Analysis on Lift-Off experiment in Halden reactor by FEMAXI-6 code

Suzuki, Masatoshi; Kusagaya, Kazuyuki; Saitou, Hiroaki; Fuketa, Toyoshi

doi:10.1016/j.jnucmat.2004.07.049

Cited by 9 publications

(8 citation statements)

References 6 publications

(3 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Structure of the RANNS code is based on that of the fuel performance code FEMAXI-6 (Suzuki et al, 2004a(Suzuki et al, , 2004b, but its mechanical model was extended. Fig.…”

Section: Model and Structurementioning

confidence: 99%

“…In this case, radial and axial displacements of pellet outer surface is shared with cladding inner surface (Suzuki et al, 2004a(Suzuki et al, , 2004b. As a result, cladding is subjected to bi-axial stress state in the hoop and axial directions.…”

Section: Bondingmentioning

confidence: 99%

“…2) is assumed to be that of the ZrO 2 with 10 m thickness, or roughly 10 W/cm s, since this thickness proved to give a satisfactory prediction in pellet temperature (Suzuki et al, 2004a(Suzuki et al, , 2004b. Also RANNS can calculate the open gap conductance by the Ross-Stoute model (Ross and Stoute, 1962).…”

Section: Gap Thermal Conductancementioning

confidence: 99%

See 2 more Smart Citations

Analysis on split failure of cladding of high burnup BWR rods in reactivity-initiated accident conditions by RANNS code

Suzuki

Saitou

Fuketa

2006

Nuclear Engineering and Design

View full text Add to dashboard Cite

“…Structure of the RANNS code is based on that of the fuel performance code FEMAXI-6 (Suzuki et al, 2004a(Suzuki et al, , 2004b, but its mechanical model was extended. Fig.…”

Section: Model and Structurementioning

confidence: 99%

Section: Bondingmentioning

confidence: 99%

See 1 more Smart Citation

Analysis on split failure of cladding of high burnup BWR rods in reactivity-initiated accident conditions by RANNS code

Suzuki

Saitou

Fuketa

2006

Nuclear Engineering and Design

View full text Add to dashboard Cite

“…IV-2(2). Both the 1-D and 2-D models accept the pre-accident conditions of high burnup rods from analysis by the FEMAXI-6 code [7][8][9] which adopts the same finite element geometries as those of RANNS.…”

Section: Mechanical Analysis Of Pellet and Claddingmentioning

confidence: 99%

“…In this case, the mechanical models assume that displacement of pellet stack outer surface is shared with that of cladding inner surface in both the radial and axial directions. 7,8) (…”

Section: (3) Pellet-clad Bondingmentioning

confidence: 99%

RANNS Code Analysis on the Local Mechanical Conditions of Cladding of High Burnup Fuel Rods under PCMI in RIA-Simulated Experiments in NSRR

Suzuki

Saitou²,

Fuketa

2006

Journal of Nuclear Science and Technology

View full text Add to dashboard Cite

The RANNS code analyzes behavior of a single fuel rod in reactivity-initiated accident (RIA) conditions. The code has two types of mechanical model; one-dimensional deformation model for each axial segment length of rod, and newly-developed two-dimensional local deformation model for one pellet length. Analyses were performed on the RIA-simulated experiments in the Nuclear Safety Research Reactor (NSRR), OI-10 with high burnup PWR rods, and results of cladding deformation were compared between calculations by the two models and PIE data. The pre-accident, or End-of-Life conditions of the rod were predicted by the fuel performance code FEAMXI-6. In the calculations by the two-dimensional model of RANNS, the plastic strain increases at the cladding ridges during PCMI were compared with those in between the ridges and with the PIE data, and effect of stress variance induced by local non-uniformity of strain on the crack growth was discussed.

show abstract