Release of fission products from irradiated SRP fuels at elevated temperature. Data report on the first stage of the SRP source term study

Abstract Nuclear power plant (NPP) safety has become a public issue since the Fukushima daiichi NPP accident. In order to evaluate the risks caused by severe accidents (SAs), it is very important to understand the on-site source term events. One of the important unsolved source term events is the decontamination efficiency of fission products (FPs) in the suppression chamber by pool scrubbing. Therefore, a mechanistic model to analyze the particle decontamination efficiency by pool scrubbing is highly regarded. Despite the demand, particle decontamination mechanism by pool scrubbing has never been understood due to the complexity of phenomena. In our experiment, we aim to develop a reliable mechanistic model to evaluate particle decontamination efficiency of pool scrubbing by conducting separate effect tests. As to obtain the fundamental process of particle decontamination from gas to liquid-phase, we focused on decontamination factor (DF) of particle from a single bubble. However, it is very difficult to calculate the initial particle concentration inside the bubble. Therefore, in our experiment, we developed a method to measure the internal particle concentration inside the bubble by combining image processing and particle measurement. By using the experimental results, we succeeded to obtain reasonable DF for glycerin particles and CsI particles as a simulant particle for FPs. From the experimental results, detailed particle decontamination efficiency for various submergence were measured. The results tend show that DF increase linearly as submergence increases which suggests that DF is constant on bubble rise region. Moreover, the fact that glycerin particle with larger particle diameter takes a higher value shows that particle diameter significantly affects DF.

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Trends in the short-term release of fission products and actinides to aqueous solution from used CANDU fuels at elevated temperature

Journal of Nuclear Materials ◽

10.1016/0022-3115(92)90079-z ◽

1992 ◽

Vol 190 ◽

pp. 87-100 ◽

Cited By ~ 8

Author(s):

S. Stroes-Gascoyne

Keyword(s):

Aqueous Solution ◽

Elevated Temperature ◽

Fission Products ◽

Short Term

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Source term of iodine and noble gas fission products in the fuel-to-sheath gap of intact operating nuclear fuel elements

Journal of Nuclear Materials ◽

10.1016/0022-3115(90)90438-s ◽

1990 ◽

Vol 172 (2) ◽

pp. 197-205 ◽

Cited By ~ 20

Author(s):

B.J. Lewis ◽

C.E.L. Hunt ◽

F.C. Iglesias

Keyword(s):

Nuclear Fuel ◽

Source Term ◽

Noble Gas ◽

Fission Products ◽

Fuel Elements

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CALCULATION OF RADIOACTIVE SOURCE TERM RELEASE FROM FLEXBLUE NPP

JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA ◽

10.17146/tdm.2021.23.2.6254 ◽

2021 ◽

Vol 23 (2) ◽

pp. 63

Author(s):

Muhammad Budi Setiawan ◽

Pande Made Udiyani

Keyword(s):

Nuclear Power ◽

Noble Metals ◽

Nuclear Reactor ◽

Source Term ◽

Reactor Core ◽

Fission Products ◽

Operating Conditions ◽

Normal Operating ◽

Small Modular Reactor ◽

Mechanistic Approach

One of the National Research Programs (PRN) in the energy sector of the Indonesian Ministry of Research and Technology for the period of 2020-2024 is small modular reactor (SMR) nuclear power plant (NPP) assessment. The France’s Flexblue is a PWR-based SMR submerged reactor with a power of 160 MWe. The Flexblue reactor module was built on the ocean site and easily provided the supply of reactor modules, in accordance with the conditions of Indonesia as an archipelagic country. Therefore, it is necessary to know the release of fission products (source term), which is necessary for the study of the radiation safety of a nuclear reactor. This paper aims to examine the source term in normal operating conditions and abnormal normal operating conditions, as well as postulated accidents. Based on the Flexblue reactor core parameter data, the calculation of the reactor core inventory uses the ORIGEN2 software is previously evaluated. The source term calculation uses a mechanistic approach and a graded approach. The normal source term is calculated assuming the presence of impurities on the fuel plate, due to fabrication limitations. Meanwhile, the abnormal source term is postulated in the LOCA event. The core reactor inventory and source term is divided into 8 radionuclide groups which are Noble gasses group (Xe, Kr); Halogen (I); Akali Metal (Cs, Rb); Tellurium Group (Te, Sb, Sc); Barium-Strontium Group (Ba, Sr); Noble Metals (Ru, Rh, Pd, Mo, Tc, Co); Lanthanides group (La, Zr, Nd, Eu, Nb, Pm, Pr, Sm, Y, Cm, Am) and Cerium Group (Ce, Pu , Np).

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Summary of Tritium Source Term Study in 10 MW High Temperature Gas-Cooled Test Reactor

Fusion Science & Technology ◽

10.1080/15361055.2020.1718856 ◽

2020 ◽

Vol 76 (4) ◽

pp. 513-525

Author(s):

X. Liu ◽

W. Peng ◽

F. Xie ◽

J. Cao ◽

Y. Dong ◽

...

Keyword(s):

High Temperature ◽

Source Term ◽

Term Study ◽

Test Reactor ◽

High Temperature Gas

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Pressure Distribution During Binder Burnout in Three-dimensional Porous Ceramic Bodies with Anisotropic Permeability

Journal of Materials Research ◽

10.1557/jmr.2002.0213 ◽

2002 ◽

Vol 17 (6) ◽

pp. 1434-1440 ◽

Cited By ~ 23

Author(s):

Stephen J. Lombardo ◽

Z. C. Feng

Keyword(s):

Elevated Temperature ◽

Gas Phase ◽

Source Term ◽

Ceramic Body ◽

Porous Ceramic ◽

Three Dimensional ◽

The Body ◽

Anisotropic Permeability ◽

Porous Bodies ◽

Binder Burnout

The flow of gas-phase products in three-dimensional porous bodies was modeled for the case when a source term is present. Analytical solutions to the governing partial differential equations were obtained for bodies of parallelepiped and cylindrical geometry. An important feature of the model is that it treats the case where the permeability in the body may be anisotropic. The evolution of pressure within the body depends on a number of parameters, including the rate of production of gas-phase species, and on the dimensions of the body. The model is thus able to describe the pressure within a porous ceramic body arising from flow during a number of elevated-temperature processing operations such as drying, binder burnout, and sintering.

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