Journal of Nuclear Science and Technology

Article	Citations
The effect of spacer grids on the stress applied to a post-LOCA cladding tube under horizontal vibrations	256
Consideration of delayed neutron effect on Rossi-α analysis for a subcritical thermal reactor	194
Transient heat transfer analysis of double-layer molten pool under severe accident	32
Improvements in the particle and heavy-ion transport code system (PHITS) for simulating neutron-response functions and detection efficiencies of a liquid organic scintillator	28
Cesium immobilization from aqueous solution by struvite synthesis	26
JENDL photonuclear data file 2016	26
Development of a dissolution method for analyzing the elemental composition of fuel debris using sodium peroxide fusion technique	15
Study on coupled heat transfer model and enhanced heat transfer law of liquid metals and supercritical fluids	14
Experimental and numerical simulation study on the combustion characteristics of nuclear-grade activated carbon	14
Evaluation of 60 Co inventory in the core of the Fukushima Daiichi Nuclear Power Plant – contribution of fuel deposits to the reactor core inventory	13
Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations	13
Sodium science and technology training at Indian sodium school	11
Effect of part-length rod arrangement on vapor redistribution in 5 × 5 rod bundle with high-energy X-ray CT measurement	11
A new separation method of hydrogen isotope by dynamically created nonequilibrium state	11
Investigation on the microstructure-mechanical property correlation in dissimilar steel welding between HARDOX and YS700 steel	11
Comprehensive simulation study on CT isotope imaging beyond the experiment on the 208 Pb based on nuclear resonance fluorescence	11
Discrimination of disposal-restricted materials in waste containers by nondestructive testing and image analysis with high-energy X-ray computed tomography	10
Advances in the interfacial interactions and decontamination strategies of radionuclides on cement surfaces: a review	10
Radio-tellurium released into the environment during the complete oxidation of fuel cladding, containment venting and reactor building failure of the Fukushima accident	10
Sorption of Cs + and Eu 3+ onto coherent and melange-type pre-neogene sedimentary rocks	10
Basic research on estimation of contamination of internal surface of spent nuclear fuel transport casks by Lasso regression	9
High temperature electrochemical reaction parameters affecting elecrochemical corrosion potential of type 316L stainless steel	9
High-temperature ex-vessel corium spreading. Part 1: experimental investigations on ceramic and sacrificial concrete substrates	9
EXFOR-based simultaneous evaluation for neutron-induced fission cross section of plutonium-242	9
Radioactivation analysis of a concrete wall in a high-energy electron accelerator facility	9

Leaching behavior of arsenic and selenium in coal fly ash by aging treatment and cement mixing	8
Molten salt oxidation and process analysis of anionic exchange resin in Na 2 CO 3 -K 2 CO	8
Direct disposal concepts of spent mixed oxide fuel from light water reactors based on heat transfer calculations	8
Evaluation of a neutron-based active interrogation system for detection of smuggled fissionable material in packages	8
Revolatilization of iodine by bubbly flow in the suppression pool during an accident	7
Development of ACE file perturbation tool using FRENDY	7
Phase behavior of oxidized Ce and Gd-doped (U,Zr)O2	7
Thermodynamic properties of liquid alkali-metal coolants: from the perspective of molecular dynamics	7
Exploratory study of nuclear magnetic resonance well logging technology on the hydrogeological characteristics of deep geological formations	7
Deterministic sampling method using simplex ensemble and scaling method for efficient and robust uncertainty quantification	7
Thermal-Neutron capture cross-section measurements of Neptunium-237 with graphite thermal column in KUR	7
A simulation study of hypervelocity jet underwater: physical protection design of offshore floating nuclear power plant against light torpedo threats	7
Absolute quantification of 137Cs activity in spent nuclear fuel with calculated detector response function	7
Thermal performance analysis of molten salt in transversely grooved tube for nuclear reactor	6
High-temperature ex-vessel corium spreading. Part 2: scaling principles for gravity-viscous spreading with slip at the melt–substrate interface	6
Transient parameter prediction and fault diagnosis for nuclear power plants based on machine learning	6
Urinary stone component identification by energy-resolved X-ray computed tomography	6
The effect of using Filtered Containment Venting System on variation in dose with distance in the prompt accident consequence assessment	6
Study on iodine adsorption capacity and adsorption mechanism of AgY	6
Technology options and cost estimates of nuclear powered desalination in the United Arab Emirates	6
A TOF spectrometer for neutron spectral measurements in a wide energy range base on a fast ionization chamber containing 6Li-235U	6
Sensitivity analysis of risk assessment for continuous Markov process Monte Carlo method using correlated sampling method	5
Experimental and computational verifications of the dose calculation accuracy of PHITS for high-energy photon beam therapy	5
Neutron yield calculation of p-Li thick target by using PHITS with JENDL-4.0/HE and ENDF/B-VII for BNCT application	5
Investigation on the similarity of turbine cascade with different working fluids	5
Uranium dissolution and uranyl peroxide formation by immersion of simulated fuel debris in aqueous H 2 O 2 solution	5
Ensuring a prudent combination of risk insights and a defense-in-depth philosophy through a reinterpretation of hierarchical safety goals	5
Power distribution re-construction based on the PHOEBE method using the method of characteristics code ‘GENESIS’	5
Numerical investigation of the accuracy of a conductance-type wire-mesh sensor for a single spherical bubble and bubbly flow	5
Verification of direct coupling code system using FRENDY version 2 and GENESIS for light water reactor lattices	5
Development of an integrated non-destructive analysis system, Active-N	5
Detailed visualization of radioactive hotspots inside the unit 1 reactor building of the Fukushima Daiichi Nuclear Power Station using an integrated Radiation Imaging System mounted on a Mecanum wheel	5
Irradiation hardening and void swelling behaviors of F82H IEA by using dual-ion irradiation	5
Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysis	5
Estimation of temporal variation of tritium inventory discharged from the port of Fukushima Dai-ichi Nuclear Power Plant:analysis of the temporal variation and comparison with released tritium invento	5
Correction	5
Measurement of the thermal neutron capture-cross section of 191 Ir at ANNRI MLF J-PARC	5
Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33	5
ACE-FRENDY-CBZ: a new neutronics analysis sequence using multi-group neutron transport calculations	5
Dosimetric effect of carbon fiber treatment couch in boron neutron capture therapy	5
Subcriticality determination methodology during fuel loading of accelerator-driven system	5
A comparative study on k-infinity uncertainty due to cross-section covariance data in nuclear data libraries	4
Enhancement of random sampling by a combined approach of control variates and Latin hypercube sampling for uncertainty quantification in light water reactor lattice calculations	4
Research on nonlinear generalized predictive control method for reactor core power based on parameter identification	4
The effectiveness of combining gadolinium and boron neutron capture therapy at the cellular level	4
Investigation into activation of accelerators at various synchrotron radiation facilities in Japan	4
Measurement and simulations of high-energy neutrons through a various thickness of concrete and steel shields using activation detectors at CHARM and CSBF	4
Correction of X-ray scattering in energy-resolved computed tomography imaging of 20-cm-diameter phantom	4
High temperature electrochemical reaction parameters affecting electrochemical corrosion potential of stainless steels in hydrogen peroxide environment	4
Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants	4

Radiation field characterization with emphasis on the collimator configuration at the compact neutron source RANS-II facility	4
Experimental techniques for investigating thermal transport in nuclear materials	4
A simulation research on thermal-pressure coupling loading of a 1:3.2 containment model	4
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure	4
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (II): 58 Fe(n,γ) 59 Fe	4
Highly promising recycled low-density polyethylene sheet adsorbents for uranium recovery from seawater	4
Experimental investigation of spray cooling behavior in 4×4 simulated fuel bundle	4
In-situ TEM observation of migration behavior of helium bubbles in F82H	4
Low-dose energy-resolved X-ray computed tomography using a filter-changing two-dimensional transXend detector	4
Test of 107 Pd transmutation with macroscopic quantities	4
Effects of correlations in uncertainties of total cross section and elastic angular distribution for a deep penetration of 14-MeV neutrons in Cu	4
Development of a critical heat flux correlation based on a mechanistic model under subcooled flow boiling conditions	4
Incineration of trans-uranium elements using chlorides molten salt fast reactors – A proposal of incineration in three steps	4
Solubility of FeSe2(cr) at 318 K in the presence of iron	4
Reactivity estimation based on the linear equation of characteristic time profile of power in subcritical quasi-steady state	4
An estimation method for an unknown covariance in cross-section adjustment based on unbiased and consistent estimator	4
Develop a framework of human reliability analysis to evaluate the human error probability in DMCR of NPPs	4
Novel concept for a filtered containment venting system with an ionic liquid to remove organic iodine (1)-proof of concept for organic iodine removal	4
Study on key technical issues of accident selection in emergency planning zone development for small modular reactors	4
Experimental study of photoneutron spectra from tantalum, tungsten, and bismuth targets for 16.6 MeV polarized photons	4
Numerical simulation of bubble hydrodynamics for pool scrubbing	4
Measurement of the water-vapor void fraction in a 4x4 unheated rod bundle	4
Radiation imaging of a highly contaminated filter train inside Fukushima Daiichi Nuclear Power Station unit 2 using an integrated Radiation Imaging System based on a Compton camera	4
Recovery and immobilization of cesium from aqueous solution after hydrothermal treatment using functional porous glass	4
Integral experiment of 129 I(n, γ) reaction using fast neutron source in the ‘YAYOI’ reactor	4
Gamma-ray irradiation induced dislocation loops in hexagonal zirconium	3
Phase stability of Cs-Si-O and Cs-Si-Fe-O compounds on stainless steel	3
Computer code analysis of irradiation performance of an annular mixed oxide fuel element	3
Bayesian approach to energy dependence of fission product yields of 235 U by data augmentation	3
Measurement of neutron spectra for various thicknesses of concrete and steel shielding at 24-GeV/c proton beam facility using Bonner sphere spectrometer	3
Integrating DeblurGAN and CNN to improve the accuracy of motion blur X-Ray image classification	3
Corrosion behavior of zirconium alloys in the aqueous environment. Phenomenological aspects. Overview	3
Development of an automatic optimization program for the weight of multi-field irradiation in BNCT based on a genetic algorithm	3
Experiences from the cutting of metallic blocks from simulant Fukushima Daiichi fuel debris	3
Effect of fuel particle size on consequences of criticality accidents in water-moderated solid fuel particle dispersion system	3
Application of neutron current method for Dancoff factor estimation of fuel particles in double-heterogeneous fuel	3
Fretting wear behavior test and numerical simulation of Inconel 690 alloy	3
Numerical simulation of flow and heat transfer in fuel assembly of floating nuclear power platform	3
Uncertainty quantification of unconfined spill fire data by coupling Monte Carlo and artificial neural networks	3
Microstructure evolution formed during early liquefaction stage between pre-oxidized Zircaloy 4 with SUS316 stainless steel at 1573 K	3
Development of a simple calculation method for the conductance of rarefied gas flow in cylindrical pipe applicable to divertor exhaust investigation of nuclear fusion reactor	3
The effect of alpha irradiation on the performance of glass matrix in simulated radioactive contaminated soil by microwave treatment	3
Thermophysical properties of molten FeO 1.5 , (FeO 1.5 ) 0.86 –(ZrO 2	3
Evaluation method of hydrogen generation rate by water radiolysis in fuel debris canisters considering the radiation energy absorption rate of water dependence on particle size	3
Activity and weight ratios of cesium, uranium, plutonium, and curium isotopes based on elaborate inventory calculations of Fukushima Dai-ichi NPP units 1 to 3	3
Research on frequency modulation technology and its verifications of superconducting synchrocyclotron for cancer therapy	3
JENDL-5 benchmarking for fission reactor applications	3
New variance reduction techniques for Monte-Carlo calculation based on first-collision source method	3
Basic study on tritium monitor using plastic scintillator for treated water discharge at Fukushima Daiichi Nuclear Power plant	3
Connection of four-dimensional Langevin model and Hauser-Feshbach theory to describe statistical decay of fission fragments	3
Study on corrosion of T-22 alloy under high temperature condition of VHTR	3
Status of the 226 Ra nuclear data library and its impact on the production amount of 225 Ac via the 226	3
Sorption of Sn and Nb on montmorillonite at neutral to alkaline pH	3
Measurement of the neutron capture cross section of 185 Re in the keV energy region	3
Nuclear data adjustment using a deterministic sampling method with unscented transformation	3
A spurious-count effect observed in Rossi-α and Feynman-α analysis using fission counter for Kyoto University Reactor	3
Reactor antineutrinos and novel application to real-time remote monitoring of nuclear reactors	3
Measurements of neutron capture cross-section for nuclides of interest in decommissioning (III): 170 Er(n,γ) 171 Er and	3
Uncertainty quantification of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly	3
Development of AR-based scanning support system for 3D model reconstruction of work sites	3
Identification and quantification of a 60 Co radiation source under an intense 137 Cs radiation field using an application-specifi	3
Neutronics and thermal-hydraulics coupling analyses on transient and accident behaviors of molten chloride salt fast reactor	3
Benchmark study of particle and heavy-ion transport code system using shielding integral benchmark archive and database for accelerator-shielding experiments	3
Research on the powderization treatment of uranium-zirconium solid solution simulated nuclear fuel debris using thermochemical redox reaction	3
Impact of MOX fuel use in light-water reactors: long-term radiological consequences of disposal of high-level waste in a geological repository	3
Uncertainty analysis for fission product inventories based on covariance data of fission product yields in JENDL-4.0 and ENDF/B-VIII.0	3
Feasibility study of reactor radiation photon spectroscopy in Fugen for nuclear decommissioning	3
Experimental and numerical study of a condensing steam jet	2
Nonuniform particle distribution and interference between removal mechanisms during unsteady aerosol deposition from a rising spherical bubble	2
EXFOR-based simultaneous evaluation for fast neutron-induced fission cross section of thorium-232	2
A design study on a metal fuel fast reactor core for high efficiency minor actinide transmutation by loading silicon carbide composite material	2
Establishing an evaluation method for the aging phenomenon by physical force in fuel debris	2
Correction	2
Dynamic performance analysis of a new low-temperature nuclear heating system with APROS	2
A membrane, pseudo-vertical p-i-n diamond detector	2
High-efficient removal of tungsten from hafnium by TOA/XAD-7 extraction resin from HCl-HF media	2
A new method of measuring ruthenium activity in ruthenium-containing alloys by using thermogravimetric analysis	2
Evaluation of beamline subsystem performance during technical commissioning of an superconducting proton therapy facility	2
Experimental study on design optimization of the core catcher for the CEFR	2
Creep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°C	2

Enhancement of applicability of high-efficiency random sampling method using control variates method and sensitivity coefficients	2
Formulation of Irradiation Assisted Stress Corrosion Crack Growth Rates for Neutron-Irradiated Stainless Steels under Hydrogen Water Chemistry Conditions of Boiling Water Reactors	2
Effect of weld geometry on irradiation damage resistance of 316L stainless steel weld at 400 ℃	2
The effects of unburned-gas temperature and pressure on the unstable behavior of cellular-flame fronts generated by intrinsic instability in hydrogen-air lean premixed flames under adiabatic and non-a	2
Nuclear data generation by machine learning (I) application to angular distributions for nucleon-nucleus scattering	2
Alteration of fuel debris simulants by Bacillus subtilis	2
Development of a theoretical scaling factor method for the inventory estimation of difficult-to-measure nuclide Cs-135 in fuel debris and radioactive wastes	2
Observation of nepheline crystallization in the Na 2 O-B 2 O 3 -Al 2	2
Correction	2
Diffusion of Cs + , I − and HDO onto pre-Neogene sedimentary rocks	2
Simulated performance evaluation of d-Be compact fast neutron source	2
Degradation of nuclear fuel debris analog by siderophore-releasing microorganisms	2
Applicability of differential die-away self-interrogation technique for quantification of spontaneous fission nuclides for fuel debris at Fukushima Daiichi Nuclear Power Plants	2
Calculations and analysis of n+ 52 Cr reactions below 20 MeV	2
Verification of in-core power distribution reconstruction based on POD for high-temperature gas-cooled reactors using ex-core detectors	2
A novel strategy for iodine removal from nuclear reactor accidental gases: Efficient adsorption of CH 3 I on the moderately hydrophobic modified silver-loaded zeolit	2
Radiation-induced amorphization behavior of thermally-aged M23C6 in F82H-BA12 steel	2
Experimental and analytical investigations on aerosol washout in a large vessel with high spray coverage ratio simulating PWR containment spray	2
Data processing and visualization of X-ray computed tomography images of a JOYO MK-III fuel assembly	2
Reactor reactivity calculations with simplified-P3 and perturbation theories	2
Role of solute titanium and oxidation in cesium chemisorption onto stainless steel	2
Benchmark specifications of TCA critical experiments for validation of thermal scattering laws of water	2
YouTube-based topic modeling and large language model sentiment analysis of Japanese online discourse on nuclear energy	2
Kinetic modeling of IG-110 oxidation in inert atmosphere with low oxygen concentration for innovative high-temperature gas-cooled reactor applications	2
Hybrid data assimilation methods for nuclear-data-induced uncertainties	2
Simulation of the self-propagating hydrogen-air premixed flame in a closed-vessel by an open-source CFD code	2
Utilize empirical models of measured relative dose output factor (rDOF) and transverse penumbra (TP) to evaluate dosimetric uncertainties of in-air spot modelling for spot-scanning carbon-ion and prot	2
Applicability of the kernel method for macroscopic cross section tabulation to planar MOC-based core transient analysis code	2
Cohesive/Adhesive strengths of CsOH-chemisorbed SS304 surfaces	2
Treatment of corner crossing ray-traces in CMFD acceleration of MOC	2
The behaviors of dislocation loops punched by helium interstitials accumulation under the temperature gradient field in tungsten	2
Development of Internal Dose Calculation Code (IDCC)	2
Monte Carlo burnup analysis of measured nuclide inventories on high-burnup PWR-UO 2 and BWR-MOX fuels in the RUBUS program	2
A study on the establishment of database for local government disaster response and decision support system in the nuclear accidents	2
Development of glass gas electron multiplier-based pulse counting imaging system with FPD front-end electronics	2
Development of integrated FEPs for safety case scenario development	2
Neutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV	2
Nuclear data uncertainty in iterative neutron spectrum unfolding	2
Preface to a special issue of journal of nuclear science and Technology on “Nuclear Data and Code Systems as a Basis of Nuclear Technology”	2
Molecular dynamics simulation study of the effect of Ce 4+ incorporation at Zr site on the threshold displacement energy in Y 4 Zr	2
EXFOR-based simultaneous evaluation of neutron-induced uranium and plutonium fission cross sections for JENDL-5	2
Enhancing magnetohydrodynamic performance of liquid metal with solid insulating powders for fusion reactor applications	2
Evaluation of the production amount of 225 Ac and its uncertainty through the 226 Ra(n,2n) reaction in the experimental fast react	2
Irradiation behavior of HfNbTaTiV in comparison of HfNbTaTiZr and F82H	2
Evaluation of influence of wall roughness on wall turbulence using LES simulation with MSGD model for liquid Li flow inside two-staged contraction nozzle	2
Power profile analysis of criticality accidents involving fissile solution boiling with considering evaporation	2
Measurements of keV-Neutron capture cross sections and capture gamma-ray spectra of 74,76,78,80,82 Se	2
Technical research on rapid source term calculation and prediction technology of nuclear accidents based on Bayesian network	2
Heat of transport for hydrogen and hydrides in Zircaloy	2
HHT-based investigation on the two-phase flow regime in the mixer for a nuclear-coupled liquid metal MHD power generation system	2
Neutron yield calculation of thin and thick d-D targets by using PHITS with frag data table	2
Design and development of the machine protection system for HIAF	2
Study of magnetic fringe fields and interference effects on beam dynamics for proton facility gantry	1
Coupled chemo-hydro-mechanical effects on volume change behaviour of compacted bentonite used as buffer/backfill material in high-level radioactive waste repository	1
Predictive accuracy of neutronics of light-water-moderated and graphite-reflected core with low-enriched uranium fuel at UTR-KINKI	1
Crucial importance of correlation between cross sections and angular distributions in nuclear data of 28 Si on estimation of uncertainty of neutron dose penetrating	1
Towards safe, efficient long-reach manipulation in nuclear decommissioning: A case study on fuel debris retrieval at Fukushima Daiichi	1
Numerical simulation method using a Cartesian grid for oxidation of core materials under steam-starved conditions	1
Spectral determination method and its application to γ-ray determination	1
Limited linear source approximation with edge detection for convergence stability of method of characteristics	1
Consideration on the concrete spalling behavior in high-temperature environments during severe accidents	1
Effect of radiation and substitution of Ce4+ at Zr site in Y4Zr3O12 using collision cascades: a molecular dynamics simulation study	1
Rare earth elements and radioactive elements in black sands from the Konkan and Malabar coasts of India	1
Optimization of BP neural network for fault parameter prediction in nuclear power plants utilizing the firefly algorithm	1
Criticality evaluation considering nonuniformity effect using Monte Carlo perturbation method	1
Stress relieved Zircaloy-4 recovery and recrystallization during fast anisothermal transients	1
Halogenation of used aluminum matrix test reactor fuel – a bench-scale demonstration with surrogate materials	1
Passive fast neutron multiplicity counting system based on a symmetric spherical design	1
Human reliability analysis of shared equipment in multi-unit site	1
Development of neutron self-indication thermometry at J-PARC	1
Synergism of radiation and steam on mechanical properties of cable insulation removed from a nuclear power plant	1
Novel concept for a filtered containment venting system with an ionic liquid to remove organic iodine (2) – Decomposition mechanism of an ionic liquid by heat and gamma-ray irradiation	1
Depletion calculation of subcritical system with consideration of spontaneous fission reaction	1
Double-differential cross sections for charged particle emissions from α particle impinging on Al at 230 MeV/u	1
Experimental investigations on flow-induced vibration characteristics of fuel rod with an independent channel for small lead-based reactor	1
Effects of azimuthal temperature distribution and rod internal gas energy on ballooning deformation and rupture opening formation of a 17 × 17 type PWR fuel cladding tube under LOCA-simulated burst co	1
Tensile properties of irradiated modified 316 stainless steel (PNC316) at slow strain rates	1
Double diffusive dissolution model of UO2 pellet in molten Zr cladding	1
High temperature corrosion of two superalloys in the impure helium environment	1
Influence of organic dispersant on nuclear grade anion exchange resin and their interaction behavior	1
Decontamination of corrosion oxides in the heat transport system of a pressurized heavy water reactor using chelate-free inorganic acid	1
Raman identification and characterization of chemical components included in simulated nuclear fuel debris synthesized from uranium, stainless steel, and zirconium	1
Redistribution of Nb and other alloying elements in Nb-doped Zr alloy under high dose ion irradiation	1
Simulation using representative data selection for transboundary radiation effect evaluation by Nuclear Accident Consequence Analysis Code (NACAC)	1
Application of dynamic mode decomposition to Rossi-α method in a critical state using file-by-file moving block bootstrap method	1
Improved neutron spectrum unfolding using residual networks and generative adversarial networks: a comparative study with baseline deep models	1
Request for 35 Cl(n,p) reaction cross-section measurements and re-evaluations from the standpoint of molten chloride salt fast reactor design	1
Analysis of work activities involved in clearance verification process of decommissioning Fugen Nuclear Power Plant	1
Localizing unknown radiation sources by unscented particle filtering based on divide-and-conquer sampling	1
Steady-state thermal-structural analysis of high-temperature heat pipes based on thermal-fluid coupling	1
Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi nuclear power plant Unit 2	1
The development of Petri net-based continuous Markov chain Monte Carlo methodology applying to dynamic probability risk assessment for multi-state resilience systems with repairable multi-component in	1
Evaluation of anisotropic elastic and plastic parameters of zircaloy-4 fuel cladding from biaxial stress test data and their application to a fracture mechanics analysis	1
Neutron total and capture cross-section measurements of 155Gd and 157Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC·MLF·	1
Chemical species of iodine during sorption by activated carbon -Effects of original chemical species and fulvic acids	1