Measurement of fission gas release, internal pressure and cladding creep rate in the fuel pins of PHWR bundle of normal discharge burnup

Viswanathan, U.K.; Sah, D.N.; Rath, B.N.; Anantharaman, S.

doi:10.1016/j.jnucmat.2009.04.021

Cited by 13 publications

(5 citation statements)

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“…where α′ 1/e −fBuQV/RT Viswanathan et al (2009) studied the fuel pins of the PHWR (pressurized heavy-water reactor) bundle discharged after the burnup of 7,528 MWd/tU. The results showed that the fission gas release from the outer ring of the fuel was about 8%, and that from the interior and central pin was below 1%.…”

Section: Single Fission Gas Behaviormentioning

confidence: 99%

“…The result of the fission gas release in fuel pins of fuel bundle No. 54505 is shown in Table 2, and the comparison of predicted and measured FGRs and internal pressures is also summarized in Supplementary Table S1 (Viswanathan et al, 2009).…”

Section: Single Fission Gas Behaviormentioning

confidence: 99%

“…The shape of the BISON FGR simulation is different from the measurement data. Thus, the original data have convergence problems for the MCMC (Markov Chain (Kim et al, 1996 (Notley et al, 1980;Kogai, 1997;Bernard et al, 2002;van Uffelen et al, 2002;Matsson et al, 2007;Kim et al, 2008;Viswanathan et al, 2009;Koo et al, 2010;Koo et al, 2010Koo et al, , 2019Khvostov et al, 2011;Pastore et al, 2013;Liu et al, 2015;Liu et al, 2016;Rest et al, 2019;Che et al, 2021;Cooper et al, 2021). (G-J) Fission gas release vs. time in the UO 2 fuel (Evans, 1996;Kogai, 1997;Zacharie et al, 1998;Khvostov et al, 2011;Pastore et al, 2013;Andersson et al, 2014;Wu et al, 2018;Verdolin et al, 2020).…”

Section: Single Fission Gas Behaviormentioning

confidence: 99%

“…Gap/plenum pressure with burnup in the U 3 Si 2 and UO 2 fuels (Viswanathan et al, 2009;Pastore et al, 2013;Liu et al, 2015;Liu et al, 2016;Yingling et al, 2021). (B) Gap/plenum pressure with burnup in the metallic fuel (Karahan et al, 2009).…”

Section: Figure 3 | (A)mentioning

confidence: 99%

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Fission Gas Behaviors and Relevant Phenomena in Different Nuclear Fuels: A Review of Models and Experiments

Guo¹,

Lai²,

Zhou

et al. 2022

Front. Energy Res.

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Reactor structural integrity and nuclear safety are seriously affected by the fission gas behaviors and relevant physical phenomena in nuclear fuels. In this review, the fission gas behavior and relevant phenomena in different fuels for both models and experiments have been comprehensively overviewed, including fission gas release, gap/plenum pressure, grain growth, swelling, fission gas diffusion coefficients, and fuel cladding mechanical and chemical interactions under irradiations. The fission gas behaviors can be classified into single fission gas behavior and combined fission gas behavior with more interacting physics together. In addition, fission gas behaviors are also profoundly influenced by fuel performance, which is different in different kinds of fuels. The data of different nuclear fuels are collected, for example, UO2, MOX, metallic, U3Si2, UN, UC, and TRISO fuels. The models and experiments on fission gas behaviors are summarized into figures and tables for better comparisons. The fission gas behaviors are mainly subjected to burnup, time, and temperature, which profoundly impact these behaviors. The burnup will motivate the fission gas release and other fission gas behaviors. With the fuel temperature increase, the extent of some fission gas behaviors will be more strengthened, including fission gas release, gap/plenum pressure, grain growth, swelling, and fuel cladding mechanical and chemical interactions. The predicted data are consistent with the measured data, and the modeling results generally agree well with the experimental data. In addition, the observation of enhanced gas release at high burnups is unexpected. However, the modeling approaches on fission gas release behaviors still have certain uncertainties. Therefore, it still has considerable space to be improved and is worth studying in future work.

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Section: Single Fission Gas Behaviormentioning

confidence: 99%

Section: Single Fission Gas Behaviormentioning

confidence: 99%

Section: Single Fission Gas Behaviormentioning

confidence: 99%

Section: Figure 3 | (A)mentioning

confidence: 99%

See 2 more Smart Citations

Fission Gas Behaviors and Relevant Phenomena in Different Nuclear Fuels: A Review of Models and Experiments

Guo¹,

Lai²,

Zhou

et al. 2022

Front. Energy Res.

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“…FGR occurs via diffusion of gas atoms at the opening grain boundary [6]. The FGR is subjected to gas sweeping on the grain boundary in the PHWR [7]. The simulation results show that fission products raise with grain diameter in the VVER [8].…”

Section: Introductionmentioning

confidence: 99%

Extended Development of a Fission Gas Release Behavior Model Inside Spherical Fuel Grains for LWR Reactors

Guo,

Cheng,

Wang

et al. 2023

Applied Sciences

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Fission gas plays a significant role in fuel rod performance following accidents. The amount of fission gas increases dramatically under accidental conditions. This leads to a subsequent rise in the fuel rod internal pressure and temperature due to aggravated gap conductance between the fuel pellet and cladding. As a result, fuel rod performance degrades. Therefore, studying fission gas behavior is crucial for accident assessment and evaluating fuel rod performance. Minimizing the Impact of fission gas on fuel rods is essential for maintaining their integrity and safety within nuclear reactors. One important aspect of ensuring safety is predicting fission gas release (FGR). In this study, we presented an extended model to be used in light water reactors (LWRs). The FGR can be modeled using COMSOL Multiphysics with the finite element method. This modeling approach considers both normal and abnormal conditions, with the latter categorized as Class-II type incidents. The model assumes that the gas diffusion inside a spherical grain varies over time. By examining perfect sinks with gas production, perfect sinks without gas production, and imperfect sinks under steady-state conditions, different initial and boundary conditions are set. To validate the accuracy and universality of expressions used in the model, input parameters from other models and experiments are utilized. By comparing the model’s results with these inputs, the accuracy and applicability of the expressions can be confirmed. This validation process ensures that the model provides reliable predictions for fission gas behavior in fuel rods under both normal and abnormal operating conditions. Based on our findings, it is evident that the FGR fraction displays an upward trend as diffusion coefficients and temperatures rise. Conversely, larger grain sizes and higher linear heat generation rates are associated with a reduction in the FGR fraction. Notably, enhanced resolution leads to a postponed onset of FGR. Furthermore, the influence of the diffusion coefficient on the FGR fraction primarily stems from the interconnected effects of temperature and linear heat generation rate.

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Uncertainty in Fission Product Transient Release Under Accident Condition

Bera

Paul

Datta

et al. 2018

Advances in Intelligent Systems and Computing

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Measurement of fission gas release, internal pressure and cladding creep rate in the fuel pins of PHWR bundle of normal discharge burnup

Cited by 13 publications

References 9 publications

Fission Gas Behaviors and Relevant Phenomena in Different Nuclear Fuels: A Review of Models and Experiments

Fission Gas Behaviors and Relevant Phenomena in Different Nuclear Fuels: A Review of Models and Experiments

Extended Development of a Fission Gas Release Behavior Model Inside Spherical Fuel Grains for LWR Reactors

Uncertainty in Fission Product Transient Release Under Accident Condition

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