Published November 12, 1999
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Estimates of thermal fatigue due to beam interruptions for an ALMR-type ATW
Description
Thermal fatigue due to beam interruptions has been investigated in a sodium cooled ATW using the Advanced Liquid Metal mod B design as a basis for the subcritical source driven reactor. A keff of 0.975 was used for the reactor. Temperature response in the primary coolant system was calculated, using the SASSYS- 1 code, for a drop in beam current from full power to zero in 1 microsecond.. Temperature differences were used to calculate thermal stresses. Fatigue curves from the American Society of Mechanical Engineers Boiler and Pressure Vessel Code were used to determine the number of cycles various components should be designed for, based on these thermal stresses
Availability note (English)
Available from INIS in electronic form; Also available from OSTI as DE00750592; PURL: https://www.osti.gov/servlets/purl/750592-hFD0Em/webviewable/Files
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 11 p.
- Report number
- ANL/RE/CP--100489
Conference
- Title
- 2. Workshop on Utilization and Reliability of High Power Proton Accelerators
- Dates
- 22-24 Nov 1999
- Place
- Aix-en-Provence (France)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 31049254
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S43: PARTICLE ACCELERATORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCELERATOR BREEDERS; BEAM CURRENTS; LIQUID METAL COOLED REACTORS; MULTIPLICATION FACTORS; PRESSURE VESSELS; PRIMARY COOLANT CIRCUITS; RADIOACTIVE WASTE PROCESSING; SUBCRITICAL ASSEMBLIES; THERMAL ANALYSIS; THERMAL FATIGUE
- Descriptors DEC
- CONTAINERS; COOLING SYSTEMS; CURRENTS; ENERGY SYSTEMS; EXPERIMENTAL REACTORS; FATIGUE; MANAGEMENT; MECHANICAL PROPERTIES; PROCESSING; RADIOACTIVE WASTE MANAGEMENT; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; WASTE MANAGEMENT; WASTE PROCESSING
Optional Information
- Contract/Grant/Project number
- W-31109-ENG-38
- Funding organization
- US Department of Energy (United States)