variance reduction may be required. Calculations employing the CADIS method use a deterministic calculation to create an importance map and a matching biased source distribution that optimize the final MC to quickly calculate one specific tally. Calculations employing the FW-CADIS method use two deterministic calculations (one forward and one adjoint) to create an importance map and a matching biased source distribution that are designed to make the MC calculate a mesh tally with more uniform uncertainties in both high-dose and low-dose areas. Depending on the geometry of the problem, the number of detectors, and the number of accident sites, different approaches to CAAS placement studies can be taken. These are summarized in Table I. SCALE 6.1 contains the MAVRIC sequence, which can be used to perform any of the forward-based approaches outlined in Table I. For analog calculations, MAVRIC simply calls the Monaco MC code. For CADIS and FW-CADIS, MAVRIC uses the Denovo discrete ordinates (SN) deterministic code to generate the importance map and biased source used by Monaco. An adjoint capability is currently being added to Monaco and should be available in the next release of SCALE. An adjoint-based approach could be performed with Denovo alone - although fine meshes, large amounts of memory, and long computation times may be required to obtain accurate solutions. Coarse-mesh SN simulations could be employed for adjoint-based scoping studies until the adjoint capability in Monaco is complete. CAAS placement studies, especially those dealing with mesh tallies, require some extra utilities to aid in the analysis. Detectors must receive a minimum dose rate in order to alarm; therefore, a simple yes/no plot could be more useful to the analyst t

Peplow, Douglas E. [ORNL; Wetzel, Larry [Babcock & Wilcox Nuclear Operations Group Inc.

2012-01-01T23:59:59.000Z

449

TERMS AND CONDITIONS OF SALE CONTROLLING PROVISIONS: No terms and conditions other than the terms and conditions contained herein shall be  

E-Print Network (OSTI)

TERMS AND CONDITIONS OF SALE CONTROLLING PROVISIONS: No terms and conditions other than the terms's authorized agent. All terms and conditions contained in any prior oral or written communication, including, without limitation, Buyer's purchase order, which are different from or in addition to the terms

Herrick, Robert R.

450

Export control helps prevent WMD proliferation  

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

Export control helps prevent WMD proliferation Export control helps prevent WMD proliferation Director's Welcome Organization Achievements Highlights Fact Sheets, Brochures & Other Documents Multimedia Library About Nuclear Energy Nuclear Reactors Designed by Argonne Argonne's Nuclear Science and Technology Legacy Opportunities within NE Division Visit Argonne Work with Argonne Contact us For Employees Site Map Help Join us on Facebook Follow us on Twitter NE on Flickr Celebrating the 70th Anniversary of Chicago Pile 1 (CP-1) Argonne OutLoud on Nuclear Energy Argonne Energy Showcase 2012 Highlights Bookmark and Share Export control helps prevent WMD proliferation A container ship in port. EXPORT CHALLENGE - Container ships are a challenge to export control enforcement. The largest ships can carry 8,000 containers, each 40 feet

451

Waste minimization and pollution prevention awareness plan  

Science Conference Proceedings (OSTI)

The purpose of this plan is to document the Lawrence Livermore National Laboratory (LLNL) Waste Minimization and Pollution Prevention Awareness Program. The plan specifies those activities and methods that are or will be employed to reduce the quantity and toxicity of wastes generated at the site. The intent of this plan is to respond to and comply with (DOE's) policy and guidelines concerning the need for pollution prevention. The Plan is composed of a LLNL Waste Minimization and Pollution Prevention Awareness Program Plan and, as attachments, Program- and Department-specific waste minimization plans. This format reflects the fact that waste minimization is considered a line management responsibility and is to be addressed by each of the Programs and Departments. 14 refs.

Not Available

1991-05-31T23:59:59.000Z

452

Lab wins six NNSA Pollution Prevention awards  

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

Lab wins six NNSA Pollution Prevention awards Lab wins six NNSA Pollution Prevention awards Lab wins six NNSA Pollution Prevention awards The Laboratory has captured awards for projects ranging from energy savings to creating fuels from algae. March 7, 2011 Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials. Los Alamos National Laboratory sits on top of a once-remote mesa in northern New Mexico with the Jemez mountains as a backdrop to research and innovation covering multi-disciplines from bioscience, sustainable energy sources, to plasma physics and new materials. Contact Fred deSousa Communications Office

453

Ultraviolet Germicidal Irradiation for Preventing Infectious Disease  

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

Ultraviolet Germicidal Irradiation for Preventing Infectious Disease Ultraviolet Germicidal Irradiation for Preventing Infectious Disease Transmission Speaker(s): Peng Xu Date: February 19, 2002 - 12:00pm Location: Bldg. 90 The transmission of tuberculosis (TB) and other infectious diseases in health-care buildings has been a recognized hazard for decades. Ultraviolet germicidal irradiation (UVGI) of upper room air is used as an engineering control method to prevent the spread of airborne infectious disease. Under full-scale conditions, the efficacy of UVGI for inactivating airborne bacterial spores and active cells was evaluated. A test room fitted with a modern UVGI system was used to conduct bio-aerosol inactivation experiments. UVGI efficacy can be affected by environmental factors such as relative humidity (RH), and air mixing

454

Waste Minimization and Pollution Prevention Awareness Plan  

SciTech Connect

The purpose of this plan is to document Lawrence Livermore National Laboratory (LLNL) projections for present and future waste minimization and pollution prevention. The plan specifies those activities and methods that are or will be used to reduce the quantity and toxicity of wastes generated at the site. It is intended to satisfy Department of Energy (DOE) requirements. This Plan provides an overview of projected activities from FY 1994 through FY 1999. The plans are broken into site-wide and problem-specific activities. All directorates at LLNL have had an opportunity to contribute input, to estimate budget, and to review the plan. In addition to the above, this plan records LLNL`s goals for pollution prevention, regulatory drivers for those activities, assumptions on which the cost estimates are based, analyses of the strengths of the projects, and the barriers to increasing pollution prevention activities.

Not Available

1994-04-01T23:59:59.000Z

455

Appendix C Draft Stormwater Pollution Prevention Plan  

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

C C Draft Stormwater Pollution Prevention Plan U.S. Department of the Interior Minerals Management Service MMS Cape Wind Energy Project January 2009 Final EIS Appendix C Draft Stormwater Pollution Prevention Plan Cover with Template.doc DRAFT Stormwater Pollution Prevention Plan CAPE WIND ENERGY PROJECT BARNSTABLE AND YARMOUTH, MASSACHUSETTS PREPARED FOR Cape Wind Associates, LLC 75 Arlington Street, Suite 704 Boston, MA 02116 PREPARED BY ESS Group, Inc. 888 Worcester Street, Suite 240 Wellesley, Massachusetts 02482 Project No. E159-000 November 29, 2006 ESS Group, Inc. © 2006 - This document or any part may not be reproduced or transmitted in any form or by any means, electronic, or mechanical, including photocopying, microfilming, and recording without the express written consent of ESS Group,

456

DOE-ID FOIA Type A Accident Investigation Board Report - July 28, 1998  

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

Electronic Reading Room Documents Electronic Reading Room Documents Freedom of Information Act (FOIA) More on FOIA/Privacy Act Electronic Request Form Frequently Ask Questions Frequently Requested Documents Guides Helpful Links Points of Contact and Privacy Act Advisory Privacy Act Reading Room DOE-ID Public Reading Room Research Library You are here: DOE-ID Home > FOIA > Type A Accident Investigation Board Report - July 28, 1998 Type A Accident Investigation Board Report - July 28, 1998 Fatality and Multiple Injuries Resulting From Release of Carbon Dioxide at Building 648, Test Reactor Area Idaho National Engineering and Environmental Laboratory Files are provided in Adobe Acrobat format. If you experience problems reading these files please download the latest Adobe Acrobat reader at http://get.adobe.com/reader/ Download Acrobat Reader . Adobe Acrobat file Reader will allow you to view, navigate, and print these PDF files on all major computing platforms.

457

Y-12 Construction hits one million-hour mark without a lost-time accident |  

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

Construction hits one ... Construction hits one ... Y-12 Construction hits one million-hour mark without a lost-time accident Posted: August 30, 2012 - 5:30pm The B&W Y-12 Direct-Hire Construction team has worked one million hours, covering a 633-day period, without a lost-time injury. Some 285 people including building trade crafts, non-manual staff and escorts worked without a lost-time accident during this period. The Construction team's last lost workday was in September 2010. A celebration was held today to mark the safety milestone. Senior leaders from National Nuclear Security Administration Production Office (NPO) and B&W Y-12 were on hand to congratulate the workers. Jim Haynes, B&W Y-12 senior vice president and deputy general manager for projects, said, "Congratulations are due the men and women of

458

Final report of the accident phenomenology and consequence (APAC) methodology evaluation. Spills Working Group  

Science Conference Proceedings (OSTI)

The Spills Working Group was one of six working groups established under the Accident Phenomenology and Consequence (APAC) methodology evaluation program. The objectives of APAC were to assess methodologies available in the accident phenomenology and consequence analysis area and to evaluate their adequacy for use in preparing DOE facility safety basis documentation, such as Basis for Interim Operation (BIO), Justification for Continued Operation (JCO), Hazard Analysis Documents, and Safety Analysis Reports (SARs). Additional objectives of APAC were to identify development needs and to define standard practices to be followed in the analyses supporting facility safety basis documentation. The Spills Working Group focused on methodologies for estimating four types of spill source terms: liquid chemical spills and evaporation, pressurized liquid/gas releases, solid spills and resuspension/sublimation, and resuspension of particulate matter from liquid spills.

Brereton, S.; Shinn, J. [Lawrence Livermore National Lab., CA (United States); Hesse, D [Battelle Columbus Labs., OH (United States); Kaninich, D. [Westinghouse Savannah River Co., Aiken, SC (United States); Lazaro, M. [Argonne National Lab., IL (United States); Mubayi, V. [Brookhaven National Lab., Upton, NY (United States)

1997-08-01T23:59:59.000Z

459

Development of an Ontology to Assist the Modeling of Accident Scenarii "Application on Railroad Transport "  

E-Print Network (OSTI)

In a world where communication and information sharing are at the heart of our business, the terminology needs are most pressing. It has become imperative to identify the terms used and defined in a consensual and coherent way while preserving linguistic diversity. To streamline and strengthen the process of acquisition, representation and exploitation of scenarii of train accidents, it is necessary to harmonize and standardize the terminology used by players in the security field. The research aims to significantly improve analytical activities and operations of the various safety studies, by tracking the error in system, hardware, software and human. This paper presents the contribution of ontology to modeling scenarii for rail accidents through a knowledge model based on a generic ontology and domain ontology. After a detailed presentation of the state of the art material, this article presents the first results of the developed model.

Maalel, Ahmed; Mejri, Lassad; Ghezela, Henda Hajjami Ben

2012-01-01T23:59:59.000Z

460