Shielding Analysis Capability of UNF-ST&amp;DARDS

Radulescu, Georgeta; Banerjee, Kaushik; Lefebvre, Robert A; Miller, L; Scaglione, John M

doi:10.1080/00295450.2017.1307643

Cited by 6 publications

(7 citation statements)

References 7 publications

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“…In this design, some fuel pellets in the assembly are covered with a thin layer of zirconium diboride. Helium is produced in consequence of the neutron absorption by 10 B and is released to plenum. The issues associated with IFBA are discussed in Section 3.2.3 .…”

Section: Helium Production and Behaviormentioning

confidence: 99%

“…Growing needs for numerical analyses concern not only fuel performance modeling but also other aspects of dry storage. Numerous publications studying criticality, shielding, thermohydraulics or mechanics of dry storage casks are available [7][8][9][10][11][12] . Such simulations provide boundary conditions and their uncertainties for fuel behavior modeling.…”

Section: Introductionmentioning

confidence: 99%

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Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling

Konarski

Cozzo

Khvostov

et al. 2021

Journal of Nuclear Materials

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The role of dry storage in spent nuclear fuel management becomes more and more important. Originally intended to serve as a temporary solution for a few decades until final disposal, now dry storage period is to be extended to 100 years and beyond. It has to be proven for licensing that the fuel rod integrity during dry storage is ensured. Since it is difficult to provide experimental support, the licensing process has to rely largely on numerical simulations. This paper reviews the literature associated with the modeling of spent nuclear fuel under dry storage conditions. The main phenomena threatening the fuel rod integrity and the numerical models representing them are described here. Moreover, the most recent or currently ongoing experimental efforts that could support the modeling of nuclear fuel in dry storage in the future are discussed. Finally, this paper reviews approaches to dry storage modeling chosen by different countries. In general, these approaches are similar and can be described as a calculation chain consisting of neutronics-thermo-hydraulics-fuel performance computations where sensitivity and uncertainty studies are crucial elements.

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Section: Helium Production and Behaviormentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Spent nuclear fuel in dry storage conditions – current trends in fuel performance modeling

Konarski

Cozzo

Khvostov

et al. 2021

Journal of Nuclear Materials

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show abstract

“…ORIGAMI, 16 a SCALE code that performs fast ORIGEN depletion calculations using pre-generated ORIGEN cross-section libraries, was used to calculate the photon and neutron sources in the fuel region and the 60 Co activation source in fuel assembly hardware regions and nonfuel hardware. These ORIGEN cross-section libraries, developed for the Used Nuclear Fuel-Storage, Transportation & Disposal Analysis Resource and Data Systems (UNF-ST&DARDS), 17,18 produce slightly conservative radiation source terms. The operating conditions used to generate the libraries (e.g., moderator density within the lower range of the typical moderator density values during normal operation and full fuel exposure to burnable absorber rods/control blades) were specifically selected to produce conservative nuclide concentrations for criticality calculations.…”

Section: Source Term Calculationsmentioning

confidence: 99%

“…The assumed cobalt impurity concentration in the fuel assembly hardware was 0.8 g/kg for stainless steel (SS) and 4.7 g/kg for Inconel. 17 The 61BT DSC requires different fuel assembly characteristics for gamma and neutron source term calculations, as determined in the safety analysis. 14 The SAR performed a source term analysis for a GE 7  7 assembly using four different combinations of burnup, initial enrichment, and post-irradiation cooling time to determine the set of parameters producing bounding gamma and neutron radiation sources for the analyzed cases.…”

Section: Nuhoms ® Hsm Model 102mentioning

confidence: 99%

“…13 The assumed cobalt impurity concentration in fuel assembly and nonfuel hardware was 0.8 g/kg for SS and 4.7 g/kg for Inconel. 17 The characteristics of the design basis fuel assembly used in source term calculations were an initial uranium mass of 375 kg, a 3.8 wt% 235 U enrichment, an assembly average burnup value of 45 GWd/MTU, and a 10-year decay time.…”

Section: Nuhoms ® Advanced Hsmmentioning

confidence: 99%

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