Nuclear model analysis and optimization of production data of the medically interesting 66,67,68 Ga via alpha induced reactions on 63,65 Cu targets.

Evaluation of the 63Cu(α,n)66Ga, 65Cu(α,2n) 67Ga and 65Cu(α,n)68Ga reactions was done to study the production of medical radionuclides 66Ga, 67Ga and 68Ga respectively. 63Cu(α,2n)65Ga and 65Cu(α,3n)66Ga reactions were also evaluated for the estimation of radioisotopic impurities. Cross section data of each reaction were compiled and normalized to the standard values of decay data and monitor reaction. To check the consistency of the literature data, three nuclear model calculations were performed, using nuclear model codes; TAYLS 1.9, ALICE-IPPE, and EMPIRE 3.2. A well-developed evaluation methodology based on the normalized experimental data and nuclear model calculations was used to generate the statistically fitted cross sections. From the fitted cross sections, thick target yields for each reaction were calculated for the estimation of radioisotopic impurities. Finally, a suitable energy region for the production of 66Ga, 67Ga and 68Ga was suggested with a minimum level of radioisotopic impurities.

Evaluation of nuclear reaction cross sections for optimization of production of the important non-standard positron emitting radionuclide 89Zr using proton and deuteron induced reactions on 89Y target.

89Zr (T1/2 = 3.27 d) is an important ß+-emitting radionuclide of zirconium used in immuno PET. The excitation functions of the 89Y(d,2n)89Zr and 89Y(p,n)89Zr reactions were analyzed to deduce the optimum conditions for the high purity production of 89Zr. The nuclear model codes ALICE-IPPE, EMPIRE 3.2 and TALYS 1.9 were used to check the consistency and reliability of the experimental data. A polynomial fit to the chosen data for each reaction gave the excitation function, which was then used for the integral yield calculation of the product. The amount of the major radioactive impurity 88Zr was precisely analyzed for both the proton and the deuteron induced reactions on the 89Y target.

Nuclear model analysis of excitation functions of α-particle induced reactions on In and Cd up to 60MeV with relevance to the production of high specific activity 117mSn.

Excitation functions were calculated for the α-particle induced reactions 115In(α,x)117mSn, 114Cd(α,n)117mSn, 116Cd(α,3n)117mSn and natCd(α,x)117mSn to analyse the production of the medically important 117mSn (T½ = 13.6 d). For calculations three nuclear model codes (i.e. TALYS, EMPIRE and ALICE-IPPE) were used and the results were compared with the available experimental data. For the most important reaction, 116Cd(α,3n)117mSn, evaluated data are presented. The yield and radionuclidic purity of 117mSn from each reaction are discussed.

Evaluation of nuclear reaction cross sections for optimization of production of the emerging diagnostic radionuclide 55Co.

The excitation functions of the (54)Fe(d,n)(55)Co, (56)Fe(p,2n)(55)Co and (58)Ni(p,α)(55)Co reactions were analyzed with relevance to the production of the ß(+)-emitter (55)Co (T½=17.53 h), a promising cobalt radionuclide for PET imaging. The nuclear model codes ALICE-IPPE, EMPIRE and TALYS were used to check the consistency of the experimental data. The statistically fitted excitation function was employed to calculate the integral yield of the product. The amounts of the radioactive impurities (56)Co and (57)Co were assessed. A comparison of the three investigated production routes is given.

Evaluation of excitation functions of the (68,67,66)Zn(p,xn)(68,67,66)Ga and 67Zn(p,α)64Cu reactions: validation of evaluated data through comparison with experimental excitation functions of the (nat)Zn(p,x)(66,67)Ga and (nat)Zn(p,x)64Cu processes.

Experimentally available cross section data for formation of the radionuclides (68)Ga, (67)Ga, (66)Ga and (64)Cu in proton induced reactions on enriched (68)Zn, (67)Zn and (66)Zn were evaluated by comparison with the excitation functions calculated by the nuclear model codes, EMPIRE and TALYS, followed by statistical fitting of the selected data. The recommended cross sections were used to obtain the integral yields. The validation of the recommended excitation functions was also attempted by normalization to (nat)Zn and comparison with the experimental data for the (nat)Zn(p,x)(67)Ga, (nat)Zn(p,x)(66)Ga and (nat)Zn(p,x)(64)Cu processes.

Nuclear model analysis of excitation functions of proton and deuteron induced reactions on (64)Zn and (3)He- and α-particle induced reactions on (59)Co leading to the formation of copper-61: Comparison of major production routes.

Cross section data for formation of the medically important radionuclide (61)Cu (T½=3.33h) in proton and deuteron induced reactions on enriched (64)Zn and in (3)He- and α-particle induced reactions on (59)Co were analyzed by using the nuclear model calculational codes, EMPIRE and TALYS. A well-defined statistical procedure was then employed to derive the recommended excitation functions, and therefrom to obtain integral yields. A comparison of major production routes of (61)Cu was done.

Nuclear model analysis of excitation functions of proton, deuteron and α-particle induced reactions on nickel isotopes for production of the medically interesting copper-61.

Excitation functions of the (61)Ni(p,n)(61)Cu, (62)Ni(p,2n)(61)Cu, (60)Ni(d,n)(61)Cu and (58)Ni(α,p)(61)Cu reactions were analyzed with respect to the production of (61)Cu (T½=3.33 h), a promising radionuclide for PET imaging. The nuclear model codes EMPIRE and TALYS reproduced the experimental data of all reactions well, except those for the (d,n) process. The fitted excitation functions were employed to calculate the integral yield of (61)Cu in all reactions. The amounts of the possible impurities (62)Cu and (60)Cu were assessed. A validation of the evaluated (p,xn) data was attempted.

Diversity array technology markers: genetic diversity analyses and linkage map construction in rapeseed (Brassica napus L.).

We developed Diversity Array Technology (DArT) markers for application in genetic studies of Brassica napus and other Brassica species with A or C genomes. Genomic representation from 107 diverse genotypes of B. napus L. var. oleifera (rapeseed, AACC genomes) and B. rapa (AA genome) was used to develop a DArT array comprising 11 520 clones generated using PstI/BanII and PstI/BstN1 complexity reduction methods. In total, 1547 polymorphic DArT markers of high technical quality were identified and used to assess molecular diversity among 89 accessions of B. napus, B. rapa, B. juncea, and B. carinata collected from different parts of the world. Hierarchical cluster and principal component analyses based on genetic distance matrices identified distinct populations clustering mainly according to their origin/pedigrees. DArT markers were also mapped in a new doubled haploid population comprising 131 lines from a cross between spring rapeseed lines 'Lynx-037DH' and 'Monty-028DH'. Linkage groups were assigned on the basis of previously mapped simple sequence repeat (SSRs), intron polymorphism (IP), and gene-based markers. The map consisted of 437 DArT, 135 SSR, 6 IP, and 6 gene-based markers and spanned 2288 cM. Our results demonstrate that DArT markers are suitable for genetic diversity analysis and linkage map construction in rapeseed.

Evaluation of excitation functions of proton, ³He- and α-particle induced reactions for production of the medically interesting positron-emitter bromine-76.

Cross section data for production of the medically interesting radionuclide 76Br (T(½)=16.2 h) via the proton induced reactions on 76Se, 77Se, 78Se and 79Br, and ³He- and α-particle induced reactions on 75As were evaluated. The nuclear model codes STAPRE, EMPIRE and TALYS were used to check the consistency in the experimental data and a statistical procedure was applied to derive the recommended excitation functions. A comparison of various production routes of 76Br (and of 75Br) is presented.

Excitation functions of α-particle induced reactions on enriched 123Sb and (nat)Sb for production of 124I.

Excitation functions of (α,xn) reactions on 98.28% enriched (123)Sb and on (nat)Sb were measured from 9 to 40 MeV. The data could be described well in terms of statistical and precompound models using the code TALYS. The discrepancies in the literature data for the formation of (125)I and (126)I were solved. The nuclear reaction (123)Sb(α,3n)(124)I on an enriched target appears to be interesting for the production of (124)I (T(1/2)=4.18 d) over the energy range E(α)=42→32 MeV, its yield being 11.7 MBq/µAh. The levels of the radionuclidic impurities (125)I and (126)I amount to 1.8% and 0.6%, respectively. The use of (nat)Sb as target material for (124)I production is unsuitable due to the high level of (123)I impurity.

Evaluation of excitation functions of 3He- and α-particle induced reactions on antimony isotopes with special relevance to the production of iodine-124.

Cross section data were evaluated for the production of the medically important positron emitter (124)I (T(1/2)=4.18d) via (3)He- and α-particle induced reactions on Sb isotopes. The consistency in the measured data available in the literature was checked against the cross section calculations of three nuclear model codes (i.e. STAPRE, EMPIRE and TALYS). The recommended excitation functions obtained by a statistical procedure were used to derive the integral yields. An assessment of the (124)I yields and associated radioisotopic impurities suggests that the (123)Sb(α,3n)(124)I process over the energy range of E(α)=45 → 32 MeV could be of potential interest for the production of (124)I.

Evaluation of excitation functions of proton and deuteron induced reactions on enriched tellurium isotopes with special relevance to the production of iodine-124.

Cross-section data for the production of medically important radionuclide (124)I via five proton and deuteron induced reactions on enriched tellurium isotopes were evaluated. The nuclear model codes, STAPRE, EMPIRE and TALYS, were used for consistency checks of the experimental data. Recommended excitation functions were derived using a well-defined statistical procedure. Therefrom integral yields were calculated. The various production routes of (124)I were compared. Presently the (124)Te(p,n)(124)I reaction is the method of choice; however, the (125)Te(p,2n)(124)I reaction also appears to have great potential.

A comprehensive evaluation of charged-particle data for production of the therapeutic radionuclide (103)Pd.

(103)Pd is an important radionuclide having a half-life of 16.99d, which is suitable for internal radiation therapy, especially used for the treatment of prostate cancer. Its production in no-carrier-added form is done via charged-particle-induced reactions and the data are available in EXFOR library. We evaluated six charged-particle-induced reactions, namely (nat)Ag(p,x)(103)Pd, (103)Rh(p,n)(103)Pd, (103)Rh(d,2n)(103)Pd, (100)Ru(alpha,n)(103)Pd, (101)Ru(alpha,2n)(103)Pd, and (102)Ru((3)He,2n)(103)Pd process. In the first case, analysis was done up to about 100MeV but in other cases only up to about 25 or 40MeV. Furthermore, an evaluation of the data for the (nat)Ag(p,x)(103)Ag process was also done since it may serve as a typical example for the (103)Ag-->(103)Pd precursor system. A statistical procedure supported by nuclear model calculations using the codes STAPRE, EMPIRE 2.19, and TALYS was used to validate and fit the experimental data. The recommended sets of data derived together with confidence limits are reported. The application of those data, particularly in the calculation of integral yields, is discussed. A comparison of the investigated routes from the viewpoint of practical applicability to the production of (103)Pd is given. Presently the (103)Rh(p,n)(103)Pd reaction is the method of choice.