PurposeThe central dry zone of Myanmar is a climatic risk area in which the inhabitants are experiencing food insecurity, demonstrating the link between water scarcity and climate risk in agricultural production. Households in the region face the challenge of developing adaptation strategies to cope with the impact of climate change on food security. This study aims to seek an effective climate change solution and analyse its impact on Myanmar's food security and household adaptation.Design/methodology/approachThe authors draw on insights from mixed-method research using a qualitative method followed by quantitative methods. In the qualitative phase, the authors used purposive sampling with two focus group discussions and three stakeholder interviews. In the quantitative phase, data were collected from 102 face-to-face interviews with members of households selected from Pauk Township, Pakokku District, Magway Region, Myanmar. The household food insecurity access scale (HFIAS) was used in the analysis.FindingsThe HFIAS indicated that 13% of households have adapted to climate change. The study illustrates that climate change adaptation strategies in production activities are related to food insecurity. The results further demonstrated the effect of climate change on crops, which impacts debt, access to food, selling assets and urban migration. The findings also suggest that climate change adaptation to improve food security has played an important role in providing outside support, which leads to household food insecurity.Originality/valueTo the authors' best knowledge, the study is one of the first to use mixed-method research to investigate climate change, food security and household adaptation in the central dry zone of Myanmar.
Thermal desorption was used to study the behavioral particulars of the ion-implanted at 20 and 650°C helium in reactor ferrite-martensite austenitic steel. It is established that compared with the thermal desorption spectrum of EP-450 and Euroffer-97 steel the temperature interval for helium release from dispersion-hardened EP-450 and Eurofer 97 steels is wider for helium implantation at room temperature and especially at 650°C. In steel hardened by disperse oxides Y 2 O 3 , a substantial amount of helium is released at high temperatures after the main maximum in the thermal desorption spectrum as a result of the formation at the incoherent particle-matrix boundary of bubbles with high bonding energy with particles. In contrast to the ferrite-martensite steel irradiated in the temper state, the thermal desorption spectrum of EK-164 austenitic steel is more complex because of the multiple stage helium release due to the structural defects introduced by cold deformation.Many different makes of reactor steel have now been developed, including steels containing aside from chromium and nickel up to three or more alloying elements. Until recently, this development work was conducted in the direction of developing or improving austenitic steels. For fast reactors, steel as a material for fuel-element cladding is characteristically used in the following sequence: Kh18N9T → Kh18N10T → Kh16N15MZB (EI-847) → Kh16N15M3BR (EP-172) → → Kh16N15M2G2TFR (ChS-68) → 07Kh16N19M2G2BTFPR (EK-164). As one can see, the work proceeded in the direction of increasing nickel content and complicating its composition in order to increase the high-temperature strength and radiation resistance. Since for the nuclear fuel burnup of about 12% h.a. attained up to now the main cladding steel ChS-68 no longer satisfies the radiation resistance requirements, first and foremost, radiation swelling, the possibility of using in BN-800 austenitic steel EK-164 with elevated nickel content and more complicated compositions than ChS-68 steel is under investigation.In addition, in the last few decades intense development and research work has been done on chromium-based steels with bcc crystal lattice, since swelling of such steel is appreciably weaker than in austenitic steels (Table 1) [1]. In connection with the main drawback of chromium steel -its low high-temperature strength under conditions characteristic for fastreactor cores, increasing attention is going to dispersion-hardened martensitic and ferrite-martensitic steel: foreign-made steel with different chromium content and domestically produced dispersion-hardened steel based on Kh13 (See Table 1) as a promising material for fast-reactor fuel-element cladding and, possibly, for the first wall of thermonuclear reactors [2].
INTRODUCTIONVanadium alloys with the rapid reduction of the induced activity of a V-Ti-Cr system are considered to be promising structural materials for application in future fusion reactors (FRs) of a DEMO type [1][2][3]. There is an interesting idea to use vanadium alloys as a fuel element cladding in fast neutron reactors (FNRs) with sodium cooling, where the required high tem perature strength is provided by a vanadium alloy and required corrosion resistance is provided by clad layers made from ferritic steel [4]. Embrittlement of vana dium alloys during operation can occur in contact with hydrogen isotopes [5][6][7][8][9]. For example,in [7], it is shown that a reduction in the relative elongation of V-Ti-Cr alloys in a hydrogen atmosphere (P ≈ 0.13 kPa) begins at a concentration of 360 wppm H 2 . There are a number of sources where hydrogen penetrates into structural material in FRs and FNRs: the main one is transmutation reactions of type (n, p), (n, d), (n, t), and (n, n I p), which have a threshold (energy) char acter. It should be noted that the amount of hydrogen accumulated in vanadium in FRs significantly exceeds that in FNRs. For example, it was calculated that 20 appm is accumulated in vanadium after 560 days of irradiation in the BN 600, whereas ~680 appm H is accumulated in the DEMO RF [10].Hydrogen can be specifically introduced into a liq uid metal coolant to eliminate oxide deposits. Another source of hydrogen input to the structural materials of the first FR wall is plasma radiation.Vanadium alloys which contain titanium, a strong hydride forming element, are currently considered as structural materials for nuclear reactors [3,11,12]. The most promising alloy for application in FR is the ternary alloy V-4% Ti-4% Cr. This work was aimed at finding the regularities of the retention of hydrogen depending on the titanium content in the V-Ti alloys saturated with hydrogen. EXPERIMENTALThe first stage was to produce the samples of V-Ti alloys, namely, to prepare a master alloy (alloy with a maximum titanium content V-10 wt % Ti) by alloying vanadium with titanium in a MIFI 9 vacuum arc fur nace. Model alloys with 0.5, 1, 5, and 10% Ti additions were prepared by alloying the master alloy with vana dium. The content of titanium was determined using a Camebax SX 50 microanalyzer. Pure vanadium served as a reference. The deviation of alloy composition from the calculated one was not more than 5%.After repeated rolling with intermediate homogeniz ing annealing at 1080 K to a final thickness of ~0.25 mm, the samples with dimensions of 25 × 7 × 0.25 mm 3 were annealed in a vacuum of 10 MPa at 1273 K for 2 h and then cooled together with a furnace. Before hydrogen saturation, the samples were electropolished to a mir ror finish in a solution of H 2 SO 4 (concentrate) + 5% ethanol.Abstract-Hydrogen retention in vanadium and its binary alloys with titanium are investigated by means of hydrogen thermal desorption spectrometry. The samples are saturated with hydrogen for 2000 h at a temper ature of 620 K in an...
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