Published January 2003 | Version v1
Report Open

Influence of coolant temperature and pressure on destructive forces at fuel failure in the NSRR experiment

Creators

  • 1. Global Nuclear Fuel - Japan Co., Ltd., Yokosuka, Kanagawa (Japan)
  • 2. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

Description

In order to design a new experimental capsule to be used in the NSRR (Nuclear Safety Research Reactor) experiment with the temperature and pressure conditions in a typical commercial BWR, coolant temperature and pressure influence is estimated for destructive forces during fuel rod failure in the experiment simulating reactivity-initiated accident (RIA). Considering steam property dependence on temperature and pressure, it is qualitatively shown that the destructive forces in the BWR operation condition are smaller than those in the room temperature and atmospheric pressure condition. Water column velocity, which determines impact by water hammer, is further investigated quantitatively by modeling the experimental system and water hammer phenomenon. As a result, the maximum velocity of the water column in the BWR operation conditions is calculated to be only about 10% of that in the room temperature and atmospheric pressure condition. (author)

Availability note (English)

Available from INIS in electronic form; Also available from JAEA; URL: http://jolisf.tokai-sc.jaea.go.jp/pdf/tec/JAERI-Tech-2002-105.pdf

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Additional details

Publishing Information

Imprint Pagination
32 p.
Report number
JAERI-Tech--2002-105

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
37002573
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COOLANTS; FUEL ELEMENT FAILURE; FUNCTIONAL MODELS; IMPACT SHOCK; IRRADIATION CAPSULES; MOCKUP; NSRR REACTOR; NUCLEAR FUELS; PRESSURE DEPENDENCE; PULSES; REACTOR ACCIDENTS; STRESS ANALYSIS; TEMPERATURE DEPENDENCE; TESTING; WATER HAMMER
Descriptors DEC
ACCIDENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FAILURES; FUELS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MATERIALS; MIXED SPECTRUM REACTORS; PULSED REACTORS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; STRUCTURAL MODELS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
16 refs., 5 figs., 3 tabs.; This record replaces 34060908