Author: OECD Nuclear Energy Agency. NORWAY. INSTITUTT FOR ATOMENERGI.Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 121
Book Description
SPECIALISTS' MEETING ON THE BEHAVIOUR OF WATER REACTOR FUEL ELEMENTS UNDER ACCIDENT CONDITIONS, SPAATIND, NORD-TORPA, NORWAY, 12-16 SEPTEMBER 1976
Author: OECD Nuclear Energy Agency. NORWAY. INSTITUTT FOR ATOMENERGI.Publisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 121
Book Description
The Behavior of Water Reactor Fuel Elements Under Accident Conditions
Author: OECD Nuclear Energy Agency. Committee on the Safety of Nuclear InstallationsPublisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages :
Book Description
Proceedings of the Specialist Meeting on the Behaviour of Water Reactor Fuel Elements Under Accident Conditions, Spåtind, Norway, 13-16 September 1976
Author: Proceedings of Specialist Meeting on the Behaviour of Water Reactor Fuel Elements under Accident Conditions
Author: Proceedings of the Specialist Meeting on the Behaviour of Water Reactor Fuel Elements Under Accident Conditions, Spåtind, Norway, 13-16 September 1976
Author: Nuclear Safety
Author: Energy Research Abstracts
Author: Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 648
Book Description
Semiannual, with semiannual and annual indexes. References to all scientific and technical literature coming from DOE, its laboratories, energy centers, and contractors. Includes all works deriving from DOE, other related government-sponsored information, and foreign nonnuclear information. Arranged under 39 categories, e.g., Biomedical sciences, basic studies; Biomedical sciences, applied studies; Health and safety; and Fusion energy. Entry gives bibliographical information and abstract. Corporate, author, subject, report number indexes.
Index to conference titles
Author: United States. Energy Research and Development Administration. Technical Information CenterPublisher:
ISBN:
Category : Power resources
Languages : en
Pages : 486
Book Description
Behaviour of Gas Cooled Reactor Fuel Under Accident Conditions
Author: International Atomic Energy AgencyPublisher:
ISBN:
Category :
Languages : en
Pages : 164
Book Description
Light water reactor fuel response during reactivity initiated accident experiments
Author: Idaho National Engineering LaboratoryPublisher:
ISBN:
Category :
Languages : en
Pages :
Book Description
Experimental results from six recent Power Burst Facility (PBF) reactivity initiated accident (RIA) tests are compared with data from previous Special Power Excursion Reactor Test (SPERT), and Japanese Nuclear Safety Research Reactor (NSRR) tests. The RIA fuel behavior experimental program recently started in the PBF is being conducted with coolant conditions typical of hot-startup conditions in a commercial boiling water reactor. The SPERT and NSRR test programs investigated the behavior of single or small clusters of light water reactor (LWR) type fuel rods under approximate room temperature and atmospheric pressure conditions in capsules containing stagnant water. As observed in the SPERT and NSRR tests, energy deposition, and consequent enthalpy increase in the PBF test fuel, appears to be the single most important variable. However, the consequences of failure at boiling water hot-startup system conditions appear to be more severe than previously observed in either the stagnant capsule SPERT or NSRR tests. Metallographic examination of both previously unirradiated and irradiated PBF fuel rod cross sections revealed extensive variation in cladding wall thicknesses (involving considerable plastic flow) and fuel shattering along grain boundaries in both restructured and unrestructured fuel regions. Oxidation of the cladding resulted in fracture at the location of cladding thinning and disintegration of the rods during quench. In addition, swelling of the gaseous and potentially volatile fission products in previously irradiated fuel resulted in volume increases of up to 180% and blockage of the coolant channels within the flow shrouds surrounding the fuel rods.