Irradiation test of HAFM and tag gas samples at the standard neutron field of "YAYOI"

*

PNC TJ9602 96-004, 49 Pages, 1996/03

PNC-TJ9602-96-004.pdf:1.53MB

To check the accuracy of helium accumulation neutron fluence monitoring (HAFM) technique and the applicability of tag gas activation analysis to fast reactor failed fuel detection, these samples were irradiated at the standard neutron field of the fast neutron source reactor "YAYOI" (Nuclear Engineering Research Laboratory, University of Tokyo). The HAFM samples of 93% enriched B powder of 1 mg contained in a V capsule were set up in the reactor core center (Glory hole :Gy) and another samples including V encapsulated natural B powder of 10 mg, natural B chips and 96% enriched LiF thermoluminescence dosimeters were in the leakage neutron field from the reactor core (Fast column :FC). These neutron fields were monitored by the activation foils consisting of Al, Fe, Co, Ni, Cu, Ti, In, Au, U, Np etc., which were used to derive the neutron flux and spectrum. At the end of March in 1996, the irradiated neutron fluence in the energy more than 0.1Mev reached up to 1.110 n/cm at Gy and 5.410 n/cm at FC, respectively. Two kinds of tag gas samples, which are the mixed gases of isotipically adjusted Xe and Kr contained in stainless steel (SUS) capsules, were irradiated twice at Gy; one is up to 9kWh and the other 7kWh, and after the irradiation, -ray spectra were measured for each sample. Through comparison with the -ray spectrum from dummy capsule of no tag gas, the -ray peaks of Kr, Xe etc., which would be produced from tag gas activation, were able to be clearly identified.

None

Isozaki, Kazunori; ; Ito, Hideaki; ; Chatani, Keiji; ;

PNC TN9520 93-006, 198 Pages, 1992/11

PNC-TN9520-93-006.pdf:6.18MB

None

Introduction of Nuclear Instrumentations and Radiation Measurements in Experimental Fast Reactor 「JOYO」

Odo, Toshihiro;

PNC TN9420 92-005, 83 Pages, 1992/04

PNC-TN9420-92-005.pdf:2.17MB

This report introduces the nuclear instrumentation system and major R&D (research and development) activities using radiation measurement techniques in Experimental Fast Reactor "JOYO". In the introduction of the nuclear instrumentation system, following items are described; (1)system function (2)roles as a reactor plant equipment (3)specifications and charactelistics of neutron detectors, (4)construction and layout of the system. For reactor dosimetry at various irradiation tests and surveillance tests, multi-foil method employed in "JOYO", neutron fluence evaluation using activation foils and HAFM (Helium Accumulation Fluence Monitor) under development are described briefly. The failed fuel detection system and some experimental equipments using radiation measurement techniques are also introduced here with main results obtained by a series of fuel failure simulation experiments. In addition, following R&Ds are picked up as some examples based on radiation measurement technology; (1)burn-up measurement of spent fuel subassembly (2)measurement and evaluation of radiation source distributions (radioactive corrosion products)

None

;

Keisoku Gijutsu, 7(12), p.34 - 42, 1979/00

no abstracts in English

Sodium in-pile loop experiment on delayed neutron-, detector-, precipitator-, and cover-gas gamma-ray spectrometer-type fuel failure detection systems

; ;

IEEE Transactions on Nuclear Science, 23(1), p.363 - 374, 1976/01

https://doi.org/10.1109/TNS.1976.4328272

no abstracts in English

Development of a portable high-resolution gamma-ray spectrometers for nuclear facilities, 2; Long-term stability of TlBr Detector at room temperature

Nogami, Mitsuhiro*; Hitomi, Keitaro*; Ito, Chikara; Tsubakiyama, Kunimi*; Watanabe, Kenichi*; Maeda, Shigetaka

no journal, , 

While many studies have been conducted on improving energy resolution and increasing the volume of TlBr detectors, little evaluation has been made on long-term stability. Therefore, in this study, we evaluated the long-term stability of the TlBr detector when it was operated continuously for about 2000 hours, assuming application to an actual nuclear power plant.