Published November 1993 | Version v1
Miscellaneous

Safety reassessment of the Hungarian NPP (the Agnes project)

  • 1. Hungarian Academy of Sciences, Budapest (Hungary). Central Research Inst. for Physics
  • 2. Paksi Atomeroemue Vallalat, Paks (Hungary)

Description

The results summarized in this paper are taken from the report of the first phase of the AGNES project, assessing the safety of the Paks nuclear power plant. The principal conclusions are as follows. The single failure analysis has not pointed out any dramatic or unknown deficiencies. The medium and large break loss of coolant accident (LOCA) scenarios do not lead to environmental doses beyond the limits. The pressurized thermal shock (PTS) analysis does not endanger the pressure vessel. In severe accidents the water inventories are large, which makes it possible to apply efficient accident management strategies. The largest contributions to probability of core melting come from interface LOCA scenarios, loss of feedwater, and small break LOCA. A significant decrease in the core melt probability will result from improving emergency operating procedures and elaborating and introducing accident management procedures, as well as from technical measures. 18 refs

Part of:
INC93: international nuclear congress. Proceedings. V. 1,2,3

Additional details

Publishing Information

ISBN
0-919784-34-8
Imprint Title
INC93: international nuclear congress. Proceedings. V. 1,2,3
Imprint Pagination
[1500 p.].
Journal Page Range
(v.2) [8 p.].
Report number
INIS-mf--14809

Conference

Title
international nuclear congress.
Acronym
INC93
Dates
3-6 Oct 1993.
Place
Toronto, ON (Canada).

INIS

Country of Publication
Canada
Country of Input or Organization
Canada
INIS RN
27056845
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
PAKS-1 REACTOR; PRESSURE VESSELS; REACTOR ACCIDENTS; REACTOR SAFETY; SAFETY ANALYSIS; THERMAL SHOCK
Descriptors DEC
ACCIDENTS; CONTAINERS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information