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

Pool boiling investigation of benzene, diphenyl, and benzene-diphenyl mixtures under pressure /

Huber, D. A.
Hoehne, J. C.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

See errata for pages 2, 4, 5, 9, 10, 11, 17, 18, 20, 27 and 30 at end of item."NAA-SR-6681 ; Reactor...

FFTF sodium service pressure measurement : state-of-the-art report /

Crocker, T. J., author.
Battelle Memorial Institute. Pacific Northwest Division. issuing body.
U.S. Atomic Energy Commission.
Pacific Northwest Laboratory.

"December 1968.""UC-80, Reactor Technology."Includes bibliographical references (pages 24-26).Operat...

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

Tsai, S. S.
Brookhaven National Laboratory. Engineering and Advanced Reactor Safety Division.
U.S. Nuclear Regulatory Commission.

"BNL-NUREG/51180.""NUREG/CR-1405.""NRC FIN no. A-3000.""Date published - March 1980."Includes biblio...

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

Kalimullah
Hummel, H.H.

May 1980

The effect of sodium compressibility and steel elasticity on the rise in inlet plenum pressure occur...

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 ...

Hydraulic studies of the lower plenum of a pressure water reactor vessel /

Weber, E.
Dittrich, W.
Germany. Bundesministerium für Forschung und Technologie.
Simens Aktiengesellschaft.

January 1977

"Translation series.""Date published by NRC: October 1977.""Original report number: BMFT-FB K 73-03....

Steam chugging in pressure suppression containment : final report, July 1976 - July 1979 /

Lee, C. K. B.
Chan, C. K. (Chung Kin), 1947-
Nuclear Regulatory Commission. Division of Reactor Safety Research.
University of California, Los Angeles. Chemical, Nuclear, and Thermal Engineering Dept.

"NRC FIN No. B5875.""NUREG/CR-1562.""Date published: July 1980."Includes bibliographical references....

Simplified analysis of nuclear fuel pin swelling /

Lietzke, Armin F.
Lewis Research Center.

Prepared at Lewis Research Center."January 1970."Cover title.Includes bibliographical references (p....

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...

Investigation of the phenomena occurring within a multi-compartment containment after rupture of the primary cooling circuit in water-cooled reactors : project RS 50, Quick look report experiment D3 /

Battelle-Institut.
U.S. Nuclear Regulatory Commission.

January 1978

"Date published by NRC: October 1978.""Translation series.""BF RS 50 - 30 - D3.""NUREG/TR-0046."Mode...

Stress analysis of bellows for the HNPF intermediate heat exchanger /

Chipman, R.
Susnir, J.
Galantine, R.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-4534 ; Reactor Technology.""Contract AT(11-1)-GEN-8 ; Issued: Apr 15 1962."Includes bibliogr...

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...

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...

LWR fuel rod post-subcooled blowdown scoping analysis /

Grubb, R. L.
U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Integration.
EG&G Idaho.

"NUREG/CR-1568.""NRC FIN no. A6269.""Date published: August 1980.""EG&G Idaho, Inc."Includes bibliog...

Ring-baffle pressure distribution and slosh damping in large cylindrical tanks /

Scholl, Harland F.
Davis, Phillip K.
Stephens, David G.
Langley Research Center.

January 1972

Prepared at Langley Research Center.Cover title.Bibliography: p. 21-22.Mode of access: Internet

Pool boiling investigation of benzene, diphenyl, and benzene-diphenyl mixtures under pressure /

Huber, D. A.
Hoehne, J. C.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

See errata for pages 2, 4, 5, 9, 10, 11, 17, 18, 20, 27 and 30 at end of item."NAA-SR-6681 ; Reactor...

FFTF sodium service pressure measurement : state-of-the-art report /

Crocker, T. J., author.
Battelle Memorial Institute. Pacific Northwest Division. issuing body.
U.S. Atomic Energy Commission.
Pacific Northwest Laboratory.

"December 1968.""UC-80, Reactor Technology."Includes bibliographical references (pages 24-26).Operat...

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

Tsai, S. S.
Brookhaven National Laboratory. Engineering and Advanced Reactor Safety Division.
U.S. Nuclear Regulatory Commission.

"BNL-NUREG/51180.""NUREG/CR-1405.""NRC FIN no. A-3000.""Date published - March 1980."Includes biblio...

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

Kalimullah
Hummel, H.H.

May 1980

The effect of sodium compressibility and steel elasticity on the rise in inlet plenum pressure occur...

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 ...

Hydraulic studies of the lower plenum of a pressure water reactor vessel /

Weber, E.
Dittrich, W.
Germany. Bundesministerium für Forschung und Technologie.
Simens Aktiengesellschaft.

January 1977

"Translation series.""Date published by NRC: October 1977.""Original report number: BMFT-FB K 73-03....

Steam chugging in pressure suppression containment : final report, July 1976 - July 1979 /

Lee, C. K. B.
Chan, C. K. (Chung Kin), 1947-
Nuclear Regulatory Commission. Division of Reactor Safety Research.
University of California, Los Angeles. Chemical, Nuclear, and Thermal Engineering Dept.

"NRC FIN No. B5875.""NUREG/CR-1562.""Date published: July 1980."Includes bibliographical references....

Simplified analysis of nuclear fuel pin swelling /

Lietzke, Armin F.
Lewis Research Center.

Prepared at Lewis Research Center."January 1970."Cover title.Includes bibliographical references (p....

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...

Investigation of the phenomena occurring within a multi-compartment containment after rupture of the primary cooling circuit in water-cooled reactors : project RS 50, Quick look report experiment D3 /

Battelle-Institut.
U.S. Nuclear Regulatory Commission.

January 1978

"Date published by NRC: October 1978.""Translation series.""BF RS 50 - 30 - D3.""NUREG/TR-0046."Mode...

Stress analysis of bellows for the HNPF intermediate heat exchanger /

Chipman, R.
Susnir, J.
Galantine, R.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

"NAA-SR-4534 ; Reactor Technology.""Contract AT(11-1)-GEN-8 ; Issued: Apr 15 1962."Includes bibliogr...

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...

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...

LWR fuel rod post-subcooled blowdown scoping analysis /

Grubb, R. L.
U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Systems Integration.
EG&G Idaho.

"NUREG/CR-1568.""NRC FIN no. A6269.""Date published: August 1980.""EG&G Idaho, Inc."Includes bibliog...

Ring-baffle pressure distribution and slosh damping in large cylindrical tanks /

Scholl, Harland F.
Davis, Phillip K.
Stephens, David G.
Langley Research Center.

January 1972

Prepared at Langley Research Center.Cover title.Bibliography: p. 21-22.Mode of access: Internet

Pool boiling investigation of benzene, diphenyl, and benzene-diphenyl mixtures under pressure /

Huber, D. A.
Hoehne, J. C.
North American Aviation. Atomics International Division.
U.S. Atomic Energy Commission.

See errata for pages 2, 4, 5, 9, 10, 11, 17, 18, 20, 27 and 30 at end of item."NAA-SR-6681 ; Reactor...

FFTF sodium service pressure measurement : state-of-the-art report /

Crocker, T. J., author.
Battelle Memorial Institute. Pacific Northwest Division. issuing body.
U.S. Atomic Energy Commission.
Pacific Northwest Laboratory.

"December 1968.""UC-80, Reactor Technology."Includes bibliographical references (pages 24-26).Operat...

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

Tsai, S. S.
Brookhaven National Laboratory. Engineering and Advanced Reactor Safety Division.
U.S. Nuclear Regulatory Commission.

"BNL-NUREG/51180.""NUREG/CR-1405.""NRC FIN no. A-3000.""Date published - March 1980."Includes biblio...

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

Abstract

Extracted data

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

Abstract

Extracted data

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