Published 2004
| Version v1
Book
LOCA induced debris characteristics for use in ECCS sump screen debris bed pressure drop calculations
Creators
- 1. Alion Science and Technology (United States)
- 2. ARTEK Inc. (United States)
- 3. Corrosion Control Consultants and Labs, Inc (United States)
Description
Pressure drop calculations across a LOCA induced fibrous debris bed have been successfully demonstrated to be accurate using the NUREG/CR-6224 semi-theoretical head loss correlation. One of the critical parameters needed for the NURE/CR-6224 correlation to predict the pressure drop across a fibrous debris bed are the characteristics of the debris constituents (density and characteristic size). This paper provides a brief description of the NUREG/CR-6224 head loss correlation and presents suggested debris characteristics of typical sources of debris found in American nuclear power plants for use in the correlation. (authors)
Additional details
Publishing Information
- Publisher
- Organisation for Economic Co-Operation and Development - Nuclear Energy Agency
- Imprint Place
- Paris (France)
- ISBN
- 92-64-00666-4
- Imprint Title
- Debris impact on emergency coolant recirculation
- Imprint Pagination
- 418 p.
- Journal Page Range
- p. 389-398
Conference
- Title
- Workshop on debris impact on emergency coolant recirculation
- Dates
- 25-27 Feb 2004
- Place
- Albuquerque, NM (United States)
INIS
- Country of Publication
- France
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 36010678
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; ECCS; EVALUATION; FIBERGLASS; LOSS OF COOLANT; MATHEMATICAL MODELS; MINERAL WOOL; PARTICLE SIZE; PRESSURE DROP; PROTECTIVE COATINGS; PWR TYPE REACTORS; THERMAL INSULATION
- Descriptors DEC
- ACCIDENTS; COATINGS; COMPOSITE MATERIALS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; MATERIALS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; SIZE; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 10 refs.