Results 21 to 30 of about 1,699,034 (145)
Innovative Design of Compact Heavy‐Load Independent Transfer Device for Nuclear Engineering System
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 The transportation of heavy equipment in nuclear engineering has always been the focus of engineers, especially those transfer devices with the characteristics of small geometric size and heavy load. According to this kind of compact heavy‐load transfer device and its engineering tasks, the core problems caused by excessive vertical and horizontal ...
Hao Wan +6 more
wiley +1 more source
STUDY OF PLUTONIUM UTILIZATION IN AP1000 REACTOR USE SRAC2006 AND JENDL 3.3 NUCLEAR DATA LIBRARY [PDF]
, 2023 Preliminary Study of Plutonium Utilization in AP1000 Reactor Use SRAC 2006 and JENDL 3.3 has been conducted. Nuclear energy, especially for nuclear reactor, become important this day because the need of energy will increase along with the increasing of ...
Waris, Abdul +2 more
core +1 more source
Nuclear Power Sustainability Path for China from the Perspective of Operations
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 Nuclear power, as a low‐carbon, stable, and efficient energy, plays an important role in replacing fossil fuels in the development of a globally sustainable energy system. However, nuclear power has deviated from the path to achieve the Sustainable Development Goals of the United Nations.
Tao Zhang +5 more
wiley +1 more source
An introduction to nuclear power : science, technology and UK policy context [PDF]
, 2012 This paper is the first in a series of 8 that make up the evidence base for SDC report 'The role of nuclear power in a low carbon economy'.Publisher ...
Sustainable Development Commission
core +2 more sources
The Implementation of Diverse Actuation System in ACPR1000 Nuclear Power Plants
Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021 In order to improve the capability of dealing with software common cause failure (CCF) of digital reactor protection and monitoring system (RPMS), the diverse actuation system (DAS) is introduced for ACPR1000 nuclear power plants. From economic and feasibility point of view, the solution of DAS sharing with RPMS sensors and actuators is suggested ...
Zhen-Ying Wang +7 more
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021 In response to a station blackout accident similar to the Fukushima nuclear accident, China’s Generation III nuclear power HPR1000 designed and developed a passive residual heat removal system connected to the secondary side of the steam generator. Based on the two‐phase natural circulation principle, the system is designed to bring out long‐term core ...
Feng Li +5 more
wiley +1 more source
Economics of nuclear power [PDF]
, 2012 This paper is the fourth in a series of 8 that make up the evidence base for SDC report 'The role of nuclear power in a low carbon economy'.Publisher ...
Science and Technology Policy Research, University of Sussex +1 more
core +2 more sources
Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021 The calculation of the core source term is affected by various factors, such as fuel consumption, enrichment, specific power, and operation mode. The activity of lanthanides, fission products, and the photon source strength were calculated using the ORIGEN program. The weights of each factor were calculated by multivariate analysis of variance.
Tao Zhou +6 more
wiley +1 more source
Condition monitoring of an advanced gas-cooled nuclear reactor core [PDF]
, 2007 A critical component of an advanced gas-cooled reactor station is the graphite core. As a station ages, the graphite bricks that comprise the core can distort and may eventually crack.
Giovanini, L. +3 more
core +4 more sources
Neutronic Performance of the VVER‐1000 Reactor Using Thorium Fuel with ENDF Library
Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021 In this paper, neutronic calculations and the core analysis of the VVER‐1000 reactor were performed using MCNP6 code together with both ENDF/B‐VII.1 and ENDF/B‐VIII libraries. The effect of thorium introduction on the neutronic parameters of the VVER‐1000 reactor was discussed.
Sonia M. Reda +4 more
wiley +1 more source