Published July 31, 2001 | Version v1
Report Metadata-only

Fuel Temperature Coefficient of Reactivity

Creators

Description

A method for measuring the fuel temperature coefficient of reactivity in a heterogeneous nuclear reactor is presented. The method, which is used during normal operation, requires that calibrated control rods be oscillated in a special way at a high reactor power level. The value of the fuel temperature coefficient of reactivity is found from the measured flux responses to these oscillations. Application of the method in a Savannah River reactor charged with natural uranium is discussed

Availability note (English)

Available from PURL: https://www.osti.gov/servlets/purl/784244-jQzVtF/native/

Additional details

Identifiers

URL
https://www.osti.gov/servlets/purl/784244-jQzVtF/native/;

Publishing Information

Imprint Pagination
[vp.]
Report number
DPSP--56-25-80

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
32046289
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
CONTROL ELEMENTS; HETEROGENEOUS REACTOR CORES; MEASURING METHODS; NATURAL URANIUM; NEUTRON FLUX; OSCILLATIONS; REACTIVITY; REACTOR CONTROL SYSTEMS; REACTOR KINETICS; REACTOR OPERATION; SAVANNAH REACTOR; STEADY-STATE CONDITIONS; TEMPERATURE COEFFICIENT
Descriptors DEC
ACTINIDES; CONTROL SYSTEMS; ELEMENTS; ENRICHED URANIUM REACTORS; KINETICS; METALS; OPERATION; POWER REACTORS; PROPULSION REACTORS; PWR TYPE REACTORS; RADIATION FLUX; REACTIVITY COEFFICIENTS; REACTOR COMPONENTS; REACTOR CORES; REACTORS; SHIP PROPULSION REACTORS; THERMAL REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract AT(07-2)-1
Funding organization
US Department of Energy (United States)