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1
Phenomenology of LNG Accidents - A Selected Bibliography.
1974-09-01

... Accession Number : ADA031665. Title : Phenomenology of LNG Accidents - A Selected Bibliography. Descriptive Note : Rept. for 1965-Sep 74,. ...

DTIC Science & Technology

2
Economic Cost to Society of Motor Vehicle Accidents: 1986 Addendum.
1987-01-01

The National Highway Traffic Safety Administration (NHTSA) estimates that the total economic cost to society of motor vehicle accidents was $74.2 billion in 1986. Included in the loss are medical costs, productivity losses, property damage, legal and cour...

National Technical Information Service (NTIS)

3
Crediting Tritium Deposition in Accident Analysis
2001-06-20

This paper describes the major aspects of tritium dispersion phenomenology, summarizes deposition attributes of the computer models used in the DOE Complex for tritium dispersion, and recommends an approach to account for deposition in accident analysis.

DOE Information Bridge

4
LMFBR Accident Delineation Study. Phase I Final Report.
1981-01-01

The report covers an accident delineation study undertaken to organize and evaluate the available information concerning LMFBR accident sequences and to identify key phenomenological and system-response uncertainties. The study can help provide a basis fo...

National Technical Information Service (NTIS)

5
Reactor Safety Research Semiannual Report, July-December 1987.
1988-01-01

Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of the accident conditions and the d...

National Technical Information Service (NTIS)

6
Reactor Safety Research Semiannual Report, January-June 1986. Volume 35.
1987-01-01

Sandia National Laboratories is conducting, under USNRC sponsorship, phenomenological research related to the safety of commercial nuclear power reactors. The research includes experiments to simulate the phenomenology of the accident conditions and the d...

National Technical Information Service (NTIS)

7
Phenomenology of LNG Accidents - A Selected Bibliography.
1974-01-01

This bibliography is the result of a request by four researchers of The Rand Corporation. It covers the chemical, physical, and environmental aspects of liquified natural gas and its transportation.

National Technical Information Service (NTIS)

8
################ arXiv:hep�ph/0204295

on their observations in ancient Babylonia, Egypt and China. It was no accident that the famous phenomenological theory winter day of 1948, but I came very poorly dressed. In turn, I was surprised by the absence of furniture

E-print Network

9
MARCH-HECTR Analysis of an Ice-Condenser Containment (PWR; BWR).
1983-01-01

Sandia National Laboratories is participating in several NRC-sponsored programs to study severe accident phenomenology. Part of that effort involves the combined use of the computer codes MARCH and HECTR to examine hydrogen behavior during severe accident...

National Technical Information Service (NTIS)

10
Advanced reactor safety research. Quarterly report, October-December 1981. Volume 20
1983-08-01

Information is presented concerning the inherent retention of core debris following a severe reactor accident; containment analysis for LWR and LMFBR type reactors; LMFBR accident delineation; advanced reactor core phenomenology; LWR damaged fuel phenomenology; and ACRR status.

Energy Citations Database

11
Summary of a workshop on severe accident management for PWRs
1991-11-01

Severe accident management can be defined as the use of existing and/or alternative resources, systems and actions to prevent or mitigate a core-melt accident. For each accident sequence and each combination of strategy, there may be several options available to the operator; and each involves phenomenological and ...

Energy Citations Database

12
Summary of a workshop on severe accident management for BWRs
1991-11-01

Severe accident management can be defined as the use of existing and/or alternative resources, systems and actions to prevent or mitigate a core-melt accident. For each accident sequence and each combination of strategies there may be several options available to the operator; and each involves phenomenological and ...

Energy Citations Database

13
LMFBR accident delineation study: approach and preliminary results
1979-01-01

Event trees have been constructed for all phases of LMFBR accidents. The trees proved useful for identifying meaningful initiating accident categories and containment responses. In these areas, quantification appears feasible, given an adequate data base. Event trees were also used to represent in-core phenomenological questions ...

Energy Citations Database

14
Computational methods for LMFBR whole-core accident analysis
1979-01-01

This chapter discusses the development of current state-of-the-art computational methods used in the United States for analysis of core meltdown accidents (Hypothetical Core Disruptive Accidents) in LMFBRs. The emphasis is on the phenomenological basis and numerical methods of the codes SAS, VENUS-II, SIMMER, and REXCO.

DOE Information Bridge

15
Assessment of uncertainties in core melt phenomenology and their impact on risk at the Z/IP facilities
1983-01-01

An evaluation of core meltdown accidents in the Z/IP facilities has been performed. Containment event trees have been developed to relate the progression of a given accident to various potential containment building failure modes. An extensive uncertainty analysis related to core melt phenomenology has been performed. A major ...

Energy Citations Database

16
Reactor Safety Research Semiannual Report, July-December 1986. Volume 36.
1987-01-01

The research includes experiments to simulate the phenomenology of the accident conditions and the development of analytical models, verified by experiment, which can be use to predict reactor and safety systems performance and behavior under abnormal con...

National Technical Information Service (NTIS)

17
LWR Core Meltdown Accident Sequence Phenomenology.
1982-01-01

The Reactor Safety Study Methodology Applications Program (RSSMAP) conducted risk analyses of four light water reactors. The plants studied were each designed by a different US reactor vendor and are enclosed within three different containment types. Thes...

National Technical Information Service (NTIS)

18
Assessment of Ice-Condenser Containment Performance Issues.
1990-01-01

Vulnerabilities of an ice-condenser containment to challenges that could arise from severe accidents have been assessed. The phenomenological issues associated with containment challenges have been evaluated. A number of containment improvements which hav...

National Technical Information Service (NTIS)

19
The EDAC system and new developments under consideration at the Commissariat a l'Energie Atomique for criticality accident detection
1987-09-01

As a result of the Commissariat a l'Energie Atomique CRAC experimental program, which studied the phenomenology and the radiological consequences of a criticality excursion in fissile solution, the EDAC system has been developed. This system detects a criticality accident and warns personnel as early as possible by triggering the necessary ...

Energy Citations Database

20
Follow - on activities to the Swedish severe accident mitigation program
1992-01-01

Due to the government requirements severe accident mitigating measures were implemented at Barseback nuclear power plant in 1985 and at the other Swedish nuclear power plants in 1988. For the latter plants these measures included protection against early containment impairment, highly redundant containment spray and filtered venting of the containment. ...

Energy Citations Database

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21
Self-mixing phenomenology in hypothetical core-disruptive accidents
1980-12-01

Physical processes are investigated that lead to the thermal equilibration of a disrupted liquid metal fast breeder reactor (LMFBR) core following a hypothetical core-disruptive accident (HCDA). Their impact is assessed, particularly as relating to the SIMMER code. The turbulent structure in the core region is characterized and bounding estimates are derived of thermal ...

DOE Information Bridge

22
Preliminary Assessment of ICRP Dose Conversion Factor Recommendations for Accident Analysis Applications
2002-03-13

Accident analysis for U.S. Department of Energy (DOE) nuclear facilities is an integral part of the overall safety basis developed by the contractor to demonstrate facility operation can be conducted safely. An appropriate documented safety analysis for a facility discusses accident phenomenology, quantifies source terms arising from ...

DOE Information Bridge

23
In-vessel flow characterization under severe accident conditions
1987-01-01

The purpose of this study is to provide a parametric framework for characterization of flow and heat transfer regimes and their associated phenomenological uncertainties following severe accidents using a two dimensional, heterogenous, porous media formulation. This approach extends the understanding of buoyancy-induced flow characteristics in the ...

DOE Information Bridge

24
Source terms for analysis of accidents at a high level waste repository
1989-01-01

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 ...

DOE Information Bridge

25
Severe accident mitigation through containment design
1990-01-01

Recent US Department of Energy plans to construct a Heavy Water Reactor for the production of defense nuclear materials have created a unique opportunity to explore ways to mitigate severe accident concerns in the design stage. Drawing on an extensive background in USNRC-sponsored severe accident work, Sandia National Laboratories has been exploring a ...

Energy Citations Database

26
Assessment of the thermal-hydraulic technology of the transition phase of a core-disruptive accident in a LMFBR
1982-11-01

The technology of thermal hydraulic aspects of the transition phase accident sequence in liquid metal fast breeder reactors has been reviewed. Previous analyses of the transition phase accident sequence have been reviewed and the current understanding of major thermal hydraulic phenomenology has been assessed. As a result of the ...

Energy Citations Database

27
Role of fuel bubble phenomenology in assessment of LMFBR source term
1985-01-01

Phenomenological aspects of a fuel vapor bubble formed in the sodium pool in a hypothetical severe accident are considered. The potential for fuel bubble collapse in the sodium pool is analyzed. It appears that for a wide range of hypothetical LMFBR accidents involving core vaporization, the fuel vapor bubble would likely be quenched ...

DOE Information Bridge

28
Posttraumatic Growth of Injured Patients after Motor Vehicle Accidents: An Interpretative Phenomenological Analysis.
2011-06-22

This study aimed to explore the process of posttraumatic growth of injured patients after a motor vehicle accident in China. Semi-structured interviews were conducted with six patients. Transcripts were analyzed using interpretative phenomenological analysis. Four main super-ordinate themes emerged: construction of meaning; perception of self; perception ...

PubMed

29
Source-Term and building-Wake Consequence Modeling for the Godiva IV Reactor at Los Alamos National Laboratory
1999-06-13

The objectives of this work were to evaluate the consequences of a postulated accident to onsite security personnel stationed near the facility during operations of the Godiva IV critical assembly and to identify controls needed to protect these personnel in case of an extreme criticality excursion equivalent to the design-basis accident (DBA). This paper ...

Energy Citations Database

30
MARCH-HECTR analysis of an ice-condenser containment. [PWR; BWR
1983-01-01

Sandia National Laboratories is participating in several NRC-sponsored programs to study severe accident phenomenology. Part of that effort involves the combined use of the computer codes MARCH and HECTR to examine hydrogen behavior during severe accidents. These codes have been applied to an ice-condenser containment. Results indicate ...

Energy Citations Database

31
Assessment of ice-condenser containment performance issues
1990-07-01

Vulnerabilities of an ice-condenser containment to challenges that could arise from severe accidents have been assessed. The phenomenological issues associated with containment challenges have been evaluated. A number of containment improvements which have the potential to mitigate severe accident challenges have been evaluated. This ...

Energy Citations Database

32
Cours ENAC 2007 - Interface ville-campagne - Prof. A. Buttler 11 Cours ENAC 1, 2007

administrative Parc naturel r�gional Parc p�riurbain � sauvage � Parc urbain � ordr� � #12;21 Cours ENAC 2007

E-print Network

33
Correspondence model of occupational accidents.
2011-08-05

We present a new generalized model for the diagnosis and prediction of accidents among the Spanish workforce. Based on observational data of the accident rate in all Spanish companies over eleven years (7,519,732 accidents), we classified them in a new risk-injury contingency table (19�19). Through correspondence analysis, we ...

PubMed

34
PHENOMENOLOGY AND INTERPRETATION OF THE ...
1988-11-01

... Title : PHENOMENOLOGY AND INTERPRETATION OF THE BARKHAUSEN EFFECT IN FERROMAGNETIC MATERIALS (INVITED). ...

DTIC Science & Technology

35
Quantification and uncertainty analysis of source terms for severe accidents in light water reactors (QUASAR). Part 1: methodology and program plan. Volume 1
1986-06-01

The methodological framework and program plan for systematic quantification and propagation of uncertainties in radiological source terms for light water reactors are presented. The QUASAR methodology is based on detailed sensitivity analysis of the Source Term Code Package (STCP), followed by a systematic uncertainty analysis on the most sensitive parameters/variables, and ...

Energy Citations Database

36
Probabilistic risk assessment for a loss of coolant accident in McMaster Nuclear Reactor and application of reliability physics model for modeling human reliability
2007-01-01

A probabilistic risk assessment (PRA) was conducted for a loss of coolant accident, (LOCA) in the McMaster Nuclear Reactor (MNR). A level 1 PRA was completed including event sequence modeling, system modeling, and quantification. To support the quantification of the accident sequence identified, data analysis using the Bayesian method and human reliability ...

NASA Astrophysics Data System (ADS)

37
Preparation of methods to calculate pin-wise intra-subassembly power density distribution of a new in-pile experimental reactor for FBR safety research.
1998-01-01

A design study of a new in-pile experimental reactor, SERAPH (Safety Engineering Reactor for Accident Phenomenology), for FBR safety research has progressed at JNC (Japan Nuclear Cycle Development Institute). SERAPH is intended for various in-pile experim...

National Technical Information Service (NTIS)

38
Overview of BWR (Boiling Water Reactor) Mark-I Containment Venting Risk Implications.
1988-01-01

Venting of boiling water reactors with Mark-I containments has been suggested as a way to prevent catastrophic failure and/or mitigate the consequences resulting from a severe accident. Based on phenomenological, human factors, and risk considerations, th...

National Technical Information Service (NTIS)

39
Internal Fuel Motion Phenomenology: FUMO-E Code Analysis of PINEX Experiments.
1982-01-01

Internal fuel motion in annular fuel during hypothetical LMFBR accidents has been postulated as an inherent safety shutdown mechanism. In this study, the recently-developed FUMO-E code was used to analyze the PINEX-2 and PINEX-3 transient overpower (TOP) ...

National Technical Information Service (NTIS)

40
Fast reactor safety and related physics. Volume IV. Phenomenology
1976-01-01

Separate abstracts are included for 58 papers concerning single-phase flow and sodium boiling; sodium boiling and subassembly flow blockages; transient-overpower and loss-of-flow experiments; fuel and cladding behavior and relocation; fuel and cladding freezing; molten-fuel-coolant interaction; aerosols and fission product release, and post-accident heat removal. Thirteen ...

DOE Information Bridge

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41
CORCON: a computer program for modelling molten fuel/concrete interactions. [PWR; BWR
1980-01-01

A computer program modelling the interaction between molten core materials and structural concrete is being developed to provide a capability for making quantitative estimates of reactor fuel-melt accidents. The principal phenomenological models, inter-component heat transfer, concrete erosion, and melt/gas chemical reactions, are described. A code test ...

DOE Information Bridge

42
Reliability and Maintainability vs. Fleet Readiness
1974-11-01

... tTS OF RELIABILITY A!D ?MAINTATINABILITY; Course Book, US Army -.sanaaement Ensrineerinp, Training_ Agency Cour-e Book; Rock Island ...

DTIC Science & Technology

43
Investigation of the Phenomenology of the Arctic Ionosphere ...
1975-06-01

... Title : Investigation of the Phenomenology of the Arctic Ionosphere and Its Relation to the Phenomenology of Arctic Particle Precipitation. ...

DTIC Science & Technology

44
Phenomenological studies of HCDA issues
1982-01-01

A framework for examining whole-core accident phenomena during the time interval beginning with loss-of-intact geometry up to the time of post-accident heat removal is presented in terms of four distinct stages of disruption: (1) disruption initiation, (2) meltout stage, (3) integral pool stage, and (4) termination stage. Each of the ...

Energy Citations Database

45
Uncertainties and severe-accident management
1991-01-01

Severe-accident management can be defined as the use of existing and or alternative resources, systems, and actions to prevent or mitigate a core-melt accident. Together with risk management (e.g., changes in plant operation and/or addition of equipment) and emergency planning (off-site actions), accident management provides an ...

Energy Citations Database

46
Quasar uncertainty study
1986-10-01

Over the last decade, substantial development and progress has been made in the understanding of the nature of severe accidents and associated fission product release and transport. As part of this continuing effort, the United States Nuclear Regulatory Commission (USNRC) sponsored the development of the Source Term Code Package (STCP), which models core degradation, fission ...

Energy Citations Database

47
Thermal-hydraulic criteria for the APT tungsten neutron source design
1998-03-01

This report presents the thermal-hydraulic design criteria (THDC) developed for the tungsten neutron source (TNS). The THDC are developed for the normal operations, operational transients, and design-basis accidents. The requirements of the safety analyses are incorporated into the design criteria, consistent with the integrated safety management and the safety-by-design ...

DOE Information Bridge

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