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in subjects: "210100 -- Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled"

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Chemistry of fission product iodine under nuclear reactor accident conditions

The radioisotopes of iodine are generally acknowledged to be the species whose release into the biosphere as a result of a nuclear reactor accident is of the greatest concern. In the course of its release, the fission product is subjected to differing chemical environments; these can alter the physicochemical form of the fission product and thus modify the manner and extent to which release occurs. Both the chemical environments which are characteristic of reactor accidents and their effect in … more

Date: January 1, 1986

Creator: Malinauskas, A.P. & Bell, J.T.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Interim reliability evaluation program, Browns Ferry 1

Probabilistic risk analysis techniques, i.e., event tree and fault tree analysis, were utilized to provide a risk assessment of the Browns Ferry Nuclear Plant Unit 1. Browns Ferry 1 is a General Electric boiling water reactor of the BWR 4 product line with a Mark 1 (drywell and torus) containment. Within the guidelines of the IREP Procedure and Schedule Guide, dominant accident sequences that contribute to public health and safety risks were identified and grouped according to release categorie… more

Date: January 1, 1981

Creator: Mays, S.E.; Poloski, J.P.; Sullivan, W.H.; Trainer, J.E.; Bertucio, R.C. & Leahy, T.J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Nuclear proliferation and civilian nuclear power. Report of the Nonproliferation Alternative Systems Assessment Program. Volume V. Economics and systems analysis

This NASAP assessment considers the economics of alternative nuclear reactor and fuel-cycle systems in the light of possible patterns of uranium supply and energy demand, as well as the economic implications of improvng the proliferation resistance of the various systems. The assessment focuses on the costs of alternative nuclear technologies and the possible timing of their implementation, based on their economic attractiveness.

Date: June 1, 1980

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Implementation and application of RCP system at BNL

The implementation of the RCPO1 Monte Carlo system at the Brookhaven National Laboratory Central Scientific Computing Facility is discussed. Initial benchmarking experience and an LWR core physics application will be described.

Date: January 1, 1982

Creator: Eisenhart, L.D. & Todosow, M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Compare containment subcompartment analysis code evaluation. [PWR; BWR]

Nuclear power plant subcompartment analyses are required to determine the containment pressure distribution that might result from a loss-of-coolant accident. The pressure distribution is used to calculate structural and mechanical design loads. The COMPARE code is used widely to perform subcompartment analysis. However, several simplifying assumptions are utilized to facilitate solution of the complex transient, two-phase, multidimensional flow problem. In particular, it is assumed that the fl… more

Date: January 1, 1982

Creator: Gido, R.G. & Koestel, A.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Implementation and application of RCP system at BNL

The implementation of the RCP01 Monte Carlo system at the Brookhaven National Laboratory Central Scientific Computing Facility is described. Newly written system independent software is stressed. Finally, initial benchmarking experience and an LWR core physics application are described.

Date: January 1, 1982

Creator: Eisenhart, L.D. & Todosow, M.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Reactor-specific spent fuel discharge projections: 1985 to 2020

The creation of four spent-fuel data bases that contain information on the projected amounts of spent fuel to be discharged from US commercial nuclear reactors through the year 2020 is described. The data bases contain detailed spent-fuel information from existing, planned, and projected pressurized water reactors (PWR) and boiling water reactors (BWR). The projections are based on individual reactor information supplied by the US reactor owners. The basic information is adjusted to conform to … more

Date: September 1, 1986

Creator: Heeb, C. M.; Libby, R. A.; Walling, R. C. & Purcell, W. L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

BWR refill-reflood program: core spray distribution experimental task plan

An experimental task plan for the BWR/4 core spray task of the Refill-Reflood Test Program is presented. The test program will provide core spray distribution data for a 30 degree sector of the BWR/4 and 5-218 design. This design uses different nozzle types and different sparger elevations than the BWR/6-218 design which was tested previously. Test parameter ranges are specified; individual tests are defined; and measurement and data utilization plans are defined.

Date: February 1, 1981

Creator: Eckert, T.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Technology, safety and costs of decommissioning a reference boiling water reactor power station. Appendices. Volume 2

Appendices are presented concerning the evaluations of decommissioning financing alternatives; reference site description; reference BWR facility description; radiation dose rate and concrete surface contamination data; radionuclide inventories; public radiation dose models and calculated maximum annual doses; decommissioning methods; generic decommissioning information; immediate dismantlement details; passive safe storage, continuing care, and deferred dismantlement details; entombment detail… more

Date: June 1, 1980

Creator: Oak, H. D.; Holter, G. M.; Kennedy, W. E. Jr. & Konzek, G. J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Identification of the impacts of maintenance and testing upon the safety of LWR power plants. Final report

The present study was designed to identify the impact of maintenance and testing (M and T) upon the safety of LWR power plants. The study involved data extraction from various sources reporting safety-related and operation-related nuclear power plant experience. Primary sources reviewed, including Licensee Event Reports (LER's) submitted to the NRC, revealed that only ten percent of events reported could be identified as M and T problems. The collected data were collated in a manner that w… more

Date: April 1, 1980

Creator: Husseiny, A. A.; Sabri, Z. A. & Turnage, J. J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

High-speed simulation of transients in nuclear power plants

A combination of advanced modeling techniques and modern, special-purpose peripheral minicomputer technology is presented which affords realistic predictions of plant transient and severe off-normal events in LWR power plants through on-line simulations at a speed ten times greater than actual process speeds. Results are shown for a BWR plant simulation. Results are shown to demonstrate computing capacity, accuracy, and speed. Simulation speeds have been achieved which are 110 times larger than… more

Date: January 1, 1984

Creator: Wulff, W.; Cheng, H.S.; Lekach, S.V. & Mallen, A.N.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Constitutive relations in TRAC-P1A

The purpose of this document is to describe the basic thermal-hydraulic models and correlations that are in the TRAC-P1A code, as released in March 1979. It is divided into two parts, A and B. Part A describes the models in the three-dimensional vessel module of TRAC, whereas Part B focuses on the loop components that are treated by one-dimensional formulations. The report follows the format of the questions prepared by the Analysis Development Branch of USNRC and the questionnaire has been att… more

Date: August 1, 1980

Creator: Rohatgi, U.S. & Saha, P.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

The use of NPAR (Nuclear Plant Aging Research) results in plant inspection activities

The US NRC's Nuclear Plant Aging Research (NPAR) Program is a hardware oriented research program which has produced a large data base of equipment and system operating, maintenance, and testing information. Equipment and systems which have a propensity for age related degradation are identified, and methods for detecting and mitigating aging effects have been evaluated. As plants age, it becomes increasingly important that NRC inspectors be cognizant of plant aging phenomena. This paper describ… more

Date: January 1, 1989

Creator: Gunther, W. & Taylor, J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Technical evaluation report on the monitoring of electric power to the reactor-protection system for the Pilgrim Nuclear Power Station

This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Pilgrim Nuclear Power Station. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications will protect the RPS from sustained abn… more

Date: April 29, 1982

Creator: Selan, J.C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Radioactive materials released from nuclear power plants. Annual report, 1983. Volume 4

Releases of radioactive materials in airborne and liquid effluents from commercial light water reactors during 1983 have been compiled and reported. Data on solid waste shipments as well as selected operating information have been included. This report supplements earlier annual reports issued by the former Atomic Energy Commission and the Nuclear Regulatory Commission. The 1983 release data are summarized in tabular form. Data covering specific radionuclides are summarized.

Date: August 1, 1986

Creator: Tichler, J. & Norden, K.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Safety analysis of thorium-based fuels in the General Electric Standard BWR

A denatured (U-233/Th)O/sub 2/ fuel assembly has been designed which is energy equivalent to and hardware interchangeable with a modern boiling water reactor (BWR) reference reload assembly. Relative to the reference UO/sub 2/ fuel, the thorium fuel design shows better performance during normal and transient reactor operation for the BWR/6 product line and will meet or exceed current safety and licensing criteria. Power distributions are flattened and thermal operating margins are increased by … more

Date: June 1, 1980

Creator: Colby, M.J.; Townsend, D.B. & Kunz, C.L.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Use of separate-effects experiments in verification of system thermal-hydraulics

In recent years, a number of advanced, best-estimate systems codes such as TRAC and RELAP5 have been developed in order to accurately predict the consequences of various postulated accidents and transients in Light Water Reactor (LWR) systems. Although these codes had to go through some verification or assessment during the developmental stage, it has been recognized that an independent assessment of these codes is necessary before they should be applied to any decision making process. The USNR… more

Date: January 1, 1982

Creator: Saha, P.

Item Type: 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

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: Article

Partner: UNT Libraries Government Documents Department

open access

Boundary effects on Zircaloy-4 cladding deformation in LOCA simulation tests. [PWR; BWR]

Deformation behavior of Zircaloy-4 cladding under simulated loss-of-coolant accident (LOCA) conditions is being investigated in the Multirod Burst Test (MRBT) program in single rod and multirod tests. In these tests, internally-pressurized unirradiated Zircaloy-4 tubes containing internal electrical heaters are heated to failure in a low-pressure, superheated-steam environment (200 < Re < 800). The results provide a data base for evaluating deformation and blockage models employed with design-b… more

Date: January 1, 1982

Creator: Longest, A.W.; Chapman, R.H. & Crowley, J.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Light-water-reactor safety research program. Quarterly progress report, January-March 1981

A mechanistic model for the prediction of microcracking (grain-boundary separation) during transient conditions has been generated within the context of the FASTGRASS computer code. A model based on the work of DiMelfi and Deitrich describing ductile/brittle behavior has been replaced by one based on the work of Beere and Speight, Chuang and Rice, and Chen and Argon. The theory underlying this new model is described and its proposed implementation in the prediction of DEH test results is outlin… more

Date: November 1, 1981

Item Type: Report

Partner: UNT Libraries Government Documents Department

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Summary and bibliography of safety-related events at boiling-water nuclear power plants as reported in 1980

This document presents a bibliography that contains 100-word abstracts of event reports submitted to the US Nuclear Regulatory Commission concerning operational events that occurred at boiling-water-reactor nuclear power plants in 1980. The 1547 abstracts included on microfiche in this bibliography describe incidents, failures, and design or construction deficiencies that were experienced at the facilities. These abstracts are arranged alphabetically by reactor name and then chronologically for… more

Date: March 1, 1982

Creator: McCormack, K.E. & Gallaher, R.B.

Item Type: Report

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

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: Article

Partner: UNT Libraries Government Documents Department

open access

Fire Protection Research Program at Sandia Laboratories. [BWR; PWR]

Sandia Laboratories is executing a program for the Nuclear Regulatory Commission to provide data needed for confirmation of the suitability of current design standards and regulatory guides for fire protection and control in water reactor power plants. This paper summarizes the activities of this ongoing program through December 1979. Characterization of electrically initiated fires revealed a margin of safety in the separation criteria of Regulatory Guide 1.75 for such fires in IEEE-383 qualif… more

Date: January 1, 1980

Creator: Klamerus, L.J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Handbook of nuclear power plant seismic fragilities, Seismic Safety Margins Research Program

The Seismic Safety Margins Research Program (SSMRP) has a gola to develop a complete fully coupled analysis procedure (including methods and computer codes) for estimating the risk of an earthquake-induced radioactive release from a commercial nuclear power plant. As part of this program, calculations of the seismic risk from a typical commercial nuclear reactor were made. These calculations required a knowledge of the probability of failure (fragility) of safety-related components in the react… more

Date: December 1, 1983

Creator: Cover, L.E.; Bohn, M.P.; Campbell, R.D. & Wesley, D.A.

Item Type: Report

Partner: UNT Libraries Government Documents Department