FY 2018 Nuclear Science User Facilities Awards

DOE Selects FY18 Awards for NSUF Workscopes

The U.S. Department of Energy (DOE) has selected four Consolidated Innovative Nuclear Research (CINR) awards under the NSUF-2 workscopes and one additional award under the NSUF-1.2 workscope that will take advantage of unique Nuclear Science User Facilities (NSUF) capabilities to increase our understanding of important phenomena associated with irradiation effects in nuclear fuels and materials. DOE will support these projects with facility access costs and expertise for experimental neutron and ion irradiation testing, post-irradiation examination, and technical assistance through the NSUF.


FY 2018 CINR Awards: Nuclear Science User Facilities Access (NSUF-2)

Title

ID

Workscope

Principle Investigator

Lead Institution

 

Understanding swelling related embrittlement of AISI316 Stainless Steel irradiated in EBR-II

14772

NSUF-2.1: Core and Structural Materials

Cheng Sun

Idaho National Laboratory

Researchers will investigate the swelling-related embrittlement behavior of AISI 316 stainless steels irradiated in fast reactor EBR-II at high neutron fluences.

Rapid simulation of irradiation damage in PWR internals

14717

NSUF-2.1: Core and Structural Materials

Kevin Field

Oak Ridge National Laboratory

Researchers will demonstrate that ion irradiation can grow an existing damage microstructure to higher dose levels such that the doses provided by self-ion and neutron irradiation produces the same microstructure.

High dose ion irradiation testing and relevant post irradiation examination of friction-stir-welded ODS MA956 alloy

14787

NSUF-2.1: Core and Structural Materials

Ramprashad Prabhakaran

Pacific Northwest National Laboratory

Researchers will perform higher-dose ion irradiation on neutron irradiated and unirradiated friction stir welded (FSW) MA956 alloy to understand microstructural evolution and radiation hardening. The study will use ion irradiations and examination to understand and compare the effects of ion, neutron and neutron+ion irradiations.

Facilitating MARMOT modeling of radiation phenomena in U-Pu-Zr fuels through experiments (MORPH experiment)

14704

NSUF-2.2: Nuclear Fuel Behavior and Advanced Nuclear Fuel Development

Assel Aitkaliyeva

University of Florida

Researchers will increase the fundamental understanding of irradiation induced metallic U-Pu-Zr fuel behavior and to obtain data needed for the development of irradiation models for metallic fuels in MARMOT. The project requests access to PIE facilities at NSUF partner facility to conduct examination of irradiated metallic fuels with the goal of providing foundational understanding of the radiation behavior in metallic fuels needed to inform the development of MARMOT models.

FY 2018 CINR Awards: NEUP/NEET R&D with Nuclear Science User Facilities Access (NSUF-1.2)

Nanodispersion strengthened metallic composites with enhanced neutron irradiation tolerance

14783

NSUF-1.2: Irradiation Testing of Materials Produced by Innovative Manufacturing Techniques

Ju Li

Massachusetts Institute of Technology

Researchers will study the neutron irradiation tolerance of nanodispersion strengthened composites produced by an innovative manufacturing method at low cost. The prolific internal interfaces between 1D/2D nanodispersions and the metal matrix provide radiation defect recombination venues to heal radiation damage. The success of this work will provide the novel concept of developing an innovative manufacturing method for advanced nuclear fuels and materials at low cost for long-term operation.