Experimental Verification of Calculated Neutron Streaming in the Bottom Reflector and Core Support Regions of a Large-Scale High-Temperature Gas-Cooled Reactor Design Concept-Reference-Cited by-同舟云学术

Experimental Verification of Calculated Neutron Streaming in the Bottom Reflector and Core Support Regions of a Large-Scale High-Temperature Gas-Cooled Reactor Design Concept

Published:1987-10 Issue:2 Volume:97 Page:123-144
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Slater C. O.¹,Muckenthaler F. J.¹,Ingersoll D. T.¹

Affiliation:

1. Oak Ridge National Laboratory, P.O. Box X, Bldg. 6025, Oak Ridge, Tennessee 37831

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE87-A27460

Reference18 articles.

1. “HTGR-SC 900-MW(e) Reference Plant Nuclear Steam Supply System Conceptual Design and Status Report,” Vol. I, GA-A15429, GA Technologies, Inc. (Sep. 1979).

2. C. O. SLATER and S. N. CRAMER, “Survey Analysis of Radiation Levels in the HTGR Lower Regions,” ORNL/TM-8141, Oak Ridge National Laboratory (Feb. 1982).

3. F. J. MUCKENTHALER, J. L. HULL, L. B. HOLLAND and J. J. MANNING, “Phase I Measurements for the HTGR Bottom Reflector and Core Support Block Neutron-Streaming Experiment,” ORNL/TM-8977, Oak Ridge National Laboratory (July 1984).

4. W. A. RHOADES et al. “The DOT-IV Two-Dimensional Discrete Ordinates Transport Code with Space-Dependent Mesh and Quadrature,” ORNL/TM-6529, Oak Ridge National Laboratory (Jan. 1979).

5. M. B. EMMETT, “The MORSE Monte Carlo Radiation Transport Code System,” ORNL-4972, Oak Ridge National Laboratory (Feb. 1975).

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