Startup data report for NRC/PNL Halden Assembly IFA-513
This report presents data from the first month of operation of IFA-513, which is a heavily instrumented 6-rod test assembly in the Halden Reactor in Norway. The assembly is jointly sponsored by the Halden Project and the Nuclear Regulatory Commission (NRC), and is part of a series of irradiation tests sponsored by the NRC to verify its single-rod fuel modeling computer programs. All the rods in the series are of the basic BWR-6 design with variations in gap size, fuel type, fill gas composition, and fill gas pressure. The first two tests in the series were IFA-431 and IFA-432. These were identical 6-rod assemblies, each containing the same variations of gap size and fuel pellet types, but operating at different power levels and burnups. The present assembly, IFA-513, is the third in the series; its 6 rods are all identical, except for variations in fill gas composition and pressure. The fourth and last assembly, designated IFA-527, is yet to be built, and will study the effects of fuel pellet cracking and relocation. The measurements made in IFA-513 and the earlier tests include: (1) fuel temperature and power (both steady-state and transient), (2) total cladding elongation, and (3) fill gas pressure. The measurements were made on a continuous basis, providing a record of their variation with both power and burnup. Along with the data, this report includes some analysis to put the IFA-513 startup data in perspective to similar data from IFA-431 and IFA-432.
- Research Organization:
- Battelle Pacific Northwest Labs., Richland, WA (United States)
- DOE Contract Number:
- EY-76-C-06-1830
- OSTI ID:
- 6169782
- Report Number(s):
- NUREG/CR-0865; PNL-2948; TRN: 79-017384
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of fuel relocation for the NRC/PNL Halden assemblies IFA-431, IFA-432, and IFA-513. Interim report
Data report for the NRC/PNL Halden Assembly IFA-432.
Related Subjects
BWR TYPE REACTORS
FUEL ASSEMBLIES
PERFORMANCE TESTING
HBWR REACTOR
IRRADIATION
BHWR TYPE REACTORS
ENRICHED URANIUM REACTORS
EXPERIMENTAL REACTORS
HEAVY WATER COOLED REACTORS
HEAVY WATER MODERATED REACTORS
POWER REACTORS
REACTORS
RESEARCH AND TEST REACTORS
TANK TYPE REACTORS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled