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Proceedings of the ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics : held at Saratoga Springs, New York, October 5-8, 1980 R. Ripple, technical program chairman ; R. Gay, general program chairman ; sponsored by the American Nuclear Society, Technical Group for Thermal-Hydraulics, the American Society of Mechanical Engineers, Heat Transfer Division, the U.S. Nuclear Regulatory Commission, Office of Nuclear Research ; proceedings prepared by the Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission.

By: ANS/ASME/NRC International Topical Meeting on Nuclear Reactor Thermal-Hydraulics Saratoga Springs, N.Y. 1980Contributor(s): Gay, Rodney R | Ripple, R | American Nuclear Society. Technical Group for Thermal-Hydraulics | American Society of Mechanical Engineers. Heat Transfer Division | U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory ResearchMaterial type: TextTextLanguage: English Series: U. S. Nuclear Regulatory Commission ; NUREG/CP-0014 | U. S. Nuclear Regulatory Commission ; vol. 3Publication details: Springfield Va Available from GPO Sales Program Division of Technical Information and Document Control U.S. Nuclear Regulatory Commission ; Washington D C The Commission : 1980 Description: 3 v. (xi, 2425 p.), ill. 28 cmReport number: NUREG/CP-0014Subject(s): Nuclear reactors -- Congresses. -- Containment | Nuclear reactors -- Congresses. -- Safety measuresDDC classification: 621.4835 ANS 1980
Contents:
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Item type Current library Home library Collection Call number Vol info Copy number Status Date due Barcode
Raporlar Raporlar
Raporlar
TENMAK Kütüphanesi
Raporlar 621.4835 ANS 1980 (Browse shelf(Opens below)) 1 1 Available T3369

"Date published: October 1980."

"NUREG/CP-0014."

Includes bibliographical references.

v. 1. PWR and BWR reactor-plant performance analysis and containment technology -- v. 2. Fundamental aspects of two-phase flow and boiling heat transfer -- v. 3. LMFBR and HTGR advanced reactor concepts and analysis methods.

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