Nuclear power plants. Instrumentation important to safety. In-core instrumentation for neutron fluence rate (flux) measurements in power reactors

2015 ◽  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Neutron Fluence ◽  
Fluence Rate ◽  
Neutron Fluence Rate ◽  
Flux Measurements

The Preliminary Shielding Analysis of CAP1400 Based on JMCT-S Code

2017 ◽  
Author(s):  
Yan Zhou ◽  
Zheng Zheng ◽  
Qiliang Mei
Keyword(s):  
Nuclear Power Station ◽  
Pressure Vessel ◽  
Nuclear Power ◽  
Neutron Fluence ◽  
Fluence Rate ◽  
Power Station ◽  
Neutron Fluence Rate ◽  
Shielding Design ◽  
Reactor Pressure ◽  
Full Core

JMCT-S[1] 3-D high resolution Monte Carlo neutron and photon transport code is proposed for shielding design due to its significant advantages such as complex geometry modeling, accurate calculation method, high efficient parallel computing and visible mass data analysis. To demonstrate its feasibility and benefits in engineering, this paper presents the verification of JMCT-S code based on primary shielding analysis for CAP1400 nuclear power station. Firstly, by employing JMCT-S code this paper completes the modeling and simulations of CAP1400 nuclear power station with full-core pin-by-pin and reactor pressure vessel internals inside of primary shield wall[2]. Secondly, neutron fluence rates are calculated based on the equilibrium cycle information. Particularly, the full-core neutron source is calculated from 3-D power distribution, fissionable nuclide fractions, fission spectrum, particle numbers and energy released per fission. Finally, JMCT-S code is verified by comparing results with those of the MCNP[3] code. According to the calculation results, JMCT-S code has similar accuracy to the MCNP code. The relative error of neutron fluence rate in active core is within ±1.5%, and deviation of neutron fluence rate for fast neutron fluence rate on inner surface of reactor pressure vessel is less than ±10%. Consequently, JMCT-S code is reliable in shielding design of reactor plant which lays the foundation for usage of JMCT-S code.

Niobium Concentration Measurement in Steel Samples with TXRF

1990 ◽  
Vol 34 ◽  
pp. 239-241
Author(s):  
F. Hegedüs ◽  
P. Winkler
Keyword(s):  
Fast Neutron ◽  
Pressure Vessel ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Sampling Method ◽  
Matrix Effects ◽  
Neutron Fluence ◽  
Concentration Measurement

In nuclear power plants the fast neutron fluence on the pressure vessel (PV) inner wall is measured by the scraping sampling method (1). As the inner plating of the pressure vessel contains 0.5 - 0.6 % of niobium, 93mNb (tt/2 = 16a) isomer is produced by the reaction 93Nb (n, n’). The activity of 93mNb is related to the fast neutron fluence.Scraping samples (few hundred of mg) were taken from the PV inner wall. The niobium was chemically extracted from steel by using a HAP column. This extraction was needed to reduce matrix effects and to avoid interferences of other activities with 93mNb

Work structure in nuclear power plants

1983 ◽  
Author(s):  
Marjorie B. Bauman ◽  
Richard F. Pain ◽  
Harold P. Van Cott ◽  
Margery K. Davidson
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Work Structure

Life Extension of Nuclear Power Plants: World Situation and the USA Case

2010 ◽  
pp. 50-56 ◽  
Author(s):  
Pablo T. León ◽  
Loreto Cuesta ◽  
Eduardo Serra ◽  
Luis Yagüe
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Life Extension ◽  
The Usa
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