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(Availability of) an international report on safety critical software for nuclear reactors by the regulator task force on safety critical software (TF-SCS) / / prepared by Sushil Birla, Russell Sydnor
| (Availability of) an international report on safety critical software for nuclear reactors by the regulator task force on safety critical software (TF-SCS) / / prepared by Sushil Birla, Russell Sydnor |
| Autore | Birla Sushil |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2015 |
| Descrizione fisica | 1 online resource (185 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico | Nuclear reactors - Safety measures |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | International report on safety critical software for nuclear reactors by the regulator task force on safety critical software (TF-SCS) |
| Record Nr. | UNINA-9910704265003321 |
Birla Sushil
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Acceptance and verification for early warning fire detection systems [[electronic resource] ] : interim guide / / J.L. Boccio and R.E. Hall and I. Asp
| Acceptance and verification for early warning fire detection systems [[electronic resource] ] : interim guide / / J.L. Boccio and R.E. Hall and I. Asp |
| Autore | Boccio J. L |
| Pubbl/distr/stampa | Washington, D.C. : , : U.S. Nuclear Regulatory Commission, , [1980] |
| Descrizione fisica | vii, 100 leaves |
| Altri autori (Persone) |
HallR. E
AspI |
| Soggetto topico |
Nuclear power plants - Fires and fire prevention - United States
Fire detectors - United States - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Acceptance and verification for early warning fire detection systems |
| Record Nr. | UNINA-9910697840403321 |
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Boccio J. L
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| Washington, D.C. : , : U.S. Nuclear Regulatory Commission, , [1980] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Accountability and performance report / / U.S. Nuclear Regulatory Commission
| Accountability and performance report / / U.S. Nuclear Regulatory Commission |
| Pubbl/distr/stampa | Washington, D.C., : U.S. Nuclear Regulatory Commission, [-2016] |
| Descrizione fisica | 1 online resource |
| Disciplina | 353 |
| Soggetto topico |
Nuclear energy - Government policy - United States
Énergie nucléaire - Politique gouvernementale - États-Unis Expenditures, Public Nuclear energy - Government policy |
| Soggetto genere / forma | Periodicals. |
| ISSN | 2375-9666 |
| Formato | Materiale a stampa |
| Livello bibliografico | Periodico |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Performance and accountability report |
| Record Nr. | UNINA-9910693409003321 |
| Washington, D.C., : U.S. Nuclear Regulatory Commission, [-2016] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding / / prepared by A. Shestopalov, K. Lioutov, L. Yegorova
| Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb (VVER type) cladding / / prepared by A. Shestopalov, K. Lioutov, L. Yegorova |
| Autore | Shestopalov A. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , April 2003 |
| Descrizione fisica | 1 online resource (xiii, 51 pages) : illustrations |
| Collana | International agreement report |
| Soggetto topico |
Nuclear fuel claddings
Niobium-zirconium alloys Nuclear fuel rods - Safety measures Fuel burnup (Nuclear engineering) - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Adaptation of USNRC's FRAPTRAN and IRSN's SCANAIR transient codes and updating of MATPRO package for modeling of LOCA and RIA validation cases with Zr-1%Nb |
| Record Nr. | UNINA-9910707861503321 |
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Shestopalov A.
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , April 2003 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Advanced nondestructive evaluation for steam generator tubing [[electronic resource] /] / prepared by Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission
| Advanced nondestructive evaluation for steam generator tubing [[electronic resource] /] / prepared by Division of Engineering Technology, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission |
| Edizione | [Corr. ed.] |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2003] |
| Descrizione fisica | xvii, 94 pages : digital, PDF file |
| Soggetto topico |
Tubes - Evaluation
Nondestructive testing Steam power plants - Equipment and supplies - Evaluation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910692060203321 |
| Washington, DC : , : U.S. Nuclear Regulatory Commission, , [2003] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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The alternate mitigation strategies study of Chinshan BWR/4 by using the LOCA and SBO analysis of TRACE / / prepared by: Jong-Rong Wang [and three others]
| The alternate mitigation strategies study of Chinshan BWR/4 by using the LOCA and SBO analysis of TRACE / / prepared by: Jong-Rong Wang [and three others] |
| Autore | Wang Jong-Rong |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 |
| Descrizione fisica | 1 online resource (57 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Boiling water reactors - Taiwan - Safety measures
Boiling water reactors - Taiwan - Computer simulation Boiling water reactors - Accidents - Taiwan - Computer simulation Nuclear power plants - Accidents - Taiwan - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910705253103321 |
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Wang Jong-Rong
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2014 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis of loss of feedwater heater transients for Lungmen ABWR by TRACE/PARCS / / prepared by: Jong-Rong Wang ... [and three others]
| Analysis of loss of feedwater heater transients for Lungmen ABWR by TRACE/PARCS / / prepared by: Jong-Rong Wang ... [and three others] |
| Autore | Wang Jong-Rong |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 |
| Descrizione fisica | 1 online resource (45 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Taiwan - Safety measures
Pressurized water reactors - Taiwan - Testing Nuclear power plants - Safety measures - Computer programs |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910704813003321 |
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Wang Jong-Rong
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis of the control rod drop accident (CRDA) for lungmen ABWR / / prepared by Chunkuan Shih [and five others]
| Analysis of the control rod drop accident (CRDA) for lungmen ABWR / / prepared by Chunkuan Shih [and five others] |
| Autore | Shih Chunkuan |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , August 2015 |
| Descrizione fisica | 1 online resource (53 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Boiling water reactors - Accidents - Computer simulation
Nuclear power plants - Safety measures |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis of the control rod drop accident |
| Record Nr. | UNINA-9910703981503321 |
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Shih Chunkuan
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , August 2015 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / / prepared by: S. Belaïd, J. Freixa, O. Zerkak
| Analysis of the test OECD-PKL2 G7.1 with the thermal-hydraulic system code TRACE / / prepared by: S. Belaïd, J. Freixa, O. Zerkak |
| Autore | Belaïd S. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 |
| Descrizione fisica | 1 online resource (xiii, 29 pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Pressurized water reactors - Testing
Emergency core cooling systems - Testing Pressurized water reactors - Equipment and supplies - Effect of temperature on - Measurement Nuclear fuel claddings - Effect of temperature on - Measurement Nuclear power plants - Safety measures - Testing |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis of the test Organisation for Economic Co-operation and Development-Primary Coolant Loop Test Facility G7.1 with the thermal-hydraulic system code TRACE |
| Record Nr. | UNINA-9910704812803321 |
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Belaïd S.
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Analysis with TRACE code of PKL-III test F 1.2 / / prepared by: J.L. Munoz-Cobo, S. Chiva, A. Escrivà
| Analysis with TRACE code of PKL-III test F 1.2 / / prepared by: J.L. Munoz-Cobo, S. Chiva, A. Escrivà |
| Autore | Muñoz-Cobo J. L. |
| Pubbl/distr/stampa | Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 |
| Descrizione fisica | 1 online resource (37 unnumbered pages) : color illustrations |
| Collana | International agreement report |
| Soggetto topico |
Light water reactors - Accidents - Computer simulation
Nuclear power plants - Accidents - Computer simulation |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Analysis with TRAC/RELAP Advanced Computational Engine code of PKL-III test F 1.2 |
| Record Nr. | UNINA-9910704414903321 |
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Muñoz-Cobo J. L.
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| Washington, DC : , : U.S. Nuclear Regulatory Commission, , 2013 | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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