Published 2001 | Version v1
Book

Estimates of thermal fatigue due to beam interruptions for an ALMR-type ATW

  • 1. Argonne National Lab., IL (United States)

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)

Part of:
Utilisation and reliability of high power proton accelerators

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.