Published May 1991 | Version v1
Report Metadata-only

Post-irradiation examination and evaluation of PWR 14 x 14 fuel assemblies

Creators

  • 1. Korea Atomic Energy Research Inst., Daeduk (Republic of Korea)

Description

Post irradiation examination and evaluation for Kori-1 NPP fuel assemblies has been conducted at the post irradiation examination facility of Korea Atomic Energy Research Institute (KAERI). The three fuel assemblies under consideration had the average burnup of about 17(1-cycle burnup), 25(2-cycle burnup), 32(3-cycle burnup) GWD/MTU. Nondestructive examination and dismantling of the fuel assemblies have been performed in the pool of the PIE facility while nondestructive and destructive examinations of fuel rods have been done in the hot cell. On the bases of PIE data and the nominal design values, fuel burnup behaviours have been evaluated. It is revealed that no noticeable abnormality is found in the fuel integrity in general. However, an apparent axial growth of peripheral fuel rods in the assembly with 2-cycle burnup seems to be high compared to that of 3-cycle burnup as an exceptional case. (author). 3 refs, 6 figs, 3 tabs

Part of:
Post-irradiation examination techniques for water reactor fuel

Additional details

Publishing Information

Imprint Title
Post-irradiation examination techniques for water reactor fuel
Imprint Pagination
164 p.
Journal Page Range
p. 50-55.
Report number
IWGFPT--37

Conference

Title
Technical committee meeting on post-irradiation examination techniques for water reactor fuel.
Dates
11-14 Sep 1990.
Place
Workington (UK).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
22077610
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BURNUP; DESTRUCTIVE TESTING; FUEL INTEGRITY; HOT CELLS; NONDESTRUCTIVE TESTING; POST-IRRADIATION EXAMINATION; PWR TYPE REACTORS; SPENT FUEL ELEMENTS
Descriptors DEC
ENRICHED URANIUM REACTORS; EQUIPMENT; FUEL ELEMENTS; LABORATORY EQUIPMENT; MATERIALS TESTING; POWER REACTORS; REACTOR COMPONENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information