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in creator/contributor: "Greene, S.R."

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The impact of BWR MK I primary containment failure dynamics on secondary containment integrity

During the past four years, the ORNL BWRSAT Program has developed a series of increasingly sophisticated BWR secondary containment models. These models have been applied in a variety of studies to evaluate the severe accident mitigation capability of BWR secondary containments. This paper describes the results of a recent ORNL study of the impact of BWR MK I primary containment failure dynamics on secondary containment integrity. A 26-cell MELCOR Browns Ferry secondary containment model is desc… more

Date: January 1, 1987

Creator: Greene, S. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Role of BWR MK I secondary containments in severe accident mitigation

The recent advent of detailed containment analysis codes such as CONTAIN and MELCOR has facilitated the development of the first large-scale, architectural-based BWR secondary containment models. During the past year ORNL has developed detailed, plant-specific models of the Browns Ferry and Peach Bottom secondary containments, and applied these models in a variety of studies designed to evaluate the role and effectiveness of BWR secondary containments in severe accident mitigation. The topology… more

Date: January 1, 1986

Creator: Greene, S. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Role of BWR secondary containments in severe accident mitigation: issues and insights from recent analyses

All commercial boiling water reactor (BWR) plants in the US employ primary containments of the pressure suppression design. These primary containments are surrounded and enclosed by a secondary containment consisting of a reactor building and refueling bay (MK I and MK II designs), a shield building, auxiliary building and fuel building (MK III), or an auxiliary building and enclosure building (Grand Gulf style MK III). Although secondary containment designs are highly plant specific, their pur… more

Date: January 1, 1988

Creator: Greene, S. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Reactor-Based Plutonium Disposition: Opportunities, Options, and Issues

The end of the Cold War has created a legacy of surplus fissile materials (plutonium and highly enriched uranium) in the United States (U.S.) and the former Soviet Union. These materials pose a danger to national and international security. During the past few years, the U.S. and Russia have engaged in an ongoing dialog concerning the safe storage and disposition of surplus fissile material stockpiles. In January 1997, the Department of Energy (DOE) announced the U. S. would pursue a dual track… more

Date: July 17, 1999

Creator: Greene, S. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Large break loss of coolant severe accident sequences at the HFIR (High Flux Isotope Reactor)

An assessment of many potential HFIR severe accident phenomena was conducted during the HFIR design effort, and many severe accident mitigating features were designed into the plant. These evaluation typically incorporated a bounding'' or highly conservative analysis approach and employed tools and techniques representative of the state of knowledge in the mid-1960s. Recently, programs to address severe accident issues were initiated at the Oak Ridge National Laboratory (ORNL) to support the HF… more

Date: January 1, 1990

Creator: Simpson, D. B. & Greene, S. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

FMDP reactor alternative summary report. Volume 1 - existing LWR alternative

Significant quantities of weapons-usable fissile materials [primarily plutonium and highly enriched uranium (HEU)] are becoming surplus to national defense needs in both the United States and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety, and health (ES&H) consequences if surplus fissile materials are not pr… more

Date: October 7, 1996

Creator: Greene, S. R. & Bevard, B. B.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Characterization of debris/concrete interactions for advanced research reactor and commercial BWR severe accidents

The core concrete interaction (CCI) is an important phase of any severe accident where the reactor vessel has failed and core debris is relocated onto the containment basemat. In recent calculations performed at the Oak Ridge National Laboratory (ORNL), CCI has been studied for severe accidents occurring in a commercial Boiling Water Reactor (BWR) and in a high-power density Department of Energy (DOE) research reactor that is currently in the conceptual design stage. Because of differences in t… more

Date: January 1, 1991

Creator: Hyman, C. R.; Taleyarkhan, R. P. & Greene, S. R.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

FMDP Reactor Alternative Summary Report: Volume 3 - partially complete LWR alternative

The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 3 of a four volume report summarizes the results of these analyses for the partially complete LWR (PCLWR) reactor based plutonium disposition alternative.

Date: September 1, 1996

Creator: Greene, S. R.; Fisher, S. E. & Bevard, B. B.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

FMDP Reactor Alternative Summary Report: Volume 2 - CANDU heavy water reactor alternative

The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 2 of a four volume report, summarizes the results of these analyses for the CANDU reactor based plutonium disposition alternative.

Date: September 1, 1996

Creator: Greene, S. R.; Spellman, D. J. & Bevard, B. B.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Potential effects of gallium on cladding materials

This paper identifies and examines issues concerning the incorporation of gallium in weapons derived plutonium in light water reactor (LWR) MOX fuels. Particular attention is given to the more likely effects of the gallium on the behavior of the cladding material. The chemistry of weapons grade (WG) MOX, including possible consequences of gallium within plutonium agglomerates, was assessed. Based on the calculated oxidation potentials of MOX fuel, the effect that gallium may have on reactions i… more

Date: October 1, 1997

Creator: Wilson, D. F.; Beahm, E. C.; Besmann, T. M.; DeVan, J. H.; DiStefano, J. R.; Gat, U. et al.

Item Type: Report

Partner: UNT Libraries Government Documents Department