Analysis of the OECD/NEA PWR main steam line break (MSLB) Benchmark exercise 3 with the coupled code system RELAP5/PANBOX:
Gespeichert in:
| Format: | Buch |
|---|---|
| Sprache: | English |
| Veröffentlicht: |
Karlsruhe
Forschungszentrum Karlsruhe
2002
|
| Schriftenreihe: | Wissenschaftliche Berichte / Forschungszentrum Karlsruhe Technik und Umwelt
6518 |
| Schlagworte: | |
| Beschreibung: | V, 44 S. graph. Darst. |
Internformat
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| 245 | 1 | 0 | |a Analysis of the OECD/NEA PWR main steam line break (MSLB) Benchmark exercise 3 with the coupled code system RELAP5/PANBOX |c V. H. Sánchez-Espinoza ... |
| 264 | 1 | |a Karlsruhe |b Forschungszentrum Karlsruhe |c 2002 | |
| 300 | |a V, 44 S. |b graph. Darst. | ||
| 336 | |b txt |2 rdacontent | ||
| 337 | |b n |2 rdamedia | ||
| 338 | |b nc |2 rdacarrier | ||
| 490 | 1 | |a Wissenschaftliche Berichte / Forschungszentrum Karlsruhe Technik und Umwelt |v 6518 | |
| 650 | 4 | |a CORE MELTING OF NUCLEAR REACTORS (NUCLEAR ENGINEERING) | |
| 650 | 4 | |a DRUCKWASSERREAKTOREN, DWR (KERNTECHNIK) | |
| 650 | 4 | |a FUSION DU COEUR DE RÉACTEURS NUCLÉAIRES (TECHNIQUE NUCLÉAIRE) | |
| 650 | 4 | |a KERNSCHMELZEN VON REAKTOREN (KERNTECHNIK) | |
| 650 | 4 | |a MATHEMATICAL MODELING IN NUCLEAR ENGINEERING | |
| 650 | 4 | |a MODELLRECHNUNG/KERNTECHNIK | |
| 650 | 4 | |a MODÉLISATION MATHÉMATIQUE EN TECHNIQUE NUCLÉAIRE | |
| 650 | 4 | |a PRESSURIZED-WATER REACTORS, PWR (NUCLEAR ENGINEERING) | |
| 650 | 4 | |a REACTOR COOLING (NUCLEAR ENGINEERING) | |
| 650 | 4 | |a REAKTORKÜHLUNG (KERNTECHNIK) | |
| 650 | 4 | |a REFROIDISSEMENT DES RÉACTEURS (TECHNIQUE NUCLÉAIRE) | |
| 650 | 4 | |a RÉACTEURS À EAU SOUS PRESSION, REP (TECHNIQUE NUCLÉAIRE) | |
| 700 | 1 | |a Sánchez Espinoza, Victor Hugo |e Sonstige |4 oth | |
| 810 | 2 | |a Forschungszentrum Karlsruhe Technik und Umwelt |t Wissenschaftliche Berichte |v 6518 |w (DE-604)BV010181833 |9 6518 | |
| 999 | |a oai:aleph.bib-bvb.de:BVB01-009984247 | ||
Datensatz im Suchindex
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| id | DE-604.BV014732627 |
| illustrated | Illustrated |
| indexdate | 2024-07-09T19:05:37Z |
| institution | BVB |
| language | English |
| oai_aleph_id | oai:aleph.bib-bvb.de:BVB01-009984247 |
| oclc_num | 633828269 |
| open_access_boolean | |
| owner | DE-12 |
| owner_facet | DE-12 |
| physical | V, 44 S. graph. Darst. |
| publishDate | 2002 |
| publishDateSearch | 2002 |
| publishDateSort | 2002 |
| publisher | Forschungszentrum Karlsruhe |
| record_format | marc |
| series2 | Wissenschaftliche Berichte / Forschungszentrum Karlsruhe Technik und Umwelt |
| spelling | Analysis of the OECD/NEA PWR main steam line break (MSLB) Benchmark exercise 3 with the coupled code system RELAP5/PANBOX V. H. Sánchez-Espinoza ... Karlsruhe Forschungszentrum Karlsruhe 2002 V, 44 S. graph. Darst. txt rdacontent n rdamedia nc rdacarrier Wissenschaftliche Berichte / Forschungszentrum Karlsruhe Technik und Umwelt 6518 CORE MELTING OF NUCLEAR REACTORS (NUCLEAR ENGINEERING) DRUCKWASSERREAKTOREN, DWR (KERNTECHNIK) FUSION DU COEUR DE RÉACTEURS NUCLÉAIRES (TECHNIQUE NUCLÉAIRE) KERNSCHMELZEN VON REAKTOREN (KERNTECHNIK) MATHEMATICAL MODELING IN NUCLEAR ENGINEERING MODELLRECHNUNG/KERNTECHNIK MODÉLISATION MATHÉMATIQUE EN TECHNIQUE NUCLÉAIRE PRESSURIZED-WATER REACTORS, PWR (NUCLEAR ENGINEERING) REACTOR COOLING (NUCLEAR ENGINEERING) REAKTORKÜHLUNG (KERNTECHNIK) REFROIDISSEMENT DES RÉACTEURS (TECHNIQUE NUCLÉAIRE) RÉACTEURS À EAU SOUS PRESSION, REP (TECHNIQUE NUCLÉAIRE) Sánchez Espinoza, Victor Hugo Sonstige oth Forschungszentrum Karlsruhe Technik und Umwelt Wissenschaftliche Berichte 6518 (DE-604)BV010181833 6518 |
| spellingShingle | Analysis of the OECD/NEA PWR main steam line break (MSLB) Benchmark exercise 3 with the coupled code system RELAP5/PANBOX CORE MELTING OF NUCLEAR REACTORS (NUCLEAR ENGINEERING) DRUCKWASSERREAKTOREN, DWR (KERNTECHNIK) FUSION DU COEUR DE RÉACTEURS NUCLÉAIRES (TECHNIQUE NUCLÉAIRE) KERNSCHMELZEN VON REAKTOREN (KERNTECHNIK) MATHEMATICAL MODELING IN NUCLEAR ENGINEERING MODELLRECHNUNG/KERNTECHNIK MODÉLISATION MATHÉMATIQUE EN TECHNIQUE NUCLÉAIRE PRESSURIZED-WATER REACTORS, PWR (NUCLEAR ENGINEERING) REACTOR COOLING (NUCLEAR ENGINEERING) REAKTORKÜHLUNG (KERNTECHNIK) REFROIDISSEMENT DES RÉACTEURS (TECHNIQUE NUCLÉAIRE) RÉACTEURS À EAU SOUS PRESSION, REP (TECHNIQUE NUCLÉAIRE) |
| title | Analysis of the OECD/NEA PWR main steam line break (MSLB) Benchmark exercise 3 with the coupled code system RELAP5/PANBOX |
| title_auth | Analysis of the OECD/NEA PWR main steam line break (MSLB) Benchmark exercise 3 with the coupled code system RELAP5/PANBOX |
| title_exact_search | Analysis of the OECD/NEA PWR main steam line break (MSLB) Benchmark exercise 3 with the coupled code system RELAP5/PANBOX |
| title_full | Analysis of the OECD/NEA PWR main steam line break (MSLB) Benchmark exercise 3 with the coupled code system RELAP5/PANBOX V. H. Sánchez-Espinoza ... |
| title_fullStr | Analysis of the OECD/NEA PWR main steam line break (MSLB) Benchmark exercise 3 with the coupled code system RELAP5/PANBOX V. H. Sánchez-Espinoza ... |
| title_full_unstemmed | Analysis of the OECD/NEA PWR main steam line break (MSLB) Benchmark exercise 3 with the coupled code system RELAP5/PANBOX V. H. Sánchez-Espinoza ... |
| title_short | Analysis of the OECD/NEA PWR main steam line break (MSLB) Benchmark exercise 3 with the coupled code system RELAP5/PANBOX |
| title_sort | analysis of the oecd nea pwr main steam line break mslb benchmark exercise 3 with the coupled code system relap5 panbox |
| topic | CORE MELTING OF NUCLEAR REACTORS (NUCLEAR ENGINEERING) DRUCKWASSERREAKTOREN, DWR (KERNTECHNIK) FUSION DU COEUR DE RÉACTEURS NUCLÉAIRES (TECHNIQUE NUCLÉAIRE) KERNSCHMELZEN VON REAKTOREN (KERNTECHNIK) MATHEMATICAL MODELING IN NUCLEAR ENGINEERING MODELLRECHNUNG/KERNTECHNIK MODÉLISATION MATHÉMATIQUE EN TECHNIQUE NUCLÉAIRE PRESSURIZED-WATER REACTORS, PWR (NUCLEAR ENGINEERING) REACTOR COOLING (NUCLEAR ENGINEERING) REAKTORKÜHLUNG (KERNTECHNIK) REFROIDISSEMENT DES RÉACTEURS (TECHNIQUE NUCLÉAIRE) RÉACTEURS À EAU SOUS PRESSION, REP (TECHNIQUE NUCLÉAIRE) |
| topic_facet | CORE MELTING OF NUCLEAR REACTORS (NUCLEAR ENGINEERING) DRUCKWASSERREAKTOREN, DWR (KERNTECHNIK) FUSION DU COEUR DE RÉACTEURS NUCLÉAIRES (TECHNIQUE NUCLÉAIRE) KERNSCHMELZEN VON REAKTOREN (KERNTECHNIK) MATHEMATICAL MODELING IN NUCLEAR ENGINEERING MODELLRECHNUNG/KERNTECHNIK MODÉLISATION MATHÉMATIQUE EN TECHNIQUE NUCLÉAIRE PRESSURIZED-WATER REACTORS, PWR (NUCLEAR ENGINEERING) REACTOR COOLING (NUCLEAR ENGINEERING) REAKTORKÜHLUNG (KERNTECHNIK) REFROIDISSEMENT DES RÉACTEURS (TECHNIQUE NUCLÉAIRE) RÉACTEURS À EAU SOUS PRESSION, REP (TECHNIQUE NUCLÉAIRE) |
| volume_link | (DE-604)BV010181833 |
| work_keys_str_mv | AT sanchezespinozavictorhugo analysisoftheoecdneapwrmainsteamlinebreakmslbbenchmarkexercise3withthecoupledcodesystemrelap5panbox |