Fission gas release under time-varying conditions

Forsberg, Karl; Massih, Ali R

doi:10.1016/0022-3115(85)90348-4

Cited by 50 publications

(37 citation statements)

References 3 publications

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“…Helium and nitrogen gasses are produced from 10 B depletion and separation from 10 BN inside of the fuel pellet, respectively. Although all generated helium is directly released to the gap volume for the case that ZrB 2 is coated onto the pellet surface, helium and nitrogen are released out through diffusion and migration in the case of BN mixed with UO 2 .…”

Section: Generatedmentioning

confidence: 99%

“…It is assumed that a nitrogen atom is released from 10 B depletion and its amount is the same as the generated helium.…”

Section: Generatedmentioning

confidence: 99%

“…In this study, Forsberg Massih model [10,11] with modification was applied to helium release, which is based on a two-stage release model. More details are explained in the following subsections.…”

Section: Model Development and Code Modificationmentioning

confidence: 99%

“…When 10 B absorbs a neutron, it generates 7 Li and 4 He. The depletion rate of 10 B is equal to the production rate of 4 He within fuel pellets. 10 B depletion rate is calculated by followed simple relation as follows [12]: where N b (t) is the 10 B number density at time t; σ b , the (n,α) cross section of 10 B, ϕ (t) the neutron flux, respectively.…”

Section: Helium Productionmentioning

confidence: 99%

“…The depletion rate of 10 B is equal to the production rate of 4 He within fuel pellets. 10 B depletion rate is calculated by followed simple relation as follows [12]: where N b (t) is the 10 B number density at time t; σ b , the (n,α) cross section of 10 B, ϕ (t) the neutron flux, respectively. Figure 1 shows a comparison of the amount of helium production calculated by two different codes, FRAPCON-UNI and ORIGEN [13].…”

Section: Helium Productionmentioning

confidence: 99%

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Gas releases and rod internal pressure of BN-added UO₂fuel

Jeong

Yang

2015

Journal of Nuclear Science and Technology

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Gadolinium (Gd), in the form of gadolinia (Gd 2 O 3 ), has been used as integral burnable absorber to UO 2 fuel by different companies. Recently, alternative burnable absorber materials are under investigation. In this paper, the results of the study on the use of boron mixed in UO 2 as an integral burnable absorber are presented. Boron nitride was selected as the form of B to be added to UO 2 fuel based on the stability of B during sintering. Fuel performance analysis code FRAPCON-UNI, which is based on FRAPCON code and has the modifications for boron and helium generation and gasses release models, was used for the calculation of fuel performance. Helium generation was calculated using a model and the result was verified against ORIGEN calculation results. Gas release calculation was based on Forsberg Massih model and different characteristics of the gasses were considered. Power histories of maximum burnup rods (B rod, no B rod, and Gd rod) were selected from reactor physics data. The results indicated significant increases in rod internal pressure by 500 ppm boron addition at the end of life with minimum influence of a grain boundary boron fraction due to high diffusivity of helium and nitrogen.

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Section: Generatedmentioning

confidence: 99%

“…It is assumed that a nitrogen atom is released from 10 B depletion and its amount is the same as the generated helium.…”

Section: Generatedmentioning

confidence: 99%

Section: Model Development and Code Modificationmentioning

confidence: 99%