The results of a study are presented which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR, or in existing commercial test reactors. To accomplish the design objectives called for, a reactor producing perturbed neutron fluxes exceeding 10/sup 15/ thermal neutrons per square centimeter per second and 1.5 x 10/sup 15/ epithermal neutrons per square centimeter per second. To accommodate the experimental samples, the reactor fuel core is four feet long in the …
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Publisher Info:
Phillips Petroleum Co. Atomic Energy Div., Idaho Falls, Idaho
Place of Publication:
Idaho Falls, Idaho
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The results of a study are presented which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR, or in existing commercial test reactors. To accomplish the design objectives called for, a reactor producing perturbed neutron fluxes exceeding 10/sup 15/ thermal neutrons per square centimeter per second and 1.5 x 10/sup 15/ epithermal neutrons per square centimeter per second. To accommodate the experimental samples, the reactor fuel core is four feet long in the direction of experimental loops. The vertical arrangement of reactor and experiments permits the use of straight and vertical loops penetrating the top cap of the reactor vessel. The design offers a high degree of accessibility of the exterior portions of the experiments and offers very convenient handling and discharge of experiments. Since the loops are to be integrated into the reactor design and the in-pile portions installed before reactor startup, it is felt that many of the problems encountered in MTR and ETR experience will cease to exist. Installation of the loops prior to startup will have an added advantage in that the flux variations experienced in experiments in ETR every time a new loop is installed will be absent. ETR II (formerly called ETR IV) has a core configuration which provides essentially nine flux-trap regions in a geometry which is almost optimum for cylindrical experiments. The geometry is similar to that of a four-leaf clover with one flux trap in each leaf, one at the intersection of the leaves, and one between each pair of leaves. The nominal power level is 250 Mw. The study was carried out in enough detail to permit the establishment of the design parameters and to develop the power requirement which, conservatively rated, will definitely reach the flux specifications. A critical mockup of an arrangement similar to ETR II was loaded into the Engineering Test Reactor Critical Facility. A two-dimensional calculation of this actual test provided a confirmation of validity of the computer techniques in predicting the behavior of this reactor. (auth)
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deBoisblanc, D R.PROPOSAL FOR AN ADVANCED ENGINEERING TEST REACTOR-ETR II,
report,
March 17, 1960;
Idaho Falls, Idaho.
(https://digital.library.unt.edu/ark:/67531/metadc872643/:
accessed December 7, 2025),
University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu;
crediting UNT Libraries Government Documents Department.
