[en] When conducting scientific research in a reactor core and especially when comparing results obtained from various types of reactors, it is often necessary to determine the contribution to the absorbed dose of individual components of the reactor radiation. Most of the proposed systems have essential deficiencies that make practical use difficult: a low upper limit of the measured dose, a significant post-irradiation effect, a demonstrated poor reproducibility or else their dosimetric parameters are insufficiently studied. Most detectors made from native glass are DTC-0.01/1.0, based on silicate glass with a Ni doping, measuring γ-ray doses in the range of (1-5) · 10² or 10³-9 · 10³ Gy, however the low measured dose limit restricts their use. Dosimetry parameters were developed for KI quartz glass in previous meterological tests at the All-Union Technical Physics and Electronics Research Institute. For the purpose of studying the applicability of quartz glass detectors for separate dosimetry of reactor radiation, in this article the method of nonstationary calorimetry was used and quartz detectors were studied in two channels of the VVR-CM reactors and a comparison of the results of the measurements was made. These two channels were located next to each other, the first in the moderator of the core (VEK-9) and the second in the water moderator at a distance of 0.6 m from the center of the core (OIR-14). This study has shown that KI quartz glass can be used as a detector for the γ-component of reactor radiation for Φ_0.1 ≤ 10¹⁹ m^-2. For the determination of the flux of fast neutrons KU-1 quartz glass is proposed. The advantages of the proposed detectors include: their small size (10 x 10 x 1), highly reproducible results (∼15%), and the possibility of multiple use after annealing at 450 degrees C (KI glass) and 900 degrees C (KU-1) glass