Published 1986
| Version v1
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Analysis of hydrogen production during a BWR6 core heatup transient
Description
An extensive study was performed for the prediction of hydrogen production during a BWR6 core heatup transient. Hydrogen production was found to be strongly affected by the transient core heat transfer and vessel hydrodynamics. Various sources important for steam generation and hydrogen production were identified. The results of the study were used by the NRC staff in their evaluation of the adequacy of the H2 release histories suggested by the Hydrogen Control Owner's Group (HCOG). The owners group are sponsoring a 1/4 scale test program to investigate the adequacy of H2 control during a degraded event. 1 ref., 2 figs
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as TI86001200.Files
17044900.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 8 p.
- Report number
- BNL-NUREG--37004
Conference
- Title
- Thermal reactor safety meeting.
- Dates
- 2-6 Feb 1986.
- Place
- San Diego, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17044900
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CHEMICAL REACTIONS; COMPUTER CALCULATIONS; EXPLOSIONS; GE STANDARD REACTOR; HEAT TRANSFER; HYDRAULICS; HYDROGEN; LOSS OF COOLANT; PRESSURIZATION; PRODUCTION; REACTOR CORE DISRUPTION; REACTOR SAFETY; REACTOR VESSELS; STEAM; ZIRCALOY
- Descriptors DEC
- ACCIDENTS; ALLOYS; BWR TYPE REACTORS; CONTAINERS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; NONMETALS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS
Optional Information
- Secondary number(s)
- CONF-860204--2.