This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Subsurface Leak Remaining Subsurface. The calculations needed to quantify the risk associated with this accident scenario are included within.
DOE Information Bridge
This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Steam Intrusion from Interfacing Systems. The calculations needed to quantify the risk associated with this accident scenario are included within.
Energy Citations Database
A study of a spectrum of pipe break accidents was made for N-Reactor as part of the accident analysis for the N-Reactor Updated Safety Analysis Report (NUSAR). From this selection of accidents, a list was made of those pipe breaks which would represent th...
National Technical Information Service (NTIS)
This document includes the calculations performed to quantify the risk associated with the unmitigated and mitigated accident scenarios described in the TWRS FSAR for the accident analysis titled: Surface Leaks Resulting in Pool.
This document includes the calculations performed to quantify the risk associated with the unmitigated and mitigated accident scenarios described in the TWRS FSAR for the accident analysis titled: Subsurface Leaks Resulting in Pool.
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 c...
This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Fire in Contaminated Area. The calculations needed to quantify the risk associated with this accident scenario are included within.
The assumptions, methods of analysis and results of the analysis of single tube accidents which have significant offsite radiological consequences are described. Those accidents described include: pressure tube flow blockage; fuel ejection; and pressure t...
Evaluation of the adequacy of the emergency cooling water addition system (ECWA system) requires analysis of the postulated accidents for which the system is required to function. Analysis of these accidents requires a knowledge of the amount of the ECW added that goes to the fuel; both the total amount to the fuel ...
This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report (FSAR): Steam Intrusion From Interfacing Systems. The calculations needed to quantify the risk associated with this accident scenario are included in the following sections to aid in ...
One aspect of fast reactor safety analysis consists of calculating the strongly coupled system of physical phenomena which contribute to the reactivity balance in hypothetical whole-core accidents: these phenomena are neutronics, fuel behaviour and heat t...
The Three Mile Island nuclear plant (TMI-2) was modeled using the Transient Reactor Analysis Code (TRAC-PIA) and a preliminary calculation, which simulated the initial part of the accident that occurred on March 28, 1979, was performed. The purpose of thi...
The CRAC2 computer code has been adapted to the calculation requirements of Draft/Final Environmental Impact Statement (DES/FES) casework analysis for the Nuclear Regulatory Commission. CRAC2 is a revised version of the CRAC (Calculation of Reactor Accide...
... Descriptors : (*AUSTRALIA, ACCIDENTS), (*ACCIDENTS, STATISTICAL ANALYSIS), MOTOR VEHICLE ACCIDENTS, INDUSTRIAL MEDICINE ...
DTIC Science & Technology
This report describes analyses of the response of a Pressurized-Water Reactor at the Zion Plant to hypothetical core-meltdown sequences. The analyses consider the progression of core meltdown, containment response, and consequences to the public for many specific accident sequences within the categories of Loss of Coolant Accidents (LOCAs), ...
Radiological and toxicological consequences are calculated for 4 postulated accidents involving the Waste Feed Delivery (WFD) diluent addition systems. Consequences for the onsite and offsite receptor are calculated. This analysis contains technical information used to determine the accident ...
The MELT-III code for analysis of a Transient Overpower (TOP) accident in an LMFBR is briefly described, including failure criteria currently applied in the code. Preliminary results of calculations exploring failure patterns in time and space in the reac...
A computer model was developed and utilized for calculating the benefits of passenger protective breathing devices and other fire safety improvements based on an analysis of accidents involving fire occurring from 1966 to 1986. The results of exercising t...
The purpose of the Calculation documented here is to support bounding in-tank vehicle fuel fire accidents with organic solvent fire and flammable gas accidents in the Document Safety Analysis.
This document contains the calculations that support the accident analyses for accidents involving organic solvents. This work was performed to support the Basis for Interim Operation (BIO) and the Final Safety Analysis Report (FSAR) for Tank Waste Remediation Systems (TWRS).
This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Caustic Spray Leak. The calculations needed to quantify the risk associated with this accident scenario are included within.
An analysis of fuel rod behavior during reactivity initiated accidents is presented. The calculational approach is described, predictions are discussed and compared to data from the SPERT power excursion tests, and the sensitivity of maximum cladding temp...
This document quantifies the offsite radiological consequence of the bounding waste transfer leak accident for comparison with the 25 rem Evaluation Guideline established in DOE-STD-3009, Appendix A. The bounding waste transfer leak accident is a large pipe break into a pit. The calculation offsite dose does not challenge the ...
This paper develops a concrete situation witch is the search for an evacuation distance in case of a road accident implying a chlorine tank. The methodological aspect is how implementing uncertainty analysis in deterministic models with random parameters....
The Accident Analysis Handbook (AAH) covers four generic facilities: fuel manufacturing, fuel reprocessing, waste storage/solidification, and spent fuel storage; and six accident types: fire, explosion, tornado, criticality, spill, and equipment failure. These are the accident types considered to make major ...
The Savannah River Site (SRS) Safety Analysis Report (SAR) covering K reactor operation assesses a spectrum of design basis accidents. The assessment includes estimation of the dose consequences from the analyzed accidents. This report discusses the methodology used to perform the dose analysis reported in the SAR ...
Accident models play a critical role in accident investigation and analysis. Most traditional models
NASA Technical Reports Server (NTRS)
This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: HEPA Filter Failure - Exposure to High Temperature or Pressure. The calculations needed to quantify the risk associated with this accident scenario are included within.
This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report. HEPA Filter Failure - Exposure to High Temperature or Pressure. The calculations needed to quantify the risk associated with this accident scenario are included within.
This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Unplanned Excavation/Drilling in Pond/Ditch/Crib. The calculations needed to quantify the risk associated with this accident scenario are included within.
A comprehensive review of accident neutron dosimetry using blood and hair analysis was performed and is summarized in this report. Experiments and calculations were conducted at Oak Ridge National Laboratory (ORNL) and the University of Tennessee (UT) to ...
This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Mixing of Incompatible Materials - Tank Pressurization.The calculations needed to quantify the risk associated with this accident scenario are included within.
The objective of this paper is to discuss how Postaccident Heat Removal (PAHR) calculations interface with the earlier accident phases in overall mechanistic accident analyses, to briefly review the evolution of the transition phase as an important path i...
This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Natural Phenomena - High Wind. The calculations needed to quantify the risk associated with this accident scenario are included within.
The first section of this report describes the methodology and computational framework for the facility accident analysis for the EM PEIS. To demonstrate the interaction of the modules, a sample calculation is presented along with a chart of the data flow...
This document includes the calculations needed to quantify the risk associated with unmitigated and mitigated pressurized spray releases from tank farm transfer equipment inside transfer enclosures. The calculations within this document support the spray ...
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 ...
This document supports the development and presentation of the following accident scenario in the TWRS Final Safety Analysis Report: Leak from Railcar/Tank Trailer. The calculations needed to quantify the risk associated with this accident scenario are included within.
This document contains the loss-of-coolant accident analysis of the representative design for the Savannah River heavy water new production reactor. Included in this document are descriptions of the primary system, reactor vessel, and loss-of-coolant accident computer input models, the results of the cold leg and hot leg ...
Fission product release analysis code, RACPAC (Fission Product Release Analysis Code from Fuel Particle in Accident Condition), was developed to calculate fractional release from the core during accident conditions of High Temperature Gas-cooled Reactor. ...
Supplementary information is presented on the calculational methods, assumptions, and criteria employed by Combustion Engineering in the analysis of the design basis pipe rupture accident. (DG)
... The computer codes RELAP-3 for reactor system blowdown and THETAl-B for fuel element heatup were used to perform these calculations at a ...
Results of the previous one-dimensional thermal analysis of interim storage accidents are confirmed by more detailed two-dimensional calculations. Waste temperatures calculated for interim storage accidents are moderately sensitive to assumptions concerning canister spacing and are much less ...
The purpose of this calculation note is to provide the basis for evaporator dump consequence for the Tank Farm Safety Analysis Report (FSAR). Evaporator Dump scenario is developed and details and description of the analysis methods are provided.
The purpose of this calculation note is to provide the basis for criticality consequences for the Tank Farm Safety Analysis Report (FSAR). Criticality scenario is developed and details and description of the analysis methods are provided.
The purpose of this calculation note is to provide the basis forcriticality consequences for the Tank Farm Safety Analysis Report(FSAR). Criticality scenario is developed and details and description of the analysis methods are provided.
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 ...
The maximum credible accident (MCA) approach to accident analysis places an upper bound on the potential adverse effects of a proposed action by using conservative but simplifying assumptions. It is often used when data are lacking to support a more realistic scenario or when MCA calculations result in acceptable ...
The present work continues our effort to perform an integrated safety analysis for the HYLIFE-II inertial fusion energy (IFE) power plant design. Recently we developed a base case for a severe accident scenario in order to calculate accident doses for HYLIFE-II. It consisted of a total loss of coolant ...
This document contains the steady-state and loss-of-pumping accident analysis of the representative design for the Savannah River heavy water new production reactor. A description of the reactor system and computer input model, the results of the steady-state analysis, and the results of four loss-of-pumping ...
The RELAP5/MOD1 computer code was used in the analysis of a loss coolant accident (LOCA), postulated for Angra-2. The power plant was simulated through a division in control volumes and junctions suitable for a small break accident calculation. Initially ...
Radioactive afterheat is an important source term for the release of radionuclides in fusion systems under accident conditions. Heat transfer calculations are used to determine time-temperature histories in regions of interest, but the true source term needs to be the effective afterheat, which considers the transport of penetrating gamma rays. Without ...
Due to accident severity and the extent of claim payments commuting accidents are a significant expense factor in the German industry. Therefore the aim of the present study was the identification of risk factors for commuting accidents in a German chemical company. A retrospective analysis of commuting ...
PubMed
Radiological and toxicological consequences are calculated for 4 postulated accidents involving the Waste Feed Delivery (WFD) diluent addition systems. Consequences for the onsite and offsite receptor are calculated. This analysis contains technical infor...
