Rod Bundle Heat Transfer Thermal-Hydraulic Program-Reference-Cited by-同舟云学术

Rod Bundle Heat Transfer Thermal-Hydraulic Program

Published:2018-10-18 Issue:1-2 Volume:205 Page:307-327
ISSN:0029-5450
Container-title:Nuclear Technology
language:en
Short-container-title:Nuclear Technology

Author:

Bajorek Stephen M.¹^ORCID,Cheung Fan-Bill²

Affiliation:

1. U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington, District of Columbia

2. Pennsylvania State University, Department of Mechanical & Nuclear Engineering, University Park, Pennsylvania

Publisher

Informa UK Limited

Subject

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

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295450.2018.1510697

Reference54 articles.

1. Engineering Uncertainty and Bureaucratic Crisis at the Atomic Energy Commission, 1964–1973

2. “Emergency Core Cooling Systems: Revisions to Acceptance Criteria,”Federal Register, V53, N 180, p. 35996, September 166 (1988); https://doi.org/10.3168/jds.S0022-0302(88)79586-7.

3. “TRACE V5.0 Theory Manual,” ADAMS ML071000097, U.S. Nuclear Regulatory Commission (2007).

4. “TRACE V5.0 Developmental Assessment Manual,” ADAMS ML120060208, ML120060187, ML120060191, ML120060172, U.S. Nuclear Regulatory Commission (2008).

5. L. E. HOCHREITER et al. “Dispersed Flow Heat Transfer Under Reflood Conditions in a 49-Rod Bundle: Test Plan and Design—Results from Tasks 1-10,” PSU ME/NE -NRC-04-98-041 Report 1, Rev. 2 (June 2002).

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