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An approach to the quantification of seismic margins in nuclear power plants : the importance of BWR plant systems and functions to seismic margins / / prepared by P.J. Amico
| An approach to the quantification of seismic margins in nuclear power plants : the importance of BWR plant systems and functions to seismic margins / / prepared by P.J. Amico |
| Autore | Amico P. J. |
| Pubbl/distr/stampa | Washington, D.C. : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1988 |
| Descrizione fisica | 1 online resource (vii, 33 pages) : illustrations |
| Soggetto topico |
Nuclear power plants - Earthquake effects - United States
Seismology - United States |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Approach to the quantification of seismic margins in nuclear power plants |
| Record Nr. | UNINA-9910706834803321 |
Amico P. J.
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| Washington, D.C. : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1988 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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A computer code for fire protection and risk analysis of nuclear plants / / prepared by A.K. Singhal, S.D. Habchi, A.J. Przekwas
| A computer code for fire protection and risk analysis of nuclear plants / / prepared by A.K. Singhal, S.D. Habchi, A.J. Przekwas |
| Autore | Singhal A. K. |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1988 |
| Descrizione fisica | 1 online resource (xi, 69 pages) : illustrations |
| Soggetto topico |
Nuclear reactors - Computer programs
Nuclear reactors - Fires and fire prevention Nuclear power plants - Fires and fire prevention |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706815303321 |
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Singhal A. K.
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| Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1988 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Estimation of fracture toughness of cast stainless steels during thermal aging in LWR systems [[electronic resource] /] / prepared by O.K. Chopra
| Estimation of fracture toughness of cast stainless steels during thermal aging in LWR systems [[electronic resource] /] / prepared by O.K. Chopra |
| Autore | Chopra O. K |
| Edizione | [Rev. 1.] |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1994 |
| Descrizione fisica | xiii, 54, 12 pages : digital, PDF file |
| Soggetto topico |
Stainless steel - Effect of temperature on
Stainless steel - Embrittlement Light water reactors - Materials - Effect of temperature on Light water reactors - Materials - Embrittlement |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910698568003321 |
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Chopra O. K
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| Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1994 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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An experimental investigation of internally ignited fires in nuclear power plant control cabinets [[electronic resource] / J.M. Chavez]
| An experimental investigation of internally ignited fires in nuclear power plant control cabinets [[electronic resource] / J.M. Chavez] |
| Autore | Chavez James M |
| Pubbl/distr/stampa | Washington, DC, : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987-1988 |
| Descrizione fisica | 2 volumes : digital, PDF file |
| Altri autori (Persone) | NowlenS. P |
| Soggetto topico |
Nuclear power plants - Fires and fire prevention
Nuclear power plants - Control rooms - Safety measures Control boards (Electrical engineering) - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Nota di contenuto | pt. 1. Cabinet effects tests / J.M. Chavez -- pt. 2. Room effects tests / prepared by J.M. Chavez, S.P. Nowlen. |
| Record Nr. | UNINA-9910697212503321 |
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Chavez James M
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| Washington, DC, : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1987-1988 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Guide for preparing operating procedures for shipping packages / / prepared by M.C. Witte
| Guide for preparing operating procedures for shipping packages / / prepared by M.C. Witte |
| Autore | Witte M. C. |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , December 1988 |
| Descrizione fisica | 1 online resource (iv, 23 pages) : illustrations |
| Soggetto topico |
Radioactive substances - Safety regulations - United States
Radioactive substances - Packing - United States |
| Soggetto genere / forma | Handbooks and manuals. |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910706736403321 |
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Witte M. C.
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| Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , December 1988 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Initial assessment of the mechanisms and significance of low-temperature embrittlement of cast stainless steels in LWR systems [[electronic resource] /] / prepared by O.K. Chopra, A. Sather
| Initial assessment of the mechanisms and significance of low-temperature embrittlement of cast stainless steels in LWR systems [[electronic resource] /] / prepared by O.K. Chopra, A. Sather |
| Autore | Chopra O. K |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1990 |
| Descrizione fisica | 1 volume (various pagings) : digital, PDF file |
| Altri autori (Persone) | SatherA |
| Soggetto topico |
Steel, Cast - Effect of temperature on - Testing
Light water reactors - Materials - Fatigue Stainless steel - Fatigue |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697212103321 |
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Chopra O. K
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| Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1990 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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An investigation of the effects of thermal aging on the fire damageability of electric cables [[electronic resource] /] / prepared by S.P. Nowlen
| An investigation of the effects of thermal aging on the fire damageability of electric cables [[electronic resource] /] / prepared by S.P. Nowlen |
| Autore | Nowlen S. P |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1991 |
| Descrizione fisica | 1 volume (various pagings) : digital, PDF file |
| Soggetto topico |
Electric cables - Thermal properties
Nuclear power plants - Electronic equipment - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697211403321 |
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Nowlen S. P
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| Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1991 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Mechanical properties of thermally aged cast stainless steels from Shippingport reactor components [[microform] /] / prepared by O.K. Chopra, W.J. Shack
| Mechanical properties of thermally aged cast stainless steels from Shippingport reactor components [[microform] /] / prepared by O.K. Chopra, W.J. Shack |
| Autore | Chopra O. K |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , [1995] |
| Descrizione fisica | xiv, 154 pages : digital, PDF file |
| Altri autori (Persone) | ShackW. J |
| Soggetto topico |
Nuclear reactors - Materials - Mechanical properties
Stainless steel - Mechanical properties |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910698567203321 |
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Chopra O. K
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| Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , [1995] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Steam Generator Tube Integrity Program/Steam Generator Group Project : final project summary report / / prepared by R.J. Kurtz [and six others]
| Steam Generator Tube Integrity Program/Steam Generator Group Project : final project summary report / / prepared by R.J. Kurtz [and six others] |
| Autore | Kurtz R. J. |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1990 |
| Descrizione fisica | 1 online resource (various pagings) : illustrations (some color) |
| Soggetto topico |
Steam-boilers - United States - Testing
Steam generating heavy water reactors - Testing Pressurized water reactors - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Steam Generator Tube Integrity Program/Steam Generator Group Project |
| Record Nr. | UNINA-9910706824003321 |
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Kurtz R. J.
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| Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , May 1990 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Sulfate-attack resistance and gamma-irradiation resistance of some Portland cement based mortars / / prepared by P. Soo, L.W. Milian
| Sulfate-attack resistance and gamma-irradiation resistance of some Portland cement based mortars / / prepared by P. Soo, L.W. Milian |
| Autore | Soo P. |
| Pubbl/distr/stampa | Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1989 |
| Descrizione fisica | 1 online resource (ix, 35 pages) : illustrations |
| Soggetto topico |
Portland cement - Effect of radiation on
Concrete - Deterioration Concrete - Chemistry - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Sulfate attack resistance and gamma-irradiation resistance of some Portland cement based mortars |
| Record Nr. | UNINA-9910706814403321 |
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Soo P.
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| Washington, DC : , : Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, , 1989 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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