Advanced Online Flux Mapping of CANDU PHWR by Least-Squares Method-Reference-Cited by-同舟云学术

Advanced Online Flux Mapping of CANDU PHWR by Least-Squares Method

Published:2005-07 Issue:3 Volume:150 Page:299-309
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Hong In Seob¹,Kim Chang Hyo¹,Suk Ho Chun²

Affiliation:

1. Seoul National University, Nuclear Engineering Department San 56-1, Shillim-dong, Kwanak-ku, Seoul 151-742, Korea

2. Korea Atomic Energy Research Institute 150 Dukjin, Yusong, Daejeon 305-353, Korea

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE05-A2517

Reference15 articles.

1. The Least-Squares Method for Three-Dimensional Core Power Distribution Monitoring in Pressurized Water Reactors

2. Estimation of Most Probable Power Distribution in BWRs by Least Squares Method Using In-Core Measurements

3. T. L. TANG, J. FINK, E. YOUNG, and G. KUGLER, “Analytical Design of the CANDU-6 On-Line Flux Mapping System,” TDAI-152, Atomic Energy of Canada Limited (1979).

4. D. A. JENKINS and B. ROUBEN, “Reactor Fuelling Simulation Program-RFSP: User’s Manual for Microcomputer Version,” TTR-321, Atomic Energy of Canada Limited (1978).

5. Core Simulations Using Actual Detector Readings for a Canada Deuterium Uranium Reactor

Cited by 9 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. A 3-D Neutron Distribution Reconstruction Method Based on the Off-Situ Measurement for Reactor;IEEE Transactions on Nuclear Science;2021-12

2. Performance of Flux Mapping System During Spatial Xenon Induced Oscillations in PHWRs;Proceedings of the 7th International Conference on Advances in Energy Research;2020-10-18

3. Optimization of flux mapping in-core detector locations in AHWR using clustering approach;Nuclear Engineering and Design;2020-09

4. Compressed Sensing Artificial Neural Network for Reactor Core Flux Mapping;IEEE Transactions on Nuclear Science;2018-08

5. Determination of control rod positions during fuel life-cycle using fixed in-core Self-Powered Neutron Detectors of Tehran Research Reactor;Nuclear Engineering and Design;2018-05