Results 1 to 10 of about 438 (64)

Containment Integrity and Sealing Assessment for HTR-PM600 Fresh Fuel Transport Package Under Impact Loading

open access: yesFrontiers in Energy Research, 2022
Reliable transportation of fuel elements is vital for High Temperature Reactor (HTR) power plant. Therefore, the safety performance of the containment boundary in HTR-PM600 fresh fuel transport package under impact loading should be assessed ...
Yuchen Hao   +7 more
doaj   +1 more source

The Innovations, Technology and Waste Management Approaches to Safely Package and Transport the World’s First Radioactive Fusion Research Reactor for Burial [PDF]

open access: yes9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3, 2003
Original estimates stated that the amount of radioactive waste that will be generated during the dismantling of the Tokamak Fusion Test Reactor (Fig. 1) will approach 2 Million Kilograms with an associated volume of 2500 cubic meters. The materials were activated by 14 Mev neutrons and were highly contaminated with tritium, which present unique ...
Keith Rule   +4 more
openaire   +3 more sources

Validation of the code package MCPV adapted for neutron transport calculation within WWER-440 reactor near-vessel space [PDF]

open access: yesNuclear Physics and Atomic Energy, 2019
Results of the validation of the code package MCPV that is used for the irradiation conditions determination methodology of the pressure vessels and surveillance specimens of the WWER-440 type reactors of Ukrainian NPPs were presented. The validation is carried out on the basis of the experimental data obtained in mock-up and full-scale experiments. It
O.M. Pugach   +4 more
openaire   +1 more source

Criticality benchmark guide for light-water-reactor fuel in transportation and storage packages [PDF]

open access: yes, 1997
This report is designed as a guide for performing criticality benchmark calculations for light-water-reactor (LWR) fuel applications. The guide provides documentation of 180 criticality experiments with geometries, materials, and neutron interaction characteristics representative of transportation packages containing LWR fuel or uranium oxide pellets ...
Lichtenwalter, J. J.   +3 more
openaire   +2 more sources

Criticality benchmark of McCARD Monte Carlo code for light-water-reactor fuel in transportation and storage packages

open access: yesNuclear Engineering and Technology, 2018
In this paper, McCARD code was verified using various models listed in the NUREG/CR-6361 benchmark guide, which provides specifications for single pin-cells, single assemblies, and the whole core classified depending on the nuclear properties and structural characteristics.
Junkyung Jang, Hochul Lee, Hyun Chul Lee
openaire   +2 more sources

Potential of acetic acid to restore methane production in anaerobic reactors critically intoxicated by ammonia as evidenced by metabolic and microbial monitoring. [PDF]

open access: yesBiotechnol Biofuels Bioprod, 2023
Lemaigre S   +8 more
europepmc   +1 more source

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