Published October 1995 | Version v1
Miscellaneous Metadata-only

Licensing of Zr-Nb spacer grids in VVER 440 fuel

Creators

  • 1. Jaderna Elektrarna, Dukovany (Czech Republic)
  • 2. Energoprojekt, Prague (Czech Republic)

Description

The effect on reactor core parameters and safety analyses is investigated of replacing stainless steel spacer grids with Zr-Nb alloy grids. The values of key safety analyses related nuclear core parameters are discussed. Based on calculations, a very small influence is expected of the planned changes on safety analyses results, particularly in those cases when initial conservatism in input data choice was adequate. (J.B.) 16 refs

Part of:
Proceedings of the international topical meeting on VVER safety

Additional details

Publishing Information

Imprint Title
Proceedings of the international topical meeting on VVER safety
Imprint Pagination
416 p.
Journal Page Range
p. 175-178.
Report number
INIS-mf--14715

Conference

Title
International topical meeting on VVER safety.
Dates
21-23 Sep 1995.
Place
Prague (Czech Republic).

INIS

Country of Publication
Czech Republic
Country of Input or Organization
Czech Republic
INIS RN
27022836
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FUEL ASSEMBLIES; NIOBIUM ALLOYS; POWER DISTRIBUTION; REACTIVITY COEFFICIENTS; REACTIVITY INSERTIONS; REACTOR SAFETY; SAFETY ANALYSIS; SPACERS; WWER TYPE REACTORS; ZIRCONIUM BASE ALLOYS
Descriptors DEC
ALLOYS; DISTRIBUTION; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; SPATIAL DISTRIBUTION; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZIRCONIUM ALLOYS

Optional Information