Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Conceptual Design Report for the I2 Instrumentation Experiment in ATRC

Program Document ·
OSTI ID:1569853

The US Department of Energy In-Pile Instrumentation (I2) program is tasked with developing advanced sensors for in-pile service as well as supporting the engineering required to implement existing nuclear sensor technologies in US high-power test reactors. The ATRC instrumentation test has been conceived to address both of these missions, specifically with respect to neutron flux measurements. Space has been allocated in the test for Self-Powered Neutron Detectors (SPNDs), fission chambers, and Micro-Pocket Fission Detectors (MPFDs). The real-time flux readings obtained from these instruments will be compared with time integrated data obtained from passive neutron dosimetry (i.e., “flux” wires). This work will be complementary to data obtained from the TREAT MIMIC-N experiment. This experiment is expected to support instrumentation efforts related to the proposed Medium-I loop and to instrumenting loop experiments conducted in the ATR center flux trap. While the MIMIC-N experiment was conducted in a dry environment, the ATRC I-19 experiment will be conducted in an aqueous environment, similar to the center flux trap loop experiments but will take place at ambient temperature and pressure, and at a much lower neutron flux. One of the challenges of the ATRC I-19 experiment will be low amplitude signals produced by the sensors in the low neutron fluxes of ATRC. However, related work conducted several years ago in ATRC was able to reliably detect signals using a similar instrument set.

Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE)
DOE Contract Number:
AC07-05ID14517
OSTI ID:
1569853
Report Number(s):
INL/MIS-19-55710-Rev000
Country of Publication:
United States
Language:
English

Similar Records

ATRC Neutron Detector Testing Quick Look Report
Technical Report · Thu Aug 01 00:00:00 EDT 2013 · OSTI ID:1111009

Initial Back-to-Back Fission Chamber Testing in ATRC
Technical Report · Sun Jun 01 00:00:00 EDT 2014 · OSTI ID:1164850

Comparative assessment of neutron flux sensor technologies for advanced reactors
S&T Accomplishment Report · Wed Feb 09 23:00:00 EST 2022 · OSTI ID:1844428