Recent plant studies using Victoria 2.0 [electronic resource]
VICTORIA 2.0 is a mechanistic computer code designed to analyze fission product behavior within the reactor coolant system (RCS) during a severe nuclear reactor accident. It provides detailed predictions of the release of radioactive and nonradioactive materials from the reactor core and transport a...
Saved in:
| Online Access: |
Online Access |
|---|---|
| Corporate Author: | |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C : Oak Ridge, Tenn. :
United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
2000.
|
| Subjects: |
MARC
| LEADER | 00000nam a22000003u 4500 | ||
|---|---|---|---|
| 001 | b6980833 | ||
| 003 | CoU | ||
| 005 | 20080205000000.0 | ||
| 006 | m d f | ||
| 007 | cr ||||||||||| | ||
| 008 | 110824e20000308dcu o| f1|||||eng|d | ||
| 035 | |a (TOE)ost752615 | ||
| 035 | |a (TOE)752615 | ||
| 040 | |a TOE |c TOE | ||
| 049 | |a GDWR | ||
| 072 | 7 | |a 22 |2 edbsc | |
| 072 | 7 | |a 21 |2 edbsc | |
| 072 | 7 | |a 99 |2 edbsc | |
| 086 | 0 | |a E 1.99:sand2000-0605c | |
| 086 | 0 | |a E 1.99:sand2000-0605c | |
| 088 | |a sand2000-0605c | ||
| 245 | 0 | 0 | |a Recent plant studies using Victoria 2.0 |h [electronic resource] |
| 260 | |a Washington, D.C : |b United States. Dept. of Energy ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, |c 2000. | ||
| 300 | |a 11 pages : |b digital, PDF file. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through the Information Bridge: DOE Scientific and Technical Information. | ||
| 500 | |a 03/08/2000. | ||
| 500 | |a "sand2000-0605c" | ||
| 500 | |a ICONE 8 Conference (8th International Conference on Nuclear Engineering), Baltimore; MD (US), 04/02/2000--04/06/2000. | ||
| 500 | |a BIXLER,THAN E.; GASSER,ROLD D. | ||
| 520 | 3 | |a VICTORIA 2.0 is a mechanistic computer code designed to analyze fission product behavior within the reactor coolant system (RCS) during a severe nuclear reactor accident. It provides detailed predictions of the release of radioactive and nonradioactive materials from the reactor core and transport and deposition of these materials within the RCS and secondary circuits. These predictions account for the chemical and aerosol processes that affect radionuclide behavior. VICTORIA 2.0 was released in early 1999; a new version VICTORIA 2.1, is now under development. The largest improvements in VICTORIA 2.1 are connected with the thermochemical database, which is being revised and expanded following the recommendations of a peer review. Three risk-significant severe accident sequences have recently been investigated using the VICTORIA 2.0 code. The focus here is on how various chemistry options affect the predictions. Additionally, the VICTORIA predictions are compared with ones made using the MELCOR code. The three sequences are a station blackout in a GE BWR and steam generator tube rupture (SGTR) and pump-seal LOCA sequences in a 3-loop Westinghouse PWR. These sequences cover a range of system pressures, from fully depressurized to full system pressure. The chief results of this study are the fission product fractions that are retained in the core, RCS, secondary, and containment and the fractions that are released into the environment. | |
| 520 | 0 | |a Aerosols; Releases; Severe Accident; Chemistry; Fission Products. | |
| 536 | |b AC04-94AL85000. | ||
| 650 | 7 | |a Radioactive Aerosols. |2 local. | |
| 650 | 7 | |a Containment Buildings. |2 local. | |
| 650 | 7 | |a Fission Product Release. |2 local. | |
| 650 | 7 | |a Bwr Type Reactors. |2 local. | |
| 650 | 7 | |a Pwr Type Reactors. |2 local. | |
| 650 | 7 | |a Biosphere. |2 local. | |
| 650 | 7 | |a Reactor Cooling Systems. |2 local. | |
| 650 | 7 | |a V Codes. |2 local. | |
| 650 | 7 | |a Reactor Accidents. |2 local. | |
| 650 | 7 | |a General And Miscellaneous//mathematics, Computing, And Information Science. |2 edbsc. | |
| 650 | 7 | |a General Studies Of Nuclear Reactors. |2 edbsc. | |
| 650 | 7 | |a Specific Nuclear Reactors And Associated Plants. |2 edbsc. | |
| 710 | 2 | |a Sandia National Laboratories. |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |4 spn. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
| 856 | 4 | 0 | |u http://www.osti.gov/servlets/purl/752615-NDdqVC/webviewable/ |z Online Access |
| 907 | |a .b69808338 |b 03-06-23 |c 03-31-12 | ||
| 998 | |a web |b 03-31-12 |c f |d m |e p |f eng |g dcu |h 0 |i 1 | ||
| 956 | |a Information bridge | ||
| 999 | f | f | |i 4ced74ca-824c-5fb1-8856-0eb241ea0df7 |s e6ec2184-ab97-5e80-99cc-2e4012672d10 |
| 952 | f | f | |p Can circulate |a University of Colorado Boulder |b Online |c Online |d Online |e E 1.99:sand2000-0605c |h Superintendent of Documents classification |i web |n 1 |