Published October 1987 | Version v1
Book

Measurements and calculations on sloshing effects in solution vessels having a free surface

  • 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki. Tokai Research Establishment

Description

A criticality safety experiment which simulates the sloshing effect in the solution vessel having a free surface has been performed using a Tank-type Critical Assembly (TCA) at Japan Atomic Energy Research Institute. In the experiments reactivity effects by surface deformation of the rectangular cores were measured by using critical water level worth method at constructed mock up cores in TCA. The experimental results suggest that the criticality safety of slab tanks which involve nuclear fuel solution can be satisfied even in the sloshing situation, when the ratio of the solution height to the slab thickness is larger than 0.5. Calculations were also performed on reactivity effects in solution deformation for typical solution systems using the Monte Carlo code KENO-IV and the diffusion code CITATION of which accuracy was established by comparison with the experimental data. (author)

Additional details

Publishing Information

Publisher
Dept. of Fuel Safety Res., Japan Atomic Energy Research Inst.
Imprint Place
Tokai, Ibaraki (Japan)
Imprint Title
ISCS'87
Imprint Pagination
503 p.
Journal Page Range
p. 50-57.

Conference

Title
International seminar on nuclear criticality safety.
Dates
19-23 Oct 1987.
Place
Tokyo (Japan).

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
19051257
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CRITICALITY; DEFORMATION; FUEL SOLUTIONS; K CODES; MOCKUP; REACTIVITY; REACTOR CORES; REACTOR SAFETY; SURFACES; TANKS; ZERO POWER REACTORS
Descriptors DEC
COMPUTER CODES; CONTAINERS; ENERGY SOURCES; EXPERIMENTAL REACTORS; FUELS; LIQUID FUELS; MATERIALS; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; STRUCTURAL MODELS