Development of a three-dimensional transient code for reactivity-initiated events in boiling water reactors; Models and code verifications--

Journal Article · Sun Oct 01 00:00:00 EDT 1989 · Nuclear Technology; (USA)

OSTI ID:6882744

Uematsu, H ^[1]; Izutsu, S ^[2]; Yamamoto, T ^[3]; Yamashita, R ^[4]; Muto, S; Toba, A ^[5]

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1. Nippon Atomic Industry Group Company, Ltd., NAIG Nuclear Research Laboratory, 4-1 Ukishima-cho Kawasaki-ku, Kawasaki 210 (JP)
2. Hitachi, Ltd., Hitachi Works, 3-1 Saiwai-cho, Hitachi 317 (JP)
3. Toshiba Corporation, Isogo Engineering Center, 8 Shinsugita-cho, Isogo-ku, Yokohama 235 (JP)
4. Hitachi Engineering Co., Ltd., 3-2 Saiwai-cho, Hitachi 317 (JP)
5. Tokyo Electric Power Co., Inc., 4-1 Uchisaiwai-cho, Chiyoda-ku, Tokyo 100 (JP)

A reactivity initiated event is a design-basis accident for the safety analysis of boiling water reactors. It is defined as a rapid transient of reactor power caused by a reactivity insertion of over 1.0 due to a postulated drop or abnormal withdrawal of the control rod from the core. Strong space-dependent feedback effects are associated with the local power increase due to control rod movement. A realistic treatment of the core status in a transient by a code with a detailed core model is recommended in evaluating this event. This paper presents three-dimensional transient code, ARIES, developed to meet this need. The code simulates the event with three-dimensional neutronics, coupled with multichannel thermal hydraulics, based on a nonequilibrium separated flow model. The models and verification of the code with a benchmark problem posed by the Nuclear Energy Agency Committee on Research Physics-Committee on the Safety of Nuclear Installations and by comparisons to the experimental data of tests with the SPERT III E-core.

• OSTI ID: 6882744
• Journal Information: Nuclear Technology; (USA), Vol. 88:1; ISSN 0029-5450
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
REACTOR SAFETY
COMPUTER CODES
A CODES
REACTOR CORES
DESIGN
FLOW MODELS
NEUTRONIC DAMAGE FUNCTIONS
THREE-DIMENSIONAL CALCULATIONS
VERIFICATION
FUNCTIONS
MATHEMATICAL MODELS
REACTOR COMPONENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220400* - Nuclear Reactor Technology- Control Systems
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
220900 - Nuclear Reactor Technology- Reactor Safety