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Nuclear reactor neutron energy spectra, by C. Z. Serpan, Jr. and B. H. Menke. (ASTM data series publication, DS 52)

Nuclear reactor neutron energy spectra, by C. Z. Serpan, Jr. and B. H. Menke. (ASTM data series publication, DS 52)
Paper図書
American Society for Testing and Materials[1974]<NG41-68>
National Diet Library
  • Author HeadingSerpan, C. Z. Menke, B. H. (Blaine Herman) ...

Analysis of reactor vessel radiation effects surveillance programs. Prepared by L. E. Steele and C. Z. Serpan, Jr. (ASTM Special technical publication 481)

Analysis of reactor vessel radiation effects surveillance programs. Prepared by L. E. Steele and C. Z. Serpan, Jr. (ASTM Special technical publication 481)
Paper図書
American Society for Testing and Materials[1970]<NG41-31>
National Diet LibraryOther Libraries in Japan
  • Author HeadingSteele, L. E. (Lendell E.) , 1928- Serpan, C. Z.

Nuclear reactor neutron energy spectra

Nuclear reactor neutron energy spectra
Paper図書
by C. Z. Serpan, Jr. and B. H. MenkeAmerican Society for Testing and Materials[1974]
Other Libraries in Japan
  • Author HeadingSerpan, C. Z. Menke, B. H. (Blaine Herman)

Analysis of reactor vessel radiation effects surveillance programs

Analysis of reactor vessel radiation effects surveillance programs
Paper図書
prepared by L.E. Steele and C.Z. Serpan, JrAmerican Society for Testing and Materialsc1970
Other Libraries in Japan
  • Author HeadingSteele, L. E. (Lendell E.) Serpan, C. Z.

Nuclear reactor neutron energy spectra. (ASTM data series publication, DS 52)

Nuclear reactor neutron energy spectra. (ASTM data series publication, DS 52)
Paper図書
Serpan, C.Z. Jr./Menke, B.H.ASTM1974.
Other Libraries in Japan

Neutron dosimetry sampling of the OMRE pressure vessel and grid plates (NRL ; NRL-MEMO-1538)

Neutron dosimetry sampling of the OMRE pressure vessel and grid plates (NRL ; NRL-MEMO-1538)
Paper図書
Serpan, C.Z. Jr., Steele, L.E.Naval Research Lab.1964.6.2.
Other Libraries in Japan

Irradiation effects on reactor structural materials (1 May 1964-31 July 1964) (NRL ; NRL-MEMO-1556)

Irradiation effects on reactor structural materials (1 May 1964-31 July 1964) (NRL ; NRL-MEMO-1556)
Paper図書
Steele, L.E., Hawthorne, J.R., Serpan, C.Z. Jr.Naval Research Lab.1964.8.15.
Other Libraries in Japan

Irradiation effects on structural materials. Quarterly progress report August 1-October 31, 1963 (NRL ; NRL-MEMO-1468)

Irradiation effects on structural materials. Quarterly progress report August 1-October 31, 1963 (NRL ; NRL-MEMO-1468)
Paper図書
Steele, L.E., Hawthorne, J.R., Serpan, C.Z. Jr.Naval Research Lab.1963.11.15.
Other Libraries in Japan

Yankee reactor pressure vessel surveillance: Evaluation of specimens exposed during the second core (NRL ; NRL-6179)

Yankee reactor pressure vessel surveillance: Evaluation of specimens exposed during the second core (NRL ; NRL-6179)
Paper図書
Serpan, C.Z. Jr., Watson, H.E., Hawthorne, J.R. [et al.]Naval Research Lab.1964.9.18.
Other Libraries in Japan

SM-1A REACTOR PRESSURE VESSEL SURVEILLANCE.:IRRADIATION OF FOLLOW-ON... (AD ; AD-717-618)

SM-1A REACTOR PRESSURE VESSEL SURVEILLANCE.:IRRADIATION OF FOLLOW-ON... (AD ; AD-717-618)
Paper図書
SERPAN, C.Z.
Other Libraries in Japan

DAMAGE-FUNCTION ANALYSIS OF NEUTRON-ENERGY AND SPECTRUM EFFECTS UP... (AD ; AD-692-072)

DAMAGE-FUNCTION ANALYSIS OF NEUTRON-ENERGY AND SPECTRUM EFFECTS UP... (AD ; AD-692-072)
Paper図書
SERPAN, C.Z.
Other Libraries in Japan

ANALYSIS OF NEUTRON-EMBRITTLEMENT AND FLUX-DENSITY CONSIDERAT... (AD ; AD-709-898)

ANALYSIS OF NEUTRON-EMBRITTLEMENT AND FLUX-DENSITY CONSIDERAT... (AD ; AD-709-898)
Paper図書
SERPAN, C.Z.
Other Libraries in Japan

THROUGH-THICKNESS NOTCH DUCTILITY AND TENSION PROPERTIES AS A FUNCTION OF NEUTRON EXPOSURE TO A SIMULATED PRESSURE VESSE (NRL ; NRL-6575)

THROUGH-THICKNESS NOTCH DUCTILITY AND TENSION PROPERTIES AS A FUNCTION OF NEUTRON EXPOSURE TO A SIMULATED PRESSURE VESSE (NRL ; NRL-6575)
Paper図書
SERPAN, C.Z.JR.
Other Libraries in Japan

DAMAGING NEUTRON EXPOSURE CRITERIA FOR EVALUATING THE EMBRITTLEMENT OF REACTOR PRESSURE VESSEL STEELS IN DIFFERENT NEUTR (NRL ; NRL-6415)

DAMAGING NEUTRON EXPOSURE CRITERIA FOR EVALUATING THE EMBRITTLEMENT OF REACTOR PRESSURE VESSEL STEELS IN DIFFERENT NEUTR (NRL ; NRL-6415)
Paper図書
SERPAN, C.Z.JR.
Other Libraries in Japan

RADIATION DAMAGE SURVEILLANCE OF POWER REACTOR PRESSURE VESSELS. (NRL ; NRL-6349)

RADIATION DAMAGE SURVEILLANCE OF POWER REACTOR PRESSURE VESSELS. (NRL ; NRL-6349)
Paper図書
SERPAN, C.Z.JR.
Other Libraries in Japan

DISCUSSION OF THE POSSIBLE DOSE RATE EFFECT IN IRRADIATION OF PRESSURE VESSEL STEEL. (NRL ; NRL-MEMO-2627)

DISCUSSION OF THE POSSIBLE DOSE RATE EFFECT IN IRRADIATION OF PRESSURE VESSEL STEEL. (NRL ; NRL-MEMO-2627)
Paper図書
SERPAN, C.Z.JR.
Other Libraries in Japan

DAMAGE-FUNCTION ANALYSIS OF NEUTRON EMBRITTLEMENT IN STEEL AT REACTOR SERVICE TEMPERATURES. (NRL ; NRL-7405)

DAMAGE-FUNCTION ANALYSIS OF NEUTRON EMBRITTLEMENT IN STEEL AT REACTOR SERVICE TEMPERATURES. (NRL ; NRL-7405)
Paper図書
SERPAN, C.Z.JR.
Other Libraries in Japan

NOTCH DUCTILITY AND TENSILE PROPERTY EVALUATION OF THE PM-2A REACTOR PRESSURE VESSEL. (NRL ; NRL-6739)

NOTCH DUCTILITY AND TENSILE PROPERTY EVALUATION OF THE PM-2A REACTOR PRESSURE VESSEL. (NRL ; NRL-6739)
Paper図書
SERPAN, C.Z.JR.
Other Libraries in Japan

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