Evaluation of Photon Shielding Capability for Epithermal Neutron Detection during Reactivity-Initiated Power Burst Experiments

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Extension of Effective Cross Section Calculation Method for Neutron Transport Calculations in Particle-dispersed Media
Determination of Gamma-Ray Exposure Rate from Short-Lived Fission Products under Criticality Accident Conditions
Simulation by Monte Carlo Method of Power Varying with Time Detected by Fission Chamber in TRACY Water-Reflected System
Time Delay of Thermal Neutron Detection during Power Burst in TRACY
Development of Solution Behavior Observation System under Criticality Accident Conditions in TRACY
Non-Destructive and Destructive Measurements on Burnup Characteristics of Japan Power Demonstration Reactor-I Full-Core Fuel Assemblies
Calculation of Criticality Condition Data for Single-unit Homogeneous Uranium Materials in Six Chemical Forms
Evaluation of Photon Shielding Capability for Epithermal Neutron Detection during Reactivity-Initiated Power Burst Experiments
Modified Quasi-Steady-State Method to Evaluate the Mean Power Profiles of Nuclear Excursions in Fissile Solution
Reactivity Effect of Iron Reflector in LWR Cores
Evaluation of Power History during Power Burst Experiments in TRACY by Combination of Gamma-Ray and Thermal Neutron Detectors
Evaluation of Time Response of Thermal Neutron Detectors in TRACY
Re-evaluation of the Effective Delayed Neutron Fraction Measured by the Substiution Technique for a Light Water Moderated Low-enriched Uranium Core
Measurements of thermal disadvantage factors in light-water moderated PuO2-UO2 and UO2 lattices.
Measurement of gamma-ray heating with thermoluminescense dosimeters including Sr2SiO4 and Ba2SiO4.
Critical experiments on light-water moderated PuO2-UO2 lattices.
Reactivity Effects of Concrete Slabs in Single and Coupled Cores of Rectangular Parallelpiped Geometry.

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