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Go Chiba, Kenji Yokoyama, Masahiro Fukushima, Taira Hazama
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A modified diffusion coefficient for heterogeneous low-density channels
10.1080/18811248.1995.9731745 · 1995
Three-dimensional transport calculation method for eigenvalue problems using diffusion synthetic acceleration
10.1080/18811248.1985.9735733 · 1985
Unresolved referenced work
1964
Unresolved referenced work
1978
Unresolved referenced work
Kept as external metadata until matched
A combined method to evaluate the resonance self-shielding effect in power fast reactor fuel calculation
10.1080/18811248.2003.9715389 · 2003
Overestimation in parallel component of neutron leakage observed in sodium void reactivity worth calculation for fast critical assemblies
10.1080/18811248.2006.9711180 · 2006
Verification of homogenization in fast critical assembly analyses
10.1080/18811248.2006.9711233 · 2006
Unresolved referenced work
Kept as external metadata until matched
Neutron transport benchmark problem proposal for fast critical assembly without homogenizations
10.1016/j.anucene.2007.02.018 · 2007
Improvement of moment-based probability table for resonance self-shielding calculation
10.1016/j.anucene.2006.05.013 · 2006
Methods of adjustment and error evaluation of neutron capture cross sections; application to fission product nuclides
10.13182/nse77-3 · 1977
Bias factor method using random sampling technique
10.1080/00223131.2015.1126541 · 2016
Development and verification of a fast reactor burnup calculation module FRBurner in a code system CBZ
10.1080/00223131.2021.1936683 · 2021
Experiments on criticality and reactivity worths in the FCA XXII-1 assembly simulating highly enriched MOX fueled tight lattice LWR cores
10.1080/00295639.2024.2347706 · 2024
A series of experiments on criticality and reflector reactivity worth in FCA XXIII-1 and FCA XXIV-1 assemblies simulating a small fast reactor with a thick stainless steel reflector
2025
Benchmark models for criticalities of FCA IX assemblies with systematically changed neutron spectra
10.1080/00223131.2015.1054911 · 2016
Benchmark calculations of sodium-void experiments with uranium fuels at the fast critical assembly FCA
10.15669/pnst.2.306 · 2011
TRU oxide sample reactivity worths measured in the FCA IX assemblies with systematically changed neutron energy spectra
10.1080/00223131.2023.2240872 · 2024
Analyses with latest major nuclear data libraries of the fission rate ratios for several TRU nuclides in the FCA IX experiments
10.1080/00223131.2017.1299644 · 2017
Unresolved referenced work
1973
Methods for the calculation of streaming corrected diffusion coefficients for pin and plate cells in fast reactors
1980
Development of a fine and ultra-fine group cell calculation code SLAROM-UF for fast reactor analyses
10.1080/18811248.2006.9711176 · 2006
Criticality evaluation for the monju restart core
10.13182/nt12-a14097 · 2012
Iterative resonance self-shielding methods using resonance integral table in heterogeneous transport lattice calculations
2018
Unresolved referenced work
1975
Iterative resonance self-shielding methods using resonance integral table in heterogeneous transport lattice calculations
10.1016/j.anucene.2010.08.022 · 2011
Unresolved referenced work
Kept as external metadata until matched
Unresolved referenced work
1978
Unresolved referenced work
1978
A new nodel sn transport method for three-dimensional hexagonal geometry
10.1080/18811248.1994.9735184 · 1994
Unresolved referenced work
1974
Unresolved referenced work
1971
Unresolved referenced work
Kept as external metadata until matched
Unresolved referenced work
Kept as external metadata until matched
ZPPR benchmarks for large LMFBR core physics from JUPITER cooperative program between United States and Japan
10.13182/nse14-9 · 2014
Unresolved referenced work
2001
Development of a unified cross-section set ADJ2000 based on adjustment technique for fast reactor analysis
10.1080/00223131.2002.10875287 · 2002
Unresolved referenced work
1997
Japanese evaluated nuclear data library version 5: JENDL-5
10.1080/00223131.2022.2141903 · 2023
Resonance calculation for large and complicated geometry using tone’s method by incorporating the method of characteristics
10.1080/18811248.2011.9711707 · doi-reference
Numerical study on applicability of Benoist’s diffusion coefficient to sodium void reactivity analysis
10.1080/18811248.1976.9734057 · doi-reference
Improved treatment of the neutron streaming through control rod followers in a sodium-cooled fast reactor
10.13182/nse79-a20393 · doi-reference
Cross-section adjustment methods based on minimum variance unbiased estimation
10.1080/00223131.2016.1146637 · doi-reference
Generalized formulation of extended cross-section adjustment method based on minimum variance unbiased linear estimation
10.1080/00223131.2018.1531078 · doi-reference
Extended cross-section adjustment method to improve the prediction accuracy of core parameters
10.1080/00223131.2012.739020 · doi-reference
Development of adjusted nuclear data library for fast reactor application
10.1051/epjconf/202328100004 · doi-reference
Three-dimensional transport correction in fast reactor core analysis
10.1080/18811248.1986.9735068 · doi-reference
Subgroup parameters based on orthgonal factorization
10.1080/18811248.2007.9711254 · doi-reference
A complement proposal for optimization of subgroup parameters
10.1080/18811248.2006.9711158 · doi-reference
Reaction rate calculation in fast reactor blanket using multiband Sn method
10.1080/18811248.2000.9714915 · doi-reference
Improvement of Tone’s method with two-term rational approximation
10.1080/18811248.2011.9711700 · doi-reference
A generalized approach to optimize subgroup parameters
10.1080/18811248.2004.9715504 · doi-reference
Background-cross-section-dependent sub-group parameters
10.1080/18811248.2003.9715368 · doi-reference
Optimization study on the diffusion synthetic acceleration algorithm in three-dimensional discrete ordinate transport
10.1080/18811248.1995.9731776 · doi-reference
Cross section adjustment method based on random sampling technique
10.1080/00223131.2014.882801 · doi-reference
APOLLO3 homogenization techniques for transport core calculations - application to the ASTRID CFV core
10.1016/j.net.2017.08.014 · doi-reference
Development of a ‘best rpresentativity’ method for experimental data analysis and an application to the critical experiments at the toshiba nca facility
10.1080/00223131.2014.884953 · doi-reference
A numerical study of heterogeneity effects in fast reactor critical assemblies
10.1080/18811248.1975.9733139 · doi-reference
A refined analysis on the power reactivity loss measurement in Monju
10.1016/j.pnucene.2017.06.004 · doi-reference
Prediction uncertainty evaluation methods of core performance parameters in large liquid-metal fast breeder reactors
10.13182/nse89-1 · doi-reference
Comparison of the anisotropic diffusion coefficients based on the Benoist and Deniz formula
10.1080/18811248.1972.9734922 · doi-reference
Calculation of the anisotropic diffusion coefficient
10.1080/18811248.1972.9734929 · doi-reference
An effective homonization method for heterogeneous assemblies
10.1016/0306-4549(82)90020-2 · doi-reference
Determination of cell averaged diffusion constants based on transport/diffusion perturbation theory
10.1080/18811248.1987.9733535 · doi-reference
Estimation of anisotropic effect of diffusion coefficient in a fast critical assembly
10.1080/18811248.1974.9730690 · doi-reference
Estimation of anisotropy of diffusion coefficient in a fast reactor
10.1080/18811248.1976.9734004 · doi-reference
Unified diffusion coefficient for analysis of sodium-void worth in fast critical assembly with control-rod channels
10.1080/18811248.1981.9733231 · doi-reference
Control rod worth evaluation for the monju restart core
10.13182/nt12-a14098 · doi-reference
An improvement of the transverse leakage treatment for nodal Sn transport calculation method in hexagonal-Z geometry
10.1080/18811248.1996.9731968 · doi-reference
Effect of polynomial expansion order of intranode flux treatment in nodal sn transport calculation code NSHEX for large-size fast power reactor core analysis
10.1080/18811248.2011.9711716 · doi-reference
Development of a unified cross-section set ADJ2010 based on adjustment technique for fast reactor core design
10.3938/jkps.59.1357 · doi-reference
Japanese evaluated nuclear data library version 3 revision-3: jendl-3.3
10.1080/18811248.2002.9715303 · doi-reference
JENDL-4.0: A new library for nuclear science and engineering
10.1080/18811248.2011.9711675 · doi-reference
A MOC-based heterogeneous leakage model
10.1016/j.anucene.2025.111449 · doi-reference
Generalized bias factor method for accurate prediction of neutronics characteristics
10.1080/18811248.2006.9711242 · doi-reference
Experimental cores for benchmark experiments of effective delayed neutron fraction βeff at FCA
10.1016/s0149-1970(99)00007-4 · doi-reference
Effective spatial homonization with neutron leakage effect for FBR control rods
10.1080/18811248.1985.9735662 · doi-reference
Diffusion coefficients for LMFBR cells calculated with MOC and Monte Carlo methods
10.1016/j.anucene.2010.08.004 · doi-reference
Use of integral experiments in the assessment of large liquid-metal fast breeder reactor basic design parameters
10.13182/nse87-333 · doi-reference