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Severe accident core heatup transients in modular high temperature gas-cooled reactors without operating Reactor Cavity Cooling Systems

Description: The ultimate decay heat removal system for the current Modular High Temperature Gas-Cooled reactors is a completely passive natural convection air cooling loop. This paper considers an extremely remote accident scenario, where even this passive system fails, and heat rejection is only via a layer of thermal insulation to the reactor silo structure and the surrounding soil. The results show that even in this case the peak fuel temperatures remain well within safe limits. However, vessel and conc… more
Date: January 1, 1988
Creator: Kroeger, P. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Integral fast reactor safety features

Description: The Integral Fast Reactor (IFR) is an advanced liquid-metal-cooled reactor concept being developed at Argonne National Laboratory. The two major goals of the IFR development effort are improved economics and enhanced safety. In addition to liquid metal cooling, the principal design features that distinguish the IFR are: (1) a pool-type primary system, (2) an advanced ternary alloy metallic fuel, and (3) an integral fuel cycle with on-site fuel reprocessing and fabrication. This paper focuses on… more
Date: January 1, 1988
Creator: Cahalan, J. E.; Kramer, J. M.; Marchaterre, J. F.; Mueller, C. J.; Pedersen, D. R.; Sevy, R. H. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

The passive safety characteristics of modular high temperature gas-cooled reactor fuel elements

Description: High-Temperature Gas-Cooled Reactors (HTGR) in both the US and West Germany use an all-ceramic, coated fuel particle to retain fission products. Data from irradiation, postirradiation examinations and postirradiation heating experiments are used to study the performance capabilities of the fuel particles. The experimental results from fission product release tests with HTGR fuel are discussed. These data are used for development of predictive fuel performance models for purposes of design, lice… more
Date: January 1, 1988
Creator: Goodin, D.T.; Kania, M.J.; Nabielek, H.; Schenk, W. & Verfondern, K.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Root cause analysis at the Savannah River Plant

Description: Events (or near misses) provide important information about ways to improve plant performance. Any particular event may have several /open quotes/root causes/close quotes/ that need correcting to prevent recurrence of the event and, thereby, improve the safety of the plant. Also, by reviewing a large number of events, one can identify cause trends or /open quotes/generic concerns./close quotes/ A method has been developed at Savannah River Plant (SRP) to systematically evaluate events, identify… more
Date: January 1, 1988
Creator: Paradies, M & Busch, D
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Evaluation of station blackout accidents at nuclear power plants: Technical findings related to unresolved safety issue A-44: Final report

Description: ''Station Blackout,'' which is the complete loss of alternating current (AC) electrical power in a nuclear power plant, has been designated as Unresolved Safety Issue A-44. Because many safety systems required for reactor core decay heat removal and containment heat removal depend on AC power, the consequences of a station blackout could be severe. This report documents the findings of technical studies performed as part of the program to resolve this issue. The important factors analyzed inclu… more
Date: June 1, 1988
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A scoping study of fission product transport from failed fuel during N Reactor postulated accidents

Description: This report presents a scoping study of cesium, iodine, and tellurium behavior during a cold leg manifold break in the N Reactor. More detail about fission product behavior than has previously been available is provided and key parameters that control this behavior are identified. The LACE LA1 test and evidence from the Power Burst Facility Severe Fuel Damage tests are used to test the key model applied to determine aerosol behavior. Recommendations for future analysis are also provided. The pr… more
Date: January 1, 1988
Creator: Hagrman, D.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Probabilities of inherent shutdown of unprotected events in innovative liquid metal reactors

Description: The uncertainty in predicting the effectiveness of inherent shutdown in innovative liquid metal cooled reactors with metallic fuel results from three broad contributing areas of uncertainty: (1) the inability to exactly predict the frequency of ATWS events with potential to challenge the safety systems and require inherent shutdown; (2) the approximation of representing all such events by a selected set of ''generic scenarios''; and (3) the inability to exactly calculate the core response to th… more
Date: January 1, 1988
Creator: Mueller, C.J. & Wade, D.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Uncertainties in source term estimates for a station blackout accident in a BWR with Mark I containment

Description: In this paper, attention is limited to a single accident progression sequence, namly a station blackout accident in a BWR with a Mark I containment building. Identified as an important accident in the draft version of NUREG-1150 a station blackout involves loss of both off-site power and dc power resulting in failure of the diesels to start and in the unavailability of the high pressure injection and core isolation cooling systems. This paper illustrates the calculated uncertainties (Probabilit… more
Date: January 1, 1988
Creator: Lee, M.; Cazzoli, E.; Liu, Y.; Davis, R.; Nourbakhsh, H.; Schmidt, E. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 6, Decontamination and decommissioning, accident management, TMI-2

Description: This six-volume report contains 140 papers out of the 164 that were presented at the Fifteenth Water Reactor Safety Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 26-29, 1987. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. This report, Volume 6, discusses decontamination and decommissioning, ac… more
Date: February 1, 1988
Creator: Weiss, A. J.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Interfacing system LOCAs at PWRs (pressurized water reactors): A new assessment

Description: Interfacing system loss-of-coolant accidents (ISL) were first identified and analyzed in the Reactor Safety Study (RSS). ISLs were found to be significant contributors to the risk estimates for the presurized water reactor (PWR) analyzed in the RSS. Some evaluations of ISL sequences in subsequent studies have also found that their contribution to risk is also significant. ISLs are potentially important to risk because a direct path is opened from the damaged reactor core which bypasses the cont… more
Date: January 1, 1988
Creator: Bozoki, G.; Kohut, P. & Fitzpatrick, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Preliminary risks associated with postulated tritium release from production reactor operation

Description: The Probabilistic Risk Assessment (PRA) of Savannah River Plant (SRP) reactor operation is assessing the off-site risk due to tritium releases during postulated full or partial loss of heavy water moderator accidents. Other sources of tritium in the reactor are less likely to contribute to off-site risk in non-fuel melting accident scenarios. Preliminary determination of the frequency of average partial moderator loss (including incidents with leaks as small as .5 kg) yields an estimate of /app… more
Date: January 1, 1988
Creator: O'Kula, K.R. & Horton, W.H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

An analysis of risk reduction methods for interfacing system LOCAs at PWRs

Description: Interfacing system loss-of-coolant accidents (ISLs) refers to events where the integrity of the Reactor Coolant System (RCS) pressure boundary is breached through failure of isolation valves which separate a support system of lower design pressure. The overpressurization of the support system will affect its availability and may further affect the availability of various safety systems required to mitigate the accident. In addition, it may result in a scenario where primary coolant is directly … more
Date: January 1, 1988
Creator: Kohut, P.; Bozoki, G. & Fitzpatrick, R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Hypothetical air ingress scenarios in advanced modular high temperature gas cooled reactors

Description: Considering an extremely hypothetical scenario of complete cross duct failure and unlimited air supply into the reactor vessel of a modular high temperature gas cooled ractor, it is found that the potential air inflow remains limited due to the high friction pressure drop through the active core. All incoming air will be oxidized to CO and some local external burning would be temporarily possible in such a scenario. The accident would have to continue with unlimited air supply for hundreds of h… more
Date: January 1, 1988
Creator: Kroeger, P. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Behavior of metallic fuel in treat transient overpower tests

Description: Results and analyses are reported for TREAT in-pile transient overpower tests of margin to cladding failure and pre-failure axial expansion of metallic fuel. In all cases the power rise was exponential on an 8 s period until either incipient or actual cladding failure was achieved. Test fuel included EBR-II driver fuel and ternary alloy, the reference fuel of the Intergral Fast Reactor concept. Test pin burnup spanned the widest range available. The nature of the observed cladding failure and r… more
Date: January 1, 1988
Creator: Bauer, T. H.; Wright, A. E.; Robinson, W. R. & Klickman, A. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

A risk characterization of safety research areas for Integral Fast Reactor program planning

Description: This paper characterizes the areas of Integral Fast Reactor (IFR) safety research in terms of their importance in addressing the risk of core disruption sequences for innovative designs. Such sequences have traditionally been determined to constitute the primary risk to public health and safety. All core disruption sequences are folded into four fault categories: classic unprotected (unscrammed) events; loss of decay heat; local fault propagation; and failure of critical reactor structures. Eve… more
Date: January 1, 1988
Creator: Mueller, C. J.; Cahalan, J. E.; Hill, D. J.; Kramer, J. M.; Marchaterre, J. F.; Pedersen, D. R. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Licensee Event Report (LER) compilation for month of March 1988

Description: This monthly report contains Licensee Event Report (LER) operational information that was processed into the LER data file of the Nuclear Safety Information Center (NSIC) during the one-month period identified on the cover of the document. The LERS, from which this information is derived, are submitted to the Nuclear Regulatory Commission (NRC) by nuclear power plant licensees in accordance with federal regulations. Procedures for LER reporting for revisions to those events occurring prior to 1… more
Date: April 1, 1988
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Experience of TSTA (Tritium Systems Test Assembly) milestone runs with 100 grams-level of tritium

Description: The first loop operation tests of the Tritium Systems Test Assembly (TSTA) with 100 grams-level of tritium were performed at the Los Alamos National Laboratory (LANL) in June and July, 1987. The July run was resumption of the June run, which was halted because of a loss of cryogenic refrigerant in the hydrogen isotope separation system. 3 refs., 3 figs.
Date: 1988~
Creator: Anderson, J.L.; Bartlit, J.R.; Varlson, R.V.; Coffin, D.O.; Damiano, F.A.; Sherman, R.H. et al.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Investigation of fire at Council, Alaska: A release of approximately 3000 curies of tritium

Description: On September 6, 1987, about 6:00 a.m., a fire was discovered in the community building at Council, Alaska, where 12 radioluminescent (RL) light panels containing approximately 3000 Ci were stored. All of the tritium in the panels was released as a result of the fire. This report summarizes the recovery of the remains of the panels destroyed in the fire and investigations completed to evaluate the fire site for possible exposure of community residents or contamination by tritium release in the e… more
Date: April 1, 1988
Creator: Jensen, G.A. & Martin, J.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

What was learned in developing the 1987 Zion Federal Field Exercise that can be used in planning other emergency response exercises

Description: The second Federal Field Exercise (FFE-2) was held in conjunction with the 1988 full participation exercise at the Zion nuclear power plant. This three-day exercise focused on the evaluation of the Federal Response plan and the numerous interfaces of the Federal agencies with the offsite authorities and the utility. Because of the many unique aspects of this exercise and the large number of participants, the planning effort for this exercise was considerably more involved than routine exercises… more
Date: January 1, 1988
Creator: Weiss, B.H.; Adler, M.V.; Gant, K.S. (Nuclear Regulatory Commission, Washington, DC (USA). Office for Analysis and Evaluation of Operational Data & Oak Ridge National Lab., TN (USA))
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Uncertainty analysis of emergency cooling system flows

Description: The Emergency Cooling System (ECS) for SRP reactors is designed to provide core cooling for postulated incidents. Recently, tests were completed in L Reactor to better define pipeline and fitting loss coefficients that are needed to predict ECS flows. Because the existing flow data are primarily based on experimental data, an experimental uncertainty exists in those flows and respective loss coefficients. The uncertainty analysis and resulting uncertainties of the data are discussed in this rep… more
Date: January 1, 1988
Creator: Mcallister, Jr, J E
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A regulatory analysis on emergency preparedness for fuel cycle and other radioactive material licensees: Final report

Description: The question this Regulatory Analysis sought to answer is: should the NRC impose additional emergency preparedness requirements on certain fuel cycle and other radioactive material licensees for dealing with accidents that might have offsite releases of radioactive material. To answer the question, we analyzed potential accidents for 15 types of fuel cycle and other radioactive material licensees. An appropriate plan would: (1) identify accidents for which protective actions should be taken by … more
Date: January 1, 1988
Creator: McGuire, S.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Gearing Up for Safety: Motor Carrier Safety in a Competitive Environment

Description: This report contains the results of that analysis. A review of critical intergovernmental issues for the Department of Transportation and State Governments has been added to the basic questions about the adequacy of Federal standards and programs. During the course of the study, it became clear that the report would have to consider how policy is implemented, and consequently, the relationship between the Department of Transportation and the States, which have become important partners in Feder… more
Date: September 1988
Creator: United States. Congress. Office of Technology Assessment.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
captions transcript

[News Clip: Airplane Down]

Description: B-roll video footage from the KXAS-TV/NBC station in Fort Worth, Texas, to accompany a news story. This story aired at 6pm.
Date: December 6, 1988, 6:00 p.m.
Duration: 1 minute 01 second
Creator: KXAS-TV (Television station : Fort Worth, Tex.)
Item Type: Refine your search to only Video
Partner: UNT Libraries Special Collections
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