Published 1997 | Version v1
Book Metadata-only

An experimental study of the effect of void-reactivity feedback in natural circulation BWRs

Creators

  • 1. Interfaculty Reactor Inst., Delft Univ. of Technology, Mekelweg Delft (Netherlands)

Description

The scaled natural circulation loop DESIRE has been implemented with a simulated real-time void-reactivity feedback. In this simulation the void-fraction in the fuel assembly is measured and the effect on the power is simulated. This simulation is used to drive the power supplies of the facility, thus closing the feedback loop. The effects of the transfer functions of the void-fraction sensor and power supplies are accounted for in the digital simulation. The void-reactivity coefficient and fuel time constant can be chosen by the experimenter. The effect of the void-reactivity feedback in natural circulation BWRs can thus be studied under many different conditions. The results can be used for model validation and code benchmarking. This paper gives a description of the implementation of the feedback and presents the first results. (author)

Part of:
Eighth international topical meeting on nuclear reactor thermal-hydraulics

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
Imprint Title
Eighth international topical meeting on nuclear reactor thermal-hydraulics
Imprint Pagination
1890 p.
Journal Page Range
p. 367-374

Conference

Title
8. international topical meeting on nuclear reactor thermal-hydraulics
Acronym
NURETH-8
Dates
30 Sep - 4 Oct 1997
Place
Kyoto (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
30016265
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; FEEDBACK; FUEL ASSEMBLIES; NATURAL CONVECTION; POWER SUPPLIES; SIMULATION; TRANSFER FUNCTIONS; VOID COEFFICIENT; VOID FRACTION
Descriptors DEC
CONVECTION; ELECTRONIC EQUIPMENT; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FUNCTIONS; HEAT TRANSFER; POWER REACTORS; REACTIVITY COEFFICIENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
Imprint:Published in 3 volumes