Published March 2012 | Version v1
Miscellaneous

Halden experience with in-reactor material property assessment

  • 1. Institut for Energiteknikk, Halden Reactor Project, Halden (Norway)

Description

An overview of the experimental work scope at the Halden reactor is provided, together with the most important achievements related to fuel and materials safety and reliability. The most important characteristics of the Halden tests consists in the in-reactor monitoring capability, which provides unique on-line data on specific performance items, such as for instance fuel temperature, fission gas release and pellet-cladding mechanical interaction for fuel rods and crack growth, creep and stress/strain relaxation for structural materials. The type of measurements, the techniques involved, the data and their relevance for the nuclear community are presented and discussed. In particular, licensing items related to high burn-up fuel, such as overpressure criteria and response to LOCA, are addressed. Considerations are also given to the long term availability of the Halden reactor as a key support tool for the nuclear industry in the decades ahead. (author)

Part of:
1st Asian nuclear fuel conference (ANFC 2012)

Additional details

Publishing Information

Imprint Title
1st Asian nuclear fuel conference (ANFC 2012)
Imprint Pagination
112 p.
Journal Page Range
p. 12-13

Conference

Title
1. Asian nuclear fuel conference
Acronym
ANFC 2012
Dates
22-23 Mar 2012
Place
Osaka (Japan)

Optional Information