Užitá reaktorová dozimetrie

Předmět není vypsán Nerozvrhuje se

Kód	Zakončení	Kredity	Rozsah	Jazyk výuky
16YURD	ZK	4	3P+0C	anglicky

Garant předmětu:

Přednášející:

Cvičící:

Předmět zajišťuje:

katedra dozimetrie a aplikace ionizujícího záření

Anotace:

The Applied Reactor Dosimetry course introduces the topic of radiation-induced material degradation and the methodology for its evaluation. The primary focus is on ensuring the safe operation of nuclear facilities, include not only reactors but also accelerators and other devices exposed to intense radiation.

After defining the fundamentals of radiation damage, the methods used to estimate the residual lifetime are introduced to students. Strong emphasis is placed on both code validation methods and the validation of the nuclear data used, as these are critical to the reliability of the computational results. Significant attention is given to the use of benchmarks in reactor and neutron physics. Students will also become familiar with the methodologies used in the benchmarking process, as well as standard instrumentation. The course concludes with an excursion to a facility involved in the Czech reactor surveillance program.

Požadavky:

Osnova přednášek:

1.Radiation degradation of materials, embrittlement, swelling, creep, issues of reactor component life.

2.Use of research reactors in the controlled aging program, irradiation and post irradiation examinations

3.Determination of doses in the environment of power nuclear reactors, calculation methods, limits, conditions and reliability of usable methodologies

4.Gamma radiation dosimetry and determination of large doses

5.Characteristics of mixed N/G fields in a nuclear reactor, possibilities of measurement and description of quantities

6.Validation and verification of flux / dose determination methodologies, associated uncertainties, effect of systematical uncertainties

7.Reference neutron fields and their use in validation, verification and evaluation of nuclear cross sections

8.Nuclear data libraries, cross-section measurement, determination, limits and uncertainties.

9.Mixed N/G fields, N/G spectrometry in reactor environments, scintillation methods, HPGe spectrometry

10.Use of integral experiments in nuclear data evaluation, benchmarks and their use in V&V

11.Scintillation materials, use for benchmark experiments, applicability in non-proliferation issues

12.Electronics of spectrometric chains, preamplifier, amplifier, multichannel analyzer, possibilities and limits of use.

13.Excursion to the Rez Labs, (LR-0, LVR-15, hot cells, LSNM Cf source)

Osnova cvičení:

Cíle studia:

Studijní materiály:

Mandatory literature:

[1] Integrity of Reactor Pressure Vessels in Nuclear Power Plants: Assessment of Irradiation Embrittlement Effects in Reactor Pressure Vessel Steels, IAEA NUCLEAR ENERGY SERIES No. NP-T-3.11, https://www-pub.iaea.org/MTCD/publications/PDF/Pub1382_web.pdf

[2] Knoll G.F., Radiation Detection and Measurement, 4th Edition, Wiley, 2012

[3] Gilmore, G., Practical Gamma-ray Spectrometry, 2nd ed., Hoboken, John Wiley eBook, 2011