The NACOM code for analysis of postulated sodium spray fires in LMFBRs /

Chromatographic analysis of gases over liquid sodium /

Johnson, Donald L.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-8448 ; Metals, Ceramics, and Materials.""Contract AT(11-1)-GEN-8 ; Issued: Sep 15 1964."Incl...

Sodium Reactor Experiment fuel irradiation experience /

Ballif, J. L.
Woolsey, C. C.
Walter, J. H.
Hayward, B. R.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-3887 ; Metallurgy and Ceramics.""Contract AT(11-1)-GEN-8 ; Issued: Sep 15 1959."Includes bib...

Analysis of results of a sodium cold trap experiment /

McDonald, J. S.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-6801 ; Reactor Technology.""Contract AT(11-1)-GEN-8 ; Issued: Jul 30 1962."Includes bibliogr...

NACOM code for analysis of postulated sodium spray fires in LMFBRs

Tsai, S.S.

March 1980

An analysis of potential sodium spills and fires in liquid metal fast breeder reactors has been made...

A study of sodium fires /

Gracie, J. D.
Droher, J. J.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-4383 ; Reactors--General.""Contract AT(11-1)-GEN-8 ; Issued: October 15, 1960."Includes bibl...

Fire risk analysis for nuclear power plants /

Kazarians, M.
Apostolakis, G.
U.S. Nuclear Regulatory Commission. Division of Risk Analysis
University of California, Los Angeles. School of Engineering and Applied Science.

January 1981

"NRC FIN B6284.""XA.""RG.""UCLA-ENG-8102.""NUREG/CR-2258.""Date published: September 1981."Includes ...

Design and thermal analysis of sodium specialties components for HNPF /

Hoschouer, W. M.
Mack, R. J.
Leonard, W. D.
Casey, D. F.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-5445 ; Reactors--Power.""Contract AT(11-1)-GEN-8 ; Issued: Feb. 15, 1961."Includes bibliogra...

Compressible analysis of inlet plenum pressure rise due to sodium boiling in fuel subassemblies during pump coast down of an LMFBR /

Kalimullah.
Hummel, H. H.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Argonne National Laboratory. Applied Physics Division.

"May 1980."Prepared under Interagency Agreement DOE 40-550-75."NRC FIN No. A2015.""ANL-80-48.""NUREG...

Comments on the application of ASME and ASA boiler and piping codes to sodium systems /

Hayes, W. C.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-4102 ; Metallurgy and Ceramics.""Contract AT(11-1)-GEN-8 ; Issued: September 15, 1959."Inclu...

LMFBR safety program. Annual technical progress report. Government fiscal year, 1977

December 1977

Information is presented concerning the development of the SOMIX-1 computer code for sodium drop bur...

A qualification testing program plan for SIMMER : a computer code for LMFBR distrupted core analysis /

Basdekas, D.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.

Prepared for Division of Reactor Safety Research."NUREG/CR-0457."Includes bibliographical references...

Simulation of sodium pumps for nuclear power plants /

Boadu, H. O.
University of Arizona. Dept. of Nuclear and Energy Engineering.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation.

January 1981

"NUREG/CR-2188.""NRC FIN A4065.""Date Published: August 1981.""Department of Nuclear and Energy Engi...

Sodium condensing heat transfer : an experimental study of one aspect of sodium cooled reactor safety /

Reed, G. L.
Noyes, R. C.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-7325 ; Reactor Technology.""Contract AT(11-1)-GEN-8."Includes bibliographical references (pa...

Development and testing of a model for fire potential in nuclear power plants /

Hockenbury, R. W.
Yeater, M. L.
U.S. Nuclear Regulatory Commission. Division of Systems and Reliability Research.

"NUREG/CR-1819.""Date published: November 1980."Includes bibliographical references.Mode of access: ...

A user's guide for MODCUT and PL-MODMC : computer codes for fault tree analysis /

Modarres, M. (Mohammad)
Wolf, Lothar, 1938-
Rasmussen, Norman C.
Massachusetts Institute of Technology. Department of Nuclear Engineering.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Staff.

"NUREG/CR-1461.""NRC FIN no. B6256.""Date published: November 1980.""Nuclear Engineering Department,...

Chromatographic analysis of gases over liquid sodium /

Johnson, Donald L.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-8448 ; Metals, Ceramics, and Materials.""Contract AT(11-1)-GEN-8 ; Issued: Sep 15 1964."Incl...

Sodium Reactor Experiment fuel irradiation experience /

Ballif, J. L.
Woolsey, C. C.
Walter, J. H.
Hayward, B. R.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-3887 ; Metallurgy and Ceramics.""Contract AT(11-1)-GEN-8 ; Issued: Sep 15 1959."Includes bib...

Analysis of results of a sodium cold trap experiment /

McDonald, J. S.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-6801 ; Reactor Technology.""Contract AT(11-1)-GEN-8 ; Issued: Jul 30 1962."Includes bibliogr...

NACOM code for analysis of postulated sodium spray fires in LMFBRs

Tsai, S.S.

March 1980

An analysis of potential sodium spills and fires in liquid metal fast breeder reactors has been made...

A study of sodium fires /

Gracie, J. D.
Droher, J. J.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-4383 ; Reactors--General.""Contract AT(11-1)-GEN-8 ; Issued: October 15, 1960."Includes bibl...

Fire risk analysis for nuclear power plants /

Kazarians, M.
Apostolakis, G.
U.S. Nuclear Regulatory Commission. Division of Risk Analysis
University of California, Los Angeles. School of Engineering and Applied Science.

January 1981

"NRC FIN B6284.""XA.""RG.""UCLA-ENG-8102.""NUREG/CR-2258.""Date published: September 1981."Includes ...

Design and thermal analysis of sodium specialties components for HNPF /

Hoschouer, W. M.
Mack, R. J.
Leonard, W. D.
Casey, D. F.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-5445 ; Reactors--Power.""Contract AT(11-1)-GEN-8 ; Issued: Feb. 15, 1961."Includes bibliogra...

Compressible analysis of inlet plenum pressure rise due to sodium boiling in fuel subassemblies during pump coast down of an LMFBR /

Kalimullah.
Hummel, H. H.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Argonne National Laboratory. Applied Physics Division.

"May 1980."Prepared under Interagency Agreement DOE 40-550-75."NRC FIN No. A2015.""ANL-80-48.""NUREG...

Comments on the application of ASME and ASA boiler and piping codes to sodium systems /

Hayes, W. C.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-4102 ; Metallurgy and Ceramics.""Contract AT(11-1)-GEN-8 ; Issued: September 15, 1959."Inclu...

LMFBR safety program. Annual technical progress report. Government fiscal year, 1977

December 1977

Information is presented concerning the development of the SOMIX-1 computer code for sodium drop bur...

A qualification testing program plan for SIMMER : a computer code for LMFBR distrupted core analysis /

Basdekas, D.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.

Prepared for Division of Reactor Safety Research."NUREG/CR-0457."Includes bibliographical references...

Simulation of sodium pumps for nuclear power plants /

Boadu, H. O.
University of Arizona. Dept. of Nuclear and Energy Engineering.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation.

January 1981

"NUREG/CR-2188.""NRC FIN A4065.""Date Published: August 1981.""Department of Nuclear and Energy Engi...

Sodium condensing heat transfer : an experimental study of one aspect of sodium cooled reactor safety /

Reed, G. L.
Noyes, R. C.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-7325 ; Reactor Technology.""Contract AT(11-1)-GEN-8."Includes bibliographical references (pa...

Development and testing of a model for fire potential in nuclear power plants /

Hockenbury, R. W.
Yeater, M. L.
U.S. Nuclear Regulatory Commission. Division of Systems and Reliability Research.

"NUREG/CR-1819.""Date published: November 1980."Includes bibliographical references.Mode of access: ...

A user's guide for MODCUT and PL-MODMC : computer codes for fault tree analysis /

Modarres, M. (Mohammad)
Wolf, Lothar, 1938-
Rasmussen, Norman C.
Massachusetts Institute of Technology. Department of Nuclear Engineering.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Probabilistic Analysis Staff.

"NUREG/CR-1461.""NRC FIN no. B6256.""Date published: November 1980.""Nuclear Engineering Department,...

Chromatographic analysis of gases over liquid sodium /

Johnson, Donald L.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-8448 ; Metals, Ceramics, and Materials.""Contract AT(11-1)-GEN-8 ; Issued: Sep 15 1964."Incl...

Sodium Reactor Experiment fuel irradiation experience /

Ballif, J. L.
Woolsey, C. C.
Walter, J. H.
Hayward, B. R.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-3887 ; Metallurgy and Ceramics.""Contract AT(11-1)-GEN-8 ; Issued: Sep 15 1959."Includes bib...

Analysis of results of a sodium cold trap experiment /

McDonald, J. S.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-6801 ; Reactor Technology.""Contract AT(11-1)-GEN-8 ; Issued: Jul 30 1962."Includes bibliogr...

The NACOM code for analysis of postulated sodium spray fires in LMFBRs /

Abstract

Extracted data

The NACOM code for analysis of postulated sodium spray fires in LMFBRs /

Abstract

Extracted data

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