The main phenomena leading to hydrogen generation in the containment of a PWR in accident conditions are described in this report. They are the following: water radiolysis, zirconium cladding oxidation and oxidation of the aluminium of internal structures...

This report is a first documentation of the KfK/PNS activities and plans to investigate the behaviour of steel containments under accident conditions. The investigations will deal with a free standing spherical containment shell built for the latest type ...

The knowledge of the leakage behavior of containments beyond design conditions is required for evaluation of severe accident mitigation strategies, risk studies, emergency preparedness, planning and siting. Strategies for managing these severe accidents will be severely hampered unless a methodology for predicting ...

The publication contains briefs of selected railroad accidents occurring in U.S. Railroad operations. The brief format presents basic facts, conditions, circumstances, and probable cause(s) in each instance.

In support of the US Nuclear Regulatory Commission Accident Management Research Program, the availability of instruments to supply accident management information during a broad range of severe accidents is evaluated for a Boiling Water Reactor with a Mark I containment. Results from this evaluation include: (1) ...

Bellows are an integral part of the containment pressure boundary in nuclear power plants. They are used at piping penetrations to allow relative movement between piping and the containment wall. In a severe accident they may be subjected to high pressure...

The knowledge of the leakage behavior of containments beyond design conditions is required for the evaluation of severe accident mitigation strategies, risk studies, emergency preparedness planning, and siting. Since each containment building has a large number of penetrations, these represent a large number of ...

The report describes a study performed by the Lawrence Livermore National Laboratory to evaluate the level of safety provided under severe accident conditions during the shipment of spent fuel from nuclear power reactors. The evaluation is performed using...

Shows a variety of tests which simulate accident conditions for containers used to ship radioactive materials. Discusses computer modeling. Compares one-eight-scale testing to scenes of full-scale impact tests of containers being carried by trucks. Shows ...

Volume 2 contains the following appendices: Severe accident data; truck accident data; railroad accident data; highway survey data and bridge column properties; structural analysis; thermal analysis; probability estimation techniques; and benchmarking for computer codes used in impact analysis. (LN)

This report describes a study performed by the Lawrence Livermore National Laboratory to evaluate the level of safety provided under severe accident conditions during the shipment of spent fuel from nuclear power reactors. The evaluation is performed using data from real accident histories and using representative truck and rail cask ...

Three types of containment configurations for large breeder reactors (1000 MWe/2500 MWt) were compared to determine characteristic responses of each type to selected hypothetical accident conditions. The three types of system configurations were the single, double and containment-confinement designs. Two types of ...

The publication contains reports of U.S. general aviation air taxi accidents occurring in 1973. Included are 163 accident Briefs, 42 of which involve fatal accidents. The brief format presents the facts, conditions, circumstances and probable cause(s) for...

The publication contains reports of U.S. general aviation aerial application accidents occurring in 1974. Included are 467 accident Briefs, 31 of which involve fatal accidents. The brief format presents the facts, conditions, circumstances, and probable c...

The publication contains reports of U.S. general aviation air taxi accidents occurring in 1974. Included are 191 accident Briefs, 40 of which involve fatal accidents. The brief format presents the facts, conditions, circumstances and probable cause(s) for...

This publication contains briefs of selected railroad accidents occurring in U.S. Railroad operations during calendar year 1980. The brief format presents basic facts, conditions, circumstances, and probable cause in each instance. Additional statistical ...

The publication contains briefs of selected railroad accidents occurring in U.S. Railroad operations during calendar year 1982. The brief format presents basic facts, conditions, circumstances, and probable cause(s) in each instance. Additional statistica...

The publication contains briefs of selected railroad accidents occurring in U.S. Railroad operations during calendar year 1982. The brief format presents basic facts, conditions, circumstances, and probable cause(s) in each instance. Additional statistica...

This publication contains briefs of selected railroad accidents occurring in U.S. Railroad operations during calendar year 1982. The brief format presents basic facts, conditions, circumstances, and probable cause(s) in each instance. Additional statistic...

This publication contains briefs of selected railroad accidents occurring in U.S. Railroad operations during calendar year 1981. The brief format presents basic facts, conditions, circumstances, and probable cause(s) in each instance. Additional statistic...

The regulatory requirement to measure the gamma radiation levels during accident conditions inside a reactor containment building is discussed. The development of a mineral-insulated cable and connector system to accurately transmit this measurement is described and a model of the response is developed.

Full scale testing to date has verified that current analytical tools and the use of scale model testing are both accurate methods for predicting shipping cask response to severe accident conditions. The containers tested are capable of surviving severe transportation accidents.

The formation of combustible atmospheres during unrestricted core heatup accidents in High Temperature Gas-Cooled Reactors is being investigated, considering the effects of only partially mixed atmospheres. It is found that the previously used assumption ...

A detailed review of the available light water reactor source term information is presented as a technical basis for development of updated source terms into the containment under severe accident conditions. Simplified estimates of radionuclide release and transport characteristics are specified for each unique combination of the ...

This report describes the heat transfer analysis of the 10-gallon and 55-gallon 6M containers. The analysis was performed with boundary conditions corresponding to a normal transport condition and a hypothetical accident condition. Computational results indicated that the insulation material in ...

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 ...

Containment piping penetration bellows are an integral part of the pressure boundary in steel containments in the United States (US). Their purpose is to minimize loading on the containment shell caused by differential movement between the piping and the ...

In support of the US Nuclear Regulatory Commission (NRC) Accident Management Research Program, the availability of instruments to supply accident management information during a broad range of severe accidents is evaluated for a pressurized water reactor with a large dry containment. Results from this evaluation ...

One of the areas of current interest in the nuclear power industry is the response of containment buildings to internal pressures that may exceed design pressure levels. Evaluating the response of structures under these conditions requires computing beyon...

An alternate to the THRESHOLD model used in most severe accident risk assessments has been investigated. One reference plant for each of six containment types has been studied to determine the magnitude of containment leakage that would result from the pressures and temperatures associated with severe accident ...

In support of the US Nuclear Regulatory Commission (NRC) Accident Management Research Program, a methodology has been developed for identifying the plant information needs necessary for personnel involved in the management of an accident to diagnose that an accident is in progress, select and implement strategies to prevent or mitigate ...

During an emergency at a nuclear power plant, the on-shift staff could be hard-pressed to sample and analyze the containment atmosphere in a timely manner. Under these conditions, the reading of a high-level radiation monitor in the containment could be t...

This report examines containment requirements for spent-fuel transport containers that are transported under normal and hypothetical accident conditions. A methodology is described that estimates the probability of rod failure and the quantity of radioact...

CONTEMPT4/MOD2 describes the long-term behavior of multicompartment pressurized water reactor (PWR) containment systems and experimental containment systems subjected to postulated loss-of-coolant accident (LOCA) conditions. The program calculates the tim...

There are at least two models used to characterize the possible leakage of a containment during a severe accident: (1) the threshold model in which the containment is assumed to be leak-tight until certain pressure/temperature conditions are reached and a...

The development of liquid metal reactor concepts with passive safety characteristics is in progress at the General Electric Company under contract to the US Department of Energy. To assess the performance of these systems under postulated severe accident conditions analyses of containment accidents relating to the ...

As a result of a literature search, equations have been compiled for estimating the flow rates of pure gases through very small orifices and capillaries. Such equations might be useful in establishing upper limits of leak rates from sealed PuO/sub 2/ containers under accident conditions.

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 ...

The program covers development of safety and safety-related studies to better understand and more accurately define safety characteristics and safety margins of GCRs under postulated accident conditions. The work reported includes core seismic studies, high-temperature gas-cooled reactor (HTGR) accident initiation and progression ...

The program covers development of safety and safety-related studies to better understand and more accurately define safety characteristics and safety margins of GCRs under postulated accident conditions. The work reported includes core seismic studies, high-temperature gas-cooled reactor (HTGR) accident initiation and progression ...

The program covers development of safety and safety-related studies to better understand and more accurately define safety characteristics and safety margins of GCRs under postulated accident conditions. The work reported includes core seismic studies, high-temperature gas-cooled reactor (HTGR) accident initiation and progression ...

The program covers development of safety and safety-related studies to better understand and more accurately define safety characteristics and safety margins of GCRs under postulated accident conditions. The work reported includes core seismic studies, high-temperature gas-cooled reactor (HTGR) accident initiation and progression ...

The publication contains reports of commuter air carrier and air taxi accidents occurring in 1975. Included are 43 commuter air carrier and 157 on-demand air taxi accident briefs. The brief format presents the facts, conditions, circumstances and probable...

A severe accident study was conducted to evaluate conservatively scoped source terms and radiological consequences to support the Advanced Neutron Source (ANS) Conceptual Safety Analysis Report (CSAR). Three different types of severe accident scenarios we...

Results of design verification tests for the FFTF reactor cavity liner system are presented which suggest that steel liners would retain their integrity even under certain hypothetical accident conditions, thus avoiding the formation of hydrogen. When liner failures are postulate in hypothetical reactor vessel meltthrough accidents, ...

Objectives are: the generation of the data base needed to assess methods for predicting the behavior of LWR containments under accidents conditions and severe environments beyond current design requirements; the assessment of selected predictive numerical...

Transport of uranium hexafluoride during the different phases of the fuel cycle is carried out using containers of various types that must meet the safety requirements provided for in the specific international regulations for this area. Qualification of ...

This report describes a background study and preliminary plans for a program to develop methodology for predicting the capacity of containment structures under severe accident and environmental conditions. Both analytical and experimental efforts were con...

Fission products are released in aerosol form from nuclear reactors under postulated accident conditions. An understanding of aerosol behavior is thus important in the estimation of potential radioactivity release from containment. A major simplifying ass...

Accident sequences from WASH-1400 were selected and analyzed with the MARCH/CORRAL code to provide an envelope of design conditions. The time-dependent pressures and temperatures in containment were calculated as were the concentrations of steam, nonconde...

The container was evaluated analytically to determine its compliance with the applicable regulations governing containers in which radioactive and fissile materials are transported, and the evaluation is the subject of this report. Computational and test procedures were used to determine the structural integrity and thermal behavior of the ...

... § 71.73 Hypothetical accident conditions. (a) Test procedures...Evaluation for hypothetical accident conditions is to be based... Tests for hypothetical accident conditions must be conducted...been assumed for criticality analysis, immersion under a head...

CHART was developed for the thermal analysis of the charcoal adsorber in a reactor containment system; maximum temperatures caused by iodine adsorption under accident conditions are estimated. A differential equation relating the charcoal slab temperature to the heat generation rate, air flow rate, and the heat parameters of air and ...

The MAAP Accident Response System (MARS) is a userfriendly computer software developed to provide management and engineering staff with the most needed insights, during actual or simulated accidents, of the current and future conditions of the plant based on current plant data and its trends. To demonstrate the reliability of the MARS ...

The US Nuclear Regulatory Commission has sponsored studies to develop a ''LEAKAGE-BEFORE-FAILURE'' model for use in severe accident risk assessments to provide a means of accounting for significant containment leakage prior to reaching the containment threshold pressure. Six ...

This book contains the proceedings on medical management of radiation accidents. Topics covered include: Fundamentals of radiation accidents, Emergency room management of radiation accidents, and Special aspects of nuclear power.

This report describes and discusses the containment accident progression and the important severe accident containment thermohydraulic phenomena. The overall objective of the report is to provide a rather detailed presentation of the present status of phe...

The critical question in evaluating various hydrogen accidents is whether or not significant quantities of fission products are released to the atmosphere. The function of containment systems is to prevent the escape of fission products. Thus, the determination of the capacity of containment structures to function during ...

Piping penetrations in nuclear power plant steel containments are surrounded by flexible metal bellows. The purpose of the bellows is to maintain the containment pressure boundary integrity while permitting relative movement between the piping and the containment wall. In a severe accident, bellows may be subjected ...

Piping penetrations in nuclear power plant steel containments are surrounded by flexible metal bellows. The purpose of the bellows is to maintain the containment pressure boundary integrity while permitting relative movement between the piping and the containment wall. In a severe accident, bellows may be subjected ...

In a nuclear reactor, the containment represents the final barrier to fission product release following a severe accident. The timing and manner of containment loading are important in determining if a failure occurs and the magnitude of radioactivity release. A variety of computer models have been developed to analyze severe ...

The thermal response of the H1616 transport container is simulated to demonstrate compliance with the Federal regulations for performance during hypothetical accident conditions (HAC). The goal is to show that tests conducted for the certification of the H1616 shipping container provide conservatively high ...

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 ...

The NRC instituted the NUREG-0737 requirements as implementation of the Post-TMI Action Plan in October, 1980. Among these requirements was the capability to obtain chemistry samples of the reactor coolant and containment building atmosphere under post accident conditions. The quantitative criteria were, in general, beyond the ...

Different hypothetical accident sequences have been simulated at Unit 1 of the Juragua nuclear power plant in Cuba, a plant with two VVER-440 V213 units under construction. The computer code MELCOR was employed for these simulations. The sequences simulated are: (1) a design-basis accident (DBA) large loss of coolant accident (LOCA) ...

A severe accident study was conducted to evaluate conservatively scoped source terms and radiological consequences to support the Advanced Neutron Source (ANS) Conceptual Safety Analysis Report (CSAR). Three different types of severe accident scenarios were postulated with a view of evaluating conservatively scoped source terms. The first scenario ...

A series of full-scale experiments were conducted to characterize the release of simulated waste from waste containers packaged in a Transuranic Package Transporter (TRUPACT) subjected to a series of drop, puncture, and thermal environments. The measureme...

The consequences of an earthquake-induced fire involving a tritium leak were analyzed using the GASFLOW computer code. Modeling features required by the analysis include ventilation boundary conditions, flow of a gas mixture in an enclosure containing obs...

The consequences of an earthquake-induced fire involving a tritium leak were analyzed using the GASFLOW computer code. Modeling features required by the analysis include ventilation boundary conditions, flow of a gas mixture in an enclosure containing obstacles, thermally induced buoyancy, and combustion phenomena.

A steam explosion is considered as a phenomenon which possibly threatens the integrity of the containment vessel of a nuclear power plant in a severe accident condition. A numerical calculation code JASMINE (JAeri Simulator for Multiphase INteraction and ...

The safety assessment and licensing of nuclear reactor plants by the United States Nuclear Regulatory Commission (USNRC) depend partially on analytical computer programs to predict the response of safeguard systems to accident conditions. CONTEMPT4/MOD2 i...

The objective of this research was to develop and demonstrate a methodology for calculation of the time interval between receipt of the containment isolation signals and the first fuel pin failure for loss-of-coolant accidents (LOCAs). Demonstration calcu...

ORNL's Advanced Neutron Source (ANS) will be a new user facility for all kinds of neutron research, centered around a research reactor of unprecedented neutron beam flux. A defense-in-depth philosophy has been adopted. In response to this commitment, ANS Project management has initiated severe accident analysis and related technology development efforts early-on in ...

ORNL`s Advanced Neutron Source (ANS) will be a new user facility for all kinds of neutron research, centered around a research reactor of unprecedented neutron beam flux. A defense-in-depth philosophy has been adopted. In response to this commitment, ANS Project management has initiated severe accident analysis and related technology development efforts early-on in the design ...

Bellows are an integral part of the containment pressure boundary in nuclear power plants. They are used at piping penetrations to allow relative movement between piping and the containment wall, while minimizing the load imposed on the piping and wall. P...

Bellows are an integral part of the containment pressure boundary in nuclear power plants. They are used at piping penetrations to allow relative movement between piping and the containment wall, while minimizing the load imposed on the piping and wall. P...

A simplified model of heat transfer and chemical reaction has been adapted to evaluate the expected behavior of droplets containing unreacted Zircaloy and stainless steel moving through the containment atmosphere during postulated accidents involving direct containment heating. The model includes internal and ...

...2010-10-01 false Reporting accidents. 195.50 Section 195.50...HAZARDOUS LIQUIDS BY PIPELINE Annual, Accident, and Safety-Related Condition Reporting § 195.50 Reporting accidents. An accident report is...

This study estimates the safety effect of road lighting on accidents in darkness on Dutch roads, using data from an interactive database containing 763,000 injury accidents and 3.3 million property damage accidents covering the period 1987-2006. Two estimators of effect are used, and the results are combined by ...

In SECY-90-016, the NTRC proposed a safety goal of a conditional containment failure probability (CCFP) of 0.1 and the alternative acceptance criteria allowed for steel containments, which specifies that the stresses should not exceed ASNE Level C allowables for severe accident pressures and temperatures. In this ...

The Nuclear Engineering Department of National Tsing Hua University organized a workshop on Severe Accident Management. The workshop was sponsored by Taiwan Power Company and was held at Taipei, Taiwan from July 31 to August 11, 1989. The topics covered in the workshop included the general in-vessel LWR severe accident phenomena, ...

The program covers development of safety and safety-related studies to better understand and more accurately define safety characteristics and safety margins of GCRs under postulated accident conditions. The work reported here includes core seismic studies, high-temperature gas-cooled reactor (HTGR) accident initiation and progression ...

The program covers development of safety and safety-related studies to better understand and more accurately define safety characteristics and safety margins of GCRs under postulated accident conditions. The work reported here includes core seismic studies, high-temperature gas-cooled reactor (HTGR) accident initiation and progression ...

The program covers development of safety and safety-related studies to better understand and more accurately define safety characteristics and safety margins of GCRs under postulated accident conditions. The work reported includes core seismic studies, high-temperature gas-cooled reactor (HTGR) accident initiation and ...

This publication contains briefs of selected railroad accidents occurring in U.S. Railroad operations during calendar year 1981. The brief format presents basic facts, conditions, circumstances, and probable cause(s) in each instance. Additional statistic...

This subgroup examined the transportation system issues which must be considered in the development and implementation of a National nuclear waste management policy. Five basic issues were discussed: standards for packagings and containment systems for normal and accident conditions, institutional controls, additional measures required ...

In the source term evaluation for severe core damage accident of light water reactor, the uncertainty on the evaluation by the occurrence of volatile iodic compounds is reduced by large margine by using the method of fixation of FP iodine as silver iodide...

In an attempt to throw light upon the etiology of neuroparalytic accidents following antirabies treatment in man, the author analyses the process and effects of experimentally induced allergic encephalitis in various animals. He concludes that the two conditions are apparently identical, and suggests that the solution to the problem of neuroparalytic ...

Examination of the lessons to be learned from the accident of the Three Mile Island nuclear power plant on 20 March 1979 led the French Safety Authorities and EDF (Electricite de France) to adopt a series of measures intended to improve the performance of...

The publication contains Briefs of 1984 aviation accidents which involved alcohol use by the pilot-in-command. The Brief Format represents the facts, conditions, circumstances and probable cause(s) for each accident. The publication is issued once each ye...

The publication contains 897 selected aircraft accident reports, in brief format, occurring in U.S. civil aviation operations during calendar year 1977. The brief format presents the facts, conditions, circumstances, and probable cause(s) for each acciden...

We have reported our findings of the pre-existing leakage areas from the subatmospheric, atmospheric (dry and ice-condenser) PWRs and the BWRs. The subatmospheric plants employ rather tight containment and hence the pre-existing leakage areas are generally quite small (perhaps inconsequential in the progression of severe accidents). The pre-existing ...

This report describes the results of tests conducted on three different designs of full-size electrical penetration assemblies (EPAs) that are used in the containment buildings of nuclear power plants. The objective of the tests was to evaluate the behavior of the EPAs under simulated severe accident conditions using steam at elevated ...

As part of the Severe Accident Sequence Analysis (SASA) program of the Nuclear Regulatory Commission (NRC), threats to containment and ways in which operators can help preserve containment integrity during severe accidents are examined. Severe accidents a...

This paper discusses an accident, which occurred in one of the radiation application centres in Iran, follow-up investigations as well as lessons learnt. In January 2004 the Regulatory Authority was informed through a university radiation protection officer of an accident regarding orphan sources. Investigations revealed that one Am-Be and three (137)Cs ...

... from 1976 to 1981, examined the relationship between aviation accidents and static ... between certain visual conditions and aircraft accidents (19,20 ...

Appendix B.In-Flight Loss of Control Accidents in Part 121 and Scheduled ... The causal factors of accidents from the National Transportation Safety Board ...

Two high-range containment radiation monitors (HRCRMs) have been installed in the drywell at the James A. FitzPatrick nuclear power station. These monitors were initially required only to provide a reasonable assessment of area radiation conditions inside the containment following a design basis accident. Recently, ...

CONTEMPT4/MOD2 is a new computer program developed to predict the long-term thermal hydraulic behavior of light-water reactor and experimental containment systems during postulated loss-of-coolant accident (LOCA) conditions. Improvements over previous containment codes include multicompartment capability and ice ...

Three sets of accident data files have been analyzed to obtain a greater understanding of the personal, situational, and vehicle-related factors involved in pedestrian accidents. These include all fatal pedestrian accidents contained in the Fatal Accident...

The Fatal Accident Reporting System (FARS) database consist of three relational tables, containing data on automobile accidents on public U.S. roads that resulted in the death of one or more people within 30 days of the accident. Truck and trailer accidents are also included....

A Five-step methodology has been developed to evaluate information needs for nuclear power plants under accident conditions and the availability of plant instrumentation during severe accidents. Step 1 examines the credible accidents and their relationships to plant safety functions. Step 2 determines the ...

A Five-step methodology has been developed to evaluate information needs for nuclear power plants under accident conditions and the availability of plant instrumentation during severe accidents. Step 1 examines the credible accidents and their relationships to plant safety functions. Step 2 determines the ...

Bellows are an integral part of the containment pressure boundary in nuclear power plants. They are used at piping penetrations to allow relative movement between piping and the containment wall. In a severe accident they may be subjected to high pressure and temperature, and a combination of axial and lateral deflections. A test ...

This report presents sample containment analyses and examples of leakage rate calculations for Type B packages used to transport various contents. Samples of acceptance standard leakage rates are developed for specific contents types at normal transport conditions and at hypothetical accident conditions. The ...

An analysis of containment environments during a postulated severe accident was performed for a pressurized water reactor (PWR) type nuclear power plant (NPP) of which electric power is 1400 MWe. Examined were four initiating events such as large break loss-of-coolant accident (LBLOCA), small break loss-of-coolant ...

The ORNL HFIR unirradiated fuel element shipping container was designed and fabricated at the Oak Ridge National Laboratory for the transport of HFIR unirradiated fuel elements. The container was evaluated analytically and experimentally to determine its compliance with the applicable regulations governing containers in which ...

The AL-SX/2 and AL-SX/3 are recently certified Type B shipping containers for tritium reservoirs. Both containers consist of an outer stainless steel drum overpack and sealed stainless steel containment vessel. WR reservoirs provide containment of tritium for normal conditions of transport. In ...

This report elucidates the probable true supply of radiolytic gas to a nitrogen-filled pressure suppression containment under accident conditions in boiling-water reactors. Calculations have been performed using a computer-based program developed at Riso National Laboratory in Denmark. Measurements of the radiolytic gas contents in ...

The design and safeguards of the Ames Laboratory Research Reactor and its associated facilities are reviewed. The causes and consequences of serious accidents are considered. It was found that the maximum credible accident for the ALRR is a quite melt-down of the aluminum core, which results from loss of D/ sub 2/O coolant. The ...

Studies and operating experience suggest that the risk of severe accidents during low power operation and/or shutdown (LP/S) conditions could be a significant fraction of the risk at full power operation. Two studies have begun at the Nuclear Regulatory Commission (NRC) to evaluate the severe accident progression from a risk ...

An application of smart sensor technology developed by Sandia National Laboratories for use in the safe and secure transportation of high value of hazardous materials is proposed for a railroad application. The Green Box would be capable of surviving most typical railroad accidents. In an accident, the system would send a distress signal notifying ...

The collection contains seven documents with the latest reports and studies from NTIS' database on truck accidents, truck safety and fatigue. Included in the collection are reports on truck accident countermeasures on urban freeways, identifying 'unsafe' ...

This book contains proceedings of Electrical Hazards and Accidents. Topics covered include: Electrical Systems; Electrical and Lightning Accidents and Fires; Conductors and Overcurrent Protection; OSHA Standards and Requirements; and High Voltage Systems: Design.

Containment piping penetration bellows are an integral part of the pressure boundary in steel containments in the United States (US). Their purpose is to minimize loading on the containment shell caused by differential movement between the piping and the containment. This differential movement is typically caused ...

...fissile materials packagings to withstand accident conditions in transportation. 173...fissile materials packagings to withstand accident conditions in transportation. Each...CFR part 71 for ability to withstand accident conditions in...

The ultimate aim of a description of iodine behavior in severe LWR accidents is a time-dependent accounting of iodine species released into containment and to the environment. Factors involved in the behavior of iodine can be conveniently divided into four general categories: (1) initial release into containment, (2) interaction of ...

A structural reassessment of the containment structure of the Palisades Nuclear Power Plant Unit 1 was performed for the Nuclear Regulatory Commission as part of the Systematic Evaluation Program. Conclusions about the ability of the containment structure to withstand the Abnormal/Extreme Environment are presented. The reassessment focused mainly on the ...

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.

This document provides the technical basis for the frequency of a tank bump and for the radiological and toxicological consequences of a tank boiling accident and associated hazardous conditions.

Under the assumption that a nonmechanistic accident induces a condition such that it is not possible to cool the core of a high temperature gas cooled reactor, the temperature of the core will gradually rise due to decay heat. There are several barriers to the release of fission products to the environment: the fuel particle coatings, the graphite ...

An analysis of the frequency of four different types of rotorcraft accidents was conducted to determine if the number of fatalities and injuries between accident conditions was different. Accidents involving rollover, no rollover, fire, and no fire were s...

...false Telephonic notice of certain accidents. 195.52 Section 195.52 ...HAZARDOUS LIQUIDS BY PIPELINE Annual, Accident, and Safety-Related Condition Reporting...52 Telephonic notice of certain accidents. (a) At the earliest...

Several probabilistic risk assessments (PRAs) have identified containment loads accompanying reactor vessel failure as a major contributor to the probability of early containment failure during severe accidents. Two significant contributors to these loads are phenomena referred to as steam spike and direct ...

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 and also can be phenomenologically inconsistent. One of the principal deficiencies lies in the static nature of conventional APETs. In the conventional event tree techniques, the sequence of events is ...

In support of the U.S. Department of Energy`s (DOE`s) Waste Management Programmatic Environmental Impact Statement, Argonne National Laboratory has developed WASTE-ACC, a computational framework and integrated PC-based database system, to assess atmospheric releases from facility accidents. WASTE-ACC facilitates the many calculations for the accident ...

Recent severe reactor accident calculations focusing on ice condenser containment issues, using the Sequoyah ice condenser containment as a representative plant, indicate that detonable hydrogen concentrations may occur within the ice condenser and possibly elsewhere in the containment. These calculations, which ...

Changing world conditions and changing technologies suggest that serious consideration should be given to siting of nuclear power plants underground. Underground siting is not a new concept. Multiple research reactors, several weapons production reactors, and one power reactor have been built underground. What is new are the technologies and incentives that may now make ...

The U.S. Nuclear Regulatory Commission (NRC's) Severe-Accident Policy Statement, Safety Goal Policy Statement, Individual Plant Examination (IPE) Generic Letter, and Containment Performance Improvement (CPI) Program seek to characterize adequate containment performance. This paper describes a framework (developed through the ...

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 ...

...accident investigation dockets, and accident database data. 837.3 Section 837.3 ...accident investigation dockets, and accident database data. (a) Demands for material...investigations, or its computerized accident database(s) shall be submitted, in...

The safety assessment and licensing of nuclear reactor plants by the United States Nuclear Regulatory Commission (USNRC) depend partially on analytical computer programs to predict the response of safeguard systems to accident conditions. CONTEMPT4/MOD2 is a new computer code to predict the long-term thermal hydraulic behavior of water-cooled nuclear ...

This paper discusses salient aspects of severe accident related phenomenological considerations, scoping studies, and mitigative design features being studied for incorporation into a high-power research reactor plant. Key results of scoping studies on steam explosions, recriticality, core-concrete interactions, and containment transport are highlighted. ...

The report provides a comprehensive review of signal installations and their impacts on accident patterns, and accident frequency and severity. It contains information on accident statistics by type and severity, accident rates for stop controlled and sig...

The report contains a review of present road accident recording system in the SADCC-countries and recommends a new, improved road accident recording system. It is recommended to report each individual accident to a central unit which prepares and compiles...

The environmental consequences of an LMFBR accident involving breach of containment are so severe that such accidents must not be allowed to happen. Present methods for analyzing hypothetical core disruptive accidents like a loss of flow with failure to s...

This publication contains summary reports of major marine accidents, adopted from August 1979 through June 1982. The summary reports present the probable cause and accident descriptions for the following accidents: Oceanographic Research Vessel PROFILER, ...

This publication contains summary reports of major marine accidents, occurring from January through June 1979. The summary reports present the probable cause and accident descriptions for the following accidents: Fishing vessel OCEAN CAPE lost on January ...

In support of the U.S. Nuclear Regulatory Commission Accident Management Research Program, the availability of instruments to supply accident management information during a broad range of severe accidents is evaluated for a Boiling Water Reactor with a M...

The statistics are compiled from summaries of fatal and personal injury accident data and exposure data submitted to the Federal Highway Administration by the State highway departments. The reports contain numbers of fatal accidents, injury accidents, fat...

The document refers to the Convention on Early Notification of a Nuclear Accident (CENNA) (IAEA-INFCIRC-335) and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (CANARE) (IAEA-INFCIRC-336). Part I contains the stat...

The document refers to the Convention on Early Notification of a Nuclear Accident (CENNA) (IAEA-INFCIRC-335) and the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (CANARE) (IAEA-INFCIRC-336). Part I contains the stat...

The document refers to the Convention on Early Notification of a Nuclear Accident (IAEA-INFCIRC-335) and to the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (IAEA-INFCIRC-336). Part I contains the status lists as of...

The document refers to the Convention on early notification of a nuclear accident (INFCIRC-335) and to the Convention on assistance in the case of a nuclear accident or radiological emergency (INFCIRC-336). Part I contains reservations/declarations made u...

The document refers to the Convention on early notification of a nuclear accident (INFCIRC-335) and to the Convention on assistance in the case of a nuclear accident or radiological emergency (INFCIRC-336). Part I of the document contains the texts of res...

The document refers to the Convention on Early Notification of a Nuclear Accident (INFCIRC-335) and to the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (INFCIRC-336). Part I of the document contains reservations/dec...

This report contains the briefs of accidents involving Taylorcraft-B aircraft occuring in 1966. There were 37 accidents involving this model aircraft out of a total of 5,712 general aviation accidents in 1966. (Author)

The report presents the record of aircraft accidents which occurred in U.S. civil aviation operations during the calendar year 1971. It includes a statistical recapitulation of all accidents, and a brief of each air carrier accident containing the essenti...

The report presents the record of aircraft accidents which occurred in U. S. Civil Aviation Operations during calendar year 1970. It includes a statistical recapitulation of all accidents, and a brief of each air carrier accident containing the essential ...

... false Contents of casualty or accident report form. 174.107 Section...174.107 Contents of casualty or accident report form. Each form for reporting a vessel casualty or accident must contain the information...

This report provides an overview of the containers that are currently stored at Pantex and available for use in response to an accident or for use in any other application where a sealed containment vessel and accident resistant overpack may be needed.

The ORNL tungsten-shielded cask was designed and fabricated at the Oak Ridge National Laboratory (ORNL) for the transport of Type B and large quantity nonfissile isotopes. The container was evaluated analytically to determine its compliance with the applicable regulations governing containers in which radioactive and fissile materials are transported. ...

Experiments on aerosol behavior in an atmosphere containing saturated vapor, which were performed in the KAEVER experimental facility and proposed for the OECD International Standard Problem No. 44, were simulated with the CONTAIN thermal-hydraulic computer code. The purpose of the work was to assess the capability of the CONTAIN code ...

Technical Basis Document for the Nuclear Criticality Representative Accident and Associate Represented Hazardous Conditions. Revision 2 of RPP-12371 provides accident consequence estimates for a hypothetical criticality event in an above grade facility (e...

This study was conducted to provide the basis for an estimate of the containment bypass risk presented by severe accident-induced steam generator tube rupture. During severe accidents, components can be heated to the extent that induced rupture might occur as a result of the combined effects of pressure and temperature. The potential ...

Because the containment structure is the last barrier against the release of radioactivity, an assessment was undertaken to identify the design weaknesses and estimate the margins of safety for the SEP containments under the postulated, combined loading conditions of a safe shutdown earthquake (SSE) and a design basis ...

The final report summarizes the results of various research areas concerned with possible disposal-site accidents involving the destruction of containers containing radioactive waste by salt brine. The physico-chemical data obtained are intended to serve ...

Risk Communication Bibliography The Risk Communication Bibliography contains more than 650 references to published documents that address the communication of public health hazards. The citations and summaries in the Risk Communication Bibliography are an essential starting point for effectively measuring how risks are communicated to and understood by the public. The ...

Helium containing some tritium is shipped at low pressure in banks of cylinders mounted on a truck trailer in compliance with 49 CFR 178.350, Specification 7A. The shipping package is not a radiological hazard under normal or accident conditions.

The results are reported of a literature search for information concerning the heterogeneous, gas phase, catalytic hydrogen-oxygen recombination. Laboratory scale experiments to test the performance of specific metal oxide catalysts under conditions simulating the atmosphere within a nuclear reactor containment vessel following a loss-of-coolant blowdown ...

An apparatus for efficiently and safely recombining hydrogen and oxygen gas to form water vapor, the apparatus being particularly adapted for use with a nuclear reactor system in which potentially dangerous hydrogen gas, evolved within the containment vessel during certain postulated accident conditions, can be eliminated. Further, ...

An apparatus is disclosed for efficiently and safely recombining hydrogen and oxygen gas to form water vapor, the apparatus being particularly adapted for use with a nuclear reactor system in which potentially dangerous hydrogen gas, evolved within the containment vessel during certain postulated accident conditions, can be eliminated. ...

The analysis indicated that the generator can be safely transported and operated with the normal precautions afforded any structure containing a radioisotope. The shielding provided for protection against direct radiation exposure is considered adequate. Integrity of the system is maintained under most conceivable accident ...

TRUPACT-I is a packaging which will be used to transport contact-handled transuranic (CH-TRU) wastes generated by defense programs in the US. This paper presents the general approach for the containment analysis for TRUPACT-I. The maximum activity per TRUPACT-I is determined for a stated seal leak rate and filter penetration efficiency in order to comply with regulatory ...

Atmospheric pressure and temperature excursions at constant volume for oxidation of high temperature sodium are investigated analytically. Data under both the adiabatic condition and the time dependent transient heat transfer condition are reported. The analyses represent parametric cases involving variations in containment geometry, ...

The paper provides a summary of efforts to date to better understand the leakage behavior of containment penetrations when subjected to severe accident conditions. The research activities discussed herein are a part of the Containment Integrity Programs, which are managed by Sandia National Laboratories for the US ...

Under the auspices of the United States Nuclear Regulatory Commission, severe accidents are being studied at the Idaho National Engineering Laboratory. The boiling water reactor (BWR) studies have focused on postulated anticipated transients without scram (ATWS) accidents which might contribute to severe core damage or containment ...