Feasibility study on tritium recoil barrier for neutron reflectors of research and test reactors-Reference-Cited by-同舟云学术

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Feasibility study on tritium recoil barrier for neutron reflectors of research and test reactors

Published:2021-03 Issue: Volume:164 Page:112181
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Kenzhina Inesh,Ishitsuka Etsuo^ORCID,Ho Hai Quan,Sakamoto Naoki,Okumura Keisuke,Takemoto Noriyuki,Chikhray Yevgeni

Funder

Japan Atomic Energy Agency

Korea Atomic Energy Research Institute

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference18 articles.

1. Study of Origin on Tritium Release Into Primary Coolant for Research and Testing Reactors -Tritium Release Rate Evaluated from JMTR, JRR-3M and JRR-4 Operation Data-, JAEA-Technology 2014-025;Ishitsuka,2014

2. Calculation by PHITS Code for Recoil Tritium Release Rate from Beryllium Under Neutron Irradiation, JAEA-Technology 2016-022;Ishitsuka,2016

3. Evaluation of tritium release curve in primary coolant of research reactors;Ishitsuka;Phys. Sci. Technol,2017

4. Calculations of Tritium Recoil Release from Li and U Impurities in Neutron Reflectors, JAEA-Technology 2018-010;Ishitsuka,2018

5. I. Kenzhina, E. Ishitsuka, K. Okumura, Hai Quan Ho, N. Takemoto, Y. Chikhray, Evaluation of Tritium Release into Primary Coolant for Research and Testing Reactors, J. Nucl. Sci. Technol (In press). https://doi.org/10.1080/00223131.2020.1791760.

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