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

Song, Jong Soon; Cho, Hoon Jo; Jung, MinYoung; Lee, Sang‐Heon

doi:10.1016/j.net.2016.11.005

Cited by 14 publications

(2 citation statements)

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“…To analyse these processes in great detail, it is necessary to use complicated numerical solution models, which require time-consuming calculations even when the computational resources are relatively high. For this reason, in practice simplifications are made by implementing empirical and semi-empirical models in computer codes (PACTOLE [9], CRUDTRAN [10], ACE-II [11], CATE [12], etc.). 1 was done employing LLWAA-DECOM computer code (Tractebel Energy Engineering, Belgium).…”

Section: Methodsmentioning

confidence: 99%

Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings

Poskas

Poškas

Šimonis

2019

Science and Technology of Nuclear Installations

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Data analyses of radioactive contamination of the RBMK-1500 reactor’s steam pipelines (SP) and components of high pressure rings (HPR) are presented in this paper. Also, modelled results of the SP-HPR system are compared to the results of other RBMK-1500 systems at Ignalina NPP Unit 1. Characteristics of SP-HPR components, thermal-hydraulic conditions of the coolant, and system operational regimes were evaluated employing the computer code LLWAA-DECOM (Tractebel Energy Engineering, Belgium). The presented results complement radiological characterization activities and facilitate the decommissioning process of nuclear facilities with RBMK type reactors. Analysis of the modelled results showed that the spread of radioactive contamination is very uneven between different components of the SP-HPR. The overall activity level of deposits of the SP-HPR is mostly determined by activated corrosion products and is lower than the activity level in the main circulation circuit (MCC) and nonpurified water subsystem activity of the purification and cooling system (PCS).

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Section: Methodsmentioning

confidence: 99%

Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings

Poskas

Poškas

Šimonis

2019

Science and Technology of Nuclear Installations

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“…During the operation of the pressurized heavy water reactor (PHWR), the carbon steel heat transport system (HTS) undergoes corrosion due to its high temperature and high pressure conditions [1]. The corrosion products are transported to the reactor core through the coolant where they are activated by neutrons [2].…”

Section: Introductionmentioning

confidence: 99%

Decontamination of corrosion oxides in the heat transport system of a pressurized heavy water reactor using chelate-free inorganic acid

Chang

Eun

Kim

et al. 2021

Journal of Nuclear Science and Technology

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Thick corrosion oxide (Fe 3 O 4 ) layers containing radioactive metals are generated in a carbon steel heat transport system (HTS) of pressurized heavy water reactors during operation. It is necessary to decontaminate the oxide layers to reduce radiation exposure to workers before maintenance and decommissioning. Since the oxide layer thickness in the HTS is about 75 μm, a considerable amounts of secondary wastes can be generated when the existing decontamination processes are applied. The aim of this study is to design a chemical decontamination process using chelate-free inorganic acid that can be effectively applied to remove the oxide layers in the HTS and to minimize the secondary waste generation. Therefore, Fe 3 O 4 dissolution behaviors were evaluated in a Hydrazine Based Reductive metal Ion Decontamination (HyBRID) process using the chelate-free inorganic acid. From this result, the decontamination process of oxide layers in the HTS using recycling of decontamination process solution and the process control method using pH monitoring were constructed. In particular, process control based on pH monitoring can be easily used because decontamination performance can be controlled according to the goal; (1) effective removing the oxide layer at decommissioning, (2) avoiding corrosion of base metal and removing the oxide layer at maintenance.

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Electrostatic-thermodynamic-kinetic (ELTHEKI) modeling of the coupled $$\text {Ni}$$/$$\text {Ni}\text {O}$$/water system, under physico-chemical conditions of pressurized water reactors

Saidi

You²,

Bataillon³

et al. 2023

J Solid State Electrochem

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

Cited by 14 publications

References 0 publications

Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings

Assessment of the Radioactive Contamination of the RBMK-1500 Reactor’s Steam Pipelines and High Pressure Rings

Decontamination of corrosion oxides in the heat transport system of a pressurized heavy water reactor using chelate-free inorganic acid

Electrostatic-thermodynamic-kinetic (ELTHEKI) modeling of the coupled $$\text {Ni}$$/$$\text {Ni}\text {O}$$/water system, under physico-chemical conditions of pressurized water reactors

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