Published 2001
| Version v1
Book
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 (accelerator transmutation of waste) 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. (authors)
Additional details
Publishing Information
- Publisher
- Organisation for Economic Co-Operation and Development - Nuclear Energy Agency
- Imprint Place
- Paris (France)
- ISBN
- 92-64-18749-9
- Imprint Title
- Utilisation and reliability of high power proton accelerators
- Imprint Pagination
- 472 p.
- Journal Page Range
- p. 267-277
Conference
- Title
- Utilisation and reliability of high power proton accelerators
- Acronym
- Workshop on
- Dates
- 22-24 Nov 1999
- Place
- Aix en Provence (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 33012485
- Subject category
- S43: PARTICLE ACCELERATORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCELERATORS; HYBRID SYSTEMS; OPTIMIZATION; RELIABILITY; THERMAL FATIGUE; THERMAL STRESSES
- Descriptors DEC
- FATIGUE; MECHANICAL PROPERTIES; STRESSES
Optional Information
- Notes
- 4 refs.