Investigation of isotopically tailored boron in advanced fission and fusion reactor systems /

This research examines the use of B^11, in the form of metallic boron and boron carbide, as a moderating and reflecting material. An examination of the neutronic characteristics of the B^11 isotope of boron has revealed that B^11 has neutron scattering and absorption cross sections favorably compara...

Full description

Bibliographic Details
Main Author: Domaszek, Gerald Raymond, 1951-
Other Authors: Hassan, Yassin A. (degree committee member.), Parish, Theodore A. (degree committee member.), Reuscher, Jon A. (degree committee member.), Wolfenden, A. (degree committee member.)
Format: Thesis Book
Language:English
Published: 1989.
Subjects:
Online Access:ProQuest, Abstract
Link to OAKTrust copy

MARC

LEADER 00000ctm a2200000Ia 4500
001 in00000921956
005 20200904152436.0
008 900801s1989 xx a bm 000 0 eng d
035 |a (OCoLC)ocm22166121 
035 |9 AEP2535AM 
040 |a TXA  |b eng  |c TXA  |d OCLCQ  |d OCLCG  |d OCLCF  |d OCLCO  |d OCLCQ  |d UMI  |d TXA 
035 |a (OCoLC)22166121 
049 |a TXAM 
099 |a 1989  |a Disser-  |a tation  |a D666 
100 1 |a Domaszek, Gerald Raymond,  |d 1951- 
245 1 0 |a Investigation of isotopically tailored boron in advanced fission and fusion reactor systems / 
264 1 |c 1989. 
300 |a xii, 125 leaves :  |b illustrations ;  |c 29 cm 
336 |a text  |b txt  |2 rdacontent 
337 |a unmediated  |b n  |2 rdamedia 
338 |a volume  |b nc  |2 rdacarrier 
500 |a Typescript (photocopy). 
502 |b Ph. D.  |c Texas A & M University  |d 1989 
500 |a Vita. 
504 |a Includes bibliographical references. 
500 |a "Major subject: Nuclear Engineering." 
520 3 |a This research examines the use of B^11, in the form of metallic boron and boron carbide, as a moderating and reflecting material. An examination of the neutronic characteristics of the B^11 isotope of boron has revealed that B^11 has neutron scattering and absorption cross sections favorably comparable to those of Be^9 and C^12. Preliminary analysis of the neutronics of B^11 were performed by conducting one dimensional transport calculations on an infinite slab of varying thickness. Results showed that B^11 is superior to graphite as a reflecting and shielding material for both fission and fusion reactor systems. Beryllium is the best of the three materials in reflecting neutrons due primarily to the contribution from (n,2n) reactions. As a shielding material the (n,2n) reaction becomes a liability for beryllium, particularly if 14 MeV neutrons are present. Tailored neutron energy beam transmission experiments were carried out to experimentally verify the predicted neutronic characteristics of B^11. To further examine the neutron moderating and reflecting characteristics of B^11, the energy dependent neutron flux was measured as a function of position in an exponential pile constructed of B4C isotopically enriched to 98.5 percent B^11. After the experimental verification of the neutronic behavior of B^11, further design studies were conducted using metallic boron and boron carbide enriched in the B^11 isotope. The use of materials isotopically enriched in B^11 as a liner in the first wall/blanket of a magnetic confinement fusion reactor demonstrated acceptable tritium regeneration in the lithium blanket. Analysis of the effect of contaminant levels of B^10 showed that B^10 contents of less than 1 percent in metallic boron produced negligible adverse effects on the tritium breeding. A comparison of the effectiveness of graphite and B[^11]4C when used as moderators in a reactor fueled with natural uranium has shown that the maximum k[infinity] for a given fuel rod design is approximately the same for both materials. Approximately half the volume of the moderator is required when B[^11]4C is substituted for graphite to obtain essentially the same k[infinity]... 
650 0 |a Boron  |x Isotopes. 
650 0 |a Nuclear fission. 
650 0 |a Nuclear fusion. 
650 4 |a Major nuclear engineering. 
655 7 |a Academic theses  |2 lcgft 
700 1 |a Schlapper, Gerald A.,  |e degree supervisor. 
700 1 |a Hassan, Yassin A.,  |e degree committee member. 
700 1 |a Parish, Theodore A.,  |e degree committee member. 
700 1 |a Reuscher, Jon A.,  |e degree committee member. 
700 1 |a Wolfenden, A.,  |e degree committee member. 
710 2 |a Texas A & M University,  |e degree granting institution. 
856 4 2 |3 ProQuest, Abstract  |u http://gateway.proquest.com/openurl?url_ver=Z39.88-2004&rft_val_fmt=info:ofi/fmt:kev:mtx:dissertation&res_dat=xri:pqm&rft_dat=xri:pqdiss:9007468  |t 0 
856 4 1 |x http://hdl.handle.net/1969.1/DISSERTATIONS-1028971  |z Link to OAKTrust copy 
856 4 1 |u http://proxy.library.tamu.edu/login?url=http://proquest.umi.com/pqdweb?did=746076561&sid=1&Fmt=2&clientId=2945&RQT=309&VName=PQD  |z Link to OAKTrust copy 
994 |a C0  |b TXA 
999 f f |s b9fa25ed-09cf-3f21-8896-623713f90809  |i b19128cd-8fe3-37a8-9c15-236edc10a81a  |t 0 
952 f f |p noncirc  |a Texas A&M University  |b J.J. Pickle Campus  |c High Density Repository  |d Remote Storage  |t 0  |e 1989 Dissertation D666  |h Other scheme  |i unmediated -- volume  |m A14841019900 
998 f f |a 1989 Dissertation D666  |t 0  |l Remote Storage 
998 f f |a 1989 Dissertation D666  |t 0  |l Available Online