Published January 1989 | Version v1
Report Metadata-only

Advanced PWRs (APWRs) and related safety considerations

Creators

  • 1. Kernforschungszentrum Karlsruhe G.m.b.H. (Germany, F.R.). Inst. fuer Neutronenphysik und Reaktortechnik

Description

The paper describes the main characteristics of a tight lattice advanced pressurized water reactor (APWR) with mixed-oxide (MOX) fuel with emphasis to nuclear data sensitivities and calculational procedures. It is concluded that certain cross-section data of actinides and fission products are not yet known with sufficient accuracy, and some problems in the calculational procedures are identified. (author). 23 refs, 1 fig., 4 tabs

Part of:
Nuclear data for the calculation of thermal reactor reactivity coefficients

Additional details

Publishing Information

Imprint Title
Nuclear data for the calculation of thermal reactor reactivity coefficients
Imprint Pagination
132 p.
Journal Page Range
p. 85-93.
Report number
IAEA-TECDOC--491

Conference

Title
Advisory group on nuclear data for the calculation of thermal reactor reactivity coefficients.
Dates
7-10 Dec 1987.
Place
Vienna (Austria).

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
20064225
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ACCURACY; GROUP CONSTANTS; MIXED OXIDE FUELS; MODIFICATIONS; PWR TYPE REACTORS; REACTIVITY COEFFICIENTS; REACTOR LATTICE PARAMETERS
Descriptors DEC
CROSS SECTIONS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; SOLID FUELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information