A Study on the Application of CRUDTRAN Code in Primary Systems of Domestic Pressurized Heavy-Water Reactors for Prediction of Radiation Source Term

Song, JS; Cho, HJo; Jung, MinY; Lee, SH

HERO ID

4725126

Reference Type

Journal Article

Year

2017

HERO ID 4725126
In Press No
Year 2017
Title A Study on the Application of CRUDTRAN Code in Primary Systems of Domestic Pressurized Heavy-Water Reactors for Prediction of Radiation Source Term
Authors Song, JS; Cho, HJo; Jung, MinY; Lee, SH
Journal Nuclear Engineering and Technology
Volume 49
Issue 3
Page Numbers 638-644
Abstract The importance of developing a source-term assessment technology has been emphasized owing to the decommissioning of Kori nuclear power plant (NPP) Unit 1 and the increase of deteriorated NPPs. We analyzed the behavioral mechanism of corrosion products in the primary system of a pressurized heavy-water reactor-type NPP. In addition, to check the possibility of applying the CRUDTRAN code to a Canadian Deuterium Uranium Reactor (CANDU)-type NPP, the type was assessed using collected domestic onsite data. With the assessment results, it was possible to predict trends according to operating cycles. Values estimated using the code were similar to the measured values. The results of this study are expected to be used to manage the radiation exposures of operators in high-radiation areas and to predict decommissioning processes in the primary system. Copyright (C) 2016, Published by Elsevier Korea LLC on behalf of Korean Nuclear Society. This is an open access article under the CC BY-NC-ND license
Doi 10.1016/j.net.2016.11.005
Wosid WOS:000404665000022
Is Certified Translation No
Dupe Override No
Is Public Yes
Keyword Activation Products; ANUCRUD; CANDU; Corrosion Product; RADTRAN 98