Results 51 to 60 of about 9,551,406 (202)
Development and Verification of Activated Source Term Library Based on ENDF/B‐VIII.0
Developed by the Oak Ridge National Laboratory (ORNL) in the United States, the ORIGEN code for computing irradiation and decay processes is one of the most widely used point depletion programs. However, the nuclear data that accompanies it, crucial for its application, has been measured and evaluated a long time ago.
Xirui Zhang +6 more
wiley +1 more source
Three-component U-Pu-Th fuel for plutonium irradiation in heavy water reactors
This paper discusses concepts for three-component fuel bundles containing plutonium, uranium and thorium for use in pressurised heavy water reactors, and cases for and against implementation of such a nuclear energy system in the United Kingdom.
Peel Ross +3 more
doaj +1 more source
Analysis of carbon‐14 discharges from Korean nuclear power plants
Comparison of radioactive effluent discharges from Korean nuclear power plants before and after carbon‐14 discharge monitoring in Korean pressurized water reactors. Abstract The routine practice accompanying the operation of nuclear facilities involves the discharge of radioactive effluents from nuclear power plants (NPPs). Regulation of this discharge
Hwapyoung Kim +6 more
wiley +1 more source
The simulated E–H diagrams of nickel could be used to predict the corrosion of steam generator tubes of Canadian Deuterium Uranium reactors. Abstract Nuclear power plant steam generator (SG) tubes contain nickel as the main alloying element and there is concern about their corrosion.
Mohammad Amin Razmjoo Khollari +2 more
wiley +1 more source
ANALISIS KEPUASAN KONSUMEN PADA CANDU KOPI DENGAN METODE CUSTOMER SATISFACTION INDEX (Studi Kasus : Candu Kopi) [PDF]
Kepuasan konsumen merupakan hal terpenting yang harus dicapai oleh penyedia layanan, salah satunya Coffee shop. Candu Kopi adalah sebuah Coffee Shop yang berdiri sejak tahun 2018.
HARKAT PUTRA, -
core +1 more source
Based on research into the diagnosis methods for fuel failures in pressurized water reactor nuclear power plants and an analysis of existing problems, this paper proposes an enhanced fuel failure diagnosis method, addressing three key improvements: identification of the occurrence of fuel failure, diagnosis of the number of failed fuel rods, and the ...
Weifeng Lyu +5 more
wiley +1 more source
The LOCA (loss of coolant accident) is a kind of severe accident in the operation of PHWR (pressurized heavy water reactor) as well as other nuclear facilities, and possible cause of LOCA can be counted on the ballooning of pressure tube (PT) contacted ...
Hyoung Tae Kim +3 more
doaj +1 more source
After the Fukushima Daiichi nuclear accident in 2011, the performance of nuclear fuel during accidents became a matter of great concern. To address this, a new type of fuel technology called accident‐tolerant fuel (ATF) has been developed with the goal of enhancing the ability of light water reactors (LWRs) to withstand severe accident conditions. Iron‐
Khalid A. Alamri +4 more
wiley +1 more source
Scaled-Down Moderator Circulation Test Facility at Korea Atomic Energy Research Institute
Korea Atomic Energy Research Institute (KAERI) started the experimental research on moderator circulation as one of a the national research and development programs from 2012.
Hyoung Tae Kim, Bo Wook Rhee
doaj +1 more source
PERDAGANGAN CANDU DI SUMATERA TENGAH PADA MASA REVOLUSI 1945-1949 [PDF]
ABSTRAK Skripsi ini berjudul “Perdagangan Candu Di Sumatera Tengah Pada Masa Revolusi 1945-1949”. Perdagangan candu dilakukan untuk mendapatkan dana biaya perang pada masa Revolusi di Sumatera Tengah khususnya dan Indonesia umumnya.
Rafiqatul, Afwa
core +1 more source

