Behavior of Defective Pressurized Water Reactor Fuel Rods during Power Ramp and Power-Cooling-Mismatch Conditions-Reference-Cited by-同舟云学术

Behavior of Defective Pressurized Water Reactor Fuel Rods during Power Ramp and Power-Cooling-Mismatch Conditions

Published:1980-11 Issue:1 Volume:51 Page:45-57
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Croucher Douglas W.¹

Affiliation:

1. EG&G Idaho, Inc., P.O. Box 1625, Idaho Falls, Idaho 83415

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/NT80-A32555

Reference15 articles.

1. W. J. QUAPP et al. “Irradiation Effects Test Series Test IE-1 Test Results Report,” TREE-NUREG-1046, EG&G Idaho, Inc. (Mar. 1977).

2. A. S. MEHNER and R. S. SEMKEN, “Postirradiation Examination Results for the Irradiation Effects Test IE-1,” TREE-NUREG-1199, EG&G Idaho, Inc. (Feb. 1978).

3. D. E. OWEN and K. VINJAMURI, “Power-Cooling-Mismatch Test Series, Test PCM-3, Test Results Report,” NUREG/CR-0902, TREE-1335, EG&G Idaho, Inc. (Aug. 1979).

4. S. L. SEIFFERT, “Power-Cooling-Mismatch Test Series Test PCM-3 Postirradiation Examination,” TREE-NUREG-1187, EG&G Idaho, Inc. (Dec. 1977).

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