Tóm tắt các kết quả mới của luận án: - Đã xây dựng thành công mô hình tương tác (p,n) trên bia chì lỏng, với chì lỏng đóng vai trò vừa là bia tương tác (p,n) sinh neutron, vừa làm chất tải nhiệt bên trong ADSR. Bằng cách sử dụng chương trình MCNPX và khai thác thư viện dữ liệu JENDL, một số tính toán đã được thực hiện để đánh giá sự phù hợp của mô hình. Các tính toán này bao gồm: hiệu suất phát neutron, phân bố neutron sinh ra từ tương tác (p,n) khi cho dòng proton với nhiều mức năng lượng khác nhau, nhỏ nhất là từ 250 MeV đến lớn nhất là 3 GeV, tương tác lên bia chì lỏng; phân bố năng lượng của các neutron phát ra, phân bố góc, hiệu suất phát neutron theo góc, vi phân bậc hai tiết diện sinh neutron theo năng lượng và theo góc khối từ phản ứng (p.n). Bằng việc so sánh với một số nghiên cứu khác, đã khẳng định sự phù hợp của mô hình tính toán - Đánh giá được khả năng sử dụng thori làm nhiên liệu cho ADSR sử dụng chì lỏng làm bia tương tác và tải nhiệt, thông qua các nghiên cứu phân rã phóng xạ thori trong chì lỏng, phân bố thông lượng neutron và tính toán hệ số nhân neutron bên. Với nghiên cứu được phổ phóng xạ hạt nhân thori trong môi trường chì lỏng, các kết quả này bao gồm phổ năng lượng của các tia alpha, beta, gamma và phản neutrino; năng lượng của các hạt nhân con tạo thành và quãng chạy của các nhân con sinh ra trong môi trường chì lỏng. Với các tính toán phân bố thông lượng neutron bên trong ADSR sử dụng nhiên liệu thori: các kết quả này bao gồm: phân bố thông lượng neutron theo năng lượng neutron phát ra, phân bố thông lượng neutron theo chiều dài, phân bố thông lượng neutron theo bán kính; tính toán được phân bố thông lượng neutron bên trong ADSR sử dụng nhiên liệu hỗn hợp của thori 12. Khả năng ứng dụng thực tiễn: Ý nghĩa khoa học và thực tiện của luận án là đã xây dựng mô hình sử dụng bia chì lỏng và thực hiện một số tính toán, so sánh với các mô hình của các tác giả khác với bia và hỗn hợp nhiên liệu khác nhau để đánh giá sự phù hợp của mô hình đề xuất; đề xuất khả năng bổ sung thori làm nhiên liệu hỗn hợp và đã khảo sát tỷ lệ thori và urani để đưa ra tỷ lệ phù hợp. 13. Các hướng nghiên cứu tiếp theo: Nghiên cứu các cấu trúc khác của ADSR cho việc tối ưu hóa sử dụng thori làm nhiên liệu. Hiện nay, một số lò phản ứng sử dụng thanh nhiên liệu dạng hình trụ lục giác thay vì hình trụ tròn. Một số nghiên cứu khác đề xuất thiết kế lõi dạng hình cầu thay vì hình trụ như truyền thống. Các cấu trúc này nên được xem xét, sử dụng cho các tính toán các tham số neutron quan trọng, so sánh với các các cấu trúc đã được tính toán, từ đó chọn được cấu hình tối ưu nhất. Thực hiện các tính toán sử dụng hỗn hợp chì-bismuth dạng rắn và lỏng, nhiên liệu urani kết hợp thori với các tỷ lệ khác nhau, nhằm lựa chọn cách kết hợp tối ưu giữa vật liệu làm bia và hỗn hợp nhiên liệu. Nghiên cứu ảnh hưởng của nhiệt độ chì lỏng đến phổ neutron phát ra, thông lượng neutron bên trong ADSR. Trong quá trình hoạt động của lò, nhiệt độ của chì lỏng có thể thay đổi và điều này ảnh hưởng như thế nào đến các tham số neutron; đây là vấn đề chưa được đề cập đến trong luận án và cần có những nghiên cứu tiếp theo. Nghiên cứu quá trình tạo ra neutron trong chu trình nhiên liệu thori. Một số mã tính toán cho phép nghiên cứu quá trình tạo ra neutron độc lập với thời gian hay phụ thuộc thời gian. Các chương trình này có thể là GEANT4, EASY-II hay FISPACT-II. Đây cũng là một vấn đề quan trong mà luận án chưa tính toán đến. Nghiên cứu quá trình tạo ra neutron bằng nguồn D-T (Deuterium - Tritium) thay thế tương tác (p,n). Máy phát neutron D-T tạo ra neutron bằng phản ứng nhiệt hạch giữa deuterium và tritium. Các nghiên cứu cho thấy máy phát neutron D-T có thể tạo ra sản lượng neutron ổn định. Máy phát neutron -DT là hệ thống lý tưởng để đáp ứng nhu cầu của bạn về bức xạ neutron nếu bạn yêu cầu năng suất neutron cao với cường độ 1013 neutron mỗi giây. Đây là một nguồn neutron lý tưởng cho hoạt động của ADSR cần được xem xét nghiên cứu.
Trang 1MINISTRY OF EDUCATION MINISTRY OF SCIENCE
VIETNAM ATOMIC ENERGY INSTITUTE
TRAN MINH TIEN
RESEARCH ABOUT POSSIBILITY OF USINGTHORIUM AS FUEL FOR THE ACCELERATORDRIVEN SUBCRITICAL REACTORS
Speciality: Atomic and nuclear physics
Code: 9.44.01.06
SUMMARY OF THE PHD THESIS
Ho Chi Minh City – 2022
Trang 2This thesis was completed at: Vietnam Atomic Energy Institute
SUPERVISORS:
1 Assoc Prof Dr TRAN QUOC DUNG
2 Assoc Prof Dr NGUYEN MONG GIAO
Referee 1:
Referee 2:
Referee 3:
This dissertation will be defended in front of the evaluat-ing assembly at academy level, place of defendevaluat-ing:
This thesis can be studied at::
Trang 3
CHAPTER 2 SIMULATING THE TURE OF ADSR USING LIQUID LEAD AND
2.1 Model of (p,n) interaction on the liquid leadtarget 62.1.1 Model and calculations 62.1.2 The distribution of the neutrons from
(p,n) reaction 72.1.3 The angular distributions of neutrons 82.1.4 The neutron yields according to angles 9
Trang 42.1.5 The double-differential of the neutrons
cross-section 92.2 Model of TRIGA Mark II subcritical reactorusing liquid lead and thorium fuel 102.2.1 Model of TRIGA Mark II reactor sim-
ulated by MCNPX 102.2.2 The neutron yields Yn/p 112.2.3 The effective neutron multiplication fac-
tor kef f 11
CHAPTER 3 CALCULATION THORIUM
3.1 Radioactive decay of thorium in the liquid lead 133.1.1 Model and calculations 133.1.2 The energy spectrums of alpha, beta,
antineutrino particles and gamma rays 133.1.3 The energy of daughter nucleus 153.2 Comparison of neutron flux distributions inADSR using liquid lead, mixed thorium fuelwith ADSR using solid target, mixed fuel ura-nium 153.2.1 The case of UZrH fuel and light water
coolant 153.2.2 The case of UZrH fuel and liquid lead
coolant 163.2.3 The case of ThUO fuel and molten
lead coolant 173.3 The distributions of neutron fluxes in ADSRusing thorium fuel 18
Trang 53.3.1 The distributions of neutron fluxes by
neutron energy 183.3.2 The axial distributions of neutron flux 193.3.3 The radial distributions of neutron flux 193.4 Neutron flux distributions using mixed tho-rium and uranium fuel 193.4.1 The radial distributions of neutron flux 203.4.2 The axial distributions of neutron flux 203.4.3 The energy ditributions of produced
neutron 213.4.4 Comparison of neutron flux distribu-
tion with fuels U O2, T h233U O2 and
T h235U O2 213.5 The neutron multiplication factors in ADSRusing thorium fuel 223.5.1 The kef f with T h233U O2 mixure fuel 233.5.2 The kef f with T h235U O2 mixure fuel 233.5.3 The kef f with T h238U O2 mixure fuel 24
Trang 6List of abbreviations
Abbreviations Meaning
ADS Accelerator Driven System
ADSR Accelerator Driven Subcritical
Re-actorADTR Accelerator Driven Thorium Reac-
torENDF Evaluated Nuclear Data File
GEANT Geometry And Tracking
JENDL Japanese Evaluated Nuclear Data
LibraryJENDL-
MCNP Monte Carlo N-Particle
MYRRHA Multi-purpose hYbrid Research
Re-actor for High-tech Applications
SCWR Super Critical Water Reactor
VHTR Very High Temperature Reactor
Trang 7List of Figures2.1 Model of (p,n) reaction on the liquid lead target 72.2 The position of the generated angles of theneutrons 82.3 The cross-section of ADSR reactor core based
on the structure of the TRIGA Mark II reactor 102.4 Structure of a fuel rod 103.1 Model of radioactive decay of thorium in liq-uid lead 14
Trang 8Nuclear energy is facing problems such as high cost, safety,uranium fuel sources, along with challenges from radioactivewaste transmutation One of the current solutions is to de-velop Accelerator Driven Subcritical Reactors - ADSRs [1-3].ADSR works on a basic principle: an accelerator generates
a high-energy proton beam, which interacts with a target,producing a (p,n) reaction The reactions take place in thesubcritical state Many previous studies have performed cal-culations of neutron parameters for the solid target; the fuel
is mainly uranium, while thorium is also a potential fuel [4].However, the using of a solid target after a period of timemust change the target, then the reactor operation must
be stopped In this thesis, liquid lead is proposed both as
an interactive target to maintain the ADSR’s activity and
a coolant and transfer heat to the outside This is a newmodel that has not been studied much in the world Withthe using of liquid lead as both coolant and target, therewill be no need to change the target during nuclear reactoroperation All liquid lead in the path of the incident pro-ton beam will be the interaction target, so the number ofneutrons generated will increase compared to using a solidtarget
The thesis is carried out towards two main objectives: (1)building a model of an accelerator driven subcritical reac-tor using liquid lead both as an interactive target and as acoolant; (2) evaluating the possibility of using thorium fuelfor ADSR through the calculation of basic neutron parame-ters of the reactor Here, the TRIGA Mark II reactor modelwas chosen because there are many other studies that alsouse this model for calculations for ADSR [5-8]
Trang 9CHAPTER 1 OVERVIEW1.1 The Accelerator Driven Subcritical Reactor (ADSR)ADSR works on a basic principle: an accelerator gener-ates a proton beam with energies from a few hundred MeV
to several GeV, which interacts on a heavy target, causing
a (p,n) interaction Proposals to use high-energy protonbeams were made decades ago [9-12] This process will pro-duce many neutrons emitted in different directions; theseneutrons will cause many reactions such as (n,n), (n,2n),(n, γ), ; participates in many processes such as neutronabsorption, elastic scattering, and inelastic scattering Theprocesses inside the reactor are maintained in a subcriticalstate The neutrons generated from the interaction (p, n)will act as additional neutrons, maintaining the subcriticaloperating state of the reactor
The basic issues related to ADSR have been studied since
2001 [13-15] Currently, the problems are being focused onsuch as thermal neutron spectrum, fast neutron; fuel type:solid (metal, oxide, nitric, carbide, ); or liquid (chloride,fluoride); target types (lead, lead-bismuth, tungsten, moltensalt, ) In Vietnam, there are also some studies on ADSR,
as Nguyen Mong Giao et al [16-19] and Vu Thanh Mai et
al [20-25]
1.2 The current development of ADSRs
Since its proposal, many international conferences on ADSRhave been organized The most typical is the conference
on technology and structure of accelerator control systems(Technology and Components of Accelerator Driven Sys-tems) held every three years, starting from 2010 [26-28] InEuropean countries, there has been a joint effort to exper-imentally design an ADSR, called XT-ADS Then, based
on this design, the Belgian Center for Nuclear Research
Trang 10(SCK.CEN) preliminary designed a project called MYRRHA(Multi-purpose hYbrid Research Reactor for High-tech Ap-plications), in which a reactor with the ability to operate
in both critical and subcritical states [29] In India, the velopment of ADSR has been in progress since 2001 [30].The first operational phase of the program began in 2002
de-At that time, India developed a 10 MeV linear accelerator,which produced a proton current with an intensity of 10 mA;used lead-bismuth as an interactive target, and started ex-perimental research for ADSR In Japan, research activities
on ADSR are located at the Proton Accelerator ResearchComplex (PARC), which is a collaboration between KEK(High Energy Accelerator Research Organization) and theIAEA In China there are also many projects to developADSR; one of them is C-ADS [31] The C-ADS project wasinitiated by the Chinese Academy of Sciences (CAS), withthe participation of four institutes: the Institute of HighEnergy Physics (IHEP); Institute of Plasma Physics (IPP),University of Science and Technology of China (USTC) InUkraine, starting in 2012, the National Science Center -Kharkov Institute of Physics and Technology (NSC KIPT)cooperates with the Argonne National Laboratory of theUSA (ANL) to build a linear accelerator and a subcriticalreactor system [32]
1.3 Studies on (p,n) reactions, neutron distribution
on solid targets for ADSR
There have been many studies on (p, n) reaction, butions of the neutron and neutron flux in the world; beloware some typical research works
distri-In 1999, the group of authors X Ledoux, F Borne, A.Boudard, et al calculated the energy spectrum of neutronsproduced at different angles when the proton beam carriedenergies of 0.8 MeV, 1.2 MeV, and 1.6 MeV interacts on
Trang 11the lead target [33] Also, in 1999, the authors S Meigo et
al calculated the neutron flux distributions generated fromthick lead targets, with incident proton flux energies of 0.5GeV and 1.5 GeV using the MCNP4A program [34] In 2000,the authors A Letourneau, J Galin, F Goldenbaum per-formed calculations of neutrons generated on thick, heavytargets such as W, Hg, Pb; the proton beam with energies0.4 GeV, 0.8 GeV, 1.2 GeV, 1.8 GeV, and 2.5 GeV; with atarget size of 15 cm [35] In 2001, the author G.S Bauerhad analyzed the physical and technical characteristics ofneutron fission sources [36] In this, the author presents theresults of calculating the angular distribution of neutronsgenerated when a proton beam with energy 2 GeV inter-acts on a 20 cm thick lead target In 2003, the authors H.Nifenecker, O Meplan, and S David presented the results
of calculating the neutron multiplier per incident proton onvarious targets, with the proton beam having different ener-gies [37] The author’s calculation results show that as theenergy of the proton beam increases, the number of neu-trons emitted per incident proton increases In 2008, au-thor A Krasa presented a study on the neutron spectrumemitted in the fission reaction on a lead target with pro-ton beam energy from 0.7 MeV to 2.0 GeV [38] In 2018,David Sangcheol Lee, in his doctoral thesis, presented manycalculation results related to neutron distributions inside anADSR [39]
1.4 Researching about using thorium as fuel in ventional nuclear reactors
con-Thorium is not a nuclear fission fuel; however, it can beconverted to U-233 by the neutron capture reaction of Th-
232 Although thorium can fission with fast neutrons of able energy; however, converting Th-232 to U-233 and using
suit-it as a fission fuel will give greater efficiency Several various
Trang 12reactors have operated based on thorium fuel or tion with others In early studies, thorium was combinedwith uranium as a fission material The pioneers of the idea
combina-of combining uranium and thorium were Alvin Weinberg,Ralph Moir, and Edward Teller, with the molten salt reac-tor (MSRE) experiment that ran successfully at Oak RidgeNational Laboratory (ORNL) in the US in 1969 [40] TheRadkowsky reactor in Russia is also one of these reactors[41] The potential of thorium in fission energy productionhas been recognized in many studies [42]
1.5 Possibility to use thorium as fuel for ADSRProposals to use thorium as fuel for ADSR have beenmade by many researchers Many countries are also hav-ing development projects related to this problem In 1994,
C Rubbia et al proposed using thorium as fuel for ADSR[1] In this proposal, the ADSR system works mainly onfast neutrons, using natural thorium fuel; all actinide el-ements are recycled independently In this proposal, leadwas used as an interaction target to generate neutrons, theheat capacity is estimated at 600 MW C Rubbia also sug-gested using Thorium as fuel for ADSR, using molten salt
as a coolant Another proposal related to using thorium forADSR is ADTR (Accelerator Driven Thorium Reactor) bythe group of authors Victoria B Ashey et al [43] Japandeveloped ADSR to convert long-term radioactive waste tolimit its impact on the environment [44-45]
Trang 13CHAPTER 2 SIMULATING THE STRUCTURE
OF ADSR USING LIQUID LEAD AND
THORI FUEL
2.1 Model of (p,n) interaction on the liquid lead get
tar-2.1.1 Model and calculations
Previous studies concentrated on solid targets [46-49].This thesis proposes to use liquid lead directly as both targetand coolant; that is, the proton beam will interact directlywith liquid lead [50] Although liquid lead has a lower massdensity than solid lead, (10.66 g.cm−3 compares with 11.7g.cm−3 ); however, this option will have great advantagessuch as:
- There is no need for a separate target for the interaction(p, n)
- The liquid lead is always convection and replaced duringthe operating of the reactor There will be no need to changethe target, and the reactor will not be shut down during theoperation
- The proton beam interacts with the liquid lead target, thelength of the target increases, and therefore the number ofneutrons produced also increases
From this idea, a model of (p,n) interaction with the liquidlead has been built to calculate some paremeters for neutronssuch as distribution of energy, the angular distributions ofemitted neutrons, the neutron yield, and the neutron pro-duction double-differential cross-section The basic interac-tion model is presented in figure 2.1
Assume a proton beam with 25 mA intensity, 4 cm radiusinteracts on the liquid lead, creating a (p,n) reaction.The data used for the calculations in this section are ex-tracted from the JENDL data (Japanese Evaluated NuclearData Library), JENDL-HE-2007 of Japan [51-53]
From these data, a Matlab program was written to calculate
Trang 14Figure 2.1: Model of (p,n) reaction on the liquid lead target
the parameters of neutrons emitted from the (p,n) reaction
on the liquid lead target The results are given and mented below
com-2.1.2 The distribution of the neutrons from (p,n)
reaction
The results have shown that for each energy level of theincident proton beam, the levels of neutron energy changefrom 0 to about 120 MeV, concentrated at energies from 1MeV to 3 MeV These results also show that the number
of neutrons with energies from 1 MeV to 3 MeV is about73.4% when the intensity proton beam has energy of 250MeV These rates are 74.4%; 68.5%; 69.1%; and 60.5% forprotons with energies of 350 MeV, 500 MeV, 1 GeV and 2GeV, respectively Comparing the neutron spectrum for dif-ferent energy levels of the incident proton, as the protonenergy increases, the neutron energy is increased The num-
Trang 15ber of neutrons in the energy range from 5 MeV to 15 MeVincreases more strongly than in other regions These resultshave a small difference compared with the calculation onsolid lead target [46].
2.1.3 The angular distributions of neutrons
The ratios of neutrons at 19 positions, corresponding to
19 different angles from 00 to 1800 compared to the totalnumber of neutrons, were calculated The positions of an-gles ares determined as shown in the figure 2.2 These resultsshow that the neutrons are concentrated at angles from 00
to 200 The proportion of neutrons generated in this region
is about 21.3% corresponding to the energy of 250 MeV ofthe incident proton beam These ratios ares 22%, 23.4%, re-spectively; 24.8%; 25% and 25.7% for incident proton energylevels of 350 MeV, respectively; 500 MeV; 1 GeV; 2 GeV and
3 GeV These results are consistent with the calculations onsolid lead targets [54]
Figure 2.2: The position of the generated angles of the neutrons
Trang 162.1.4 The neutron yields according to anglesThe neutron yields in 19 angles from 00 to 1800 were cal-culated The calculation results have shown that the higherthe incident proton energy levels, the higher the neutronyield The calculation results show that the higher the in-cident proton energy levels, the higher the neutron yield.When compared with other studies on solid lead targets,such as that of David Sangcheol Lee [30], These results arequite consistent at positions corresponding to angles of 900
or more, however, at larger angles, there are big differences.Calculation results have shown the difference in the angulardistribution of neutrons from the reaction (p, n) on the leadtarget with two cases of solid and liquid [55-56]
2.1.5 The double-differential of the neutrons
cross-section
Calculating the double-differential of the neutrons section will evaluate the energy distribution of the neutronsproduced; how neutrons produced at the corresponding en-ergy level The results have shown that neutrons were con-centrated at an energy of about 2 MeV Comparison withthe results from calculations on solid lead by the group ofauthors X Ledoux, F Borne, A Boudard et al [57] calcu-lated at 1200 MeV proton energy, there are similarities atenergies of 5 MeV and higher However, there is a difference
cross-in the neutron energy region of less than 5 MeV; These showthe difference between liquid and solid targets [57]
Trang 172.2 Model of TRIGA Mark II subcritical reactor ing liquid lead and thorium fuel
us-2.2.1 Model of TRIGA Mark II reactor simulated
by MCNPX
The basic details of the TRIGA Mark II reactor weresimulated and shown in figure 2.3
The basic structure of the core consists of 108 fuel rods
ar-Figure 2.3: The cross-section of ADSR reactor core based on the structure of the TRIGA Mark II reactor
ranged in 6 rings around, all placed in a liquid lead medium.The details of one fuel rod was shown in the figure 2.4
Figure 2.4: Structure of a fuel rod
From this structure, the input data file was built, the NPX program read the data, and output the calculation re-
Trang 18MC-sults The neutron yields (Yn/p) were calculated as a protonbeam with 2 mA current, carrying different energies inter-acted on the liquid lead in the core The energy levels of theproton beam were chosen according to the parabolic spatialdistribution The effective neutron multiplication factors(kef f) were calculated from kcode in MCNPX.
2.2.2 The neutron yields Yn/p
The neutron yields Yn/p is the number of average trons produced per incident proton In these calculations,the proton beam with energies ranging from 115 MeV to
neu-2000 MeV interacts on the liquid lead target The results ofcalculating the neutron yield are compared with those fromthe work of Hasanzadeh, C Rubbia et al [51-54] The re-sults show that the neutron yield increases with increasingthe energy of the incident proton beam At an energy of 115MeV, the neutron yield on liquid lead and on tungsten dif-fers by 4.2 %; for an energy level of 300 MeV, this difference
is 14.2 %; these values are 8.2% and 2.9% for 600 MeV and
1000 MeV energy levels, respectively This difference is notsignificant, indicating that it is completely feasible to useliquid lead as an interaction target to generate neutrons forADSR
2.2.3 The effective neutron multiplication factor
Trang 19mixture The results have been shown that for UZrH mixedfuel, the higher the ratio of Uranium in the mixture, thehigher the k Let the k reach to values higher than 0.9 thenthe proportion of uranium in the mixture must be greaterthan 24% For Th-UO mixture fuel, the results show a cor-relation between Th-232 and U-233 in fuel composition Thecomponent ratio U-233 increases, the k coefficient increases.The parameter k reaches a value greater than 0.9 when U-
233 accounts for about 29% of the mixture
With the simulation and calculation results using the TRIGAMark II reactor model, the conditions for the fuel compo-sition have been shown for the values of the neutron yieldand the effective neutron multiplication factors to reach thenecessary values for the ADSR
Trang 20CHAPTER 3CALCULATION THORIUM FUEL FOR ADSR3.1 Radioactive decay of thorium in the liquid lead
To evaluate the possibility of using thorium in ADSRusing liquid lead both as a target and coolant, one of theissues is studying about the radioactive decay spectrum ofthorium in the liquid lead Knowing the energy characteris-tics, running distance, ratio, of radioactive rays, and thedaughter nucleus, we can study their influence on the oper-ation of ADSR The GEANT4 program was used for thesestudies [58]
3.1.1 Model and calculations
Model: Th-233 was placed in the center of a cylindricaltube, the radius and height were 20 cm and 60 cm These di-mensions were chosen to correspond to the TRIGA reactor;which was filled with liquid lead The detailed structureswere shown in Figure 3.1 Here, the GEANT4 program wasused for simulations and calculations
3.1.2 The energy spectrums of alpha, beta,
antineu-trino particles and gamma rays
From this model, the average energy, the ratio % of theemitted energy, particles, the energy spectrum of the alpha,beta, gamma, and antineutrino rays were calculated Theresults have shown that the alpha particles have the largestaverage energy, with more than 6.2 %, and also accountsfor the highest percentage of emitted energy compared toother particles, with nearly 90 %; the number of beta parti-cles accounts for the most proportion with more than 45 %.Meanwhile, gamma radiation and neutrinos were producedwith low average energy, and the percentage % of particles is
Trang 21Figure 3.1: Model of radioactive decay of thorium in liquid lead
also low These results have shown that the effects of theseparticles on the thorium fuel cycle are negligible The alphaparticles produced are concentrated at energies of about 3.7MeV, 5.0 MeV, 6.7 MeV, and 8.4 MeV and are most con-centrated at the peak energy of 3.7 MeV Although betaparticles are abundant, they have energies very low , andthe energy peaks are not very clearly Some energy peaks as0.025 MeV, 0.09 MeV and 0.2 MeV can be seen The gen-erated gamma rays were concentrated at some energy peakssuch as 0.2 MeV, 0.6 MeV, 0.9 MeV, and 1.4 MeV The gen-erated neutrinos are concentrated at the energies of 0.5 MeV,1.5 MeV, and 2.5 MeV From these results, it is possible tofurther study the effects of the generated radioactive rays
on the neutron parameters during the (p, n) interaction, aswell as the uranium, thorium fuel cycles; in the operations ofADSR, especially the influence of alpha particles and betarays