Results 1 to 10 of about 475,598 (275)

Few Group Diffusion Calculations of a Light Water Moderated Lattice [PDF]

Journal of Nuclear Science and Technology, 1966
An analysis was made of a light water moderated lattice based on few group diffusion calculations. The lattice under investigation consisted of 468 fuel rods in a square lattice arranged in a cylindrical core of 22.46 cm effective radius and 127.2 cm core height, with a water to fuel volume ratio of 2.918.
MIZUTA, Hiroshi, MAKINO, Kakuji
exaly   +3 more sources

Uncertainty quantification of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly

Journal of Nuclear Science and Technology, 2022
A series of uncertainty quantifications are successfully conducted by the eigenvalue calculations, the uncertainty of criticality and reactivity, and the reduction of uncertainty using the KENO-VI code, the TSUNAMI-3D, the TSAR and the TSURFER modules of the SCALE code system, respectively.
Cheol Ho Pyeon
exaly   +3 more sources

Critical Experiments on Light-Water Moderated PuO 2 -UO 2 Lattices

Journal of Nuclear Science and Technology, 1978
A series of critical experiments using mixed-oxide (PuO2-UO2) plutonium fuels was carried out at the Tank type Critical Assembly (TCA) in the Japan Atomic Energy Research Institute in cooperation with the Power Reactor and Nuclear Fuel Development Corporation.
Takenori Suzaki, Shojiro Matsuura, Akio Ohno   +2 more
exaly   +3 more sources

Monte Carlo analyses of light-water-moderated and light-water-reflected cores with highly-enriched uranium fuel at Kyoto University Critical Assembly

Journal of Nuclear Science and Technology, 2021
The applicability of Monte–Carlo calculations is examined for the analyses of light-water-moderated and light-water-reflected cores at the Kyoto University Critical Assembly with the use of the experimental data of criticality, reactivity, and reaction rates.
Cheol Ho Pyeon, Kota Morioka
openaire   +2 more sources

Uncertainties in the Analysis of Plutonium Fueled Light Water Moderated Assemblies [PDF]

, 1973
A theoretical analysis of UO/sub 2/-- PuO/sub 2/ fueled, light-water- moderated lattice experiments has been performed to aid in establishing technical bases and design criteria for the utilization of plutonium bearing fuel in thermal power reactors.
Liikala, R. C., Uotinen, V. O., Jenquin, U. P.   +2 more
openaire   +3 more sources

Re-evaluation of the Effective Delayed Neutron Fraction Measured by the Substitution Technique for a Light Water Moderated Low-enriched Uranium Core

Journal of Nuclear Science and Technology, 2001
Ken Nakajima
exaly   +4 more sources

MPACT VERIFICATION WITH MAGNOX REACTOR NEUTRONICS PROGRESSION PROBLEMS [PDF]

EPJ Web of Conferences, 2021
MPACT is a state-of-the-art core simulator designed to perform high-fidelity analysis using whole-core, three-dimensional, pin-resolved neutron transport calculations on modern parallel computing hardware.
Luciano Nicholas P., Ade Brian J., Kim Kang Seog, Conant Andrew J.   +3 more
doaj   +1 more source

Temperature Effects on Reactivity in Light Water Moderated UO2 Cores with Soluble Poisons. [PDF]

Journal of Nuclear Science and Technology, 1992
MIYOSHI, Yoshinori, YAMAMOTO, Toshihiro, SUZAKI, Takenori, KOBAYASHI, Iwao   +3 more
openaire   +2 more sources

Review of pressurized thermal shock studies of large scale reactor pressure vessels in Hungary [PDF]

Fracture and Structural Integrity, 2016
In Hungary, four nuclear power units were constructed more than 30 years ago; they are operating to this day. In every unit, VVER-440 V213-type light-water cooled, light-water moderated, ressurized water reactors are in operation.
Tamás Fekete
doaj   +3 more sources

DEVELOPMENT OF THE MPACT 69-GROUP LIBRARY FOR MAGNOX REACTOR ANALYSIS USING CASL VERA [PDF]

EPJ Web of Conferences, 2021
The Consortium for Advanced Simulation of Light Water Reactors (CASL) has developed the CASL toolset, Virtual Environment for Reactor Analysis (VERA), for pressurized water reactor (PWR) analysis.
Kim Kang Seog, Ade Brian J., Luciano Nicholas P.   +2 more
doaj   +1 more source