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...
National Technical Information Service (NTIS)
Light water reactor fuel behaviors under reactivity-initiated accident (RIA) conditions have been investigated at the Nuclear Safety Research Reactor (NSRR) utilizing uranium oxide fuel rods. Furthermore, the NSRR program will be initiating RIA tests for ...
An in-reactor experimental research on fuel behavior under reactivity initiated accident (RIA) conditions is being conducted in the Nuclear Safety Research Reactor (NSRR). The optical system in which a non-browning lens periscope is directly installed in ...
Chemical reactions between UO sub 2 fuel and Zircaloy-4 cladding material under reactivity initiated accident (RIA) conditions are described. Post-irradiation examination of the fuel rods, in the NSRR experiments, was made with an optical microscope and a...
In the Nuclear Safety Research Reactor (NSRR), inpile experiments have been conducted to study the fuel behavior under reactivity-initiated accident (RIA) conditions. The simulation of an RIA in the present NSRR operation is done by generating a sharp pul...
Pulse irradiation tests of irradiated fuel are performed in the Nuclear Safety Research Reactor (NSRR) to investigate the fuel behavior under Reactivity Accident Conditions (RIAS). The severity of the RIA is represented by energy deposition or peak fuel e...
Irradiation experiments were conducted at the Nuclear Safety Research Reactor (NSRR) to examine the effects of fuel rod support conditions on light water reactor fuel behavior during a reactivity initiated accident (RIA). Two rod-support conditions, (1) b...
This document describes the experiment operating specifications for the Reactivity Initiated Accident (RIA) Test RIA 1-4 to be conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory as part of the Nuclear Regulatory Commi...
This report presents experimental data for Test TS-2 which was the second test in a series of Reactivity Initiated Accident (RIA) condition test using pre-irradiated BWR fuel rods, performed at the Nuclear Safety Research Reactor (NSRR) in February, 1990....
This report presents experimental data for Test TS-1 which was the first in a series of tests, simulating Reactivity Initiated Accident (RIA) conditions using pre-irradiated BWR fuel rods, performed in the Nuclear Safety Research Reactor (NSRR) in October...
The fuels behavior research in PBF is directed towards providing a detailed understanding of the response of nuclear fuel assemblies to off-normal and hypothetical accident conditions. Single fuel rods and clusters of highly instrumented fuel rods are installed within a central test space of the PBF core for testing. The core can be operated in various ...
Energy Citations Database
The integrity of the reactor pressure vessel (RPV) head and reactor internals was assessed by means of fluid and fluid-structural coupled analyses to evaluate the water hammer phenomenon arising from postulated high burnup fuel failure under reactivity initiated accident (RIA) conditions. The fluid viscosity effect on the water column ...
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...
Experience from irradiation in PWRs has confirmed the M5{sup R} possesses all the properties required for upgraded operation including new fuel management approaches and high duty reactor operation. In this paper accident behavior is demonstrated through a comparison of M5{sup R} and Zircaloy-4 cladding behavior under RIA (Reactivity Insertion ...
Fuel behavior studies with simulated reactivity-initiated accident (RIA) conditions have been performed using Nuclear Safety Research Reactor (NSRR) since October 1975. This report describes the results obtained from January to June, 1980. 37 tests were c...
Results are presented from preliminary tests designed to investigate the behavior of preirradiated fuel rods under reactivity initiated accident (RIA) conditions. The tests were conducted in 1970 as part of the SPERT/Capsule Driver Core (CDC) program. The...
Fuel behavior studies under simulated reactivity-initiated accident (RIA) conditions have been performed in the Nuclear Safety Research Reactor (NSRR) since 1975. This report gives the results of experiments performed from April, 1989 through March, 1990 ...
In a light water reactor fuel, stress from pellet-cladding interaction (PCI) will have the possibility to cause stress corrosion cracking (PCI failure) under an environment of corrosive fission product ; line iodine. A pulse irradiation experiment by NSRR...
Series of pulse irradiation tests have been performed in the Nuclear Safety Research Reactor (NSRR) to investigate irradiated fuel rod performance under the Reactivity Initiated Accident (RIA) conditions. Five tests, called Tests TS-1 through TS-5, were c...
Fuel behavior studies in simulated reactivity initiated accident (RIA) conditions have been performed by utilizing Nuclear Safety Research Reactor (NSRR) since October, 1975. This report describes the results obtained from July to December, 1981. A total ...
Fuel behavior studies in simulated reactivity initiated accident (RIA) conditions have been performed by utilizing Nuclear Safety Research Reactor (NSRR) since October 1975. This report describes the results obtained from experiments performed from Januar...
Fuel behavior studies in simulated reactivity initiated accident (RIA) conditions have been performed by utilizing Nuclear Safety Research Reactor (NSRR) since October 1975. This report describes the results obtained from January through December, 1985. A...
Fuel behavior studies under simulated reactivity-initiated accident (RIA) conditions have been performed in Nuclear Safety Research Reactor (NSRR) since 1975. This report gives the results of experiments performed from January through December, 1986 and c...
Fuel behavior studies in simulated reactivity initiated accident (RIA) conditions have been performed by utilizing Nuclear Safety Research Reactor (NSRR) since October, 1975. This report describes the results obtained from January through December, 1983. ...
Fuel behavior studies in simulated reactivity initiated accident (RIA) conditions have been performed by utilizing Nuclear Safety Research Reactor (NSRR) since October, 1975. This report describes the results obtained from January through December, 1982. ...
Fuel behavior studies in simulated reactivity initiated accident (RIA) conditions have been performed by utilizing Nuclear Safety Research Reactor (NSRR) since October, 1975. This report describes the results obtained from January through December, 1984. ...
In a reactivity-initiated accident (RIA), a control rod ejection or drop causes a sudden increase in reactor power, which in turn deposits a large amount of energy into the fuel. The resulting thermal expansion and fission gas release loads the cladding into the plastic regime and may cause it to fail. In order to predict cladding survivability, there has ...
DOE Information Bridge
The safe containment of molten debris following a hypothetical core meltdown accident in a light water reactor depends on the postaccident distribution and freezing of the debris. The objective of the present work is to analyze the freezing of molten debris produced during a severe, in-pile reactivity initiated accident experiment, designated ...
During the last decade, the failure behavior of high-burnup fuel rods under a reactivity-initiated accident (RIA) condition has been a serious concern since fuel rod failures at low enthalpy have been observed. This has resulted in the reassessment of existing licensing criteria and failure-mode study. To address the issue, a ...
A study on post-accident core coolability of LWR is discussed based on the practical fuel failure behavior experienced in NSRR, PBF, PNS and others. The fuel failure behavior at LOCA, RIA and PCM conditions are reviewed, and seven types of fuel failure modes are extracted as the basic failure mechanism at accident ...
This report presents and discusses results from the final test in the Reactivity Initiated Accident (RIA) Test Series, Test RIA 1-4. Nine preirradiated fuel rods in a 3 x 3 bundle configuration were subjected to a power burst while at boiling water reacto...
The report presents and discusses the results from the Reactivity Initiated Accident (RIA) Test RIA 1-2 conducted in the Power Burst Facility. Four, individually shrouded, previously irradiated fuel rods were subjected to a power burst while at boiling wa...
Analyses, interpretations, and discussions of results from the Reactivity Initiated Accident (RIA) Test Series, Test RIA 1-1, conducted in the Power Burst Facility reactor are presented. Four light water reactor (LWR) type test fuel rods, two previously i...
Recorded test data are presented for the second of six planned tests in the Reactivity Initiated Accident (RIA) Test Series 1, Test RIA 1-2. This test, conducted at the Power Burst Facility, had the following objectives: (1) Characterize the response of p...
Reactivity insertion accident (RIA) limits have been under intense review by regulators since 1993 with respect to what should be the proper limit as a function of burnup. Some national regulators have imposed new lower limits while in the United States the limits are still under review. The data being evaluated with respect to RIA ...
This paper shows the numerical simulation study on the growth of the bubble in the transient pool boiling using MPS-MAFL method. The growth process of a bubble with the different initial radii is calculated in a high heat-flux and high subcooling condition expected in nuclear reactor core during RIA. The smaller initial radius is, the earlier the growth ...
The Reactor Safety Research Program of the Nuclear Regulatory Commission includes a series of transient experiments in the Power Burst Facility (PBF) to investigate the fuel failure modes and consequences of postulated Reactivity Initiated Accidents (RIA)...
Light water reactor (LWR) fuel rod behavior during transient experiments conducted in the Power Burst Facility is reviewed. The experiments examined simulated hypothetical reactivity initiated accidents (RIA) and power-cooling-mismatch (PCM) events. Fuel rod behavior calculated by the Fuel Rod Analysis Program-Transient (FRAP-T) is compared with the test ...
This paper is mainly dedicated to the development of an out-of-pile test reproducing the thermo-mechanical loading conditions encountered during the first stage of a Reactivity Initiated Accidents (RIA) transient, dominated by Pellet Clad Mechanical Interaction (PCMI). In particular, the strain-controlled clad loading under high strain ...
The High Burnup Cladding Performance program is being conducted at ANL to provide data in support of Loss-of-Coolant Accident (LOCA) and Reactivity-Initiated Accident (RIA) licensing criteria assessments for fuels at high burnup, as well as licensing crit...
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...
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 ...
Recorded test data are presented for Test RIA 1-1 of the Thermal Fuels Behavior Program Reactivity Initiated Accident Test Series I. This test, conducted at the Power Burst Facility, was designed to characterize the response of unirradiated and preirradia...
Specific aspects of irradiated fuel result from the increasing retention of gaseous and volatile fission products with burnup, which, under overpower conditions, can lead to solid fuel pressurization and swelling causing severe PCMI (pellet clad mechanical interaction). In order to assess the reliability of high burnup fuel under RIAs, experimental ...
NASA Astrophysics Data System (ADS)
To study the fuel behavior and to evaluate the fuel enthalpy threshold of fuel rod failure under reactivity initiated accident (RIA) conditions, a series of experiments using pulse irradiation capability of the Nuclear Safety Research Reactor (NSRR) has been performed. During the experiments with 50 MWd/kg U PWR fuel rods (HBO test ...
With the increased emphasis on establishing the presence or absence of drugs associated with aircraft accidents and the fact that fragmentation of tissue may be a problem in investigating these accidents, the need arises for a rapid, sensitive, and specific toxicologic means for detecting drugs that may be present in nanogram concentrations and when only ...
PubMed
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 conducted with coolant conditions typical of hot-startup ...
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 fuel behavior experimental program recently started in the PBF is being conducted ...
In this work were chosen the optimal conditions in order to diminish binding of the labelled prolactin with I-125 to the walls of the assay tubes used in the prolactin RIA-Kit of national production. We found out that the addition of tweed-20 (0.1%) to th...
The RIA 1-3 test would employ a square array of four pre-irradiated BWR rods to provide information on fuel failure modes and consequences of postulated Reactivity Initiated Accidents in power reactors. Calculations were done to: (1) predict R-O power dis...
... § 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...
Code of Federal Regulations, 2011
Radioimmunoassay (RIA) employing iodinated ligands represents a popular measurement method for small molecules due to its excellent sensitivity and specificity. Yet performing RIAs of large numbers of tubes remains a tedious laboratory chore due to the need to individually handle tubes multiple times. We here present a method in which conventional ...
The main subjects of the meeting were the discussion of regulatory background, integral tests and analysis, plant calculations, separate-effect test and analysis, concerning high burnup phenomena during RIA accidents in reactors, especially LWR, BWR and P...
With respect to the simulated reactivity initiated accident (RIA) experiments with pre-irradiated LWR type fuel rods at nuclear safety research reactor (NSRR), there were principally three technical difficulties which should be overcome: (1) Fabrication o...
This paper presents recent activity on control rod drop accident (CRDA) analyses in a typical BWR core and uses a best-estimated kinetics code, the kinetics version of SIMULATE (SIMULATE-K).
An understanding of the freezing of molten debris on cold core structures following a hypothetical core meltdown accident in a light water reactor (LWR) is of importance to reactor safety analysis. The purpose of the present investigation was to analyze the transient freezing of the molten debris produced in a severe reactivity initiated accident ...
An understanding of the freezing of molten debris on cold core structures following a hypothetical core meltdown accident in a light water reactor (LWR) is of importance to reactor safety analysis. The purpose of the present investigation was to analyze t...
The TREAT Facility was designed and built in the late 1950s at Argonne National Laboratory to provide a transient reactor for safety experiments on samples of reactor fuels. It first operated in 1959. Throughout its history, experiments conducted in TREAT have been important in establishing the behavior of a wide variety of reactor fuel elements under conditions predicted to ...
The Transient Reactor Test (TREAT) facility was designed and built in the late 1950s at Argonne National Laboratory (ANL) to provide a transient reactor for safety experiments on samples of reactor fuels. It first operated in 1959. Throughout its history, experiments conducted in TREAT have been important in establishing the behavior of a wide variety of reactor fuel elements under ...
An analysis is performed to determine the effect of disassembling the radial reflector of the TOPAZ-II reactor, following a hypothetical severe Reactivity Initiated Accident (RIA). Such an RIA is assumed to occur during the system start-up in orbit due to a malfunction of the drive mechanism of the control drums, causing the drums to ...
The Nuclear Safety Research Reactor(NSRR) in Japan Atomic Energy Research Institute (JAERI) is a modified TRIGA-ACPR(Annular Core Pulse Reactor) which was constructed in 1975 in order to investigate the fuel behavior mainly under reactivity initiated accident (RIA) conditions. This reactor generates very sharp pulse power with the ...
An analysis is performed to investigate the merits of using the TOPAZ-II safety drums for a backup control to prevent a reactivity excursion, stabilize the reactor, and achieve steady-state power operation, following a severe hypothetical reactivity initiated accident (RIA). Such an RIA is assumed to occur during the system start-up in ...
... Abstract : Radioimmunoassay and nitrocellulose filter-binding competition experiments were ... Competition RIA experiments verify the presence of a Z ...
DTIC Science & Technology
This thesis describes the development of a radioimmunoassay (RIA) for antidiuretic hormone (ADH) or vasopressin, which can be used for the quantitative measurement of the urinary excretion of the hormone in man during physiological and pathological condit...
... Osteocalcin Radioimmunoassay (RIA): Human osteocalcin concentrations in conditioned medium samples (1,3,5,7 days) were measured by ...
An experimental research program, named Nuclear Safety Research Reactor (NSRR) Program, has been progressing in Japan Atomic Energy Research Institute (JAERI) using a modified TRIGA-ACPR. This paper is prepared to describe the outline of the NSRR program. The purpose of the NSRR program is to examine the behaviors of fuel rods under various accidental conditions of power ...
Excessive oxidation, hydriding, and extensive irradiation damage occur in high-burnup fuel cladding, and as result, mechanical properties of high-burnup fuels are degraded significantly. This may influence the current fuel cladding failure limits for loss-of- coolant-accident (LOCA) situations, which are based on fuel cladding behavior for zero burnup. To avoid cladding ...
...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...
Code of Federal Regulations, 2010
The Ria de Vigo constitutes the southernmost ria of the Rias Bajas. The reconnaisance studies of this ria indicate a heterogeneous distribution of both terrigenous and carbonate sediments with a major axial deposit of cohesive sediments. These fine sediments are relatively rich in organic matter, particularly in ...
This report discusses the results from the Reactivity Initiated Accident Scoping Test conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Laboratory. Four unirradiated test fuel rods were subjected, one during each of the four te...
This report presents experimental data for Test TS-5 which was the fifth test in a series of Reactivity Initiated Accident (RIA) tests using pre-irradiated BWR fuel rods, performed in the Nuclear Safety Research Reactor (NSRR) in January, 1993. Test fuel ...
This report presents experimental data for Test TS-3 which was the third test in a series of Reactivity Initiated Accident (RIA) tests using pre-irradiated BWR fuel rods, performed in the Nuclear Safety Research Reactor (NSRR) in September, 1990. Test fue...
This report presents experimental data for Test TS-4 which was the fourth test in a series of Reactivity Initiated Accident (RIA) test using pre-irradiated BWR fuel rods, performed in the Nuclear Safety Research Reactor (NSRR) in January, 1991. Test fuel ...
The results of a reactivity-initiated accident experiment, designated RIA-ST-4, are discussed and analyzed with regard to molten fuel-coolant interaction (MFCI). In this experiment, extensive amounts of molten UO sub 2 fuel and zircaloy cladding were prod...
This paper discusses fission product release from light-water-reactor-type fuel rods to the coolant loop during design basis accident tests. One of the tests was a power-cooling-mismatch test in which a single fuel rod was operated in film boiling beyond failure. Other tests discussed include reactivity initiated accident (RIA) tests, ...
... 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 ...
NASA Website
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 extended use of Zircaloy cladding in light water reactors degrades its mechanical properties by a combination of irradiation embrittlement, coolant-side oxidation, hydrogen pickup, and hydride formation. The hydrides are usually concentrated in the form of a dense layer or rim near the cooler outer surface of the cladding. Utilizing plane-strain ring-stretch tests to approximate the loading ...
A field trial of an enzyme-linked immunosorbent assay (ELISA) for the detection of the hepatitis Be markers is reported. It is simple to perform, is designed to be read by eye and does not require any expensive apparatus. When compared with a commercially available RIA kit for the detection of the same markers, ELISA was shown to be as sensitive as RIA for ...
PubMed Central
The rias of Galicia in northwestern Spain are local areas of high primary production. In this article, the fluxes of organic and inorganic carbon and the processes of photosynthesis, remineralization, and sedimentation of particulate organic carbon in one of these, the ria of Vigo, are quantified using the box model method. In 1986 the mean photosynthesis ...
The technique of RIAs for indol alkaloids (ajmaline, ergotamine, ergocristine, ergometrine, and lysergic acid) is described, and applications for this RIA and the RIA for raubasine and serpentine are mentioned. The indol alkaloide RIAs are shown to be sui...
...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...
is used. Optimal conditions for the mini-RIA were established using two workup methods using multiple channel pipettors. Because the method is flexible with regard to assay workup, we predict setup, workup, centrifugation, and separation of anti- body�antigen complexes. For this reason
E-print Network
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...
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...
Epidermal growth factor (EGF), a polypeptide hormone originally discovered in the mouse submaxillary gland, stimulates growth in a variety of tissues in several species. This hormone has recently been identified in human urine. A homologous RIA for human EGF (RIA-hEGF) has been developed. In general, levels were similar to those recently reported using a ...
The region of the arginine--vasopressin (AVP) molecule critical for binding to the effective antibodies in a RIA has been localized to the vicinity of the Phe/sup 3/ position by using the cross-reaction in the assay between AVP and a number of its structural analogs. Binding seems to be almost independent of any direct contributions from components of the tripeptide tail of ...
A recombinant soluble version of the human high-affinity receptor for IgG, rh-FcgammaRIA or CD64A, was expressed in mammalian cells and purified from their conditioned media. As assessed by circular dichroism, size exclusion chromatography and dynamic light scattering, incubation of rh-FcgammaRIA at 37 degrees C resulted in ...
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...
New data from the continental shelf off the southwest of Galicia are presented. The objective of this study is to characterize the present seabed topography, geomorphology and surface sedimentary distribution of the three major Galician Rias (Arousa, Pontevedra and Vigo) and their adjacent continental shelf. For the performance of a detailed bathymetry, available echo sounder ...
The objectives of fuel safety research program at Japan Atomic Energy Agency (JAEA) are; to evaluate adequacy of present safety criteria and safety margins; to provide a database for future regulation on higher burnup UO{sub 2} and MOX fuels, new cladding and pellets; and to provide reasonably mechanistic computer codes for regulatory application. The JAEA program is comprised of ...
The established weekly monitoring of the oceanographic conditions at 37 oceanographic stations in Rias Baixas (NW Spain) was used to study the dissolved aromatic hydrocarbons (DAHs) and dissolved and dispersed aromatic hydrocarbons (DDPAHs) in the water column, after the Prestige oil spills. They were performed in situ with an ultraviolet fluorimeter (UVF) ...
The mathematical and statistical theory of radioimmunoassays (RIAs) has been used to develop a series of computer programs to optimize sensitivity or precision at any desired dose level for either equilibrium or nonequilibrium assays. These computer programs provide for the calculation of the equilibrium constants of association and binding capacities for antisera (parameters ...
The consequences of two upwelling events in mid- (MW) and late (LW) winter on biogeochemical and phytoplankton patterns were studied in the Pontevedra Ria and compared with the patterns measured under typical winter conditions and under a summer upwelling event. Thermohaline patterns measured during the mid-winter upwelling event (MW-up) revealed the ...
... National Park Factors that can contribute to visitor accidents Not relevant ...
NBII National Biological Information Infrastructure
... The identification of the true causes of hazardous failures and accidents of technical equipment is the necessary condition for developing and ...
This paper discusses fission product release from light-water-reactor-type fuel rods to the coolant loop during design basis accident tests. One of the tests was a power-cooling-mismatch test in which a single fuel rod was operated in film boiling beyond ...
A one-dimensional physical model was developed to study the transient freezing of the molten debris layer (a mixture of UO sub 2 fuel and zircaloy cladding) produced in a severe reactivity initiated accident in-pile test and deposited on the inner surface...
Types of accidents and violations were compared for 1701 drivers with chronic medical conditions known to the California Department of Motor Vehicles and 921 drivers not known to have medical conditions. Drivers without medical conditions were found to be...
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 experimentally known ...
An overview of the analysis of core-disruptive accidents is given. These analyses are for the purpose of understanding and predicting fast reactor behavior in severe low probability accident conditions, to establish the consequences of such conditions and to provide a basis for evaluating consequence limiting ...
The U.S. Nuclear Regulatory Commission is conducting an accident management research program that emphasizes the use of severe accident research to enhance the ability of plant operating personnel to effectively manage severe accidents. Hence, it is necessary to ensure that the plant instrumentation and information systems adequately ...
This paper describes the technical approach used in the Modal Study performed by the Lawrence Livermore National Laboratory to evaluate the level of safety provided during the shipment of spent fuel from nuclear power reactors. The evaluation is performed by calculating the responses of representative spent fuel casks to severe highway and railway accidents and the ...
The authors recently proposed a model for irradiation-induced recrystallization (grain subdivision) and swelling in UO{sub 2} fuels wherein the stored energy in the material is concentrated in a network of sink-like nuclei that diminish with dose due to interaction with radiation-produced defects. It is of considerable interest to explore the consequences of recrystallization on gas release during ...
...CONTINUED) PIPELINE SAFETY TRANSPORTATION OF HAZARDOUS... Annual, Accident, and Safety-Related Condition Reporting...prescribes requirements for periodic reporting and for reporting of accidents and safety-related...
Peracarid crustaceans inhabit many marine benthic habitats and are good indicators of environmental conditions. There is, however, a lack of information about diversity and distribution of peracarid crustaceans on the shallow subtidal sediments of the Galician rias. In the summer of 1997, 27 subtidal stations were sampled in the R�a de Ald�n, a ...
This paper presents a model for Pellet-Cladding Mechanical Interaction (PCMI) failure of LWR fuel during an RIA. The model uses the J-integral as a driving parameter to characterize the failure potential during PCMI. The model is implemented in the FRAPTRAN code and is validated by CABRI and NSRR simulated RIA test data. Simulation of PWR and BWR ...
Energy-absorbed-per-fission values during 30 to 40 millisecond transients were calculated for three Reactivity Insertion Accident (RIA) tests in the Power Burst Facility (PBF). The values obtained were 177.4 MeV/fission for four 5.7% enriched rods, 172.4 MeV/fission for a single 20% enriched rod, and 173.8 MeV/fission for a single 5.8% enriched rod. Energy ...
An analysis was performed to investigate the effect of disassembling the radial reflector of the TOPAZ-II space nuclear reactor following a postulated reactivity initiated accident (RIA). In this RIA, the control drums, starting in the full-in position, are assumed to run out at their maximum speed of 1.4[degrees]/s to their full-out ...
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.
...conditions, and circumstances and the cause or probable cause or causes of: all accidents involving civil aircraft, and certain public aircraft; highway accidents, including railroad grade-crossing accidents, the investigation of which...
...injuries, and property damage from traffic accidents. Most traffic accidents can be prevented. Investigation of motor vehicle accidents should examine all factors, operator status, vehicle condition, and supervisory control measures...
