Show simple item record

contributor authorPetkov, Gueorgui I.
date accessioned2019-02-28T11:05:37Z
date available2019-02-28T11:05:37Z
date copyright3/5/2018 12:00:00 AM
date issued2018
identifier issn2332-8983
identifier otherners_004_02_020905.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4252596
description abstractAnalysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP;The whole core model of China experimental fast reactor (CEFR) is established according to the parameters of China experimental fast reactor, which are given by technical publication from the International Atomic Energy Agency (IAEA-TECDOC-1531), and the physical parameters of CEFR are simulated with the Monte Carlo N-particle code (MCNP4a). The calculation results are compared with the data contained in the safety analysis report of CEFR. The calculation results are consistent with the design values, which successfully demonstrate the acceptable fidelity of the MCNP model. The MCNP model will be further refined and applied for nuclear safety review of the CEFR in the future.
publisherThe American Society of Mechanical Engineers (ASME)
titleEnhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events
typeJournal Paper
journal volume4
journal issue2
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4039000
journal fristpage20905
journal lastpage020905-11
treeJournal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002
contenttypeFulltext


Files in this item

Thumbnail

This item appears in the following Collection(s)

Show simple item record