Research graph
References from The history of reactor physics studies for fast-spectrum reactor application in Japan. Local targets link to admitted publications; unresolved targets remain external evidence.
A modified diffusion coefficient for heterogeneous low-density channels
10.1080/18811248.1995.9731745 · 1995 · External reference
Three-dimensional transport calculation method for eigenvalue problems using diffusion synthetic acceleration
10.1080/18811248.1985.9735733 · 1985 · External reference
Unresolved reference
1964 · External reference
Unresolved reference
1978 · External reference
Unresolved reference
External reference
A combined method to evaluate the resonance self-shielding effect in power fast reactor fuel calculation
10.1080/18811248.2003.9715389 · 2003 · External reference
Overestimation in parallel component of neutron leakage observed in sodium void reactivity worth calculation for fast critical assemblies
10.1080/18811248.2006.9711180 · 2006 · External reference
Verification of homogenization in fast critical assembly analyses
10.1080/18811248.2006.9711233 · 2006 · External reference
Unresolved reference
External reference
Neutron transport benchmark problem proposal for fast critical assembly without homogenizations
10.1016/j.anucene.2007.02.018 · 2007 · External reference
Improvement of moment-based probability table for resonance self-shielding calculation
10.1016/j.anucene.2006.05.013 · 2006 · External reference
Methods of adjustment and error evaluation of neutron capture cross sections; application to fission product nuclides
10.13182/nse77-3 · 1977 · External reference
Bias factor method using random sampling technique
10.1080/00223131.2015.1126541 · 2016 · External reference
Development and verification of a fast reactor burnup calculation module FRBurner in a code system CBZ
10.1080/00223131.2021.1936683 · 2021 · External reference
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 · External reference
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 · External reference
Benchmark models for criticalities of FCA IX assemblies with systematically changed neutron spectra
10.1080/00223131.2015.1054911 · 2016 · External reference
Benchmark calculations of sodium-void experiments with uranium fuels at the fast critical assembly FCA
10.15669/pnst.2.306 · 2011 · External reference
TRU oxide sample reactivity worths measured in the FCA IX assemblies with systematically changed neutron energy spectra
10.1080/00223131.2023.2240872 · 2024 · External reference
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 · External reference
Unresolved reference
1973 · External reference
Methods for the calculation of streaming corrected diffusion coefficients for pin and plate cells in fast reactors
1980 · External reference
Development of a fine and ultra-fine group cell calculation code SLAROM-UF for fast reactor analyses
10.1080/18811248.2006.9711176 · 2006 · External reference
Criticality evaluation for the monju restart core
10.13182/nt12-a14097 · 2012 · External reference
Iterative resonance self-shielding methods using resonance integral table in heterogeneous transport lattice calculations
2018 · External reference
Unresolved reference
1975 · External reference
Iterative resonance self-shielding methods using resonance integral table in heterogeneous transport lattice calculations
10.1016/j.anucene.2010.08.022 · 2011 · External reference
Unresolved reference
External reference
Unresolved reference
1978 · External reference
Unresolved reference
1978 · External reference
A new nodel sn transport method for three-dimensional hexagonal geometry
10.1080/18811248.1994.9735184 · 1994 · External reference
Unresolved reference
1974 · External reference
Unresolved reference
1971 · External reference
Unresolved reference
External reference
Unresolved reference
External reference
ZPPR benchmarks for large LMFBR core physics from JUPITER cooperative program between United States and Japan
10.13182/nse14-9 · 2014 · External reference
Unresolved reference
2001 · External reference
Development of a unified cross-section set ADJ2000 based on adjustment technique for fast reactor analysis
10.1080/00223131.2002.10875287 · 2002 · External reference
Unresolved reference
1997 · External reference
Japanese evaluated nuclear data library version 5: JENDL-5
10.1080/00223131.2022.2141903 · 2023 · External reference
Fuel pin and subassembly heterogeneity effect on neutronics properties of fast power reactor
10.1080/18811248.1981.9733225 · 1981 · External reference
Error due to nuclear data uncertainties in the prediction of liquid-metal fast breeder reactor core performance parameters
10.13182/nse83-1 · 1983 · External reference
Unresolved reference
1967 · External reference
Effective admixture corss section in plate lattice heterogeneous systems
10.1080/18811248.1974.9730651 · 1974 · External reference
Second version of japanese evaluated nuclear data library (JENDL-2)
10.1080/18811248.1985.9735704 · 1985 · External reference
New control rod homonization method for fast reactors
10.1080/18811248.1994.9735205 · 1994 · External reference
Theoretical study on new bias factor methods to effectively use critical experiments for improvement of prediction accuracy of neutronic characteristics
10.1080/18811248.2007.9711400 · 2007 · External reference
.1 Correlation between the integral data obtained in partial and full mock-up systems
10.1080/18811248.1972.9734923 · 1973 · External reference
Unresolved reference
1973 · External reference
Unresolved reference
1976 · External reference
Adjusted cross section library AGLI and reliability of analysis of integral data
1973 · External reference
Unconditionally stable diffusion-synthetic acceleration methods for the slab geometry discrete ordinates equations. Part I: theory
10.13182/nse82-1 · 1982 · External reference
Unresolved reference
External reference
Unresolved reference
External reference
Resonance self-shielding methods for fast reactor calculations - comparison of a new Tone’s method with the subgroup method in APOLLO3
10.1080/00295639.2017.1332890 · 2017 · External reference
Uncertainty reduction of sodium void reactivity using data from a sodium shielding experiment
10.1080/00223131.2023.2244512 · 2024 · External reference
Hybrid data assimilation methods for nuclear-data-induced uncertainties
10.1080/00223131.2025.2500579 · 2026 · External reference
A new experimental method of estimating physics parameters in large fast reactors
10.1080/18811248.1976.9733987 · 1976 · External reference
Adjustment of group cross sections by means of integral data, (I) theoretical study
10.1080/18811248.1972.9734867 · 1972 · External reference
Adjustment of group cross sections by means of integral data, (II) numerical study
10.1080/18811248.1972.9734917 · 1972 · External reference
Unresolved reference
1980 · External reference
Unresolved reference
1967 · External reference
Unresolved reference
1968 · External reference
Isothermal temperature coefficient evaluation for the monju restart core
10.13182/nt12-a14099 · 2012 · External reference
Evaluation of sodium radioactivity in the primary system of the prototype fast reactor monju
10.1080/00295450.2023.2181044 · 2023 · External reference
Actinide integral measurements in FCA assemblies
10.1080/00337578608207441 · 1986 · External reference
An evaluation of different methods for space-dependent resonance shielding of cross sections in fast reactors
10.13182/nse80-a21326 · 1980 · External reference
Generalization of the tibere B1 leakage model to the method of characteristics
10.1016/j.anucene.2022.109160 · 2022 · External reference
Unresolved reference
External reference
Double heterogeneity effect of fuel pin and subassembly in a fast power reactor
10.13182/nse83-a18215 · 1983 · External reference
Japanese evaluated nuclear data library, version 3 revision-2; JENDL-3.2
10.1080/18811248.1995.9731849 · 1995 · External reference
Analysis of sodium void reactivity measured in FCA V-1 assembly
10.1080/18811248.1973.9733040 · 1973 · External reference
Unresolved reference
2020 · External reference
Evaluation of reaction rate distribution measurement in the prototype fast reactor monju
10.1080/00295450.2023.2295168 · 2024 · External reference
Unresolved reference
1998 · External reference
Experiments and analyses on sodium void reactivity worth in mock-up cores of metallic fueled and MOX fueled fast reactors at FCA
10.1080/18811248.1998.9733856 · 1998 · External reference
Experiments and analyses on sodium void reactivity worth in uranium-free fast reactor at FCA
10.1080/18811248.2002.9715254 · 2002 · External reference
A proposal of benchmark calculation on reactor physics for metallic fueled and MOX fueled LMFBR based upon mock-up experiment at FCA
10.1080/18811248.2000.9714883 · 2000 · External reference
Unresolved reference
1992 · External reference
Resonance interaction effect between hot sample and cold core in analysis of Doppler effect measurement
10.1080/18811248.1994.9735264 · 1994 · External reference
Use of integral experiments in the assessment of large liquid-metal fast breeder reactor basic design parameters
10.13182/nse87-333 · 1984 · External reference
Unresolved reference
2017 · External reference
Unresolved reference
External reference
Diffusion coefficients for LMFBR cells calculated with MOC and Monte Carlo methods
10.1016/j.anucene.2010.08.004 · 2011 · External reference
THe ZEBRA MOZART programme. Part 1. MZA and MZB ZEBRA assemblies 11 and 12
2010 · External reference
THe ZEBRA MOZART programme. Part 2. MZC and the control rod studies ZEBRA assemblies 12/4 and 12/5
2010 · External reference
Unresolved reference
2011 · External reference
Effective spatial homonization with neutron leakage effect for FBR control rods
10.1080/18811248.1985.9735662 · 1985 · External reference
Experimental cores for benchmark experiments of effective delayed neutron fraction βeff at FCA
10.1016/s0149-1970(99)00007-4 · 1999 · External reference
Method and approaches to provide feedback from nuclear and covariance data adjustment for improvement of nuclear data files: Major findings of the NEA WPEC subgroup 39
2020 · External reference
Unresolved reference
2013 · External reference
Generalized bias factor method for accurate prediction of neutronics characteristics
10.1080/18811248.2006.9711242 · 2006 · External reference
A MOC-based heterogeneous leakage model
10.1016/j.anucene.2025.111449 · 2025 · External reference
JENDL-4.0: A new library for nuclear science and engineering
10.1080/18811248.2011.9711675 · 2011 · External reference
Japanese evaluated nuclear data library version 3 revision-3: jendl-3.3
10.1080/18811248.2002.9715303 · 2002 · External reference
Unresolved reference
1975 · External reference
Unresolved reference
1982 · External reference
Development of a unified cross-section set ADJ2010 based on adjustment technique for fast reactor core design
10.3938/jkps.59.1357 · 2011 · External reference
Unresolved reference
1998 · External 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 · 2011 · External reference
An improvement of the transverse leakage treatment for nodal Sn transport calculation method in hexagonal-Z geometry
10.1080/18811248.1996.9731968 · 1996 · External reference
Control rod worth evaluation for the monju restart core
10.13182/nt12-a14098 · 2012 · External reference
Unresolved reference
1980 · External reference
Unified diffusion coefficient for analysis of sodium-void worth in fast critical assembly with control-rod channels
10.1080/18811248.1981.9733231 · 1981 · External reference
Estimation of anisotropy of diffusion coefficient in a fast reactor
10.1080/18811248.1976.9734004 · 1976 · External reference
Estimation of anisotropic effect of diffusion coefficient in a fast critical assembly
10.1080/18811248.1974.9730690 · 1974 · External reference
Determination of cell averaged diffusion constants based on transport/diffusion perturbation theory
10.1080/18811248.1987.9733535 · 1987 · External reference
An effective homonization method for heterogeneous assemblies
10.1016/0306-4549(82)90020-2 · 1982 · External reference
Calculation of the anisotropic diffusion coefficient
10.1080/18811248.1972.9734929 · 1972 · External reference
Comparison of the anisotropic diffusion coefficients based on the Benoist and Deniz formula
10.1080/18811248.1972.9734922 · 1972 · External reference
Prediction uncertainty evaluation methods of core performance parameters in large liquid-metal fast breeder reactors
10.13182/nse89-1 · 1989 · External reference
A refined analysis on the power reactivity loss measurement in Monju
10.1016/j.pnucene.2017.06.004 · 2017 · External reference
A numerical study of heterogeneity effects in fast reactor critical assemblies
10.1080/18811248.1975.9733139 · 1975 · External reference
Unresolved reference
1985 · External 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 · 2014 · External reference
APOLLO3 homogenization techniques for transport core calculations - application to the ASTRID CFV core
10.1016/j.net.2017.08.014 · 2017 · External reference
Cross section adjustment method based on random sampling technique
10.1080/00223131.2014.882801 · 2014 · External reference
Optimization study on the diffusion synthetic acceleration algorithm in three-dimensional discrete ordinate transport
10.1080/18811248.1995.9731776 · 1995 · External reference
Background-cross-section-dependent sub-group parameters
10.1080/18811248.2003.9715368 · 2003 · External reference
A generalized approach to optimize subgroup parameters
10.1080/18811248.2004.9715504 · 2004 · External reference
Improvement of Tone’s method with two-term rational approximation
10.1080/18811248.2011.9711700 · 2011 · External reference
Angular dependent transmission probability method for fast reactor core transport analysis
2015 · External reference
Reaction rate calculation in fast reactor blanket using multiband Sn method
10.1080/18811248.2000.9714915 · 2000 · External reference
A complement proposal for optimization of subgroup parameters
10.1080/18811248.2006.9711158 · 2006 · External reference
Subgroup parameters based on orthgonal factorization
10.1080/18811248.2007.9711254 · 2007 · External reference
Three-dimensional transport correction in fast reactor core analysis
10.1080/18811248.1986.9735068 · 1986 · External reference
Development of adjusted nuclear data library for fast reactor application
10.1051/epjconf/202328100004 · 2023 · External reference
Extended cross-section adjustment method to improve the prediction accuracy of core parameters
10.1080/00223131.2012.739020 · 2012 · External reference
Generalized formulation of extended cross-section adjustment method based on minimum variance unbiased linear estimation
10.1080/00223131.2018.1531078 · 2019 · External reference
Cross-section adjustment methods based on minimum variance unbiased estimation
10.1080/00223131.2016.1146637 · 2016 · External reference
Improved treatment of the neutron streaming through control rod followers in a sodium-cooled fast reactor
10.13182/nse79-a20393 · 1979 · External reference
Numerical study on applicability of Benoist’s diffusion coefficient to sodium void reactivity analysis
10.1080/18811248.1976.9734057 · 1976 · External reference
Resonance calculation for large and complicated geometry using tone’s method by incorporating the method of characteristics
10.1080/18811248.2011.9711707 · 2011 · External reference
An effective homonization method for heterogeneous assemblies
10.1016/0306-4549(82)90020-2 · ExternalCitation · doi-reference
Improvement of moment-based probability table for resonance self-shielding calculation
10.1016/j.anucene.2006.05.013 · ExternalCitation · doi-reference
Neutron transport benchmark problem proposal for fast critical assembly without homogenizations
10.1016/j.anucene.2007.02.018 · ExternalCitation · doi-reference
Diffusion coefficients for LMFBR cells calculated with MOC and Monte Carlo methods
10.1016/j.anucene.2010.08.004 · ExternalCitation · doi-reference
Iterative resonance self-shielding methods using resonance integral table in heterogeneous transport lattice calculations
10.1016/j.anucene.2010.08.022 · ExternalCitation · doi-reference
Generalization of the tibere B1 leakage model to the method of characteristics
10.1016/j.anucene.2022.109160 · ExternalCitation · doi-reference
A MOC-based heterogeneous leakage model
10.1016/j.anucene.2025.111449 · ExternalCitation · doi-reference
APOLLO3 homogenization techniques for transport core calculations - application to the ASTRID CFV core
10.1016/j.net.2017.08.014 · ExternalCitation · doi-reference
A refined analysis on the power reactivity loss measurement in Monju
10.1016/j.pnucene.2017.06.004 · ExternalCitation · doi-reference
Experimental cores for benchmark experiments of effective delayed neutron fraction βeff at FCA
10.1016/s0149-1970(99)00007-4 · ExternalCitation · doi-reference
Development of adjusted nuclear data library for fast reactor application
10.1051/epjconf/202328100004 · ExternalCitation · doi-reference
Development of a unified cross-section set ADJ2000 based on adjustment technique for fast reactor analysis
10.1080/00223131.2002.10875287 · ExternalCitation · doi-reference
Extended cross-section adjustment method to improve the prediction accuracy of core parameters
10.1080/00223131.2012.739020 · ExternalCitation · doi-reference
Cross section adjustment method based on random sampling technique
10.1080/00223131.2014.882801 · ExternalCitation · 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 · ExternalCitation · doi-reference
Benchmark models for criticalities of FCA IX assemblies with systematically changed neutron spectra
10.1080/00223131.2015.1054911 · ExternalCitation · doi-reference
Bias factor method using random sampling technique
10.1080/00223131.2015.1126541 · ExternalCitation · doi-reference
Cross-section adjustment methods based on minimum variance unbiased estimation
10.1080/00223131.2016.1146637 · ExternalCitation · doi-reference
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 · ExternalCitation · doi-reference
Generalized formulation of extended cross-section adjustment method based on minimum variance unbiased linear estimation
10.1080/00223131.2018.1531078 · ExternalCitation · doi-reference
Development and verification of a fast reactor burnup calculation module FRBurner in a code system CBZ
10.1080/00223131.2021.1936683 · ExternalCitation · doi-reference
Japanese evaluated nuclear data library version 5: JENDL-5
10.1080/00223131.2022.2141903 · ExternalCitation · doi-reference
TRU oxide sample reactivity worths measured in the FCA IX assemblies with systematically changed neutron energy spectra
10.1080/00223131.2023.2240872 · ExternalCitation · doi-reference
Uncertainty reduction of sodium void reactivity using data from a sodium shielding experiment
10.1080/00223131.2023.2244512 · ExternalCitation · doi-reference
Hybrid data assimilation methods for nuclear-data-induced uncertainties
10.1080/00223131.2025.2500579 · ExternalCitation · doi-reference
Evaluation of sodium radioactivity in the primary system of the prototype fast reactor monju
10.1080/00295450.2023.2181044 · ExternalCitation · doi-reference
Evaluation of reaction rate distribution measurement in the prototype fast reactor monju
10.1080/00295450.2023.2295168 · ExternalCitation · doi-reference
Resonance self-shielding methods for fast reactor calculations - comparison of a new Tone’s method with the subgroup method in APOLLO3
10.1080/00295639.2017.1332890 · ExternalCitation · doi-reference
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 · ExternalCitation · doi-reference
Actinide integral measurements in FCA assemblies
10.1080/00337578608207441 · ExternalCitation · doi-reference
Adjustment of group cross sections by means of integral data, (I) theoretical study
10.1080/18811248.1972.9734867 · ExternalCitation · doi-reference
Adjustment of group cross sections by means of integral data, (II) numerical study
10.1080/18811248.1972.9734917 · ExternalCitation · doi-reference
Comparison of the anisotropic diffusion coefficients based on the Benoist and Deniz formula
10.1080/18811248.1972.9734922 · ExternalCitation · doi-reference
.1 Correlation between the integral data obtained in partial and full mock-up systems
10.1080/18811248.1972.9734923 · ExternalCitation · doi-reference
Calculation of the anisotropic diffusion coefficient
10.1080/18811248.1972.9734929 · ExternalCitation · doi-reference
Analysis of sodium void reactivity measured in FCA V-1 assembly
10.1080/18811248.1973.9733040 · ExternalCitation · doi-reference
Effective admixture corss section in plate lattice heterogeneous systems
10.1080/18811248.1974.9730651 · ExternalCitation · doi-reference
Estimation of anisotropic effect of diffusion coefficient in a fast critical assembly
10.1080/18811248.1974.9730690 · ExternalCitation · doi-reference
A numerical study of heterogeneity effects in fast reactor critical assemblies
10.1080/18811248.1975.9733139 · ExternalCitation · doi-reference
A new experimental method of estimating physics parameters in large fast reactors
10.1080/18811248.1976.9733987 · ExternalCitation · doi-reference
Estimation of anisotropy of diffusion coefficient in a fast reactor
10.1080/18811248.1976.9734004 · ExternalCitation · doi-reference
Numerical study on applicability of Benoist’s diffusion coefficient to sodium void reactivity analysis
10.1080/18811248.1976.9734057 · ExternalCitation · doi-reference
Fuel pin and subassembly heterogeneity effect on neutronics properties of fast power reactor
10.1080/18811248.1981.9733225 · ExternalCitation · doi-reference
Unified diffusion coefficient for analysis of sodium-void worth in fast critical assembly with control-rod channels
10.1080/18811248.1981.9733231 · ExternalCitation · doi-reference
Effective spatial homonization with neutron leakage effect for FBR control rods
10.1080/18811248.1985.9735662 · ExternalCitation · doi-reference
Second version of japanese evaluated nuclear data library (JENDL-2)
10.1080/18811248.1985.9735704 · ExternalCitation · doi-reference
Three-dimensional transport calculation method for eigenvalue problems using diffusion synthetic acceleration
10.1080/18811248.1985.9735733 · ExternalCitation · doi-reference
Three-dimensional transport correction in fast reactor core analysis
10.1080/18811248.1986.9735068 · ExternalCitation · doi-reference
Determination of cell averaged diffusion constants based on transport/diffusion perturbation theory
10.1080/18811248.1987.9733535 · ExternalCitation · doi-reference
A new nodel sn transport method for three-dimensional hexagonal geometry
10.1080/18811248.1994.9735184 · ExternalCitation · doi-reference
New control rod homonization method for fast reactors
10.1080/18811248.1994.9735205 · ExternalCitation · doi-reference
Resonance interaction effect between hot sample and cold core in analysis of Doppler effect measurement
10.1080/18811248.1994.9735264 · ExternalCitation · doi-reference
A modified diffusion coefficient for heterogeneous low-density channels
10.1080/18811248.1995.9731745 · ExternalCitation · doi-reference
Optimization study on the diffusion synthetic acceleration algorithm in three-dimensional discrete ordinate transport
10.1080/18811248.1995.9731776 · ExternalCitation · doi-reference
Japanese evaluated nuclear data library, version 3 revision-2; JENDL-3.2
10.1080/18811248.1995.9731849 · ExternalCitation · doi-reference
An improvement of the transverse leakage treatment for nodal Sn transport calculation method in hexagonal-Z geometry
10.1080/18811248.1996.9731968 · ExternalCitation · doi-reference
Experiments and analyses on sodium void reactivity worth in mock-up cores of metallic fueled and MOX fueled fast reactors at FCA
10.1080/18811248.1998.9733856 · ExternalCitation · doi-reference
A proposal of benchmark calculation on reactor physics for metallic fueled and MOX fueled LMFBR based upon mock-up experiment at FCA
10.1080/18811248.2000.9714883 · ExternalCitation · doi-reference
Reaction rate calculation in fast reactor blanket using multiband Sn method
10.1080/18811248.2000.9714915 · ExternalCitation · doi-reference
Experiments and analyses on sodium void reactivity worth in uranium-free fast reactor at FCA
10.1080/18811248.2002.9715254 · ExternalCitation · doi-reference
Japanese evaluated nuclear data library version 3 revision-3: jendl-3.3
10.1080/18811248.2002.9715303 · ExternalCitation · doi-reference
Background-cross-section-dependent sub-group parameters
10.1080/18811248.2003.9715368 · ExternalCitation · doi-reference
A combined method to evaluate the resonance self-shielding effect in power fast reactor fuel calculation
10.1080/18811248.2003.9715389 · ExternalCitation · doi-reference
A generalized approach to optimize subgroup parameters
10.1080/18811248.2004.9715504 · ExternalCitation · doi-reference
A complement proposal for optimization of subgroup parameters
10.1080/18811248.2006.9711158 · ExternalCitation · doi-reference
Development of a fine and ultra-fine group cell calculation code SLAROM-UF for fast reactor analyses
10.1080/18811248.2006.9711176 · ExternalCitation · doi-reference
Overestimation in parallel component of neutron leakage observed in sodium void reactivity worth calculation for fast critical assemblies
10.1080/18811248.2006.9711180 · ExternalCitation · doi-reference
Verification of homogenization in fast critical assembly analyses
10.1080/18811248.2006.9711233 · ExternalCitation · doi-reference
Generalized bias factor method for accurate prediction of neutronics characteristics
10.1080/18811248.2006.9711242 · ExternalCitation · doi-reference
Subgroup parameters based on orthgonal factorization
10.1080/18811248.2007.9711254 · ExternalCitation · doi-reference
Theoretical study on new bias factor methods to effectively use critical experiments for improvement of prediction accuracy of neutronic characteristics
10.1080/18811248.2007.9711400 · ExternalCitation · doi-reference
JENDL-4.0: A new library for nuclear science and engineering
10.1080/18811248.2011.9711675 · ExternalCitation · doi-reference
Improvement of Tone’s method with two-term rational approximation
10.1080/18811248.2011.9711700 · ExternalCitation · doi-reference
Resonance calculation for large and complicated geometry using tone’s method by incorporating the method of characteristics
10.1080/18811248.2011.9711707 · ExternalCitation · 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 · ExternalCitation · doi-reference
ZPPR benchmarks for large LMFBR core physics from JUPITER cooperative program between United States and Japan
10.13182/nse14-9 · ExternalCitation · doi-reference
Methods of adjustment and error evaluation of neutron capture cross sections; application to fission product nuclides
10.13182/nse77-3 · ExternalCitation · doi-reference
Improved treatment of the neutron streaming through control rod followers in a sodium-cooled fast reactor
10.13182/nse79-a20393 · ExternalCitation · doi-reference
An evaluation of different methods for space-dependent resonance shielding of cross sections in fast reactors
10.13182/nse80-a21326 · ExternalCitation · doi-reference
Unconditionally stable diffusion-synthetic acceleration methods for the slab geometry discrete ordinates equations. Part I: theory
10.13182/nse82-1 · ExternalCitation · doi-reference
Error due to nuclear data uncertainties in the prediction of liquid-metal fast breeder reactor core performance parameters
10.13182/nse83-1 · ExternalCitation · doi-reference
Double heterogeneity effect of fuel pin and subassembly in a fast power reactor
10.13182/nse83-a18215 · ExternalCitation · doi-reference
Use of integral experiments in the assessment of large liquid-metal fast breeder reactor basic design parameters
10.13182/nse87-333 · ExternalCitation · doi-reference
Prediction uncertainty evaluation methods of core performance parameters in large liquid-metal fast breeder reactors
10.13182/nse89-1 · ExternalCitation · doi-reference
Criticality evaluation for the monju restart core
10.13182/nt12-a14097 · ExternalCitation · doi-reference
Control rod worth evaluation for the monju restart core
10.13182/nt12-a14098 · ExternalCitation · doi-reference
Isothermal temperature coefficient evaluation for the monju restart core
10.13182/nt12-a14099 · ExternalCitation · doi-reference
Benchmark calculations of sodium-void experiments with uranium fuels at the fast critical assembly FCA
10.15669/pnst.2.306 · ExternalCitation · doi-reference
Development of a unified cross-section set ADJ2010 based on adjustment technique for fast reactor core design
10.3938/jkps.59.1357 · ExternalCitation · doi-reference
