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Background and derivation of ANS-5.4 standard fission product release model [[electronic resource] /] / prepared by J.A. Turnbull, C.E. Beyer
| Background and derivation of ANS-5.4 standard fission product release model [[electronic resource] /] / prepared by J.A. Turnbull, C.E. Beyer |
| Autore | Turnbull J. A |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] |
| Descrizione fisica | 1 online resource (41 pages) : illustrations |
| Altri autori (Persone) | BeyerC. E |
| Soggetto topico |
Light water reactors - Testing
Fission products - Spectra Nuclear fuels Fission gases Radioisotopes |
| Formato | Materiale a stampa  |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910698442503321 |
Turnbull J. A
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Computational fluid dynamics analysis of natural circulation flows in a pressurized-water reactor loop under severe accident conditions [[electronic resource] /] / prepared by C.F. Boyd and K.W. Armstrong
| Computational fluid dynamics analysis of natural circulation flows in a pressurized-water reactor loop under severe accident conditions [[electronic resource] /] / prepared by C.F. Boyd and K.W. Armstrong |
| Autore | Boyd Christopher Fred |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] |
| Descrizione fisica | 1 online resource (78 pages) : illustrations |
| Altri autori (Persone) | ArmstrongK. W |
| Soggetto topico |
Computational fluid dynamics - Accidents
Steam generating heavy water reactors - Accidents |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697025703321 |
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Boyd Christopher Fred
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Essential elements of an electric cable condition monitoring program [[electronic resource] /] / prepared by M. Villaran and R. Lofaro
| Essential elements of an electric cable condition monitoring program [[electronic resource] /] / prepared by M. Villaran and R. Lofaro |
| Autore | Villaran M (Michael) |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] |
| Descrizione fisica | 1 online resource (123 pages) : illustrations |
| Altri autori (Persone) | LofaroR (Robert) |
| Soggetto topico | Electric cables - Monitoring |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910696912903321 |
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Villaran M (Michael)
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Modeling a digital feedwater control system using traditional probabilistic risk assessment methods [[electronic resource] ] : final report / / prepared by T.L. Chu ... [and others]
| Modeling a digital feedwater control system using traditional probabilistic risk assessment methods [[electronic resource] ] : final report / / prepared by T.L. Chu ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2009] |
| Descrizione fisica | 1 online resource (158 pages) : illustrations |
| Altri autori (Persone) | ChuT. L |
| Soggetto topico |
Nuclear power plants - Computer programs - Risk assessment
Feed-water - Control - Computer programs - Risk assessment Digital control systems - Risk assessment |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Altri titoli varianti | Modeling a digital feedwater control system using traditional probabilistic risk assessment methods |
| Record Nr. | UNINA-9910697065703321 |
| Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2009] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Review of information for spent nuclear fuel burnup confirmation [[electronic resource] /] / prepared by B.B. Bevard ... [and others]
| Review of information for spent nuclear fuel burnup confirmation [[electronic resource] /] / prepared by B.B. Bevard ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2009] |
| Descrizione fisica | 1 online resource (xvi, 60 pages) : illustrations |
| Altri autori (Persone) | BevardB. B |
| Soggetto topico |
Spent reactor fuels - United States
Fuel burnup (Nuclear engineering) |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910699346703321 |
| Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2009] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Sensitivity studies of the probabilistic fracture mechanics model used in FAVOR [[electronic resource] /] / prepared by M. EricksonKirk ... [and others]
| Sensitivity studies of the probabilistic fracture mechanics model used in FAVOR [[electronic resource] /] / prepared by M. EricksonKirk ... [and others] |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] |
| Descrizione fisica | 1 online resource (84 pages) : illustrations |
| Altri autori (Persone) | EricksonKirkM |
| Soggetto topico |
Nuclear reactors - Reactivity
Fracture mechanics Materials - Fatigue |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697026103321 |
| Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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Spent fuel decay heat measurements performed at the Swedish central interim storage facility [[electronic resource] /] / prepared by B.D. Murphy and I.C. Gauld
| Spent fuel decay heat measurements performed at the Swedish central interim storage facility [[electronic resource] /] / prepared by B.D. Murphy and I.C. Gauld |
| Autore | Murphy B. D |
| Pubbl/distr/stampa | Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] |
| Descrizione fisica | 1 online resource (xi, 67, 7, 5 pages) : color illustrations |
| Altri autori (Persone) | GauldI. C |
| Soggetto topico |
Radioactive decay - Measurement
Spent reactor fuels - Storage - Sweden |
| Formato | Materiale a stampa |
| Livello bibliografico | Monografia |
| Lingua di pubblicazione | eng |
| Record Nr. | UNINA-9910697066503321 |
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Murphy B. D
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| Washington, DC : , : U. S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, , [2010] | ||
| Materiale a stampa | ||
| Lo trovi qui: Univ. Federico II | ||
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