Temperature Dependence of Fission Product Release Rates

Kelly, J.L.; Reynolds, Amy L.; McGown, Michael E.

doi:10.13182/nse84-a28402

Cited by 17 publications

(7 citation statements)

References 5 publications

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“…Emission yields [14][15][16][17]. The decrease of emission yields, beyond 1500° C, has to be explained on the basis of XRD analyses performed on the residues of the pellets after the thermal shock (see Table 1).…”

Section: Resultsmentioning

confidence: 99%

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The Emission and Mobilization of Mo from Overheated Nuclear Fuel - the Importance of 'Maturation' of the Aerosols

et al. 1997

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Section: Resultsmentioning

confidence: 99%

“…16(X)°C, there is a reduction of emission as a consequence of increased formation of metallic Mo (reaction (d)).-at 2380°C, the pellets melt: the graphite of the oven reduces the oxides and forms carbides.…”

mentioning

confidence: 99%

The Emission and Mobilization of Mo from Overheated Nuclear Fuel - the Importance of 'Maturation' of the Aerosols

et al. 1997

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“…However, the escape rate coefficient used to calculate the FP release rate of the APR‐1400 was measured experimentally for fuel rods with a high heat generation rate of 591 W/cm, which is conservative for both APR‐1400 and KAIST‐MMR. APR‐1400 and KAIST‐MMR have different temperature conditions, which may affect the FP release rate . In addition, even though the core exit temperature of KAIST‐MMR (550°C) is higher than the APR‐1400 (330°C), KAIST‐MMR has lower fuel temperature (850°C of peak fuel temperature) than the APR‐1400 (1712°C of peak fuel temperature).…”

Section: Methodsmentioning

confidence: 99%

Radionuclide transport in a long‐term operation supercritical CO ₂ ‐cooled direct‐cycle small nuclear reactor

Son

Kwon

et al. 2020

Int J Energy Res

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Summary In recent years, to overcome the challenges of nuclear power plants due to their large scale, numerous types of small modular reactors are being designed worldwide. Small modular reactors are required to have a capability to operate in environmentally challenging regions with long refueling time. Supercritical CO2 (S‐CO2)‐cooled direct‐cycle reactor is one of the candidates that can meet these requirements. In order to evaluate if the design achieves this goal, transport of generated radionuclides from the long‐term operation has to be evaluated in order to estimate the radioactivity accumulation in the system. However, existing radionuclide transport evaluation method does not reflect the characteristics of supercritical fluids properly. In this paper, the fission product plate‐out behavior of Korea Advanced Institute of Science and Technology Micro Modular Reactor (KAIST‐MMR), a 10‐MWe class S‐CO2‐cooled fast reactor with direct S‐CO2 power conversion system, is studied. The evaluation methodology was developed via integrating suitable models while considering the shape of the nuclear fuel, component geometries, characteristics of a working fluid in supercritical state, and the fast reactor design. As a result of the analysis, the degree of plate‐out of KAIST‐MMR is not expected to have serious radioactivity accumulation within the components. Most of the sorption occurred at the turbine and recuperator hot‐side inlet region. In particular, the dose rate of the turbine was quite low, because the size of the turbine is very small.

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“…The steam oxidation model of Cubicciotti 3) has been selected to calculate the release rate of the volatile fission products from the fuel. For non-volatile fission products, Kelly's correlations 4) have been used to calculate the release rate. No fission products are released until the cladding fails.…”

Section: Methodsmentioning

confidence: 99%

Comparative Analysis of a Fission Product Behavior during Severe Accidents for a Typical PLWR and PHWR

Park

Song

2008

Journal of Nuclear Science and Technology

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The fission product behaviors of a severe accident sequence were analyzed for the typical pressurized light water reactor (PLWR) and heavy water reactor (PHWR) operated in Korea. The OPR-1000 and the Wolsong-2 plant were selected as reference plants. The obtained results are for:(1) the fission product release from the core, (2) the fission product distributions in a reactor coolant system, a molten corium, a reactor vessel, or a containment building, (3) the fission product release from the containment. The thermal hydraulic, severe accident phenomenological, and radiological analyses for their evaluation have been performed by using the MAAP(Modular Accident Analysis Program) and ISAAC (Integrated Severe Accident Analysis Code for CANDU Plant) computer program. Based on the ISAAC and MAAP calculation, the results show that the accident progression, including the fission product transportation, of the CANDU-6 type reactor is much more delayed than the typical PLWR, however, the possibility of a fission product release to the environment can be earlier due to the lower reactor building design pressure.

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Temperature Dependence of Fission Product Release Rates

Cited by 17 publications

References 5 publications

The Emission and Mobilization of Mo from Overheated Nuclear Fuel - the Importance of 'Maturation' of the Aerosols

The Emission and Mobilization of Mo from Overheated Nuclear Fuel - the Importance of 'Maturation' of the Aerosols

Radionuclide transport in a long‐term operation supercritical CO ₂ ‐cooled direct‐cycle small nuclear reactor

Comparative Analysis of a Fission Product Behavior during Severe Accidents for a Typical PLWR and PHWR

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Temperature Dependence of Fission Product Release Rates

Cited by 17 publications

References 5 publications

The Emission and Mobilization of Mo from Overheated Nuclear Fuel - the Importance of 'Maturation' of the Aerosols

The Emission and Mobilization of Mo from Overheated Nuclear Fuel - the Importance of 'Maturation' of the Aerosols

Radionuclide transport in a long‐term operation supercritical CO 2 ‐cooled direct‐cycle small nuclear reactor

Comparative Analysis of a Fission Product Behavior during Severe Accidents for a Typical PLWR and PHWR

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Radionuclide transport in a long‐term operation supercritical CO ₂ ‐cooled direct‐cycle small nuclear reactor