Published 1977
| Version v1
Report
Experimental and analytical characterization of fuel rod thermal behaviour
Creators
- 1. OECD Halden Reactor Project, Le Seine Saint-Germain, 92 - Issy-les-Moulineaux (France)
Description
The report reviews results of fuel temperature measurements at the Halden Reactor Project under steady state as well as transient power conditions (reactor scrams and rapid power reductions). The influence of pellet-to-cladding clearance, linear power and burn-up on gap conductance, and stored energy is evaluated. The time-dependent development of the xenon content in fuel rods is assessed as a function of fission gas release rate and pre-pressurization level of helium, and its effect on the mixed-gas thermal conductivity is illustrated. Further, it is shown how the heat transfer characteristics of a fuel rod under irradiation can be analyzed through application of noise analysis techniques
Additional details
Publishing Information
- Imprint Title
- Proceedings of a specialist meeting on the behaviour of water reactor fuel elements under accident conditions
- Imprint Pagination
- 774 p.
- Journal Page Range
- p. 514-533
- Report number
- NEA-CSNI-R--1977-13
Conference
- Title
- Specialist meeting on the behaviour of water reactor fuel elements under accident conditions
- Dates
- 13-16 Sep 1976
- Place
- Spaatind (Norway)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 42006210
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DATA ANALYSIS; FUEL RODS; FUEL-CLADDING INTERACTIONS; HBWR REACTOR; HEAT TRANSFER; NEA; ON-LINE MEASUREMENT SYSTEMS; REACTOR ACCIDENT SIMULATION; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SCRAM; SIGNAL-TO-NOISE RATIO; STEADY-STATE CONDITIONS; TEMPERATURE MEASUREMENT; THERMODYNAMIC PROPERTIES; TRANSIENTS
- Descriptors DEC
- BHWR TYPE REACTORS; DIMENSIONLESS NUMBERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL ELEMENTS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INTERNATIONAL ORGANIZATIONS; OECD; ON-LINE SYSTEMS; PHYSICAL PROPERTIES; POWER REACTORS; REACTOR COMPONENTS; REACTOR SHUTDOWN; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SHUTDOWN; SIMULATION; TANK TYPE REACTORS; THERMAL REACTORS
Optional Information
- Notes
- 4 refs.