Conceptual Neutronics Scoping for Ramp Testing in the Advanced Test Reactor

Conference · Wed Nov 15 00:00:00 EST 2023

OSTI ID:2375462

Labossiere-Hickman, Travis J ^[1]; Woolstenhulme, Nicolas E ^[1]; Durtschi, Brian P ^[1]; Kamerman, David W ^[1]

---

1. Idaho National Laboratory

With the closure of the Halden Boiling Water Reactor in 2018, the global capacity for in-reactor power ramp testing has been lost. As such tests provide valuable data for understanding pellet-cladding interaction (PCI) phenomena, finding new facilities for ramp testing is of interest to the United States Accident-Tolerant Fuel (ATF) Program. Several options at Idaho National Laboratory (INL) are being evaluated for adding ramp test capabilities. In the Transient Reactor Test Facility (TREAT), one option is testing inside a Transient Water Irradiation System in TREAT (TWIST) capsule. In the Advanced Test Reactor (ATR), one option under consideration is testing in an I-Loop toward the outer edge of the core. Another is testing in Loop-2A, located in the Center Flux Trap (CFT) of the ATR. In this paper, we examine the conceptual scoping for the Loop-2A experiment known as ATF-2Ramp.

• Research Organization: Idaho National Laboratory (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: 58
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 2375462
• Report Number(s): INL/CON-23-75394-Rev000
• Conference Information: 2023 ANS Winter Meeting and Technology Expo, Washington, D.C., 11/12/2023 - 11/15/2023
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
Accident Tolerant Fuel
Irradiation Experiments
PCI Ramp Testing