A Study of Plateout Fission Product Behavior During a Large-Scale Pipe Rupture Accident in a High-Temperature Gas-Cooled Reactor-Reference-Cited by-同舟云学术

A Study of Plateout Fission Product Behavior During a Large-Scale Pipe Rupture Accident in a High-Temperature Gas-Cooled Reactor

Published:1994-06 Issue:3 Volume:106 Page:265-273
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Sawa Kazuhiro¹,Murata Isao¹,Shiozawa Shusaku¹,Matsumoto Mikio²

Affiliation:

1. Japan Atomic Energy Research Institute Department of the High Temperature Engineering Test Reactor Project Oarai-machi, Oarai Research Establishment, Narita-cho, Oarai-machi Higashiibaraki-gun, Ibaraki-ken, 311-13, Japan

2. Japan Atomic Energy Research Institute Japan Atomic Energy Research Institute, Oarai-machi Oarai Research Establishment, Narita-cho, Oarai-machi, Higashiibaraki-gun Ibaraki-ken, 311-13, Japan

Publisher

Informa UK Limited

Subject

Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://www.tandfonline.com/doi/pdf/10.13182/NT94-A34957

Reference12 articles.

1. R. P. WICHNER, “Fission Product Plateout and Liftoff in the MHTGR Primary System: A Review,” NUREG/CR-5647, U.S. Nuclear Regulatory Commission (1991).

2. Plate-out of fission products and its effect on maintenance and repair

3. K. SAWA et al. “Evaluation of Fission Product Sources for Shielding Design of HTTR,” JAERI-M 91-198, Japan Atomic Energy Research Institute (1991) (in Japanese).

4. O. BABA, N. TSUYUZAKI, and K. SAWA, “Fission Products Plate-Out Analysis Code in the HTGR-PLAIN,” JAERI-M 88-266, Japan Atomic Energy Research Institute (1988) (in Japanese).

5. K. SAWA and O. BABA, “The Verification of Fission Products Plate-Out Analysis Code for HTGR-PLAIN,” JAERI-M 91-084, Japan Atomic Energy Research Institute (1991) (in Japanese).

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1. POSCA: A computer code for fission product plateout and circulating coolant activities within the primary circuit of a high temperature gas-cooled reactor;Nuclear Engineering and Technology;2020-09

2. Experimental study of thermophoretic deposition of HTGR graphite particles in a straight pipe;Progress in Nuclear Energy;2018-08