Analysis of reactor vessel radiation effects surveillance programs / / prepared by L.E. Steele and C.Z. Serpan, Jr |
Pubbl/distr/stampa | Philadelphia : , : American Society for Testing & Materials, , 1970 |
Descrizione fisica | 1 online resource (270 pages) : illustrations, forms |
Disciplina | 621.4831 |
Altri autori (Persone) | SteeleL. E <1928-> (Lendell E.) |
Collana | ASTM special technical publication |
Soggetto topico |
Nuclear pressure vessels - Testing
Steel - Effect of radiation on |
ISBN | 0-8031-4592-6 |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910164726703321 |
Philadelphia : , : American Society for Testing & Materials, , 1970 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Characterization of flaws in U.S. reactor pressure vessels |
Pubbl/distr/stampa | Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1998-2000 |
Descrizione fisica | 1 online resource (3 volumes) : illustrations |
Soggetto topico |
Nuclear pressure vessels - Testing
Nondestructive testing |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Nota di contenuto | vol. 1. Density and distribution of flaw indications in PVRUF / prepared by G.J. Schuster, S.R. Doctor, P.G. Heasler -- vol. 2. Validation of flaw density and distribution in the weld metal of the PVRUF vessel / G.J. Schuster [and three others] -- vol. 3. Density and distribution of flaw indications in PVRUF / prepared by G.J. Schuster [and three others]. |
Altri titoli varianti |
Characterization of flaws in US reactor pressure vessels
Characterization of flaws in United States reactor pressure vessels |
Record Nr. | UNINA-9910707106303321 |
Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1998-2000 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Final results of the hydrogen igniter experimental program / / prepared by W. E. Lowry, B. R. Bowman, B. W. Davis |
Autore | Lowry W. E. |
Pubbl/distr/stampa | Washington, D.C. : , : Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , February 1982 |
Descrizione fisica | 1 online resource (ix, 51 pages) : illustrations |
Soggetto topico |
Nuclear reactor kinetics
Nuclear reactors - Materials - Thermal properties Nuclear reactors - Containment Nuclear pressure vessels - Testing |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910706521403321 |
Lowry W. E. | ||
Washington, D.C. : , : Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, , February 1982 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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A generalized procedure for generating flaw-related inputs for the FAVOR code / / prepared by F.A. Simonen [and three others] |
Autore | Simonen F. A. |
Pubbl/distr/stampa | Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , March 2004 |
Descrizione fisica | 1 online resource (various pagings) : illustrations |
Soggetto topico |
Ultrasonic testing
Pressure vessels - Testing Nuclear pressure vessels - Testing |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910707679503321 |
Simonen F. A. | ||
Washington, DC : , : Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , March 2004 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Implementation of regulatory guide 1.150, Ultrasonic testing of reactor vessel welds during preservice and inservice examinations, revision 1 |
Pubbl/distr/stampa | Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1983 |
Descrizione fisica | 1 online resource |
Collana | Generic letter |
Soggetto topico |
Nuclear pressure vessels - Testing
Nuclear pressure vessels - Welding |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910716082503321 |
Washington, D.C. : , : United States Nuclear Regulatory Commission, , 1983 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Integrated chemical effects test project [[electronic resource] /] / J Dallman ... [and others] |
Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Fuel, Engineering and Radiological Research, , [2007] |
Descrizione fisica | 1 electronic text (5 volumes) : HTML, digital, PDF file |
Altri autori (Persone) | DallmanJ |
Soggetto topico |
Nuclear pressure vessels - Testing
Nuclear power plants - Testing |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910696858303321 |
Washington, DC : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Fuel, Engineering and Radiological Research, , [2007] | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Peer review of GSI-191 chemical effects research program / / prepared by P.A. Torres |
Autore | Torres P. A. |
Pubbl/distr/stampa | Washington, DC : , : Division of Fuel, Engineering and Radiological Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , December 2006 |
Descrizione fisica | 1 online resource (various pagings) : illustrations |
Soggetto topico |
Pressurized water reactors - Loss of coolant
Pressurized water reactors Emergency core cooling systems Nuclear pressure vessels - Testing Nuclear reactor accidents |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Altri titoli varianti |
Peer review of GSI 191 chemical effects research program
Peer review of generic safety issue 191 chemical effects research program |
Record Nr. | UNINA-9910707945103321 |
Torres P. A. | ||
Washington, DC : , : Division of Fuel, Engineering and Radiological Research, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , December 2006 | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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Post-refueling outage reactor pressure vessel leak testing before core criticality [[electronic resource]] |
Pubbl/distr/stampa | Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1998] |
Descrizione fisica | 1 online resource |
Collana | NRC information notice |
Soggetto topico |
Nuclear pressure vessels - Testing
Nuclear reactors - Reactivity |
Formato | Materiale a stampa |
Livello bibliografico | Monografia |
Lingua di pubblicazione | eng |
Record Nr. | UNINA-9910699604303321 |
Washington, D.C. : , : U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, , [1998] | ||
Materiale a stampa | ||
Lo trovi qui: Univ. Federico II | ||
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