Results of the QUENCH-09 Experiment Compared to QUENCH-07 with Incorporation of B<sub>4</sub>C Absorber

Sepold, L.; Schanz, G.; Steinbrück, M.; Stuckert, J.; Miassoedov, A.; Палагин, А. В.; Veshchunov, M.S.

doi:10.13182/nt06-a3721

Cited by 24 publications

(11 citation statements)

References 2 publications

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“…It is noteworthy that a similar result has been reported (Haste et al, 2010) in B 4 C tests in the integral QUENCH series (Sepold et al, 2006) performed at Karlsruhe Institute of Technology (KIT), in separate-effects tests performed at KIT (BOX facility, Steinbrück, 2005) and in separate-effects tests performed at IRSN Cadarache (the BECARRE series under the International Source Term Programme (ISTP), (Dominguez et al, 2008). The absence of methane for core meltdown accident conditions is of importance for radiological consequences for this type of accident, because a large amount of methane in the containment would favour the production of volatile methyl iodide, a gas which is likely to increase the radioactive iodine releases to the environment in the case of a containment breach.…”

Section: Oxidation Productssupporting

confidence: 84%

See 1 more Smart Citation

Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle tests

Luze¹,

Haste²,

Barrachin³

et al. 2013

Annals of Nuclear Energy

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Section: Oxidation Productssupporting

confidence: 84%

“…Turning now to the effect on the oxide layer thickness, one can consider the B 4 C QUENCH tests carried out at KIT (Sepold et al, 2006). In particular, the QUENCH-07 test was performed under steam-rich conditions, whereas QUENCH-09 featured a steam-poor period lasting about 11 min.…”

Section: Effect On the Zircaloy Oxide Layer Thicknessmentioning

confidence: 99%

Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle tests

Luze¹,

Haste²,

Barrachin³

et al. 2013

Annals of Nuclear Energy

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“…In a B 4 C oxidation process, similar to Zr oxidation, not only are large amounts of reaction heat and H 2 generated, but also CO, CO 2 , and CH 4 that may influence the chemical forms of iodine. The main chemical reactions are listed along with the Zr oxidation reaction formula, as follows: 5,6) Oxidation of B 4 C 5) (1) 342 INSIGHTS CONCERNING THE FUKUSHIMA DAIICHI NUCLEAR ACCIDENT Vol. 4 (2) (3) Reactions related to boron oxide (B 2 O 3 ) 5) metaboric acid orthoboric acid (4) (5) (6) Reactions related to decomposition of CH 4 6) (7) (8) Oxidation of Zr (9) where, the enthalpies of the reactions in formulas ( 1)-( 9) were calculated using the formation enthalpy at 1,500 K in the cited literature 7) .…”

Section: Chemical Reactionsmentioning

confidence: 99%

Effect of B₄C Absorber Material on Melt Progression and Chemical Forms of Iodine or Cesium under Severe Accident Conditions

Hidaka

2021

Insights Concerning the Fukushima Daiichi Nuclear Accident Vol. 4

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Boron carbide (B 4 C) used for BWR or EPR absorbers could cause phenomena that never occur in PWR with silver-indium-cadmium absorbers during a severe accident. B 4 C would undergo a eutectic interaction with stainless steel and enhance core melt relocation. Boron oxidation could increase H 2 generation, and the change of liberated carbon to CH 4 could enhance the generation of organic iodide (CH 3 I). HBO 2 generated during B 4 C oxidation could be changed to cesium borate (CsBO 2 ) by combining it with cesium. This may increase cesium deposition into the reactor coolant system. There could be differences in the configuration, surface area, and stainless-steel to B 4 C weight ratio between the B 4 C powder absorber and pellet absorber. The present task is to clarify the effect of these differences on melt progression, B 4 C oxidation, and the iodine or cesium source term. Advancement of this research field could contribute to further sophistication of prediction tools for melt progression and source terms of the Fukushima Accident, and the treatment of organic iodide formation in safety evaluation.

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“…However, the amount of creep that occurs is known to be related to homologous temperature, or the ratio of the operational temperature to the melting temperature [7]. Additionally, this ratio functions like a design safety factor in the event of a meltdown, which can raise temperatures experienced by the control rods to 1200 • C or higher [7,8]. To enhance safety, it is important to maximize the temperature that the control rods can endure so that their structural integrity can be maintained as long as possible during a meltdown.…”

Section: Creep Resistance and Thermal Property Retentionmentioning

confidence: 99%

Nanoporous Tungsten for Improved Mechanical Performance and Safety in Nuclear Control Rod Cladding

et al. 2018

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Driven by both the implications of the recent disaster in Fukushima as well as the coming maturity of fusion reactors in energy infrastructure, the nuclear industry is experiencing a renaissance not only in reactor design and fuel systems but also in safety. However, the combination of high temperature, high pressure, and radiation intensity of a reactor core poses a challenge to material selection for engineers, particularly related to nuclear cladding. For example, in a pressurized water reactor, the most prevalent reactor type currently in operation, control rod cladding can be subjected to temperatures over 500 • C, pressures at 15 MPa, and a neutron flux of 3.5 × 10 19 neutrons per cm 2 s. Thus, creep and cracking pose a threat to the cladding's functional integrity. As a result, high fracture toughness, low thermal expansion coefficient, and wear resistance become crucial metrics for the design and selection of nuclear cladding material for control rods. In response to these metrics, boron carbide (B4C) and Ag-In-Cd alloy have emerged as promising candidates for usage in control rod claddings. However, nanoporosity can impart significant mechanical advantages including higher fracture toughness, increased defect annihilation, and suppressed irradiation swelling. Density-modulated tungsten thin films with tunable nanoporosity can be manufactured through sputter coating. Consequently, density-modulated tungsten thin films have the potential to contribute to next-generation control rod cladding. Thus, the objective of this paper is to investigate the suitability of density-modulated tungsten thin films for nuclear control rod cladding through the analytical hierarchy process. Overall, conservative analytical hierarchy process analysis indicates that nanoporous tungsten is competitive with B4C for control rod cladding. As a result, our study may motivate current and future control rod cladding material development efforts focusing specifically on hybrid density-modulated tungsten thin film and B4C architectures for next-generation nuclear power plants.

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Results of the QUENCH-09 Experiment Compared to QUENCH-07 with Incorporation of B₄C Absorber

Cited by 24 publications

References 2 publications

Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle tests

Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle tests

Effect of B₄C Absorber Material on Melt Progression and Chemical Forms of Iodine or Cesium under Severe Accident Conditions

Nanoporous Tungsten for Improved Mechanical Performance and Safety in Nuclear Control Rod Cladding

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Results of the QUENCH-09 Experiment Compared to QUENCH-07 with Incorporation of B4C Absorber

Cited by 24 publications

References 2 publications

Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle tests

Early phase fuel degradation in Phébus FP: Initiating phenomena of degradation in fuel bundle tests

Effect of B4C Absorber Material on Melt Progression and Chemical Forms of Iodine or Cesium under Severe Accident Conditions

Nanoporous Tungsten for Improved Mechanical Performance and Safety in Nuclear Control Rod Cladding

Contact Info

Product

Resources

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Results of the QUENCH-09 Experiment Compared to QUENCH-07 with Incorporation of B₄C Absorber

Effect of B₄C Absorber Material on Melt Progression and Chemical Forms of Iodine or Cesium under Severe Accident Conditions