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 postulated hypothetical ...

This report presents the comparisons between calculated and measured fuel rod behavior and the analysis of stress for preirradiated LWR type fuel rods during reactivity initiated accident (RIA) conditions. For the calculations, FPRETAIN computer code whic...

The US and FRG have developed methodologies to determine the performance of and fission product release from TRISO-coated fuel particles under postulated accident conditions. The paper presents a qualitative and quantitative comparison of US and FRG model...

The Nuclear Regulatory Commission (NRC) approves new package designs for shipping fissile quantities of UF{sub 6}. Currently there are three packages approved by the NRC for domestic shipments of fissile quantities of UF{sub 6}: NCI-21PF-1; UX-30; and ESP30X. For approval by the NRC, packages must be subjected to a sequence of physical tests to simulate transportation accident ...

... § 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...

The Three Mile Island nuclear plant (Unit 2) was modeled using the Transient Reactor Analysis Code (TRAC-P1A) and a base case calculation, which simulated the initial part of the accident that occurred on March 28, 1979, was performed. In addition to the base case calculation, several parametric calculations were performed in which a single hypothetical change was made in the ...

The report presents a preliminary record of aircraft accidents which occurred in U.S. Civil Aviation Operations during calendar year 1974. It includes a statistical recapitulation of all accidents; a comparison of accidents, fatalities, accident rates, an...

... Title : Hospitalizations for Accidents and Induries in the US Navy. IV. A Comparison of Nuclear and Conventionally Powered Surface Ships. ...

Tables of statistics are presented of fatal accidents in Tennessee and the United States for purposes of comparison and to indicate important points of attack in the reduction of accidents.

Accidents in Utah coal mines are considered in comparison with morbidity rates for typhoid and smallpox.

A description of natural circulation cooling characteristics is presented. Data were obtained from several pressurized water reactor accident simulations in the Loss-of-Fluid Test (LOFT) pressurized water reactor (PWR). The reliability of natural circulation cooling, its cooling effectiveness, and the effect of changing system conditions are described. ...

An atmospheric dispersion and consequence model called RADIS has been developed by the University of Hong Kong for nuclear accident consequence analysis. The model uses a two-dimensional plume trajectory derived from wind data for Hong Kong. Dose, health effects, and demographic models are also developed and implemented in RADIS so that accident ...

...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...

General Aviation pilots have been involved in a steadily decreasing number of accidents over the past 20 years. Changes in the age distribution, certification, and flying habits of these pilots make direct comparison of accident statistics inaccurate. This study reviews changes in the pilot population over the past 20 years to analyze ...

This calculation note documents an evaluation of the doses from submersion and ground shine due to a release of tank farm radioactive materials, and a comparison of these doses to the doses from inhalation of the materials. The submersion and ground shine doses are insignificant compared to the inhalation doses. The doses from resuspension are also shown to be negligible for ...

Experiments were done on several aerosols in air atmospheres at varying temperatures and humidity conditions of interest in forming a data base for testing aerosol behavior models used as part of the process of evaluating the ''source term'' in light water reactor accidents. This paper deals with the problems of ...

... 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 ...

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 ...

The result of VVER-1000 computational benchmarks, calculations obtained with the use of various Russian codes (such as MCU-RFFI/A, TVS-M and WIMS-ABBN) are presented. List of benchmarks includes LEU and MOX cells with fresh and spent fuel under various conditions (for calculation of kinetic parameters, Doppler coefficient, reactivity effect of decreasing the water density). ...

The present regulations for packaging and transportation of radioactive materials, IAEA Safety Series No. 6; 1985, establish specific criteria for the thermal environment of a hypothetical accident. The regulation states: The scope of this paper is to examine the effects on modeling that result with the Fry proposed thermal boundary conditions. The ...

AIMS: The current study investigated the effect of a media health message for drinking on risk perception estimates (comparative optimism). METHODS: Sixty-five young adults who regularly drink alcohol watched an anti-drinking scenario (having an accident due to drinking). There were two intervention conditions: 30 participants 'imagined' they were part of ...

This paper reports on a cooperative effort among European and U.S. analysts, which is an assessment of the comparative safety performance of metal and oxide fuels during accidents in a 3500-MW (thermal), pool-type, liquid-metal-cooled reactor (LMR) is performed. The study focuses on three accident initiators with failure to scram: the unprotected ...

This survey looks at a sample of 450 injured motorcyclists involved in 425 accidents over a period of one year (1974). A comparison of several aspects of the accident situation between the sample and national accident data indicated that the detailed info...

The results of a dynamic analysis of the LOFT Reactor Core Barrel for faulted conditions are presented in this report. Loading conditions considered were seismic accelerations resulting from a Safe Shutdown Earthquake (SSE) and pressure loadings from both a hot leg and a cold leg Loss-of-Coolant Accident (LOCA) break. Maximum stresses ...

The General Atomic codes TAP (Transient Analysis Program) and RECA (Reactor Emergency Cooling Analysis) are evaluated with respect to their capability for predicting the dynamic behavior of high-temperature gas-cooled reactors (HTGRs) for postulated accident conditions. Several apparent modeling problems are noted, and the susceptibility of the codes to ...

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 condenser analytical models. A program ...

Preliminary results of comparison disassembly calculations for a representative LMFBR model (2100-l voided core) and arbitrary accident conditions are described. The analytical methods employed were the computer programs: FX2- POOL, PAD, and VENUS-II. The calculated fission energy depositions are in good agreement, as are ...

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 ...

...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...

Analysis has been made of the changes in road accident rates up to July 1975 following fuel conservation measures imposed by the UK Government since November 1973. Predictions have been made, based on trends and variations observed in past accident rates, of the rates that would have occurred in the absence of the fuel shortage. ...

The risks associated with the transport of spent nuclear fuel by truck and rail have been reexamined and compared to results published in NUREG-O170 and the Modal Study. The full reexamination considered transport of PWR and BWR spent fuel by truck and rail in four generic Type B spent fuel casks. Because they are typical, this paper presents results only for transport of PWR spent fuel in ...

Recent comparisons of MELCOR predictions to three sets of experiments, the ABCOVE Aerosol Experiments, the HDR-V44 Steam Blowdown Experiments, and the Battelle-Frankfurt Gas Mixing Experiments are presentd. All three comparisons involve conditions that are of concern in an LWR containment during a severe 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.

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...

The purpose of this document is to record and evaluate the hazardous conditions associated with remote pit refurbishment using the Pit Viper. These hazardous conditions were identified during a Hazard and Operability Analysis (HAZOP). Included in the evaluation is a comparison to the hazardous conditions currently ...

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...

The Light-Water-Reactor (LWR) Aerosol Containment Experiments (LACE) are being performed in Richland, Washington, at the Hanford Engineering Development Laboratory (HEDL) under the leadership of an international project board and the Electric Power Research Institute. These tests have two objectives: (1) to investigate, at large scale, the inherent aerosol retention behavior in LWR containments ...

As part of verification and validation, the Advanced Neutron Source reactor RELAP5 system model was benchmarked by the Advanced Neutron Source dynamic model (ANSDM) and PRSDYN models. RELAP5 is a one-dimensional, two-phase transient code, developed by the Idaho National Engineering Laboratory for reactor safety analysis. Both the ANSDM and PRSDYN models use a simplified single-phase equation set ...

Collability models for post-accident nuclear reactor debris are compared with data for volume-heated debris under various conditions (uniform debris on an impermeable support for various fluids and pressures, debris with forced liquid flow from below, and stratified debris). Comparisons are presented in graphical form and by ...

The common aim of many research projects concerning reactor safety in Germany is to prove that the integrity of components important for safety remains ensured even under the most unfavorable operating and accident conditions. Both component tests and cal...

An estimate is presented of the amount of visible light produced by gamma-ray ionization in air such as might exist around a reactor or as might be observed in an accident. An examination is made of the conditions under which a shielded aircraft reactor would produce enough visible light to be seen. A comparison is made with ...

The purpose of this analysis is to calculate the offsite radiological consequence of the bounding flammable gas accident. DOE-STD-3009-94, ''Preparation Guide for U.S. Department of Energy Nonreactor Nuclear Facility Documented Safety Analyses'', requires the formal quantification of a limited subset of accidents ...

Thermodynamic accident analyses have been performed with computer simulation models to investigate core heatup sequences, sensitivity analyses, power variations, anticipated transients without scram, and core displacement considerations for probabilistic safety analyses (PSA) of small gas-cooled high-temperature reactors (e.g. HTR-Module). In worst case considerations where ...

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...

... the opinion of the authors, the 24 month accident airman populations on the ... age, weight, BW/BSA, and PI active airman population recognizing the ...

High burnup Zircaloy-clad UO{sub 2} fuel specimens have been heated to study the release of fission products in tests simulating LWR accident conditions. The dominant variable was found to be temperature, with atmosphere, time, and burnup also being significant variables. Comparison of data from tests in steam and hydrogen, at ...

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 ...

The River Protection Project (RPP) Authorization Basis (AB) contains controls that address spray leaks in tanks. However, there are no hazardous conditions in the Hazards Database that specifically identify in-tank spray leak scenarios. The purpose of this Hazards Evaluation is to develop hazardous conditions related to in-tank spray leaks for the Hazards ...

This document quantifies the offsite radiological consequences of the bounding flammable gas accident for comparison with the 25 rem Evaluation Guideline established in DOE-STD-3009, Appendix A. The bounding flammable gas accident is a detonation in a SST. The calculation applies reasonably conservative input parameters in accordance ...

... The identification of the true causes of hazardous failures and accidents of technical equipment is the necessary condition for developing and ...