Published 1992 | Version v1
Miscellaneous

Determination of allowable transient power levels to maintain the mechanical integrity for 17 x 17 KOFA fuel

  • 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

Fuel rod design criteria require that the fuel rod should maintain the mechanical integrity during ANS conditions I and II. Transient power level of the fuel rod is one of the key parameters for the transient behavior. By doing comprehensive survey of relevant data bases and sensitivity study of related parameters such as rod power history, neutron flux, fuel enrichment and cycle length the allowable transient power levels below which mechanical integrity is maintained have been determined for 17 x 17 KOFA fuel

Part of:
Proceedings of the KNS spring meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS spring meeting
Imprint Pagination
706 p.
Journal Page Range
p. 35-40

Conference

Title
1992 spring meeting of the KNS
Dates
29-30 May 1992
Place
Kori (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
38022670
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CLADDING; COMPUTER CALCULATIONS; DESIGN; FUEL RODS; SENSITIVITY; TRANSIENTS
Descriptors DEC
DEPOSITION; FUEL ELEMENTS; REACTOR COMPONENTS; SURFACE COATING

Optional Information

Notes
6 refs, 6 figs