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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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OECD NEA meeting focuses on irradiation experiments
Members of the OECD Nuclear Energy Agency’s Second Framework for Irradiation Experiments (FIDES-II) joint undertaking gathered from September 29 to October 3 in Ketchum, Idaho, for the technical advisory group and governing board meetings hosted by Idaho National Laboratory. The FIDES-II Framework aims to ensure and foster competences in experimental nuclear fuel and structural materials in-reactor experiments through a diverse set of Joint Experimental Programs (JEEPs).
Charles W. Forsberg
Nuclear Technology | Volume 72 | Number 2 | February 1986 | Pages 121-134
Technical Paper | Fission Reactor | doi.org/10.13182/NT86-A33735
Articles are hosted by Taylor and Francis Online.
A new type of boiling water reactor (BWR)—the process inherent ultimate safety (PIUS) BWR—has been conceived. A PIUS BWR is an advanced BWR that differs from the typical BWR in that a prestressed concrete reactor vessel (PCRV) with special internals replaces the conventional pressure vessel, emergency core cooling system, containment shell, spent fuel storage ponds, and most other components on the nuclear island. The reactor core and balance of plant are similar to current BWR designs. This approach effectively eliminates the possibility of reactor core meltdown and simplifies plant design. The PIUS BWR does not require operation of any mechanical or electrical components in any emergency for reactor shutdown or afterheat cooling, nor does it depend on any equipment outside the PCRV. The PCRV contains a natural circulation BWR; cool, borated water for emergency core cooling; a mechanism “X” that allows the cool, borated water to enter the reactor core if there is insufficient water in the core; and a mechanism “Y” that limits core power levels to available cooling capabilities.