Neutron dosimetry at commercial nuclear plants. Annual report of Subtask D: TEPC feasibility

Technical Report · Fri Jun 01 04:00:00 EDT 1984

DOI:https://doi.org/10.2172/6278473· OSTI ID:6278473

Cummings, F M; Endres, G W.R.; McDonald, J C; Brackenbush, L W

This study was designed to observe the feasibility of the use by NRC licensees of the tissue equivalent proportional counter (TEPC) system as a neutron monitoring instrument. Laboratory tissue equivalent proportional counters were irradiated using /sup 252/Cf sources at NBS and PNL and were irradiated inside containment of four operating nuclear power plants (two boiling water reactors and two pressurized water reactors). On the average, neutron dose-equivalent rates determined using the TEPC were 1.05 times the calculated dose-equivalent rates for the bare and moderated /sup 252/Cf sources and 0.86 times the dose-equivalent rates determined using the multispheres inside containment of nuclear power plants. Further, neutron dose equivalent rates determined using portable remmeters were an average of 1.71 times the dose equivalent determined using the multispheres inside the containment of nuclear power plants. It was observed that while electronic noise from temperature and vibrational effects inside containment prohibited an adequate measure of absorbed dose from gammas, the measurement of neutron absorbed dose was unaffected by these environmental parameters. It is recommended that for use inside containment at nuclear power plants: (1) the laboratory scale TEPC is the superior technique for accurate determination of neutron dose equivalent, (2) for remmeters similar to the one evaluated in this study, neutron dose equivalent response should be corrected to account for dependence of response on neutron energy or the remmeters should be calibrated using a moderated neutron source, and (3) at present, the TEPC should not be used to measure absorbed dose from gammas. Upon the advent of a proven miniaturized TEPC, this instrument may prove to be a desirable replacement for current portable neutron monitoring devices for the determination of dose equivalent inside containment of commercial nuclear power plants.

• Research Organization: Pacific Northwest Lab., Richland, WA (USA)
• DOE Contract Number: AC06-76RL01830
• OSTI ID: 6278473
• Report Number(s): PNL-5137; ON: DE84014890
• Country of Publication: United States
• Language: English

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22 GENERAL STUDIES OF NUCLEAR REACTORS
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ALPHA DECAY RADIOISOTOPES
BWR TYPE REACTORS
CALIFORNIUM 252
CALIFORNIUM ISOTOPES
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NUCLEAR POWER PLANTS
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THERMAL POWER PLANTS
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WATER COOLED REACTORS
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