The systematics of the characteristics of twenty-one criticality accidents occurring in nuclear processing facilities of the Russian Federation, the United States, and the United Kingdom are examined. By systematics the authors mean the degree of consistency or agreement between the factual parameters reported for the accidents and the ...

Consequences of nuclear fuel cycle facility accidents can be evaluated using aerosol release factors developed at Pacific Northwest Laboratory. These experimentally determined factors are compiled and consequence assessment methods are discussed. Release ...

The behavior of nuclear facility ventilation systems subjected to both natural and man-caused accidents is being investigated. The purpose of the paper is to present a program overview and highlight recent results of the investigations. The program includes both analytical and experimental investigations. Computer codes for predicting ...

The whole-pin furnace system is a new in-cell experimental facility constructed to investigate how irradiated fuel pins may fail under potential reactor accident conditions. Extensive checkouts have demonstrated excellent performance in remote operation, ...

This paper describes a multilaboratory research program that is directed toward addressing many questions that analysts face when performing air cleaning accident consequence assessments. The program involves developing analytical tools and supportive experimental data that will be useful in making more realistic assessments of ...

Sandia National Laboratories is presently involved in several NRC-sponsored experimental projects to provide data that will help quantify the threat of hydrogen combustion during LWR accidents. One project, which employs several experimental facilities: is the Variable Geometry Experimental ...

Experimental results from six recent Power Burst Facility (PBF) reactivity initiated accident (RIA) tests are compared with data from previous SPERT, TREAT and NSRR programs. The RIA fuel behavior experimental program recently started in the PBF is being ...

... requirements for this facility include: penetration ... Descriptors : *UNDERGROUND FACILITIES, *ACCIDENTS, *UNDERGROUND STRUCTURES ...

Included are sections dealing with the following topics: (1) perspective and philosophy of fast reactor safety analysis; (2) status of accident analysis and experimental needs; (3) experiment and facility definitions; (4) existing in-pile facilities; (5) new facility options; and (6) data ...

Sandia National Laboratories is currently involved in a number of experimental projects to provide data that will help quantify the threat of hydrogen combustion during nuclear plant accidents. Several experimental facilities are part of the Variable Geometry Experimental System (VGES). The ...

The facility will operate at a power level of 30.4 Mw. Analysis of various operating accidents and postulated releases of radioactivity was made. Results of these general studies are the basis of a conclusion that the EOCR is not a significant hazard to off-site personnel. (J.R.D.)

In aerial gamma radiation survey for emergency response, the measurements of radiological distribution resulted from the nuclear facility accident are made over its surroundings from an accidental site to locations further from it, and the measuring level...

The safety of Pajarito Site critical assembly operations depends upon protection built into the facility, upon knowledgeable personnel, and upon good practice as defined by operating procedures and experimental plans. Distance, supplemented by shielding in some cases, would protect personnel against an extreme accident generating ...

This paper presents an overview of the results of the experimental program being conducted in the Power Burst Facility and the relationship of these results to certain safety and licensing issues. The safety issues that were addressed by the Power-Cooling-Mismatch, Reactivity Initiated Accident, and Loss of Coolant ...

Air cleaning system response to the stress of accident conditions are being investigated. A program overview and hghlight recent results of our investigation are presented. The program includes both analytical and experimental investigations. Computer codes for predicting effects of tornados, explosions, fires, and material transport are described. The ...

Experimental results from six recent Power Burst Facility (PBF) reactivity initiated accident (RIA) tests are compared with data from previous Special Power Excursion Reactor Test (SPERT), and Japanese Nuclear Safety Research Reactor (NSRR) tests. The RIA...

This paper presents results from a Los Alamos National Laboratory Engineering and Safety Analysis Group assessment of the worse-case design-basis accident associated with the Clinton P. Anderson Meson Physics Facility (LAMPF)/Weapons Neutron Research (WNR) Facility. The primary goal of the analysis was to quantify the ...

This paper presents results from a Los Alamos National Laboratory Engineering and Safety Analysis Group assessment of the worse-case design-basis accident associated with the Clinton P. Anderson Meson Physics Facility (LAMPF)/Weapons Neutron Research (WNR) Facility. The primary goal of the analysis was to quantify the ...

The General Electric Test Reactor is described and a summary of the facility safety evaluation is presented. The description includes the General Electric Test Reactor history; the Vallecitos Nuclear Center Site and area characteristics; the facility adequacy criteria; a detailed facility description; descriptions of radioactive waste ...

The Nuclear Safety Mission consists of a broad, integrated program of experimental and analytical studies designed to permit more accurate assessment of the consequences of accidents at Hanford nuclear facilities. Information obtained will assist in the design of facilities to further mitigate the consequences of ...

For several years, the US Nuclear Regulatory Commission has sponsored the development of methods for improving capabilities to analyze the effects of postulated accidents in nuclear facilities; the accidents of interest are those that could occur during nuclear materials handling. At the Los Alamos National Laboratory, this program has ...

The expansion of the experimental capabilities of the TREAT Upgrade (TU) reactor also tends to increase the potential risks associated with off-normal reactivity insertion incidents compared to the TREAT reactor. To provide adequate prtection for the public and the facility, while meeting experimenter's requirements, a ...

One of the most important uses of dose assessment models in response to accidents at nuclear facilities is to help provide guidance to emergency response managers for identifying, and mitigating, the consequences of an accident once the accident has been ...

A summary of studies conducted on the pressurizedwater reactor loss-of- coolant accident is presented, and an experimental safety program is proposed. The various phenomena involved in the loss-of-coolant accident, related research and development programs, assumptions currently used to predict the various physical ...

The International Thermonuclear Experimental Reactor (ITER) Program is performing accident analyses for ITER�s �Rapport Préliminaire de Sûreté� (Report Preliminary on Safety - RPrS) with a modified version of the MELCOR 1.8.2 code. The RPrS is an ITER safety document required in the ITER licensing process to obtain a �Décret Autorisation de ...

The International Thermonuclear Experimental Reactor (ITER) Program is performing accident analyses for ITER�s �Rapport Pr�liminaire de S�ret� (Report Preliminary on Safety - RPrS) with a modified version of the MELCOR 1.8.2 code. The RPrS is an ITER safety document required in the ITER licensing process to obtain a �D�cret Autorisation de ...

This document provides the toxicological dose caculations related to the toxic chemical releases from spill accidents at T Plant Facility.

This document provides the toxicological dose caculations related to the toxic chemical releases from spill accidents at T Plant Facility.

With careful organization and training of both plant and community health facilities the confusion of radiation accidents can be significantly decreased. Rational approaches to potential radiation accidents are described and discussed. (C.H.)

Two large-scale test facilities with capabilities for a wide range of safety related testing are described. These facilities, situated at Stern Labs. Inc. are being used to provide experimental data for demonstration and safety code verification of the characteristics of flashing water jets in fission reactor containments. The ...

A computer code (TRAC-PF1/MOD1) developed for predicting transient thermal and hydraulic integral nuclear steam supply system (NSSS) response was benchmarked. Post-small break loss-of-coolant accident (LOCA) data from a scaled, experimental facility, desi...

The construction of a critical assembly is proposed for determining the characteristics of the PWAC Na-cooled, heterogeneous aircraft reactor design. The experimental facility would be located at the CANEL site. The site meteorology, hydrology, geology, and topography are considered; the facility and critical assembly ...

The maximum and minimum transient and steady state limits of operation for the reactor are set forth. Detailed discussions are presented on the site and environmental factors, the containment vessel and its design basis, the reactor description and performance data, proposed experimental facilities, reactor facility operating ...

Descriptions and evaluations are included of modifications to be made to the VBWR installation to obtain information contributing to the development of safer, more efficient and more economical boiling-water reactor power plants. Sufficient changes are proposed that the accident analyses have of necessity changed from those of previous editions, but analyses of the ...

A matrix of eleven experiments on aerosol retention behaviour in submerged beds and supresion pools in water-cooled reactors under severe accident conditions has been performed, for these experiments, an intermediate scale, multi-purpose facility was set ...

Addendum C to the 30 Degree Sector Test Facility (30 SSTF) Experimental Task Plan defines the objectives, specific test conditions, and summarized test operating procedures for the transient loss of coolant accident (LOCA) simulation tests performed in th...

The reactor safety analysis group of Jozef Stefan Institute (IJS) has participated in analyses of International Standard Problem 27 (ISP-27), which was based on test 9.1 b performed at the BETHSY experimental facility (France). In addition, we realized the ISP-27 transient scenario in the analysis of a small-break loss-of-coolant ...

The Waste Receiving and Processing Facility Module 1 Auditable Safety Analysis analyzes postulated accidents and determines controls to prevent the accidents or mitigate the consequences.

The whole-pin furnace system is a new in-cell experimental facility constructed to investigate how irradiated fuel pins may fail under potential reactor accident conditions. Extensive checkouts have demonstrated excellent performance in remote operation, temperature control, pin breach detection, and fission gas handling. The system is ...

A brief review is presented of the U. S. effort, between fall 1969 and spring 1972, relating to evaluation of the behavior of the fuel and coolant in liquid-metal-cooled fast breeder reactors under accident conditions. The experimental work is centered largely around the Transient Reactor Test facility. Investigations of ...

All the pertinent information describing the Vallecitos Boiling Water Reactor contained in the first edition, amendments to the License Application, the results of analytical studies, and experimental data obtained during operation is consolidated. The maximum and minimum limits of reactor operation are set forth. Descriptions of the reactor, the ...

Accidents and potential accidents involving plutonium in processing facilities and accidents are briefly reviewed. Data available regarding plutonium aerosol released are used to access the release of plutonium aerosols in potentially serious accidents, a...

Consistent methodology should be adopted in accident analyses sections of SARs. These accident sections should describe both consequence and risk from potential accidents that could occur in a facility being assessed. These analyses should consider three ...

The Accident Analysis in the Safety Analysis Report (SAR) for the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) has recently undergone an upgrade. Non-reactor SARs at SRS (and other Department of Energy (DOE) sites) use probabilistic techniques to assess the frequency of accidents at their ...

During the 1970s and early 1980s, the Oak Ridge National Laboratory (ORNL) operated large out-of-reactor experimental facilities to resolve thermal-hydraulic safety issues in nuclear reactors. The fundamental research ranged from material mechanical behavior of fuel cladding during the depressurization phase of a loss-of-coolant ...

During the 1970s and early 1980s, the Oak Ridge National Laboratory (ORNL) operated large out-of-reactor experimental facilities to resolve thermal-hydraulic safety issues in nuclear reactors. The fundamental research ranged from material mechanical behavior of fuel cladding during the depressurization phase of a loss-of-coolant ...

The SMART is an integral type reactor with new innovative design features aimed at achieving a highly enhanced safety and improved economics. This paper focuses on the thermal hydraulic experimental program for the development of SMART. Thermal hydraulic responses for the transient operations of the SMART-P are experimentally investigated by using an ...

A Criticality Alarm System is normally designed to detect immediately the minimum accident of concern. This report covers the methodology to establish a different minimum accident of concern developed for shielded facilities and applied to a case of the canyon sump excursion in a Savannah River Site facility.

... to render the facility non-responsive ... COMPONENTS, OVERSEAS, UNDERGROUND, ACCIDENTS ... STATES, MILITARY FACILITIES, DENSITY, ...

The Transient Reactor Analysis Code (TRAC) is being developed at the Los Alamos National Laboratory to provide advanced best-estimate predictions of postulated accidents in light-water reactors. TRAC-PD2, the latest publicly released version of the code, is currently being tested against small-break and other transients in experimental ...

This paper discusses the role the Loss-of-Fluid Test (LOFT) Experimental Program has played and will play in addressing licensing issues of interest to the US Nuclear Regulatory Commission (NRC), nuclear steam supply system vendors, and utility power companies. The LOFT facility is an operating, prototypically scaled pressurized water reactor (PWR) system ...

In this paper the experimental response of ex-core neutron detectors during both actual and simulated loss-of-coolant accidents (LOCAs) at a pressurized water reactor are analyzed to determine their cause. Various analytical techniques are used to reproduce the ex-core detector response during large-break LOCAs. These techniques include both discrete ...

This report discusses a radiation exposure accident of personnel at the Hanford production reactor facilities.

... STOCKPILES, HAZARDS, CHEMICALS, ARMY FACILITIES, SUPPLY DEPOTS, LIMITATIONS, ACCIDENTS, STABILITY, CHEMICAL ORDNANCE ...

In a reprocessing facility where nuclear fuel solutions are processed, one could observe a series of power peaks, with the highest peak right after a criticality accident. The criticality alarm system (CAS) is designed to detect the first power peak and warn workers near the reacting material by sounding alarms immediately. Consequently, exposure of the ...

A large experimental in-pile program has been set up at the PHEBUS facility to investigate the actual behavior of .8 m active height, 25-rod PWR-type pressurized fresh fuel bundles under typical accident conditions. The program consists of four stages. St...

Experimental investigations into the interface reaction between a steam atmosphere and a stagnant sodium pool have been conducted at the General Electric San Jose Test Facility. The objectives of the tests were to create worst case accident situations and evaluate the consequences with respect to the design of LMFBR Steam Generators. ...

ON NUCLEAR PHYSICS LABORATORY AT CANEL. The critical experiment facility at CANEL is described. Information of the mature of experimental assemblies and operations is included. Safety features of the building, equipment, and operations are pointed out. Possible accidents and the resulting hazards to surrounding areas ...

Two experiments, DCH-3 and DCH-4, were performed at the Surtsey test facility to investigate phenomena associated with a high-pressure melt ejection (HPME) reactor accident sequence resulting in direct containment heating (DCH). These experiments were per...

Operating specifications for the Semiscale Small Break Test Series are presented. This series of tests will be conducted in the Semiscale Mod-3 test facility to investigate the thermal-hydraulic phenomena resulting from a small break loss-of-coolant accid...

The report contains the analysis, findings and recommendations as determined by the National Transportation Safety Board, applicable to a Boeing 707's crash during a simulated three-engine, missed approach. The flight originated at John F. Kennedy Interna...

Simplified evaluation models are developed at the Japan Atomic Energy Research Institute (JAERI) to predict the first peak power, energy, and total fission numbers during a criticality accident for design and installation of a criticality alarm system and for quick response with measures to avoid excessive exposure of the general public. These models were first derived in ...

Consistent methodology should be adopted in accident analyses sections of SARs. These accident sections should describe both consequence and risk from potential accidents that could occur in a facility being assessed. These analyses should consider three general classes of accidents; they are ...

Several advanced nuclear plant concepts are characterized by the use of innovative cooling systems that remove the heat released inside the containment following a hypothetical accident, such as a loss-of-coolant accident, through passive heat transfer mechanisms. The design and installation of a localized passive containment cooling system (PCCS) inside a ...

This report revision incorporates new experimental evidence regarding AP600 behavior during small break loss-of-coolant accidents. This report documents the results of Phenomena Identification and Ranking Table (PIRT) efforts for the Westinghouse AP600 reactor. The purpose of this PIRT is to identify important phenomena so that they may be addressed in ...

The General Electric Test Reactor and experimental facility designs, operations, and evaluations are described. Topics covered include: reactor core assembly, reactor vessel, control rods and drives, reactor performance, instrumentation, shielding, containment building and arrangement, reactor cooling system, ventilation, utilities, mechanical and ...

The Zero Power Reactor facility is an experimental system for exponential and miniature lattice studies in conjunction with the TRlGA, MK II Reactor and critical experiments. The reactor has light water moderated cores with high density, low enrichment Al clad UO/sub 2/ fuel. The maximum credible accident for this core was ...

This paper presents a simple, systematic approach for developing accident scenarios using generic accident types. Result is a necessary and sufficient set of accident scenarios that can be used to establish the safety envelope for a facility or operation. Us of this approach along with the methodology of ...

Some years ago, within the framework of the study for the International Thermonuclear Experimental Reactor (ITER), ENEA assessed the RELAP5 code capability to simulate Helium cooled systems on the experimental data provided by the helium facility HEFUS3 (Brasimone, Italy). This activity allowed acquiring a certain experience on the ...

Single-phase natural circulation heat removal experiments are described. The natural-circulation facility is composed of four loops with a U-tube heat exchanger in each loop. A complete description of the facility is included. Results are given for the thirty experimental conditions tested, including: one to four active loops, three ...

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 151, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant ...

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 103, which is part of the ORNL Pressurized-Water Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant ...

The Nuclear Safety Mission consists of seven programs of broad integrated experimental and analytical studies designed to answer long-standing nuclear safety questions and thus assist in providing safeguards against nuclear accidents. It will provide data leading to the technical bases for controlling the consequences of postulated nuclear incidents. ...

... ENVIRONMENT IN THE EXPERIMENTAL FACILITIES OF THE ... Laboratories' Diamond Ordnance Radiation Facility. ... at a reactor power level of 250 ...

Video describing the National Risk Management Research Laboratory's Experimental Streams Facility....

EXPERIMENTAL FACILITY FOR MEASURING THE IMPACT OF ENVIRONMENTAL NOISE AND SPEAKER VARIATION ON SPEECH-TO- ...

... EXPERIMENTAL AERODYNAMIC FACILITIES OF THE AERODYNAMICS RESEARCH AND CONCEPTS ASSISTANCE BRANCH Miles C. Miller ...

The SL-1'' critioality accident provided an opportunity for atomic energy installations to examine their capabilities and facilities for handling such an accident. It became apparent to Hanford personnel that they were unprepared for such an occurrence and corrective measures were initiated. The resulting ...

... EXTENSIVE STUDIES WERE CONDUCTED ON LOCAL AND BULK SODIUM BOILING PHENOMENA AND THE EXPERIMENTAL RESULTS ...

Language: English ...

In this paper we present verification results of the BAGIRA code that was performed using data from integral thermal-hydraulic experimental test facilities as well as data obtained from operating nuclear power plants. BAGIRA is a three-dimensional numerical best-estimate code that includes non-homogeneous modeling. Special consideration was given to the ...

Japan Atomic Energy Research lnstitute has been making experiments on the loss of coolant accident in water-cooled reactor, maximum credible accident. The experiment are called ROSA program ''. Sumitomo Shipbuilding & Machinery Co., Ltd. designed and constructed facilities for experiments in 1970. The ...

...false How must I notify BLM of accidents occurring at my utilization facility...15 How must I notify BLM of accidents occurring at my utilization facility...You must orally inform us of all accidents that affect operations or...

Key results relating to emergency core cooling (ECC) behavior during the LOFT nonnuclear tests are discussed. LOFT test results are compared with results from counterpart experiments performed in the Semiscale facility to evaluate the scaling. Experimental results are also compared with pretest analytical model predictions made with the RELAP/MOD5 computer ...

Oct 8, 1996 ... Hazardous Waste Accidents (401 SDI Group): Definition: Number of accidents in hazardous waste handling facilities that released waste into ...

...does not set forth Federal agency responsibilities or capabilities for responding to an accident at a fixed nuclear facility or a transportation accident involving radioactive materials. These responsibilities are addressed in the...

...planning and preparedness activities. Assignments in this part are applicable to radiological accidents at fixed nuclear facilities and transportation accidents involving radioactive...

In-reactor, safety experiments performed in the Sodium Loop Safety Facility (SLSF) rely on comprehensive posttest examinations (PTE) to characterize the postirradiation condition of the cladding, fuel, and other test-subassembly components. PTE information and on-line instrumentation data, are analyzed to identify the sequence of events and the severity of the ...

Powder blenders are used in nuclear fuel fabrication facilities to blend dry low-enriched uranium (LEU) oxide powder to achieve uniform physical and chemical characteristics as required by product and process specifications. Blenders rely principally on moderation control for nuclear criticality safety and are, therefore, subject to criticality reviews since an inadvertent ...

The FIRAC computer code predicts fire-induced transients in nuclear fuel cycle facility ventilation systems. FIRAC calculates simultaneously the gas-dynamic, material transport, and heat transport transients that occur in any arbitrarily connected network system subjected to a fire. The network system may include ventilation components such as filters, dampers, ducts, and ...

The 2D/3D Program is a multinational (Germany, Japan, and the United States) experimental and analytical nuclear reactor safety research program having as its main purpose the investigation of multidimensional thermal-hydraulic behavior during the refill and reflood phases of loss-of-coolant accidents (LOCAs) in pressurized water reactors (PWRs). The ...

An experimental program at the University of Pisa provides specific data for the evaluation of heat and mass transfer by falling film evaporation. The problem is addressed primarily because of its relevance to the study of the behavior of passive containment cooling systems in simplified pressurized water reactors. In these plants, after an accident that ...

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 MELCOR Accident Consequence Code System (MACCS) has been applied to the radiological consequence assessment of potential accidents from a non-reactor nuclear facility. MACCS has been used in a variety of applications to evaluate radiological dose and ...

This report describes the 11 year medical course of Harold R. McCluskey, a Hanford nuclear chemical operator, who, at age 64, was involved in an accident in an americium recovery facility in August 1976. As a result of the accident, he was heavily contami...

The Department of Energy has developed new capabilities to predict how an accident event would spread through a facility. These capabilities arose as a part of the development of a future generation accident code - CONACS. They can be used to predict the ...

Dose calculation procedures to be used in the event of a truck transportation accident involving radioactive waste being shipped from a TVA facility. Two types of accidents are considered: one involving fire, and one involving a spill of packaged waste an...

Cheap and clean energy can be supplied with nuclear power plant whose accident probability is very low comparing with that of the other industrial facilities. However, the consequences of severe accident of nuclear power plant may result in a critical imp...

The risks of building related home accidents may be reduced by planning, designing and constructing safe buildings. European regulations and standards regarding the safety of buildings, building features and facilities are described in this report. The re...

The experimental system and types of test specimens as well as safety features of the system are described. Descriptions of the possible accidents, including the maximum credible accidents are analyzed. ( auth)

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 ...

Thermal-Hydraulic Test Facility (THTF) test series 3.07.9 was conducted by members of the Oak Ridge National Laboratory Pressurized-Water Reactor (ORNL-PWR) Blowdown Heat Transfer (BDHT) Separate-Effects Program on September 11, September 18, and October 1, 1980. The objective of the program is to investigate heat transfer phenomena believed to occur in PWRs during ...

Thermal-Hydraulic Test Facility (THTF) Test 3.05.5B was conducted by members of the ORNL PWR Blowdown Heat Transfer Separate-Effects Program on July 3, 1980. The objective of the program is to investigate heat transfer phenomena believed to occur in PWRs during accidents, including small and large break loss-of-coolant accidents. Test ...

Reduced instrument responses are presented for Thermal-Hyraulic Test Facility (THTF) Test 3.06.6B. This test was conducted by members of the Oak Ridge National Laboratory Pressurized-Water-Reactor (PWR) Blowdown Heat Transfer (BDHT) Separate-Effects Program on August 29, 1980. The objective of the program was to investigate heat transfer phenomena believed to occur in ...

This document presents a description of the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory and briefly describes a number of experimental methods and designs of test trains used in past programs and planned for new programs to study the behavior of light water reactor fuel under conditions ranging from normal to severe ...

Experimental programs carried-out in integral test facilities are relevant for validating the best estimate thermal-hydraulic codes(1), which are used for accident analyses, design of accident management procedures, licensing of nuclear power plants, etc. The validation process, in fact, is based on well designed ...

TRAC is a best-estimate, multidimensional, nonequilibrium computer code intended for the analysis of loss-of-coolant accidents (LOCA's) in light water reactors. TRAC-PD2 is the third, detailed, pressurized water reactor version of the code. The TRAC code is modular both by components and by function. That is, vessels, pipes, pumps, etc. can be coupled together in any ...

In present German nuclear power plants, safety is enhanced by prescription of preemptive measures and accident mitigation measures. If preemptive measures (e.g. backfitting, improved safety procedures) should fail, mitigative procedures are foreseen to take credit of all safety-related systems available on site. As usual in daily life, no guarantee of complete success of ...

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

The TRAC-BD1/MOD1 version of the computer code provides a best-estimate analysis capability for analyzing the full range of postulated accidents in boiling water reactor (BWR) systems and related experimental facilities. This version provides a consistent and unified analysis capability for analyzing all areas of a large or small break ...

This report was prepared at the request of the President's Commission on the Accident at Three Mile Island to provide the members of the Commission with some insight into the nature and significance of accidents that have occurred at nuclear reactor facilities in the past. Toward that end, this report presents a brief ...

...2010-07-01 false With what accident and fire prevention standards must Federal...MANAGEMENT Facility Management Accident and Fire Prevention § 102-74.355 With what accident and fire prevention standards must...

...2009-07-01 false With what accident and fire prevention standards must Federal...MANAGEMENT Facility Management Accident and Fire Prevention § 102-74.355 With what accident and fire prevention standards must...

Steam generator tube rupture (SGTR) incidents, such as those, which occurred in various operating pressurized, water reactors in the past, are serious operational concerns and remain among the most risk-dominant events. Although considerable efforts have been spent to understand tube degradation processes, develop improved modes of operation, and take preventative and corrective measures, SGTR ...

After code damage during a severe accident in a nuclear reactor, the degraded core has to be cooled down and the decay heat should be removed in order to cease the accident progression and maintain a stable state. The cooling of core melt is divided into ...

This paper summarizes experiments on creep rupture of reactor pressure vessel (RPV) lower heads under the thermal and pressure loads of a core meltdown accident. Lower head failure (LHF) is of importance to accident assessment and accident management.

The report documents an investigation into the feasibility of using accident data to derive estimates of the rate at which errant vehicles unintentionally encroach into the roadside on level, tangent sections of two-lane rural roads. In addition, issues r...

The response of the pressure-suspension containment system of Mark I boiling-water reactors to a loss-of-coolant accident (LOCA) is being studied. This response is a design basis for light-water nuclear reactors. Part of the study is being carried out on a /sup 1///sub 5/-scale experimental facility that models the pressure-suppression ...

As a result of the Three Mile Island Unit-2 (TMI-2) accident, the Nuclear Regulatory Commission has initiated a severe fuel damage test program to evaluate fuel rod and core response during severe accidents similar to TMI-2. The first test of Phase I of this series has been successfully completed in the Power Burst Facility at the ...

The upgrading of the Transient Reactor Test (TREAT) Facility at ANL-Idaho has been designed to provide additional experimental capabilities for the study of core disruptive accident (CDA) phenomena. In addition, a programmable Automated Reactor Control System (ARCS) will permit high-power transients up to 11,000 MW having a controlled ...

A description of the EOCR is presented in which safety and accident analyses are included. The EOCR is a 40-Mw facility designed and constructed to develop information in the field of organic reactor technology. Results of analyses show that the system is stable under normal conditions and that its instrumentation is able to detect departures ...

Argonne National Laboratory (ANL) conducts experimental work on the development of waste forms suitable for several types of spent fuel at its facility on the Idaho National Engineering and Environmental Laboratory (INEEL) located 48 km West of Idaho Falls, ID. The objective of this paper is to compare the offsite radiological consequences of hypothetical ...

Argonne National Laboratory has proposed an experimental reactor facility known as the Zero Power Plutonium Reactor, ZPPR. As much as 3,000 kilograms of plutonium may be in the facility at one time. Therefore, the containment of heavy-element particles in event of a major accident is a primary concern in the safety ...

For presentation at International Atomic Energy Agency Symposium on Reactor Safety, Vienna, Austria, May 14The Westinghouse Testing Reactor (WTR), a privately owned 60 megawatt tank type reactor, underwent a fuel element failure on April 3, 1960. A meltdown of one fuel element occurred causing the spread of fission products through the reactor cooling system. There were no ...

During the past years, a number of reduced-scale test facilities have been constructed to investigate the physical phenomena of transients or accidents occurring in nuclear power plants. Since the behavior of a nuclear power plant is complicated, it is quite impossible for a small-scaled facility to simulate all the physical phenomena ...

The purpose of the test program was to determine the effect of cladding surface thermocouples on time-to-critical heat flux (CHF) under blowdown conditions similar to those in the Loss-of-Fluid Test (LOFT) facility during a Loss-of-Coolant Experiment (LOCE). Previous steady state CHF tests indicated that cladding surface thermocouples reduce the CHF over the pressure range of ...

A major area of interest to reactor safety technology is the prediction of actual vapor generation rates under conditions of thermal nonequilibrium as would be encountered during a loss-of-coolant accident (LOCA) in a light water reactor. In support of the development of advanced codes dealing with LOCA induced flashing, analytical models of the nonequilibrium vapor generation ...

New design of nuclear power plant with pressurized water reactor entitled 'NPP-2006' is under progress in Russia. It is evolutionary type of design based on existing NPP with VVER-1000 reactors. Intensive thermal-hydraulic experimental activities support design development. They are aimed at increasing of NPP safety and efficiency. Integral test ...

This preliminary preclosure radiological safety analysis assesses the scenarios, probabilities, and potential radiological consequences associated with postulated accidents in the underground facility of the potential Yucca Mountain repository. The analys...

During the past quarter century, the development of commercial nuclear power with its supporting fuel cycle facilities has been associated with a record of nuclear safety which has in general been excellent. A potential for a seriuos accident does arise, ...

Detailed analysis of massive water ingress accidents in high temperature reactors supposes a numerical simulation of the whole facility behaviour. For the AVR-reactor such a model was developed to describe both the graphite corrosion processes and the acc...

Hazardous radioactive materials can be released into the atmosphere by accidents at nuclear power plants, fuel processing facilities, and other facilities, and by transportation accidents involving nuclear materials. In addition, the post-cold-war prolife...

The Reactivity Initiated Accident (RIA) test series is being conducted in the Power Burst Facility (PBF) to provide information on nuclear fuel rod behavior during postulated accidents involving sudden rapid transients in power reactors. During a tyical R...

By the use of an American statistic of accidents on roads the risk of body burden is estimated resulting from the transport of radioactive wastes to the central collection, conditioning and storage facilities in Seibersdorf. It is shown that the risk of t...

A study was made to assess nuclear criticality safety in DOE Facilities and to assess the effects of various types of possible improvements. The accident statistics in DOE operations show that the fatalities caused by Nuclear Criticality accidents are sma...

A risk-based logic model is suggested as an appropriate basis for better predicting accident progression and ensuing source terms to the environment from process upset conditions in complex chemical process facilities. Under emergency conditions, decision...

... facilities available for commercial use - establishing liability insurance requirements - acting ... of the report on the Challenger accident, the President ...

... event of a larger accident, the physical ... facility regulated by the Nuclear Regulatory Commission. ... Protection Program Technical Assistance Visits to ...

Astronaut Participation in Neutral Buoyancy Operations ..... embolism and other barotoma accidents. a. Licensed Physician. ...

Mayak Production Association (Mayak PA) in the Southern Ural is the first Russian nuclear facility of plutonium production for weapons. Due to the lack of knowledge and experience in operating nuclear facilities, 19 radiation accidents including criticality accidents occurred and 59 individuals developed acute ...

... data collected immediately after the accident and an evaluation ... LOGISTICS, MILITARY FACILITIES AND SUPPLIES RADIATION POLLUTION AND ...

... the need for site remediation, and to ... AIR FORCE FACILITIES, *NUCLEAR WARHEADS, *ACCIDENT ... JERSEY, MAPS, INSTALLATION, HUMANS ...

... TEST FACILITIES, EXPLOSIONS, RISK MANAGEMENT, ACCIDENTS, RISK ANALYSIS, BUILDINGS, MANUFACTURING, SYMPOSIA, FRANCE. ...

... RISK, *DEMILITARIZATION, ACCIDENTS, ARMY, ARMY FACILITIES, CHEMICAL AGENTS, CHEMICALS, DISPOSAL, EARTHQUAKES, ERRORS ...

... HIGH EXPLOSIVES, SHOCK WAVES, LOADS(FORCES), STATE OF THE ART, ACCIDENTS, MILITARY FACILITIES, LITERATURE SURVEYS. ...

The Rig of Safety Assessment (ROSA) III facility is a volumetrically scaled (1/424) boiling water reactor (BWR) system with an electrically heated core designed for integral loss-of-coolant accident (LOCA) and emergency-core-cooling-system (ECCS) tests. Experimental results obtained so far confirm that the severest single failure ...

The experience in the past 7 years to improve the shielding and radiation control systems at the Los Alamos Meson Physics Facility (LAMPF) and the Manuel Lujan Jr. Neutron Scattering Center (LANSCE) provides important lessons for the design of radiation control systems at future, high beam power proton accelerator facilities. Major issues confronted and ...

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 to model aerosol ...

Accident Prevention Federal Facilities Restoration and Reuse Underground Storage Tanks Resource and Conservation Recovery Act Superfund Additional FFRRO Information: FFRRO...

This safety analysis report describes the Fourth Calcined Solids Storage Facility and presents the results of a safety evaluation of the facility including a design basis accident. The Idaho Chemical Processing Plant (ICPP) is a multi-purpose facility for...

The Stockpile Stewardship Program (SSP) is a single, highly integrated technical program for maintaining the safety and reliability of the U.S. nuclear stockpile. The SSP uses past nuclear test data along with future non-nuclear test data, computational modeling and simulation, and experimental facilities to advance understanding of nuclear weapons. It ...

The TREAT facility at the Argonne National Laboratory site in the Idaho National Engineering Laboratory is being upgraded to provide capabilities for fast-reactor-safety transient experiments not possible at any other experimental facility. Principal TREAT Upgrade (TU) goal is provision for 37-pin size experiments on energetics of ...