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

Nuclear reactor neutron energy spectra. (ASTM data series publication, DS 52)
紙図書
Serpan, C.Z. Jr./Menke, B.H.ASTM1974.
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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)
紙図書
Serpan, C.Z. Jr., Steele, L.E.Naval Research Lab.1964.6.2.
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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)
紙図書
Steele, L.E., Hawthorne, J.R., Serpan, C.Z. Jr.Naval Research Lab.1964.8.15.
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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)
紙図書
Steele, L.E., Hawthorne, J.R., Serpan, C.Z. Jr.Naval Research Lab.1963.11.15.
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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)
紙図書
Serpan, C.Z. Jr., Watson, H.E., Hawthorne, J.R. [et al.]Naval Research Lab.1964.9.18.
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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)
紙図書
SERPAN, C.Z.JR.
全国の図書館
  • 著者標目SERPAN, C.Z.JR.

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)
紙図書
SERPAN, C.Z.JR.
全国の図書館
  • 著者標目SERPAN, C.Z.JR.

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

RADIATION DAMAGE SURVEILLANCE OF POWER REACTOR PRESSURE VESSELS. (NRL ; NRL-6349)
紙図書
SERPAN, C.Z.JR.
全国の図書館
  • 著者標目SERPAN, C.Z.JR.

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)
紙図書
SERPAN, C.Z.JR.
全国の図書館
  • 著者標目SERPAN, C.Z.JR.

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)
紙図書
SERPAN, C.Z.JR.
全国の図書館
  • 著者標目SERPAN, C.Z.JR.

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)
紙図書
SERPAN, C.Z.JR.
全国の図書館
  • 著者標目SERPAN, C.Z.JR.

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