Transient response of LWR fuels (RIA)

Udagawa, Yutaka; Fuketa, Toyoshi*

Comprehensive Nuclear Materials, 2nd Edition, Vol.2, p.322 - 338, 2020/08

https://doi.org/10.1016/B978-0-12-803581-8.11682-0

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

Kusagaya, Kazuyuki*; Sugiyama, Tomoyuki; Nakamura, Takehiko; Uetsuka, Hiroshi

JAERI-Tech 2002-105, 24 Pages, 2003/01

JAERI-Tech-2002-105.pdf:1.4MB

High-temperature and high-pressure influence on the destructive force at the fuel rod failure in reactivity-initiated-accident (RIA) simulating experiment using the NSRR (Nuclear Safety Research Reactor) is estimated, for the purpose of mechanical designing of a new experimental capsule for simulating the temperature and pressure condition of typical commercial BWR. When knowledge on pressure impulse and water hammer, which are the cause of the destructive force, and steam property dependence on temperature and pressure are taken into account, one can qualitatively estimate that the destructive force in the BWR operation condition is smaller than that in the room temperature and atmospheric pressure condition. The water column velocity, which determines the impact by water hammer, is further investigated quantitatively by modeling the experimental system and the water hammer phenomenon. As a result, the maximum velocity of water column in the BWR operation condition is calculated to be only about 10% of that in the room temperature and atmospheric pressure condition.

Modeling of fuel performance and fission product release behaviour during HTTR normal operation; A Comparative study on the FZJ and JAERI Modeling approach

Verfondern, K.*; Sumita, Junya; Ueta, Shohei; Sawa, Kazuhiro

JAERI-Research 2000-067, 127 Pages, 2001/03

JAERI-Research-2000-067.pdf:6.64MB

no abstracts in English

Distribution of fission products in graphite sleeves and blocks of the eleventh and twelfth OGL-1 fuel assemblies

Hayashi, Kimio; Fukuda, Kosaku; Tsuruta, Harumichi; Kikuchi, Teruo

JAERI-M 94-075, 90 Pages, 1994/06

JAERI-M-94-075.pdf:2.41MB

no abstracts in English

The Effects of coolant/fuel ratio on fuel behavior under reactivity initiated accident conditions; Flow shroud parameter test in the NSRR experiments

Tanzawa, Sadamitsu; ;

JAERI-M 91-215, 40 Pages, 1992/01

JAERI-M-91-215.pdf:2.03MB

no abstracts in English

Annual progress report on the NSRR experiments, 17; January 1985 through December 1985

;

JAERI-M 89-097, 155 Pages, 1989/08

JAERI-M-89-097.pdf:5.58MB

no abstracts in English

Effects of waterlogged fuel rod rupture on adjacent fuel rods and channel box under an RIA conditions

;

Journal of Nuclear Science and Technology, 24(1), p.23 - 32, 1986/01

https://doi.org/10.3327/jnst.24.23

no abstracts in English

IN-CORE BURNOUT FAILURE OF PWR TYPE FUEL ROD AND ITS BEHAVIOURAL ANALYSIS BY USING EQUIPPED INSTRUMENTATIONS

JAERI-M 84-009, 45 Pages, 1984/02

JAERI-M-84-009.pdf:1.95MB

no abstracts in English

Semiannual Progress Report on the NSRR Experiments(13)

;

JAERI-M 83-193, 112 Pages, 1983/11

JAERI-M-83-193.pdf:4.31MB

no abstracts in English

Semiamual Progress Report on the NSRR Experiments,10

;

JAERI-M 9319, 85 Pages, 1981/02

JAERI-M-9319.pdf:3.12MB

no abstracts in English

Quarterly Progress Report on the NSRR Experiments,2; Combined April 1976June 1976

;

JAERI-M 6790, 85 Pages, 1976/11

JAERI-M-6790.pdf:2.49MB

no abstracts in English