Published May 1999 | Version v1
Report Metadata-only

Alpha-beta allotropic transformation of Zircaloy during temperature transients

Creators

Description

Zircaloy-2 BWR-type cladding tubes have been investigated with respect to alpha-beta allotropic transformation during a short time temperature excursion. Short tube samples have been induction heated from approx. 250 C, reactor moderator temperature, up to 950 - 1150 C within approximately 60 sec. and quenched. Metallographic samples have been prepared and examined in optical microscope. The objective of the investigation was to find the lowest peak temperature, which resulted in a fully transformed p-structure. The investigation is related to structures seen in the cladding material after dry-out test of fuel rods in the first loading of the 'In-reactor dry-out experiment IFA-613.1.' The work concludes with an estimation of the peak cladding temperature in the dry-out test of the IFA-613.1 rods (author) (ml)

Part of:
Enlarged Halden programme group meeting on high burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects and man-machine systems research. Volume II

Additional details

Publishing Information

Imprint Title
High burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects and man-machine systems research
Imprint Pagination
vp.
Journal Page Range
p. 38
Report number
HPR--351-V2

Conference

Title
Enlarged HPG meeting on high burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects and man-machine systems research
Dates
24-29 May 1999
Place
Loen (Norway)

INIS

Country of Publication
Norway
Country of Input or Organization
Norway
INIS RN
38108767
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE;
Resource subtype / Literary indicator
Non-conventional Literature, Conference, Numerical Data
Descriptors DEI
ALLOTROPY; BETA PARTICLES; CLADDING; CRYSTAL STRUCTURE; DRYOUT; EXPERIMENTAL DATA; FUEL PELLETS; FUEL RODS; HBWR REACTOR; MICROSTRUCTURE; PHASE TRANSFORMATIONS; RECRYSTALLIZATION; TEMPERATURE RANGE 0400-1000 K; TEMPERATURE RANGE 1000-4000 K; TRANSIENTS; ZIRCALOY 2
Descriptors DEC
ALLOY-ZR98SN-2; ALLOYS; BHWR TYPE REACTORS; CHARGED PARTICLES; CHROMIUM ADDITIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; DATA; DEPOSITION; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUEL ELEMENTS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INFORMATION; IONIZING RADIATIONS; IRON ADDITIONS; IRON ALLOYS; MATERIALS; NICKEL ADDITIONS; NICKEL ALLOYS; NUMERICAL DATA; PELLETS; POWER REACTORS; RADIATIONS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SURFACE COATING; TANK TYPE REACTORS; TEMPERATURE RANGE; THERMAL REACTORS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; ZIRCALOY; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS

Optional Information

Notes
5 refs., 17 figs., 1 tab