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@book{ilich_bondarenko_group_1964,
	title = {Group constants for nuclear reactor calculations},
	publisher = {Consultants Bureau},
	author = {́Ilích Bondarenko, Igor},
	year = {1964}
}

@article{williams_computation_1995,
	title = {Computation of continuous-energy neutron spectra with discrete ordinates transport theory},
	volume = {121},
	number = {2},
	journal = {Nuclear Science and Engineering},
	author = {Williams, Mark L. and Asgari, Mehdi},
	year = {1995},
	note = {Publisher: Taylor \& Francis},
	pages = {173--201},
	file = {Snapshot:/Users/john/Zotero/storage/ZW3E69SG/NSE95-1.html:text/html}
}

@techreport{rearden_modernization_2015,
	title = {Modernization enhancements in {SCALE} 6.2},
	author = {Rearden, Bradley T. and Lefebvre, Robert A. and Lefebvre, Jordan P. and Clarno, Kevin T. and Williams, M. A. and Petrie, L. M. and Mertyurek, Ugur},
	year = {2015},
	file = {Snapshot:/Users/john/Zotero/storage/T3F8CJKF/search.html:text/html}
}

@article{williams_resonance_2011,
	title = {Resonance {Self}-{Shielding} {Methodologies} in {SCALE} 6},
	volume = {174},
	issn = {0029-5450},
	url = {https://doi.org/10.13182/NT09-104},
	doi = {10.13182/NT09-104},
	abstract = {SCALE 6 includes several problem-independent multigroup (MG) libraries that were processed from the evaluated nuclear data file ENDF/B using a generic flux spectrum. The library data must be self-shielded and corrected for problem-specific spectral effects for use in MG neutron transport calculations. SCALE 6 computes problem-dependent MG cross sections through a combination of the conventional Bondarenko shielding-factor method and a deterministic continuous-energy (CE) calculation of the fine-structure spectra in the resolved resonance and thermal energy ranges. The CE calculation can be performed using an infinite medium approximation, a simplified two-region method for lattices, or a one-dimensional discrete ordinates transport calculation with pointwise (PW) cross-section data. This paper describes the SCALE-resonance self-shielding methodologies, including the deterministic calculation of the CE flux spectra using PW nuclear data and the method for using CE spectra to produce problem-specific MG cross sections for various configurations (including doubly heterogeneous lattices). It also presents results of verification and validation studies.},
	number = {2},
	urldate = {2020-11-04},
	journal = {Nuclear Technology},
	author = {Williams, Mark L.},
	month = may,
	year = {2011},
	note = {Publisher: Taylor \& Francis
\_eprint: https://doi.org/10.13182/NT09-104},
	pages = {149--168},
	file = {Full Text PDF:/Users/john/Zotero/storage/RNDDJ4IH/Williams - 2011 - Resonance Self-Shielding Methodologies in SCALE 6.pdf:application/pdf;Snapshot:/Users/john/Zotero/storage/IB25H5RK/NT09-104.html:text/html}
}