NECP-Atlas: A new nuclear data processing code

Briesmeister, J.F., 2000. MCNP-A General Monte Carlo N-Particle Transport Code. LA-13709M.

Chen, 2018, A new high-fidelity neutronics code NECP-X, Ann. Nucl. Energy, 116, 417, 10.1016/j.anucene.2018.02.049

Cullen, 1976, Exact Doppler broadening of tabulated cross sections, Nucl. Sci. Eng., 60, 199, 10.13182/NSE76-1

Cullen D.E., 2010. Nuclear Data Preparation, volume 1 of Handbook of Nuclear Engineering. pp. 319–350.

Cullen, 2016

Cullen, 2017

Ducru, 2017, Kernel reconstruction methods for Doppler broadening – Temperature interpolation by linear combination of reference cross section at optimally chosen temperatures, J. Comp. Phys., 335, 535, 10.1016/j.jcp.2017.01.039

Forget, 2014, Direct Doppler broadening in Monte Carlo simulations using the multipole representation, Ann. Nucl. Energy, 64, 78, 10.1016/j.anucene.2013.09.043

Godfrey, 2014

Hebert, A., 2013. DRAGON5: Designing computational schemes dedicated to fission nuclear reactor for space. In: Proceeding of Nuclear and Emerging Technologies for Space 2013. Albuquerque, NM, Feb. 25-28, 2013.

Hong, 2011, Iterative resonance self-shielding methods using resonance integral table in heterogeneous transport lattice calculations, Ann. Nucl. Energy, 38, 32, 10.1016/j.anucene.2010.08.022

IAEA, Yang, H., https://www.iaea.org/NuclearPower/Downloadable/Meetings/2013/2013-09-11-09-13-TM-NPTD/7.yang.pdf.

IAEA. WIMS-D Library update. https://www-nds.iaea.org/wimsd/.

Lee, 2009, The impact of 238U resonance elastic scattering approximations on thermal reactor Doppler reactivity, Ann. Nucl. Energy, 36, 274, 10.1016/j.anucene.2008.11.026

Levitt, 1972, The probability table method for treating unresolved neutron resonances in Monte Carlo calculations, Nucl. Sci. Eng., 49, 450, 10.13182/NSE72-3

Liu, P., Wu, X., Ge, Z., Li, S., Wu, H., Wen L., Wang, W., Zhang, H., 2016. Progress on China nuclear data processing code system. Proceedings of the ND2016, Sep 11-16, Bruges, Bergium, 2016.

Liu, 2018, On-the-fly treatment of temperature dependent cross sections in the unresolved resonance region in RMC code, Ann. Nucl. Energy, 111, 234, 10.1016/j.anucene.2017.09.010

Liu, 2016, Development of on-the-fly temperature-dependent cross sections treatment in RMC code, Ann. Nucl. Energy, 94, 144, 10.1016/j.anucene.2016.02.026

Liu, 2016, Assessment of homogeneous and heterogeneous resonance integral tables and their applications to the embedded self-shielding method, Ann. Nucl. Energy, 92, 186, 10.1016/j.anucene.2016.01.045

MacFarlane, 2016

Marleau, G., Hebert, A., Roy, R., 2018. A user guide for DRAGON Version5. Technical Report: IGE-335.

Mosteller, 2006

Mattoon, 2012, Generalized nuclear data: a new structure (with supporting infrastructure) for handling nuclear data, Nucl. Data Sheets, 113, 3145, 10.1016/j.nds.2012.11.008

OECD-NEA, 2006

Ouisloumen, 1991, A model for neutron scattering off heavy isotopes that accounts for thermal agitation effect, Nucl. Sci. Eng., 107, 189, 10.13182/NSE89-186

Ouisloumen, 2015, Anisotropic elastic resonance scattering model for the neutron transport equation, Nucl. Sci. Eng., 179, 59, 10.13182/NSE13-99

Pusa, 2012, Incorporating sensitivity and uncertainty analysis to a lattice physics code with application to CASMO-4, Ann. Nucl. Energy, 40, 153, 10.1016/j.anucene.2011.10.013

Romano, 2015, Comparison of algorithms for Doppler broadening pointwise tabulated cross sections, Ann. Nucl. Energy, 75, 358, 10.1016/j.anucene.2014.08.046

She, 2016, XPZ: development of a lattice code for HTR, Ann. Nucl. Energy, 97, 183, 10.1016/j.anucene.2016.07.017

Tada, 2017, Development and verification of a new nuclear data processing system FRENDY, J. Nucl. Sci. Tech., 54, 806, 10.1080/00223131.2017.1309306

Trkov, 2012

Walsh, 2017, On-the-fly Doppler broadening of unresolved resonance region cross sections, Prog. Nucl. Energy, 101, 444, 10.1016/j.pnucene.2017.05.032

Wiarda, 2016

Zhang, 2016, The Shandong Shidao Bay 200 MWe High-temperature gas-cooled reactor pebble-bed module (HTR-PM) demonstration power plant: an engineering and technological innovation, Engineering, 2, 112, 10.1016/J.ENG.2016.01.020

Zheng, 2018, SARAX: a new code for fast reactor analysis part II: verification, validation and uncertainty quantification, Nucl. Eng. Des., 331, 41, 10.1016/j.nucengdes.2018.02.033

Zu, 2016, Total uncertainty analysis for PWR assembly based on the statistical sampling method, Nucl. Sci. Eng., 183, 371, 10.13182/NSE15-96