Multiphase transients with coolant and core materials in LMFBR core disruptive accident energetics evaluations /

Evaluation of long-term post-accident core cooling of Three Mile Island Unit 2 : NRC staff report.

U.S. Nuclear Regulatory Commission. Division of Systems Safety.

January 1979

"Date published: May 1979.""Docket 50-320.""NUREG-0557."Mode of access: Internet

Fuel temperatures in an argonaut reactor core following a hypothetical design basis accident (DBA) /

Cort, G. E. (G. Edward)
U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Licensing.
Los Alamos National Laboratory.

"Date published: June 1981.""NRC FIN A7122.""NUREG/CR-2198."Includes bibliographical references.Mode...

Elementary neutronics considerations in LMFBR design /

Golden, G. H., author.
Argonne National Laboratory.

See errata at end of item."March 1969"Includes bibliographical references.Mode of access: Internet

Condensation of fuel onto the above-core structure during an LMFBR core-disruptive accident /

Gardner, P. L.
Reynolds, Albert B. (Albert Barnett), 1931-
Erdman, C. A.
University of Virginia. Dept. of Nuclear Engineering.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.

Manuscript completed August 1977, published October 1977.Prepared under contract no. AT(49-24)-0316 ...

Bubble behavior in LMFBR core disruptive accidents : annual report, October 1979 - September 1980 /

Reynolds, Albert B. (Albert Barnett), 1931-
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation.
University of Virginia. Dept. of Nuclear Engineering and Engineering Physics.

"Date published: July 1981.""NRC FIN B5616.""NUREG/CR-2111."Includes bibliographical references.Mode...

Bubble behavior in LMFBR core disruptive accidents : annual report, July 1, 1976 - September 30, 1977 /

Reynolds, Albert B. (Albert Barnett), 1931-
Erdman, C. A.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
University of Virginia. Dept. of Nuclear Engineering.

January 1978

"Date published: February 1978."Prepared under contract no. AT(49-24)-0316."NUREG/CR-0002."Includes ...

Generic assessment of delayed reactor coolant pump trip during small break loss-of-coolant accidents in pressurized water reactors /

Sheron, B. (Brian)
U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force.

January 1979

"NUREG-0623.""Date Published: November 1979."Includes bibliographical references.Mode of access: Int...

LMFBR fuel analysis task B : post-accident heat removal : final report, October 1977 - November 1978 /

Catton, I. (Ivan), 1934-
U.S. Nuclear Regulatory Commission. Division of Project Management.
University of California, Los Angeles. School of Engineering and Applied Science.

January 1979

"Date published: March 1979."Prepared under contract no. NRC-03-77-001."NUREG/CR-0737."Includes bibl...

Hypothetical core disruptive accident

Simpson, D.E.

July 1975

The hypothetical core disruptive accident in an LMFBR is discussed under the following main headings...

Analysis of severe accident energetics in metallic-fueled, liquid metal cooled reactors /

Morris, E. E., author.
Tentner, A. M., author.
University of Chicago, issuing body.
Argonne National Laboratory, issuing body.

"IFR Technical Memorandum No. 235.""August 1994."Includes bibliographical references (pages 47-49)Op...

Anticipated transients without scram for light water reactors : staff report.

United States Nuclear Regulatory Commission. Division of Systems Safety.

January 1978

"NUREG-0460".Includes bibliographical references.v. 1. Staff report (April 1978) -- v. 2. Staff repo...

Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Combustion Engineering designed operating plants /

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force.

January 1980

"NUREG-0635.""Date published: January 1980."Includes bibliographical references.Mode of access: Inte...

LMFBR fuel analysis task C : reliability : final report, October 1977 - November 1978 /

Cave, L.
Kastenberg, W. E.
U.S. Nuclear Regulatory Commission. Division of Project Management.
University of California, Los Angeles. School of Engineering and Applied Science.

"Date published: March 1979.""NRC-03-77-001.""NUREG/CR-0736."Includes bibliographical references.Mod...

LMFBR fuel analysis task A : oxide fuel dynamics : final report, October 1977 - September 1978 /

Dhir, V. K.
U.S. Nuclear Regulatory Commission. Division of Project Management.
University of California, Los Angeles. Chemical, Nuclear, and Thermal Engineering Dept.

January 1979

"Date published: March 1979."Prepared under contract no. NRC-03-77-001."NUREG/CR-0721."Includes bibl...

BWR blowdown/emergency core cooling nineteenth quarterly progress report, July 1-September 30, 1980 /

Shimon, J. E.
General Electric Company. Nuclear Engineering Division.
Electric Power Research Institute.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
United States. Government Printing Office.
United States. National Technical Information Service.

"GEAP-21304-19.""NUREG/CR-1154.""NRC FIN no. B3014.""Date published: April 1981."Includes bibliograp...

Evaluation of long-term post-accident core cooling of Three Mile Island Unit 2 : NRC staff report.

U.S. Nuclear Regulatory Commission. Division of Systems Safety.

January 1979

"Date published: May 1979.""Docket 50-320.""NUREG-0557."Mode of access: Internet

Fuel temperatures in an argonaut reactor core following a hypothetical design basis accident (DBA) /

Cort, G. E. (G. Edward)
U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Licensing.
Los Alamos National Laboratory.

"Date published: June 1981.""NRC FIN A7122.""NUREG/CR-2198."Includes bibliographical references.Mode...

Elementary neutronics considerations in LMFBR design /

Golden, G. H., author.
Argonne National Laboratory.

See errata at end of item."March 1969"Includes bibliographical references.Mode of access: Internet

Condensation of fuel onto the above-core structure during an LMFBR core-disruptive accident /

Gardner, P. L.
Reynolds, Albert B. (Albert Barnett), 1931-
Erdman, C. A.
University of Virginia. Dept. of Nuclear Engineering.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.

Manuscript completed August 1977, published October 1977.Prepared under contract no. AT(49-24)-0316 ...

Bubble behavior in LMFBR core disruptive accidents : annual report, October 1979 - September 1980 /

Reynolds, Albert B. (Albert Barnett), 1931-
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation.
University of Virginia. Dept. of Nuclear Engineering and Engineering Physics.

"Date published: July 1981.""NRC FIN B5616.""NUREG/CR-2111."Includes bibliographical references.Mode...

Bubble behavior in LMFBR core disruptive accidents : annual report, July 1, 1976 - September 30, 1977 /

Reynolds, Albert B. (Albert Barnett), 1931-
Erdman, C. A.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
University of Virginia. Dept. of Nuclear Engineering.

January 1978

"Date published: February 1978."Prepared under contract no. AT(49-24)-0316."NUREG/CR-0002."Includes ...

Generic assessment of delayed reactor coolant pump trip during small break loss-of-coolant accidents in pressurized water reactors /

Sheron, B. (Brian)
U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force.

January 1979

"NUREG-0623.""Date Published: November 1979."Includes bibliographical references.Mode of access: Int...

LMFBR fuel analysis task B : post-accident heat removal : final report, October 1977 - November 1978 /

Catton, I. (Ivan), 1934-
U.S. Nuclear Regulatory Commission. Division of Project Management.
University of California, Los Angeles. School of Engineering and Applied Science.

January 1979

"Date published: March 1979."Prepared under contract no. NRC-03-77-001."NUREG/CR-0737."Includes bibl...

Hypothetical core disruptive accident

Simpson, D.E.

July 1975

The hypothetical core disruptive accident in an LMFBR is discussed under the following main headings...

Analysis of severe accident energetics in metallic-fueled, liquid metal cooled reactors /

Morris, E. E., author.
Tentner, A. M., author.
University of Chicago, issuing body.
Argonne National Laboratory, issuing body.

"IFR Technical Memorandum No. 235.""August 1994."Includes bibliographical references (pages 47-49)Op...

Anticipated transients without scram for light water reactors : staff report.

United States Nuclear Regulatory Commission. Division of Systems Safety.

January 1978

"NUREG-0460".Includes bibliographical references.v. 1. Staff report (April 1978) -- v. 2. Staff repo...

Generic evaluation of feedwater transients and small break loss-of-coolant accidents in Combustion Engineering designed operating plants /

U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Bulletins and Orders Task Force.

January 1980

"NUREG-0635.""Date published: January 1980."Includes bibliographical references.Mode of access: Inte...

LMFBR fuel analysis task C : reliability : final report, October 1977 - November 1978 /

Cave, L.
Kastenberg, W. E.
U.S. Nuclear Regulatory Commission. Division of Project Management.
University of California, Los Angeles. School of Engineering and Applied Science.

"Date published: March 1979.""NRC-03-77-001.""NUREG/CR-0736."Includes bibliographical references.Mod...

LMFBR fuel analysis task A : oxide fuel dynamics : final report, October 1977 - September 1978 /

Dhir, V. K.
U.S. Nuclear Regulatory Commission. Division of Project Management.
University of California, Los Angeles. Chemical, Nuclear, and Thermal Engineering Dept.

January 1979

"Date published: March 1979."Prepared under contract no. NRC-03-77-001."NUREG/CR-0721."Includes bibl...

BWR blowdown/emergency core cooling nineteenth quarterly progress report, July 1-September 30, 1980 /

Shimon, J. E.
General Electric Company. Nuclear Engineering Division.
Electric Power Research Institute.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
United States. Government Printing Office.
United States. National Technical Information Service.

"GEAP-21304-19.""NUREG/CR-1154.""NRC FIN no. B3014.""Date published: April 1981."Includes bibliograp...

Evaluation of long-term post-accident core cooling of Three Mile Island Unit 2 : NRC staff report.

U.S. Nuclear Regulatory Commission. Division of Systems Safety.

January 1979

"Date published: May 1979.""Docket 50-320.""NUREG-0557."Mode of access: Internet

Fuel temperatures in an argonaut reactor core following a hypothetical design basis accident (DBA) /

Cort, G. E. (G. Edward)
U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Licensing.
Los Alamos National Laboratory.

"Date published: June 1981.""NRC FIN A7122.""NUREG/CR-2198."Includes bibliographical references.Mode...

Elementary neutronics considerations in LMFBR design /

Golden, G. H., author.
Argonne National Laboratory.

See errata at end of item."March 1969"Includes bibliographical references.Mode of access: Internet

Multiphase transients with coolant and core materials in LMFBR core disruptive accident energetics evaluations /

Abstract

Extracted data

Multiphase transients with coolant and core materials in LMFBR core disruptive accident energetics evaluations /

Abstract

Extracted data

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