Published 1985 | Version v1
Report Open

Reactivity parameters for safety analysis

Creators

Description

The reactor core model in the most commonly used computer programs for safety analysis is a point kinetics model. The core average fission rate is calculated knowing the reactivity, neutron generation time and delayed-neutron parameters. The reactivity is a time dependent function taking account of the effect of changes in water density and temperature, fuel temperature, control rod position and soluble boron concentration. In this presentation some of the alternative ways of representing this reactivity function are reviewed

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as TI85006729.

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Additional details

Publishing Information

Imprint Pagination
5 p.
Report number
BNL-NUREG--35848

Conference

Title
Annual meeting of the American Nuclear Society.
Dates
9-14 Jun 1985.
Place
Boston, MA (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
16068308
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; PWR TYPE REACTORS; REACTIVITY WORTHS; REACTOR KINETICS; REACTOR SAFETY
Descriptors DEC
ENERGY TRANSFER; ENRICHED URANIUM REACTORS; KINETICS; POWER REACTORS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Secondary number(s)
CONF-850610--15.