Evaluation of high temperature gas cooled reactor fuel particle coating failure models and data /

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...

The analysis of fuel densification /

Meyer, R. O. (Ralph O.)
U.S. Nuclear Regulatory Commission. Division of Systems Safety.

January 1976

"Date published: July 1976.""NUREG-0085."Includes bibliographical references.Mode of access: Interne...

Loss-of-coolant accident simulations in the National Research Universal Reactor /

Bennett, W. D.
Mohr, C. L.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Pacific Northwest Laboratory.

"FIN B2277.""PNL-3093.""NUREG/CR-1208.""Date published: February 1981.""Safety analysis report."Bibl...

Models for fission-gas release from coated fuel particles /

Prados, John W.
Scott, J. L.
U.S. Atomic Energy Commission.
Oak Ridge National Laboratory. Metals and Ceramics Division.

January 1963

"Date issued Jun 20 1963"."ORNL-3421."Bibliography references included.Mode of access: Internet

Dimensional behavior of the experimental gas-cooled reactor fuel element at elevated temperatures /

Martin, W. R.
Weir, J. R.
U.S. Atomic Energy Commission.
Oak Ridge National Laboratory. Metallurgy Division.

January 1961

"Date issued Aug 2 1961".Bibliography references included.Mode of access: Internet

A failure analysis for the low-temperature performance of dispersion fuel elements /

Weir, J. R.
U.S. Atomic Energy Commission.

January 1960

"Date issued Jun 15 1960".Bibliography references : p. 29Mode of access: Internet

Technical bases for estimating fission product behavior during LWR accidents /

Sandia National Laboratories.
Oak Ridge National Laboratory.
Battelle Memorial Institute. Columbus Laboratories.
U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.

January 1981

"NUREG-0772.""Date published: June 1981."Includes bibliographical references.Mode of access: Interne...

Development of nondestructive tests for the experimental gas-cooled reactor fuel element /

McClung, R. W.
Nance, R. A.
U.S. Atomic Energy Commission.

January 1961

"Date issued Mar 2 1961".Bibliography references included.Mode of access: Internet

Coated particle fuels--thermal, mechanical, and stress properties : a bibliography /

Furnish, Jean.
Los Alamos Scientific Laboratory.
U.S. Atomic Energy Commission.

January 1967

"United States Atomic Energy Commission Contract W-7405-eng.36."--Cover."LA-3791-MS ; UC-80, Reactor...

High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research : quarterly progress report, January 1-March 31, 1980 /

Ball, S. J.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Oak Ridge National Laboratory.

January 1980

"Date published: August 1980.""Dist. Category R8.""Contract No. W-7405-eng-26."Prepared under Intera...

Fission gas release from fuel at high burnup /

Meyer, R. O. (Ralph O.)
Voglewede, J. C.
Beyer, C. E.
U.S. Nuclear Regulatory Commission. Division of Systems Safety.

"Date Published: March 1978.""NUREG-0418."Includes bibliographical references (p. 31-32).Mode of acc...

Erosion resistance of swaged UO₂ following an in-reactor fuel rod cladding failure /

Millhollen, M. K.
Bates, J. L. joint author.
Horn, G. R. joint author.
U.S. Atomic Energy Commission. AEC research and develpment report.
U.S. Atomic Energy Commission. TID.
U.S. Atomic Energy Commission.
Hanford Atomic Products Operation.
Pacific Northwest Laboratory.

January 1961

"June, 1961."Includes bibliographical references.Work performed between the Atomic Energy Commission...

Failure of reactor fuels : a literature search /

Smith, Richard J., compiler.
U.S. Atomic Energy Commission.

AEC Report No. TID-3573.December 1962.Includes bibliographical references.Mode of access: Internet

Investigation and evaluation of cracking incidents in piping in pressurized water reactors /

U.S. Nuclear Regulatory Commission.
PWR Pipe Crack Study Group (U.S.)

January 1980

"NUREG-0691.""Date published : September 1980."Includes bibliographical references.Mode of access: I...

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...

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...

The analysis of fuel densification /

Meyer, R. O. (Ralph O.)
U.S. Nuclear Regulatory Commission. Division of Systems Safety.

January 1976

"Date published: July 1976.""NUREG-0085."Includes bibliographical references.Mode of access: Interne...

Loss-of-coolant accident simulations in the National Research Universal Reactor /

Bennett, W. D.
Mohr, C. L.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Pacific Northwest Laboratory.

"FIN B2277.""PNL-3093.""NUREG/CR-1208.""Date published: February 1981.""Safety analysis report."Bibl...

Models for fission-gas release from coated fuel particles /

Prados, John W.
Scott, J. L.
U.S. Atomic Energy Commission.
Oak Ridge National Laboratory. Metals and Ceramics Division.

January 1963

"Date issued Jun 20 1963"."ORNL-3421."Bibliography references included.Mode of access: Internet

Dimensional behavior of the experimental gas-cooled reactor fuel element at elevated temperatures /

Martin, W. R.
Weir, J. R.
U.S. Atomic Energy Commission.
Oak Ridge National Laboratory. Metallurgy Division.

January 1961

"Date issued Aug 2 1961".Bibliography references included.Mode of access: Internet

A failure analysis for the low-temperature performance of dispersion fuel elements /

Weir, J. R.
U.S. Atomic Energy Commission.

January 1960

"Date issued Jun 15 1960".Bibliography references : p. 29Mode of access: Internet

Technical bases for estimating fission product behavior during LWR accidents /

Sandia National Laboratories.
Oak Ridge National Laboratory.
Battelle Memorial Institute. Columbus Laboratories.
U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research.

January 1981

"NUREG-0772.""Date published: June 1981."Includes bibliographical references.Mode of access: Interne...

Development of nondestructive tests for the experimental gas-cooled reactor fuel element /

McClung, R. W.
Nance, R. A.
U.S. Atomic Energy Commission.

January 1961

"Date issued Mar 2 1961".Bibliography references included.Mode of access: Internet

Coated particle fuels--thermal, mechanical, and stress properties : a bibliography /

Furnish, Jean.
Los Alamos Scientific Laboratory.
U.S. Atomic Energy Commission.

January 1967

"United States Atomic Energy Commission Contract W-7405-eng.36."--Cover."LA-3791-MS ; UC-80, Reactor...

High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research : quarterly progress report, January 1-March 31, 1980 /

Ball, S. J.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Oak Ridge National Laboratory.

January 1980

"Date published: August 1980.""Dist. Category R8.""Contract No. W-7405-eng-26."Prepared under Intera...

Fission gas release from fuel at high burnup /

Meyer, R. O. (Ralph O.)
Voglewede, J. C.
Beyer, C. E.
U.S. Nuclear Regulatory Commission. Division of Systems Safety.

"Date Published: March 1978.""NUREG-0418."Includes bibliographical references (p. 31-32).Mode of acc...

Erosion resistance of swaged UO₂ following an in-reactor fuel rod cladding failure /

Millhollen, M. K.
Bates, J. L. joint author.
Horn, G. R. joint author.
U.S. Atomic Energy Commission. AEC research and develpment report.
U.S. Atomic Energy Commission. TID.
U.S. Atomic Energy Commission.
Hanford Atomic Products Operation.
Pacific Northwest Laboratory.

January 1961

"June, 1961."Includes bibliographical references.Work performed between the Atomic Energy Commission...

Failure of reactor fuels : a literature search /

Smith, Richard J., compiler.
U.S. Atomic Energy Commission.

AEC Report No. TID-3573.December 1962.Includes bibliographical references.Mode of access: Internet

Investigation and evaluation of cracking incidents in piping in pressurized water reactors /

U.S. Nuclear Regulatory Commission.
PWR Pipe Crack Study Group (U.S.)

January 1980

"NUREG-0691.""Date published : September 1980."Includes bibliographical references.Mode of access: I...

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...

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...

The analysis of fuel densification /

Meyer, R. O. (Ralph O.)
U.S. Nuclear Regulatory Commission. Division of Systems Safety.

January 1976

"Date published: July 1976.""NUREG-0085."Includes bibliographical references.Mode of access: Interne...

Loss-of-coolant accident simulations in the National Research Universal Reactor /

Bennett, W. D.
Mohr, C. L.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Pacific Northwest Laboratory.

"FIN B2277.""PNL-3093.""NUREG/CR-1208.""Date published: February 1981.""Safety analysis report."Bibl...

Evaluation of high temperature gas cooled reactor fuel particle coating failure models and data /

Abstract

Extracted data

Evaluation of high temperature gas cooled reactor fuel particle coating failure models and data /

Abstract

Extracted data

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